Licenses, Certifications, and Approvals for Nuclear Power Plants; Supplemental Proposed Rule, 61330-61359 [06-8656]
Download as PDF
61330
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
NUCLEAR REGULATORY
COMMISSION
10 CFR Parts 2, 50, 51 and 52
RIN 3150–AG24
Licenses, Certifications, and
Approvals for Nuclear Power Plants;
Supplemental Proposed Rule
Nuclear Regulatory
Commission.
ACTION: Supplemental proposed rule.
AGENCY:
The Nuclear Regulatory
Commission (NRC) is proposing to
supplement its proposed rule entitled
‘‘Licenses, Certifications, and Approvals
for Nuclear Power Plants,’’ which was
published on March 13, 2006 (71 FR
12782). The NRC is proposing to
supplement that proposed rule by
amending the regulations applicable to
limited work authorizations (LWA),
which allow limited construction
activities on nuclear power plants to
commence before a construction permit
or combined license is issued. This
supplemental proposed rule would
modify the scope of activities that are
considered construction requiring a
LWA and would also make changes to
the review and approval process for
LWA requests. The NRC is proposing
these changes to enhance the efficiency
of its licensing and approval process for
new nuclear reactors.
DATES: Submit comments by November
16, 2006. Comments received after this
date will be considered if it is practical
to do so, but the Commission is able to
ensure consideration only for comments
received on or before this date.
ADDRESSES: You may submit comments
by any one of the following methods.
Please include the following number
RIN 3150–AG24 in the subject line of
your comments. Comments on
rulemakings submitted in writing or in
electronic form will be made available
to the public in their entirety on the
NRC rulemaking Web site. Personal
information will not be removed from
your comments.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, Attn:
Rulemakings and Adjudications Staff.
E-mail comments to: SECY@nrc.gov. If
you do not receive a reply e-mail
confirming that we have received your
comments, contact us directly at (301)
415–1966. You may also submit
comments via the NRC’s rulemaking
Web site at https://ruleforum.llnl.gov.
Address questions about our rulemaking
Web site to Carol Gallagher (301) 415–
5905; e-mail cag@nrc.gov. Comments
pwalker on PROD1PC61 with PROPOSALS2
SUMMARY:
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
may also be submitted via the Federal
eRulemaking portal https://
www.regulations.gov.
Hand deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m.
Federal workdays. (Telephone (301)
415–1966).
Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at (301)
415–1101.
Publicly available documents related
to this rulemaking may be examined
and copied for a fee at the NRC’s Public
Document Room (PDR), Public File Area
O1 F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland.
Selected documents, including
comments, can be viewed and
downloaded electronically via the NRC
rulemaking Web site at https://
ruleforum.llnl.gov.
Publicly available documents created
or received at the NRC after November
1, 1999, are available electronically at
the NRC’s Electronic Reading Room at
https://www.nrc.gov/NRC/ADAMS/
index.html. From this site, the public
can gain entry into the NRC’s
Agencywide Document Access and
Management System (ADAMS), which
provides text and image files of NRC’s
public documents. If you do not have
access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC
Public Document Room (PDR) Reference
staff at 1–800–397–4209, 301–415–4737
or by e-mail to pdr@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Mr.
Geary Mizuno, Office of the General
Counsel, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone (301) 415–1639; e-mail:
GSM@nrc.gov.
SUPPLEMENTARY INFORMATION:
I.. Background
A. History of the Part 52 Rulemaking
Proceeding
II. Discussion
A. History of the NRC’s Concept of
Construction and the LWA
B. NRC’s Proposed Concept of
Construction and the LWA (PRM–50–82)
C. NRC’s Proposed Concept of
Construction and the AEA
D. Proposed Supplement Complies With
NEPA
1. NRC’s Proposed Concept of Construction
Is Consistent With the Legal Effect of
NEPA
2. NRC’s Proposed Concept of the ‘‘Major
Federal Action’’ Is Consistent With
NEPA Law
3. NRC’s Phased Approval Approach Is not
Illegal Segmentation Under NEPA
E. Inclusion of Additional Activities as
‘‘Construction’’ under § 50.10(b)
F. Phased Application and Approval Process
G. EIS Prepared, but Facility Never
Constructed
PO 00000
Frm 00002
Fmt 4701
Sfmt 4702
III. Section-by-Section Analysis
IV. Specific Request for Comments
V. Availability of Documents
VI. Plain Language
VII. Agreement State Compatibility
VIII. Voluntary Consensus Standards
IX. Environmental Impact—Categorical
Exclusion
X. Paperwork Reduction Act Statement
XI. Regulatory Analysis
XII. Regulatory Flexibility Act Certification
XIII. Backfit Analysis
I. Background
A. History of the Part 52 Rulemaking
Proceeding
The NRC issued 10 CFR part 52 on
April 18, 1989 (54 FR 15372), to reform
its licensing process for future nuclear
power plants. The rule added
alternative licensing processes in 10
CFR part 52 for early site permits,
standard design certifications, and
combined licenses. These were
additions to the two-step licensing
process that already existed in 10 CFR
part 50. The processes in 10 CFR part
52 allow for resolving safety and
environmental issues early in the
licensing proceedings and were
intended to enhance the safety and
reliability of nuclear power plants
through standardization.
The NRC had planned to update 10
CFR part 52 after using the standard
design certification process. The
proposed rulemaking action began with
the issuance of SECY–98–282, ‘‘Part 52
Rulemaking Plan,’’ on December 4,
1998. The Commission issued a staff
requirements memorandum on January
14, 1999 (SRM on SECY–98–282),
approving the NRC staff’s plan for
revising 10 CFR part 52. Subsequently,
the NRC obtained considerable
stakeholder comment on its planned
action, conducted three public meetings
on the proposed rulemaking, and twice
posted draft rule language on the NRC’s
rulemaking Web site before issuance of
the initial proposed rule on July 3, 2003
(68 FR 40026). However, a number of
factors led the NRC to question whether
the July 2003 proposed rule would meet
the NRC’s objective of improving the
effectiveness of its processes for
licensing future nuclear power plants
(71 FR 12782). As a result, the NRC
decided that a substantial rewrite and
expansion of the original proposed
rulemaking was desirable so that the
agency may more effectively and
efficiently implement the licensing and
approval processes for future nuclear
power plants under part 52.
Accordingly, the Commission decided
to revise the July 2003 proposed rule
and published the revised proposed rule
for public comment on March 13, 2006
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
(71 FR 12782). The public comment
period on the March 2006 proposed rule
ended on May 30, 2006.
II. Discussion
pwalker on PROD1PC61 with PROPOSALS2
A. History of the NRC’s Concept of
Construction and the LWA
Section 101 of the Atomic Energy Act
of 1954, as amended (AEA) prohibits the
manufacture, production, or use of a
commercial nuclear power reactor,
except where the manufacture,
production or use is conducted under a
license issued by the Commission.
While construction of a nuclear power
reactor is not mentioned in section 101,
section 185 of the AEA requires that the
Commission grant construction permits
to applicants for licenses to construct or
modify production or utilization
facilities, if the applications for such
permits are acceptable to the
Commission. However, the term
construction is not defined anywhere in
the AEA or in the legislative history of
the Act.
To prevent the construction of
production or utilization facilities
before a construction permit is issued,
the NRC proposed a regulatory
definition of construction in 1960 (25
FR 1224; February 11, 1960). The
definition of construction was adopted
in a final rule that same year and
codified in 10 CFR 50.10(b) (25 FR 8712;
September 9, 1960). As promulgated,
§ 50.10(b) stated that no person shall
begin the construction of a production
or utilization facility on a site on which
the facility is to be operated until a
construction permit had been issued.
Construction was defined in § 50.10(b)
as including:
pouring the foundation for, or the installation
of, any portion of the permanent facility on
the site; but [not to] include: (1) Site
exploration, site excavation, preparation of
the site for construction of the facility and
construction of roadways, railroad spurs and
transmission lines; (2) Procurement or
manufacture of components of the facility; (3)
Construction of non-nuclear facilities (such
as turbo-generators and turbine buildings)
and temporary buildings (such as
construction equipment storage sheds) for
use in connection with the construction of
the facility; and (4) with respect to
production or utilization facilities, other than
testing facilities, required to be licensed
pursuant to section 104a. or section 104c. of
the Act, the construction of buildings which
will be used for activities other than
operation of a facility and which may also be
used to house a facility. (For example, the
construction of a college laboratory building
with space for installation of a training
reactor is not affected by this paragraph). (25
FR 8712; September 9, 1960)
The definition of construction
remained unchanged until 1968, when
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
the driving of piles was specifically
excluded from the definition (33 FR
2381; January 31, 1968). This change
was implemented by amending
§ 50.10(b)(1) to read: ‘‘Site exploration,
site excavation, preparation of the site
for construction of the reactor, including
the driving of piles, and construction of
roadways, railroad spurs, and
transmission lines.’’ The rationale for
this change, as articulated in the
proposed rule (32 FR 11278; August 3,
1967), seems to have been that the
driving of piles was closely related to
‘‘preparation of the site for
construction’’ and that the performance
of this type of site preparation activity
would not affect the NRC’s subsequent
decision to grant or deny the
construction permit. With the exception
of the exclusion of the driving of piles
from the definition of construction in
1968, the NRC’s interpretation of the
scope of activities requiring a
construction permit under the AEA has
remained largely unchanged.
However, following the enactment of
the National Environmental Policy Act
of 1969, as amended (NEPA), the
Commission adopted a major
amendment to the definition of
construction in § 50.10 (37 FR 5745;
March 21, 1972). In that rulemaking, the
Commission adopted a much more
expansive concept of construction.
Specifically, a new § 50.10(c) was
adopted stating that no person shall
effect ‘‘commencement of construction’’
of a production or utilization facility on
the site on which such facility will be
constructed until a construction permit
has been issued. ‘‘Commencement of
construction’’ was defined as
any clearing of land, excavation or other
substantial action that would adversely affect
the natural environment of a site and
construction of nonnuclear facilities (such as
turbogenerators and turbine buildings) for
use in connection with the facility, but does
not mean: (1) Changes desirable for the
temporary use of the land for public
recreational uses, necessary boring to
determine foundation conditions or other
preconstruction monitoring to establish
background information related to the
suitability of the site or to the protection of
environmental values; (2) Procurement or
manufacture of components of the facility;
and (3) With respect to production or
utilization facilities, other than testing
facilities, required to be licensed pursuant to
section 104a or section 104c of the Act, the
construction of buildings which will be used
for activities other than operation of a facility
and which may also be used to house a
facility * * * . (37 FR 5748)
The Commission explained that expansion
of the NRC’s permitting authority was:
[C]onsistent with the direction of the
Congress, as expressed in section 102 of the
National Environmental Policy Act of 1969,
PO 00000
Frm 00003
Fmt 4701
Sfmt 4702
61331
that, to the fullest extent possible, the
policies, regulations and public laws of the
United States shall be interpreted and
administered in accordance with the policies
set forth in that Act. Since site preparation
constitutes a key point from the standpoint
of environmental impact, in connection with
the licensing of nuclear facilities and
materials, these amendments will facilitate
consideration and balancing of a broader
range of realistic alternatives and provide a
more significant mechanism for protecting
the environment during the earlier stages of
a project for which a facility or materials
license is being sought. (37 FR 5746)
Thus, the Commission’s interpretation
of its responsibilities under NEPA, not
the AEA, was the driving factor leading
to its adoption of § 50.10(c).1
Two years after the expansion of the
Commission’s permitting authority
resulting from the promulgation of
§ 50.10(c), the NRC promulgated
§ 50.10(e) (39 FR 14506; April 24, 1974).
This provision created the current LWA
process, which was added to allow site
preparation, excavation and certain
other on-site activities to proceed before
issuance of a construction permit. Prior
to the promulgation of § 50.10(e), NRC
permission to engage in site preparation
activities before a construction permit
was issued could only be obtained via
an exemption issued under § 50.12. The
provisions of § 50.10(e) allowed the
NRC to authorize the commencement of
both safety-related (known as ‘‘LWA–II’’
activities) and non safety-related
(known as ‘‘LWA–I’’ activities) on-site
construction activities before issuance
of a construction permit if the NRC had
completed a final environmental impact
statement (FEIS) on the issuance of the
construction permit and the presiding
officer in the construction permit
proceeding had made the requisite
environmental and, in the case of an
LWA–II, safety-related findings.
B. NRC’s Proposed Concept of
Construction and the LWA (PRM–50–82)
The NRC received several comments
in response to its Part 52 proposed rule
revision published on March 13, 2006
(71 FR 12782), including comments
submitted by the Nuclear Energy
Institute (NEI) dated May 25, 2006.2
1 See The Carolina Power and Light Company
(Shearon Harris Nuclear Power Plant, Units 1, 2, 3
and 4), 7 AEC 939, 943 (June 11, 1974) (hereinafter
Shearon Harris) (‘‘The regulations were revised in
1972, not because of any requirements of the
Atomic Energy Act, but rather to implement the
precepts of NEPA which had then recently been
enacted.’’); Kansas Gas and Electric Company (Wolf
Creek Nuclear Generating Station, Unit No. 1), 5
NRC 1, 5 (Jan. 12, 1977) (explaining that NEPA led
the AEC to amend its regulations in several
respects, including the changes to 50.10(c)).
2 See Letter from Adrian P. Heymer, Nuclear
Energy Institute to Annette L. Vietti-Cook,
E:\FR\FM\17OCP2.SGM
Continued
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
61332
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
NEI’s comments suggested
modifications to the NRC’s LWA
process including: (1) That non-safety
related ‘‘LWA–I’’ activities, currently
reflected in § 50.10(c) and § 50.10(e)(1),
be allowed to proceed without prior
authorization from the NRC, and (2) that
the approval process for safety-related
‘‘LWA–II’’ activities be accelerated.
NEI’s comment also stated that the
current definition of construction in
§ 50.10(b) reflects the correct
interpretation of the Commission’s
licensing authority under the AEA.
Further, NEI’s comment letter stated
that ‘‘[t]o the extent the NRC determines
that these LWA issues cannot be
addressed in the current rulemaking, we
ask that the Commission initiate an
expedited rulemaking.’’ The NRC has
determined that the changes suggested
in the NEI comment could not be
incorporated into the final Part 52 rule
without re-noticing. Therefore, the
Commission has decided that the NEI
letter meets the sufficiency
requirements described in 10 CFR
2.802(c) and is docketing the letter as a
petition for rulemaking (PRM–50–82).
Furthermore, the NRC has determined
that it is appropriate to seek public
comment on the action requested by
petitioner within the context of this
supplemental proposed rule, which has
been developed in response to NEI’s
request, as allowed under 10 CFR
2.802(e).
NEI supported its suggested changes
to the LWA process, stating that the
business environment requires that new
plant applicants seek to minimize the
time interval between a decision to
proceed with a combined license
application and the start of commercial
operation. In order to achieve this goal,
NEI states that non safety-related
‘‘LWA–I’’ activities would need to be
initiated up to two years before the
activities currently defined as
‘‘construction’’ in § 50.10(b). In NEI’s
view, the current LWA approval process
would constrain the industry’s ability to
use modern construction practices and
needlessly add eighteen (18) months to
estimated construction schedules for
new plants that did not reference an
early site permit (ESP) with LWA
authority.
The NRC agrees, in part, with NEI’s
comments and is now issuing this
supplement to the March 13, 2006
Secretary, U.S. Nuclear Regulatory Commission,
Pre-Licensing Construction Activity and Limited
Work Authorization Issues relating to NRC
Proposed Rule, ‘‘Licenses, Certifications and
Approvals for Nuclear Power Plants,’’ 71 FR 12, 782
(March 13, 2006) (RIN 3150–AG24) (May 25, 2006).
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
proposed rule.3 This supplemental
proposed rule would narrow the scope
of activities requiring permission from
the NRC in the form of limited work
authorizations (LWA) by eliminating the
concept of ‘‘commencement of
construction’’ currently described in
§ 50.10(c) and the authorization
described in § 50.10(e)(1). Instead,
under the supplemental proposed rule,
NRC authorization would only be
required before undertaking activities
that have a reasonable nexus to
radiological health and safety and/or
common defense and security (i.e.
excavation, subsurface preparation,
installation of the foundation, and onsite, in-place fabrication, erection,
integration or testing, for any structure,
system or component of a facility
required by the Commission’s rules and
regulations to be described in the site
safety analysis report or preliminary or
final safety analysis report). While this
redefinition of ‘‘construction’’ would
result in fewer activities requiring NRC
permission in the form of a LWA, it also
redefines certain activities (such as the
driving of piles), that are currently
excluded from the regulatory definition
of construction given in § 50.10(b), as
construction requiring a LWA.
Further, this proposed rule would
provide an optional, phased application
and approval procedure for construction
permit and combined license applicants
to obtain limited work authorizations.
Specifically, the proposed rule would
provide an environmental review and
approval process for LWA requests that
would allow the NRC to grant an
applicant permission to engage in LWA
activities after completion of a limited
environmental impact statement
addressing those activities, but before
completion of the comprehensive
environmental impact statement
addressing the underlying request for a
construction permit or combined
license. Finally, this proposed rule
would specifically address the
environmental review required in
situations where the LWA activities are
to be conducted at sites for which the
Commission has previously prepared an
environmental impact statement for the
construction and operation of a nuclear
3 Industry stakeholders did not raise issues
relating to perceived problems either with the LWA
process or, more generally, with the definition of
construction during the period leading to the March
2006 proposed rule and no such changes were
suggested in the proposed rule. Therefore, the NRC
is providing notice and an opportunity for public
comment on the changes proposed in this
supplement. The Commission may adopt this
supplemental proposed rule either as part of the
final rule promulgating the changes to Part 52 (see
71 FR 12782; March 13, 2006), or in a separate final
rule.
PO 00000
Frm 00004
Fmt 4701
Sfmt 4702
power plant, and for which a
construction permit was issued, but
construction of the plant was never
completed.
C. NRC’s Proposed Concept of
Construction and the AEA
This change is fully consistent with
the Commission’s radiological health
and safety and common defense and
security responsibilities under the
AEA.4 Specifically, the Commission has
determined that the site-preparation
activities that would no longer be
considered construction under this
proposed rule do not have a reasonable
nexus to radiological health and safety,
or the common defense and security.
Further, as previously mentioned, the
term ‘‘construction’’ is not defined in
the AEA or in the Act’s legislative
history. Instead of expressly defining
the term in the AEA, Congress entrusted
the agency with the responsibility of
determining what activities constitute
construction.5 The Commission believes
that its proposed definition of the term
‘‘construction’’ is reasonable.
D. Proposed Supplement Complies With
NEPA
1. NRC’s Proposed Concept of
Construction is Consistent with the
Legal Effect of NEPA
The proposed change in the definition
of construction is also consistent with
the legal effect of NEPA. Section
50.10(c) was originally added to part 50
due to the interpretation that the
enactment of NEPA, not a change in the
powers delegated to the agency in the
AEA, required the NRC to expand its
permitting/licensing authority.
However, subsequent judicial decisions
have made it clear that NEPA is a
procedural statute and does not expand
the jurisdiction delegated to an agency
by its organic statute.6 Therefore, while
NEPA may require the NRC to consider
the environmental effects caused by the
exercise of its permitting/licensing
authority, the statute cannot be the
source of the expansion of the NRC’s
authority to require construction
permits, combined licenses, or other
forms of permission for activities that
are not reasonably related to
radiological health and safety or
protection of the common defense and
security. Since NEPA cannot expand the
4 See State of New Hampshire v. Atomic Energy
Commission, 406 F.2d 170, 174–75 (1st Cir. 1969).
5 Shearon Harris, 7 AEC 939.
6 See, e.g., Robertson v. Methow Valley Citizens
Council, 490 U.S. 332, 350–52 (1989); Natural
Resources Defense Counsel v. U.S. Environmental
Protection Agency, 822 F.2d 104, 129 (D.C. Cir
1987); Kitchen v. Federal Communications
Commission, 464 F.2d 801, 802 (D.C. Cir. 1972).
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
pwalker on PROD1PC61 with PROPOSALS2
Commission’s permitting/licensing
authority under the AEA, the
elimination of the blanket inclusion of
site preparation activities in the
definition of construction under
§ 50.10(c) does not violate NEPA.
2. NRC’s Proposed Concept of the
‘‘Major Federal Action’’ is Consistent
with NEPA Law
Because the AEA does not authorize
NRC to require an applicant to obtain
permission before undertaking site
preparation activities that do not
implicate radiological health and safety
or common defense and security, as a
general matter the Commission
considers these activities ‘‘non-Federal
action’’ for the purposes of
implementing its NEPA responsibilities.
Generally, non-Federal actions are not
subject to the requirements of NEPA.7
Further, the Commission believes that
these non-Federal site preparation
activities would not generally be
‘‘federalized’’ if the Commission were to
ultimately grant a combined license or
construction permit. The grant of a
construction permit or combined license
by the Commission is not a legal
condition precedent to these nonFederal, site preparation activities.
While the Commission recognizes that
there may be a ‘‘but for’’ causal
relationship between certain nonFederal site preparation activities and
the major Federal action of issuing a
construction permit or combined
license, such a ‘‘but for’’ causal
relationship is not sufficient to require
non-Federal site preparation activities to
be treated as Federal action for the
purposes of NEPA.8
In addition, under the proposed
definition of construction, the
Commission does not believe that it has
sufficient ability or discretion to
influence or control the non-Federal,
site preparation activities to the extent
that its influence or control would
constitute practical or factual veto
power over the non-Federal action.
Further, the Commission does not
believe that allowing the non-Federal,
site preparation activities to be
undertaken would restrict its
consideration of alternative sites or the
need to assess whether there is an
‘‘obviously superior’’ site. Specifically,
while the Commission recognizes that
narrowing the definition of construction
may result in substantial changes to the
physical properties of a site, many of the
fundamental elements that enter into a
7 Save the Bay, Inc. v. U.S. Army Corps of
Engineers, 610 F.2d 322, 326 (5th Cir. 1980).
8 See Landmark West! v. U.S. Postal Service, 840
F.Supp. 994, 1006 (S.D.N.Y. 1993) (citing cases).
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
determination of the existence of an
‘‘obviously superior’’ site would not be
affected by the changes to those
physical properties. For example,
meteorology and seismology would not
be affected in any significant way by the
non-Federal site preparation activities.
However, while the effects caused by
the non-Federal, site preparation
activities would not be considered
effects of the Commission’s licensing
action, the effects of the non-Federal
activities would be considered during
any subsequent ‘‘cumulative impacts’’
analysis. Specifically, the effects of the
non-Federal activities would be
considered in order to establish a
baseline against which the incremental
effect of the Commission’s major
Federal action (i.e. issuing a LWA,
construction permit or combined
license) would be measured. These
incremental impacts may be additive or
synergistic.
3. NRC’s Phased Approval Approach is
not Illegal Segmentation Under NEPA
The phased application and approval
of LWAs does not raise the concerns
underlying the prohibition of
segmentation under NEPA law.
Generally, the NEPA segmentation
problem arises when the environmental
impacts of projects are evaluated in a
piecemeal fashion and, as a result, the
comprehensive environmental impacts
of the entire Federal action are never
considered or are only considered after
the agency has committed itself to
continuation of the project. Another
associated segmentation problem arises
when pieces of a Federal action are
evaluated separately and, as a result,
none of the individual pieces are
considered ‘‘major federal actions’’
requiring an EIS.9
Neither of these segmentation
concerns are presented by the approach
proposed here. First, under both LWA
application options, the environmental
effects associated with the LWA
activities and the project as a whole (i.e.
issuance of a construction permit or
combined license) would be evaluated
in an EIS. Therefore, the segmentation
problem of considering a project in
phases, thereby avoiding completion of
an EIS, is not an issue. In addition, all
of the environmental impacts associated
with the construction and operation of
the proposed plant, including the
impacts associated with the LWA
activities, would be considered together,
through incorporation by reference, in
the EIS prepared on the construction
permit or combined license application.
9 Daniel R. Mandelker, NEPA Law and Litigation,
9–25 (2nd ed. 2004).
PO 00000
Frm 00005
Fmt 4701
Sfmt 4702
61333
This comprehensive consideration of
environmental impacts would take
place before the NRC is committed to
issuing any construction permit or
combined license. The fact that the NRC
will not have prejudged the ultimate
decision of whether to grant a
construction permit or a combined
license by issuing the LWA, coupled
with the requirement that the site
redress plan be implemented in the
event that the permit or license is
ultimately not issued, also ensures that
issuance of the LWA would not
foreclose reasonable alternatives.
In addition, the proposed application
and approval process is consistent with
the Commission’s previously expressed
position that NEPA does not, as a
general matter, prohibit an agency from
undertaking part of a project without a
complete environmental analysis of the
whole project.10 The key factors used to
support the Commission’s position in
Clinch River were; (1) That the site
preparation activities in that case would
not result in irreversible or irretrievable
commitments to the remaining portions
of the project and (2) the environmental
impacts of the site preparation activities
allowed in that case were substantially
redressable.11
These considerations are reflected in
the provisions of the supplemental
proposed rule. Specifically, § 50.10(c)(6)
of the proposed rule states that any
activity undertaken pursuant to a LWA
are entirely at the risk of the applicant,
that the issuance of the LWA has no
bearing on whether the construction
permit or combined license should be
issued, and that the environmental
impact statement associated with the
underlying request will not consider the
sunk costs associated with the LWA
activities. In addition, § 50.10(c)(3)
would require an applicant requesting a
LWA to submit a plan for redress of the
site to be implemented in the event that
the LWA holder is ultimately not issued
a construction permit or combined
license. This site redress plan must
‘‘achieve an environmentally stable and
aesthetically acceptable site suitable for
whatever non-nuclear use may conform
with local zoning laws’’ in the event
that the LWA holder is not ultimately
issued a construction permit or
combined license. The redress plan
would achieve this objective by
addressing site impacts resulting from
LWA activities. Impacts associated with
pre-LWA activities would not be
addressed in the redress plan. Further,
10 See Tennessee Valley Authority (Clinch River
Breeder Reactor Plant), 16 NRC 412, 424 (Aug. 17,
1982) (hereinafter Clinch River).
11 Id.
E:\FR\FM\17OCP2.SGM
17OCP2
61334
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
§ 50.10(c)(7) would require that the site
redress plan be implemented within a
reasonable time and that the redress of
the site occur within eighteen (18)
months of the Commission’s final
decision denying a construction permit
or combined license.
It should be noted that while redress
of site impacts may have the practical
effect of mitigating some environmental
impacts, the redress plan is not a
substitute for a thorough evaluation of
environmental impacts, or development
of mitigation measures that may be
necessary to provide relief from
environmental impacts associated with
the proposed LWA activities. The
primary purpose of the site redress plan
is to ensure that impacts associated with
any LWA activities performed at the site
will not prevent the site from being
utilized for a permissible, non-nuclear
alternative use. In this way, the redress
plan helps to preserve the Commission’s
ability to objectively evaluate an
application for a construction permit or
combined license, despite the fact that
LWA activities have been undertaken at
the site.
pwalker on PROD1PC61 with PROPOSALS2
E. Inclusion of Additional Activities as
‘‘Construction’’ Under § 50.10(b)
A significant change proposed in this
supplemental proposed rule is the
inclusion of activities—such as the
driving of piles and excavation of
foundations for safety-related
structures—in the definition of
construction that are not currently
defined as construction in § 50.10(b).
Although the driving of piles was not
expressly included in the definition of
‘‘construction’’ contained in § 50.10(b)
before the amendment of § 50.10(b)(1) in
1968, this activity was generally
considered to be encompassed in the
existing definition of construction at
that time (See 33 FR 2381; January 31,
1968). The proposed rule suggesting that
the driving of piles be expressly
excluded from the definition of
construction simply states that the
‘‘activity is closely related to, and may
be appropriately included in’’ site
preparation activities, which were not
considered construction (32 FR 11278;
August 3, 1967).12 The rationale for not
including the driving of piles, and site
preparation activities generally, in the
definition of construction seems to have
been that these activities would have no
effect on the NRC’s ultimate decision to
grant or deny a construction permit and
that these activities were undertaken
12 The proposed rule language was promulgated
without modification in the final rule. 33 FR 2381.
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
entirely at the applicant’s risk (32 FR
11278).
The NRC does not currently believe
that the exclusion of a site preparation
activity from the definition of
construction should hinge on this factor.
The Commission believes that the site
preparation activities described in
§ 50.10(b) of this supplement, including
the driving of piles and excavation of
foundations in certain situations, have a
reasonable nexus to radiological health
and safety, and/or common defense and
security and, therefore, are properly
considered ‘‘construction’’ as that term
is used in § 185 of the AEA. In addition,
the inclusion of these activities in the
definition of construction (i.e. requiring
an LWA before they are undertaken),
coupled with the phased approval
process suggested in this supplemental
proposed rule, would allow for early
resolution of the safety issues associated
with these activities. Early resolution of
safety issues is consistent with the
general rationale underlying the
licensing and permitting processes
provided in 10 CFR part 52.
F. Phased Application and Approval
Process
Another significant change suggested
in this supplemental proposed rule is
the modification of the procedure for
obtaining LWA approval by
implementing an optional phased
application and approval process.
Specifically, as proposed, § 2.101(a)(9)
would allow applicants for construction
permits and combined licenses the
option of submitting either: (1) A
complete application or (2) a two part
application with part one including
information required for the NRC to
make a decision on the applicant’s
request to undertake LWA activities and
part two containing all other
information required to obtain the
underlying license or permit. The
proposed rule would allow the NRC to
consider the environmental impacts
attributable to the requested LWA
activities separately, either as part of a
comprehensive environmental impact
statement (EIS) in the case where a
complete application is submitted, or in
a separate EIS addressing only the LWA
activities in the case of a two-part
application. After consideration of the
environmental impacts and the relevant
safety-related issues associated with the
LWA activities, the NRC would be
permitted to allow the applicant to
undertake the LWA activities, even if
the EIS on the underlying request (i.e.
construction permit or combined
license) is not complete.
The NRC believes that this phased
application/approval process would add
PO 00000
Frm 00006
Fmt 4701
Sfmt 4702
efficiencies to the licensing/
construction process by preventing
unnecessary delay in construction
schedules, which would result if
issuance of an LWA for safety-related
activities were delayed until the final
environmental impact statement and
adjudicatory hearing on the entire
underlying license application were
complete. In addition, the proposed
application/approval process would
result in the timely resolution of
relevant safety and environmental
issues at an earlier stage in the licensing
process. As previously discussed, the
NRC believes that these efficiencies can
be gained without compromising the
agency’s NEPA responsibilities, as the
phased approach presented in this
supplemental proposed rule does not
constitute illegal segmentation.
G. EIS Prepared, but Facility Never
Constructed
The supplemental proposed rule also
specifically addresses the situation
where a request is made to perform
LWA activities at a site for which an EIS
has previously been prepared for the
construction and operation of a nuclear
power plant, and a construction permit
has been issued, but construction of the
plant was never completed. In this
special situation, the proposed
supplement would allow an applicant to
reference the previous EIS in its
environmental report, but requires that
the applicant identify any new and
significant information material to the
matters required to be addressed in the
proposed § 51.49(a). Further, in these
special cases the proposed supplement
would allow the NRC to incorporate the
previous EIS by reference when
preparing its draft EIS on the LWA
activities. The draft EIS on the LWA
request would be limited to the
consideration of any significant new
information dealing with the
environmental impacts of construction,
relevant to the activities to be carried
out under the LWA. Further, in a
hearing on issuance of an LWA at such
sites, the presiding officer would be
limited to determining whether there is
significant new information pertaining
to the environmental impacts of the
construction activities encompassed by
the previous EIS that are analogous to
the activities to be conducted under the
LWA. The presiding officer would
evaluate significant new information
indetermining whether an LWA should
be issued as proposed by the Director of
Nuclear Reactor Regulation.
This provision is designed to gain
efficiency by using existing
environmental impact statements to
evaluate the environmental impacts of
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
activities to be performed under an
LWA. The Commission believes that
this practice is appropriate because the
referenced environmental review will
come in the form of a FEIS prepared by
NRC staff for sites on which permission
to construct a nuclear power plant was
ultimately granted by the Commission.
The Commission understands that the
activities proposed in a current LWA
request may be different from the
activities proposed and analyzed in the
previous FEIS referenced by an
applicant and relied upon by NRC staff.
However, it is the Commission’s intent
that if such differences will likely result
in significant changes to the
environmental impacts caused by the
LWA activities currently proposed by
the applicant, then the differences
should be considered ‘‘new and
significant information’’ material to the
environmental impacts that may
reasonably be expected to result from
the LWA activities and, therefore,
should be addressed in the applicant’s
environmental report, analyzed by the
staff in a supplement to the existing
FEIS, and considered by the presiding
officer.
Further, for the reasons previously
discussed in section D.3, the
Commission does not believe that
authorizing LWA activities before
completion of the FEIS on the combined
license or construction permit would
have the effect of prejudging the license/
permit, or foreclosing reasonable
alternatives.
III. Section-by-Section Analysis
pwalker on PROD1PC61 with PROPOSALS2
Part 2
Section 2.101 Filing of Application
Section 2.101 would be revised to add
a new paragraph (a)(9), which would
state that an applicant for a construction
permit or combined license may submit
a request for an LWA either as part of
a complete application under
paragraphs (a)(1) through (4), or in two
parts under this paragraph (i.e., a
‘‘phased LWA application’’). If the LWA
application is submitted as part of a
complete construction permit or
operating license application, the
application must include the
information required by § 50.10(c).
If the application is a phased LWA
application, the first part must contain
the information required by § 50.10(c)
on the LWA, as well as the general
information required of all production
and utilization facility applicants under
§ 50.33(a) through (f). The second part of
the application would contain the
remaining information otherwise
required to be filed in a complete
application under § 2.101(a)(1) thorough
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
(4). However, the applicant would have
the further option of submitting part two
in additional subparts in accordance
with § 2.101(a–1). The second part (or
the first subpart of multiple subparts
under § 2.101(a–1)) must be filed no
later than twelve (12) months after the
filing of part one. Part two of the
application (or the first subpart of any
additional subparts submitted in
accordance with § 2.101(a–1)) must be
submitted no later that twelve (12)
months after submission of part one of
the application.
An applicant for an early site permit
may not submit its LWA application in
advance of the underlying early site
permit application, and therefore is not
permitted to use the procedures of
Subpart F.
Section 2.104
Notice of Hearing
Paragraph (d)(1)(iii) of § 2.104 would
be modified to more clearly refer to the
authority requested under § 52.17(c) as
the limited work authorization under
§ 50.10.
Subpart F
The title of Subpart F would be
revised to reflect the broader scope of
matters covered under this section, as
described under § 2.600.
Section 2.600
Scope of Subpart
The statement of scope in § 2.600
would be revised to reflect the new set
of procedures for phased LWA
applications in proposed §§ 2.641
through 2.649.
Section 2.601
Sections
Applicability of Other
Section 2.601 would be corrected to
add references to subparts C, L and N of
part 2, in order to make clear that these
subparts (in addition to subparts A and
G) apply to applications and
proceedings under subpart F, except as
specifically provided in subpart F.
Section 2.606 Partial Decision on Site
Suitability Issues
Paragraph (a) of § 2.606, which
provides that a LWA may not be issued
without completion of the ‘‘full review’’
required by NEPA, would be revised to
remove the reference to a LWA,
inasmuch as LWAs would now be
covered in §§ 2.641 through 2.649.
Section 2.641
Filing Fees
Section 2.641, which is comparable to
current § 2.602, provides that a phased
LWA application shall be accompanied
by the applicable filing fees in § 50.30(e)
and part 170 of this chapter.
PO 00000
Frm 00007
Fmt 4701
Sfmt 4702
61335
Section 2.643 Acceptance and
Docketing of Application for Limited
Work Authorization
Section 2.643, which is comparable to
current § 2.603, describes the
acceptance and docketing requirements
for phased LWA applications, and the
requirement for publication in the
Federal Register of a notice of docketing.
Paragraph (a) provides that each part of
the application, when first received,
will be treated as a tendered application
and assessed for sufficiency. If the
submitted part of the application is
determined to be incomplete, the
Director of NRR (Director) will inform
the applicant. The determination of
completeness will generally be made in
30 days, barring unusual circumstances.
Under paragraph (b), the Director will
docket part one of the application only
if that part is ‘‘complete.’’ The NRC
would use the existing guidelines and
practices for determining the
completeness of applications under this
section, as are used in determining
completeness under § 2.101. Upon
docketing, the Director will assign a
docket number that will be used
throughout the entire proceeding
(including that part of the proceeding on
part two of the application). Under
paragraph (c), the Director would make
the designated distributions to the
Governor of the state in which the
nuclear power plant will be located, and
publish a notice of docketing in the
Federal Register. Often in practice, the
notice of hearing required by the AEA
is included in the notice of docketing,
but as with existing applications, this
will remain a matter of discretion by the
NRC, who will determine what is the
most efficient course of action in this
regard.
Paragraph (d) provides that part two
of the application will be docketed, as
with part one, when it is determined to
be complete. The Commission reiterates
that ‘‘part two’’ could be submitted in
several subparts, if the applicant chose
to take advantage of the provisions of
§ 2.101(a–1), which provides for
submission of applications in three
parts.
Finally, under paragraph (e), the
Director will publish a second notice of
docketing in the Federal Register, in
this case for part two of the application.
As with the notice of docketing for part
one, the notice of docketing for part two
may also include a notice of hearing on
the second part of the application.
The Commission notes that nothing in
§ 2.101(a)(9), or any part of subpart F,
requires that the hearing on part one of
the application be completed and an
initial decision issued by the presiding
E:\FR\FM\17OCP2.SGM
17OCP2
61336
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
pwalker on PROD1PC61 with PROPOSALS2
officer, before part two of the
application is filed.
Section 2.645 Notice of Hearing
Section 2.645, which is comparable to
current § 2.604, sets forth the content of
the notice of hearing for each of the two
parts of the proceeding. Paragraph (a)
provides that the notice of hearing for
part one specify that the hearing will
relate only to consideration of the
matters related to § 50.33(a) through (f),
and the limited work authorization
issues under review. Although not
explicitly stated in this paragraph,
interested persons who seek to
intervene in the hearing on part one of
the application must file a petition to
intervene in accordance with the notice
of hearing, and § 2.309.
Under paragraph (b), a supplementary
notice of hearing will be published in
the Federal Register when part two of
the application is docketed. This
provides a second opportunity for
interested persons to file petitions to
intervene with respect to the matters
relevant to part two of the application.
These petitions must be filed within the
time period specified in the notice of
hearing, and must meet the applicable
requirements of subpart C of part 2,
including the contention requirements
in § 2.309.
Paragraph (c) of the proposed rule
differs somewhat from § 2.604, in that
the Commission proposes not to allow
a party admitted in part one of the
proceeding, who did not withdraw or
was not otherwise dismissed, to
automatically continue as a party in
phase two of the proceeding. Instead,
each party who wishes to participate in
the second phase must submit a second
petition to intervene in accordance with
§ 2.309, but the petition need not
address the interest and standing
requirements in § 2.309(d). The petition
must be filed within the time period
provided by the supplementary notice
of hearing published in the Federal
Register for part two of the application.
As noted in the section-by-section
analysis for § 2.643, nothing in
§ 2.101(a)(9) or subpart F requires that
the hearing on part one of the
application be completed and an initial
decision issued by the presiding officer,
before part two of the application is
filed. Thus, there may be simultaneous
hearings on parts one and two of the
application. However, as reflected in
paragraph (e), the Commission’s intent
is that the membership of the Atomic
Safety and Licensing Board designated
for hearings under part one be the same
as for the hearings under part two, to the
extent practical and consistent with
timely completion of each hearing.
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
Section 2.647 [Reserved]
This section is reserved for future use
by the Commission.
Section 2.649 Partial Decisions on
Limited Work Authorization
Section 2.649, which is comparable to
§ 2.606, denotes the provisions in
subparts C and G relative to issues such
as oral arguments, immediate
effectiveness of the presiding officer’s
initial decision, and petitions for
Commission review, that apply to
partial initial decisions on a LWA
rendered in accordance with this
subpart. This section also states that the
LWA may not be issued without
completion of the environmental review
required for LWAs under subpart A of
part 51. Finally, this section provides
that the time periods for the
Commission to exercise its review and
sua sponte authority are the same time
periods provided for in part 2 with
respect to a final decision on issuance
of a construction permit or combined
license.
Part 50
Section 50.10 License Required;
Limited Work Authorization
Paragraph (a). This paragraph, which
is unchanged from the current rule,
prohibits any person within the United
States from transferring or receiving in
interstate commerce, manufacturing,
producing, transferring, acquiring,
possessing, or using any production or
utilization facility except as authorized
by a license issued by the Commission,
or as provided in § 50.11.
Paragraph (b). This paragraph, which
is substantially modified from the
current rule, prohibits any person from
beginning the ‘‘construction’’ of a
production or utilization facility on a
site on which the facility is to be
operated until that person has been
issued a construction permit, a
combined license under part 52, or a
limited work authorization under
paragraph (c) of this section.
The remainder of this paragraph is
devoted to specifying what activities
are, and are not, deemed to constitute
‘‘construction’’ for purposes of this
paragraph’s prohibition. Activities, such
as site clearing, grading, site
exploration, test boring, erection of
temporary buildings and erection of
permanent structures which are not
required to be described in the site
safety analysis report, preliminary safety
analysis report, or final safety analysis
report, would not be regarded as
‘‘construction,’’ and no NRC approval
would be needed to conduct those
activities. The only work that would be
PO 00000
Frm 00008
Fmt 4701
Sfmt 4702
considered construction would be the
excavation, subsurface preparation, and
on-site, in-place fabrication, erection,
integration or testing (including the
installation of foundations) of any
structure, system or component required
by the Commission’s rules and
regulations to be described in the site
safety analysis report, preliminary safety
analysis report, or final safety analysis
report. The term, ‘‘on-site, in place,
fabrication, erection, integration or
testing’’ is intended to describe the
historical process of constructing a
nuclear power plant in its final, on-site
location, where components or modules
are integrated into the final, in-plant
location and elevation. The definition is
intended to exclude persons from
having to obtain a LWA, construction
permit, or combined license, in order to
fabricate, assemble and test components
and modules in a shop building,
warehouse, or laydown area located onsite.
Thus, the proposed redefinition of
construction for the most part returns to
the pre-1972 definition of
‘‘construction’’ in § 50.10(b), and
removes the need for NRC approval to
conduct the activities currently
described in § 50.10(e)(1), except in two
important respects. First, whereas
existing § 50.10(b) allows the driving of
piles for the facility, proposed § 50.10(b)
would not permit driving of piles for
any structure, system or component
required to be described in an SSAR,
PSAR, or FSAR unless NRC permission
is obtained in the form of a LWA,
construction permit, or combined
license. Second, existing § 50.10(e)(1)
allows a person, with NRC permission
in the form of a LWA, to excavate and
install the structural foundations for any
structure, systems and components
‘‘which do not prevent or mitigate the
consequences of postulated accidents
that could cause undue risk to the
health and safety of the public.’’ The
proposed redefinition would not remove
the need for NRC approval, but
substitutes a slightly different scope of
structures, systems and components
whose excavation and foundation
installation may be allowed under an
LWA, viz., those which are required to
be described in the FSAR.
‘‘Excavation,’’ as used in paragraph
(b), excludes initial site grading to attain
the final ground elevation, and erosion
control measures to preclude run-off, at
the location where further excavation
will be required for a structure, systems
or component required by the
Commission’s regulations to be
described in the FSAR. By contrast, the
removal of any soil, rock, gravel or other
material below the final ground
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
elevation, in preparation for the
placement of the foundation and
associated retaining walls, is excavation
that may not be performed without an
LWA, construction permit, or combined
license under part 52. The ‘‘driving of
piles’’ not related to ensuring the
structural stability or integrity of any
structure, systems or component
required by the Commission’s
regulations to be described in the FSAR
does not fall within the definition of
construction in this paragraph.
Therefore, piles driven to support the
erection of a bridge for a temporary or
permanent access road would not be
considered ‘‘construction’’ under this
section and may be performed without
a LWA, construction permit, or
combined license. ‘‘Installation of the
foundation,’’ means soil compaction;
the installation of drainage systems and
geofabric; the placement of concrete
(e.g., ‘‘mudmats’’) or other materials
which will not be removed prior to
placement of the foundation of a
structure; the placement and
compaction of a subbase; the
installation of reinforcing bars to be
incorporated into the foundation of the
structure; the erection of concrete forms
for the foundations that will remain inplace permanently (even if nonstructural); and placement of concrete or
other material constituting the
foundation of any structure, systems or
component required by the
Commission’s regulations to be
described in the FSAR. Foundation
installation activities will require a
LWA, construction permit, or combined
license.
Construction is deemed to also
include the ‘‘on-site, in-place,’’
fabrication, erection, integration or
testing activities for any structure,
system or component required by the
Commission’s regulations to be
described in the FSAR. The use of the
term, ‘‘on-site, in place,’’ is intended to
allow such structures, systems and
components, including any ‘‘modules’’
and subassemblies, to be fabricated,
assembled and tested in a shop
building, warehouse, or laydown area
located on-site without a LWA,
construction permit, or combined
license. However, the installation or
integration of that structure, system, or
component into its final location in the
reactor would require either a
construction permit or combined
license. The Commission notes that this
paragraph does not apply to
manufacturing, inasmuch as
‘‘manufacturing’’ is not ‘‘construction.’’
Moreover, paragraph (b) refers to
construction ‘‘on a site on which the
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
facility is to be operated;’’ which is not
within the scope of a ‘‘manufacturing
license’’ under subpart F of part 52.
Accordingly, manufacturing is not
covered by paragraph (b).
Paragraph (c). This paragraph, which
is substantially modified from the
current rule, addresses the need for,
nature and contents of an application
for a LWA. Paragraph (c)(1) allows the
Commission to issue an LWA in
advance of a construction permit or
combined license, authorizing the
holder to perform certain delineated
construction requirements.
Paragraph (c)(2) provides that an LWA
application may be submitted as:
—Part of a complete application for a
construction permit or combined
license under § 2.101(a)(1) through
(4).
—Part one of a phased application
under § 2.101(a)(9).
—Part of a complete application for an
early site permit under § 2.101(a)(1)
through (4).
—An amendment to an already-issued
early site permit
Paragraph (c)(3) establishes the
requirements for the content of an LWA
application. The application must
include a safety analysis report, an
environmental report, and a redress
plan. The safety analysis report, which
may be a stand-alone document or
incorporated into the construction
permit or combined license
application’s preliminary or final safety
analysis report, as applicable, must
describe the LWA activities that the
applicant seeks to perform, provide the
final design for the structures to be
constructed under the LWA and a safety
analysis for those portions of the
structure, and provide a safety analysis
of the design demonstrating that the
activities will be conducted in
accordance with applicable Commission
safety requirements.
The environmental report must meet
the requirements of 10 CFR 51.49,
which is discussed in more detail in the
section by section analysis for that
provision.
The redress plan must describe the
activities that would be implemented by
the LWA holder, should construction be
terminated by the holder, the LWA is
revoked by the NRC, or upon
effectiveness of the Commission’s final
decision denying the associated
operating license application or the
underlying combined license
application, as applicable. The primary
purpose of the redress plan is to return
the site to an environmentally stable
and aesthetically acceptable condition
that would allow the site to be utilized
PO 00000
Frm 00009
Fmt 4701
Sfmt 4702
61337
for alternative, non-nuclear uses that
conform with local zoning laws. This
will be accomplished through redress of
site impacts resulting from LWA
activities performed at the site. Redress
of site impacts resulting from pre-LWA
activities will not be required under the
redress plan. In addition, while redress
of site impacts may have the practical
effect of mitigating some environmental
impacts, the redress plan is not a
substitute for a thorough evaluation of
environmental impacts, or development
of mitigation measures that may be
necessary to provide relief from
environmental impacts associated with
the proposed LWA activities.
Paragraph (d). This paragraph, which
is substantially modified from the
current rule, generally addresses the
requirements associated with issuance
of a LWA. Paragraph (d)(1) sets forth the
requirements for the appropriate
Director to issue an LWA under this
section. The Director may issue an LWA
only after making the appropriate
findings on: (i) Necessary technical
qualifications, and the matter of foreign
ownership or control relevant to the
information required by § 50.33(a)
through (f), as mandated by sections
103.d. and 182.a. of the AEA; (ii)
making the necessary findings on public
health and safety and common defense
and security with respect to the
activities to be carried out under the
LWA; (iii) NRC staff issuance of a final
EIS on the LWA in accordance with the
applicable requirements of part 51; and
(iv) the presiding officer finding on the
environmental issues relevant to the
LWA in accordance with the applicable
requirements of part 51, and a finding
on the safety issues relevant to the
LWA.
Paragraph (d)(2) requires that the
LWA specify the activities that the
holder is authorized to perform,
consistent with the LWA application
and as modified based upon the NRC’s
review. In addition, each LWA will be
issued with a condition requiring
implementation of the redress plan if
the LWA holder terminates
construction, the LWA is revoked, or
upon effectiveness of the Commission’s
final decision denying the associated
operating license application or the
underlying combined license
application, as applicable. As discussed
in the analysis of paragraph (e), this
condition survives the merging of the
LWA into the underlying construction
permit, early site permit, or combined
license.
Paragraph (e). This paragraph, which
is substantially modified from the
current rule, addresses the legal effect of
an issued LWA. Paragraph (e)(1)
E:\FR\FM\17OCP2.SGM
17OCP2
61338
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
provides that any activities undertaken
under a limited work authorization shall
be entirely at the risk of the applicant
and, with exception of the matters
determined under paragraph (c)(4)(ii)
and (iii), the issuance of the limited
work authorization shall have no
bearing on the issuance of a
construction permit or combined license
with respect to the requirements of the
Act, and rules, regulations, or orders
promulgated pursuant thereto. Thus,
this paragraph states that the
environmental impact statement for a
construction permit or combined license
application for which a limited work
authorization was previously issued
will not address, and the presiding
officer will not consider, the sunk costs
of the holder of limited work
authorization in determining the
proposed action (i.e., issuance of the
construction permit or combined
license).
Paragraph (f). This new paragraph
would require the LWA holder to begin
implementation of the redress plan in a
reasonable time, and complete the
redress no later than eighteen (18)
months after termination of construction
by the holder, revocation of the LWA, or
upon effectiveness of the Commission’s
final decision denying the associated
operating license application or the
underlying combined license
application, as applicable.
Part 51
Section 51.4
Definitions
pwalker on PROD1PC61 with PROPOSALS2
Section 51.4 would be revised by
adding a new definition of
‘‘construction,’’ which would make
applicable throughout part 51 the
definition of construction in proposed
§ 50.10(b). This would have the effect of
excluding from an EIS for any early site
permit, construction permit, combined
license, or LWA issued under § 50.10(c),
any discussion, evaluation or
consideration of the environmental
impacts or benefits associated with nonconstruction activities as effectively
defined in § 50.10(b). This would also
remove the need for the NRC decision
maker, including a presiding officer, to
make a NEPA finding with respect to
the environmental impacts or benefits
associated with those non-construction
activities.
Section 51.17 Information collection
requirements; OMB approval
Paragraph (b) of § 51.17 of the March
2006 proposed rule would be further
modified by adding a reference to a new
§ 51.49, which requires submission of
an environmental report by LWA
applicants. While § 51.49 contains a
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
new information collection requirement,
it is not expected to result in a net
increase in the burden placed on LWA
applicants because the information
required under this new section was
formerly required to be submitted by
such applicants as part of a complete
environmental report for the underlying
construction permit or combined license
under § 51.50, or for the ESP application
(or amendment) under Part 52. The
primary effect of this supplementary
proposed rule would be to delay
submission of most of the
environmental information to the time
that the underlying construction permit
or combined license application and
environmental report is submitted.
Thus, the environmental report
submitted under § 51.49 at the LWA
stage would be limited in scope to
address environmental impacts of LWA
activities.
Section 51.20 Criteria for and
identification of licensing and
regulatory actions requiring
environmental impact statements
Section 51.20 would be revised by
adding a new paragraph (b)(6),
explicitly stating that issuance of a LWA
under § 50.10 is one of the actions
requiring the preparation of an
environmental impact statement (or a
supplement to environmental impact
statement).
Section 51.49 Environmental reportlimited work authorization
Section 51.49 is a new section that the
Commission proposes to add to part 51,
to require the applicant for an LWA to
submit an environmental report
containing certain specified
information. Both paragraph (a), which
applies to an applicant requesting a
LWA as part of a complete application,
and paragraph (b), which applies to an
applicant submitting its application in
two parts under § 2.101(a)(9), must
submit an environmental report which
describes the activities proposed to be
conducted under the LWA, the need to
conduct those activities in advance of
the main action, a description of the
environmental impacts that may
reasonably be expected to result from
the conduct of the requested activities,
the mitigation measures to be
implemented in order to achieve the
level of environmental impacts
described, and a discussion of the
reasons for rejecting other mitigation
measures that could be utilized to
further reduce environmental impacts.
Paragraph (c) describes the contents of
the environmental report when the
request for the LWA is submitted as part
of an early site permit application.
PO 00000
Frm 00010
Fmt 4701
Sfmt 4702
There is no opportunity for an early site
permit holder to submit its application
in two parts, with the LWA information
submitted in advance of the main early
site permit application.
Paragraph (d) describes the contents
of the environmental report when the
LWA request is submitted by an early
site permit holder. In this situation, the
environmental report need only contain
information on the LWA activities and
their environmental impact, and would
not include the general information
required by § 51.50(b).
Paragraph (e) establishes a limited
exception from the information required
by paragraphs (a) and (b) to be
submitted in an environmental report.
For those situations where the LWA is
to be conducted at a site: (i) For which
the Commission previously prepared an
environmental impact statement for the
construction and operation of a nuclear
power plant, (ii) the construction permit
was issued, but (iii) the construction of
the plant was never completed, then the
applicant’s environmental report may
reference the earlier environmental
impact statement. However, in the event
of such referencing, the environmental
report must identify whether there is
new and significant information relative
to the matters required to be addressed
in the environmental report with respect
to the environmental impacts of the
requested LWA activities, as specified
in paragraphs (a) or (b).
Paragraph (f) would require, for any
application containing a LWA request,
that the environmental report must
separately evaluate the environmental
impacts and proposed alternatives to the
activities proposed to be conducted
under the limited work authorization.
However, at the option of the applicant,
the environmental report may also
include the information required by
§ 51.50 to be submitted in the
environmental report for the
construction permit or combined license
application. In those situations, the
‘‘integrated’’ environmental report
would separately address the total
impacts of constructing (including the
LWA activities) and operating the
proposed facility. This will allow the
NRC to prepare in parallel the EIS for
the LWA activities and a supplemental
EIS for the underlying construction
permit or operating license, or a
complete EIS at the LWA stage.
Section 51.50 Environmental reportconstruction permit, early site permit, or
combined license stage
Section 51.50 of the March 2006
proposed rule would be modified by
deleting in its entirety, proposed
paragraph (c)(4), and revising paragraph
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
(b), to eliminate the requirements for
submission of a redress plan by an early
site permit applicant. The redress plan
would be required under
§ 50.10(c)(3)(iii).
pwalker on PROD1PC61 with PROPOSALS2
Section 51.71 Draft environmental
impact statement-contents
Section 51.71 would be modified by
redesignating the current paragraph (e)
as paragraph (f), and a new paragraph
(e) would be added to re-emphasize that
the draft environmental impact
statement for the underlying
construction permit or combined license
will not address or consider the sunk
costs associated with the LWA.
Paragraph (e) is consistent with
§§ 50.10(c)(6) and 51.71(e).
Section 51.76 Draft environmental
impact statement-limited work
authorization
Section 51.76 is a new section that the
Commission proposes to add to part 51,
governing the NRC’s preparation of a
draft environmental impact statement to
support a decision on a LWA. The
internal organization of § 51.76 parallels
that of § 51.49. Paragraph (a) addresses
the EIS to be prepared in connection
with a complete application for a
construction permit or combined
license. This section allows the NRC to
prepare either an EIS limited to LWA
activities (to be followed by a
supplemental EIS on the underlying
construction permit or combined
license), or a single, complete EIS for
the construction permit or combined
license. The Commission notes that this
paragraph addresses the situation where
the application for the construction
permit or combined license is complete
and includes the request and necessary
information for a LWA. Paragraph (b),
by contrast, addresses the situation
where the LWA request is submitted in
advance of the complete application for
the construction permit or combined
license.
Paragraph (b) applies to an EIS
prepared in support of a phased LWA
under § 2.101(a)(9). In this situation, if
the environmental report submitted in
part one is limited to the LWA
activities, then the NRC will prepare an
EIS limited to the LWA activities. Once
part two of the application is received,
which includes the environmental
report required by § 51.50, the NRC will
prepare a supplemental EIS for the
construction permit or combined license
in accordance with § 51.71, and ‘‘
51.75(a) or (c), as applicable. By
contrast, if the environmental report
submitted in part one is a complete
environmental report required by
§ 51.50, then the NRC will prepare a
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
single, complete EIS for the construction
permit or combined license in
accordance with § 51.71, and § 51.75(a)
or (c), as applicable.
Paragraph (c) applies to an EIS
prepared for issuance of an early site
permit which will also include an LWA.
The EIS will address the scope of
matters required to be addressed under
§ 51.75(d), which depends upon the
matters which the applicant chooses to
address in its environmental report, as
well as the environmental impacts of
conducting the LWA activities
requested.
Paragraph (d) addresses the situation
where an early site permit holder (as
opposed to an applicant) requests a
limited work authorization. In this
situation, siting and many of the
environmental issues have been
addressed and resolved in the EIS
supporting issuance of the ESP. This
paragraph provides for the NRC to
prepare a supplemental EIS, addressing
the impacts of conducting LWA
activities (including any new and
significant information that would
change the NRC’s prior conclusion with
respect to those construction activities
which would actually be conducted
earlier under the LWA instead of a
referencing construction permit or
combined license), and the adequacy of
the proposed redress plan. Other than
this updating, the supplemental EIS will
not present any updated information on
the matters resolved in the ESP EIS.
Paragraph (e) addresses the nature of
the EIS prepared for an LWA requested
for a site that was approved by the NRC
for a plant which was never built. In
such cases, the EIS will incorporate by
reference the earlier EIS, address
whether there is any significant new
information with respect to the
environmental impacts of construction
relevant to the scope of activities to be
performed under the LWA, and evaluate
any such information in accordance
with § 51.71 in determining if the LWA
should be issued, or issued with
appropriate conditions.
Paragraph (f) indicates that in all
cases, the EIS must separately address
the impacts of and proposed alternatives
to the activities to be conducted under
the LWA, in order to ensure that there
are specific environmental findings
addressing LWA activities for purposes
of transparency of the final NRC NEPA
findings and decision on the LWA
request.
Section 51.103 Record of decision—
general
Section 51.103 would be revised by
adding a new paragraph (a)(6), which
specifies that in a construction permit or
PO 00000
Frm 00011
Fmt 4701
Sfmt 4702
61339
combined license proceeding, where an
LWA was previously issued, the
Commission’s decision on the
construction permit or combined license
application will not address or consider
the sunk costs associated with the LWA.
This provision, which is consistent with
§§ 50.10(c)(6) and 51.71(e), is intended
to ensure that the Commission’s
decision whether to issue the
construction permit or combined license
is not biased in favor of issuance in
evaluating the environmental impacts
and benefits of the construction permit
or combined license.
Section 51.104 NRC proceedings using
public hearings, consideration of
environmental impact statements or
environmental assessment
Section 51.104 would be revised by
adding a new paragraph (c) specifying
that in an LWA proceeding, a party may
only take a position and offer evidence
on the aspects of the proposed action
within the scope of NEPA and this
subpart which are within the scope of
that party’s admitted contention. This
paragraph would also specify that the
presiding officer will decide the matters
in controversy among the parties, viz.,
the contentions related to the adequacy
of the environmental impact statement
prepared for the LWA.
Section 51.105 Public hearings in
proceedings for issuance of construction
permits or early site permits; limited
work authorizations
Section 51.105 of the March 2006
proposed rule would be modified in two
respects. The title of this section would
be modified to add a reference to LWAs,
reflecting the expanded scope of matters
addressed in this section. Second, a new
paragraph (c) would be added to specify
the determinations which must be made
by the presiding officer in an LWA
hearing associated with either a
construction permit or early site permit.
Under this new paragraph, the presiding
officer would:
—Determine whether the requirements
of section 102(2)(A), (C) and (E) of
NEPA have been met with respect to
the activities to be conducted under
the LWA.
—Independently consider the balance
among conflicting factors with respect
to the LWA.
—In an uncontested proceeding,
determine whether the NRC’s NEPA
review has been adequate.
—In a contested proceeding, determine
whether in accordance with the
regulations in subpart 51 the LWA
should be issued.
E:\FR\FM\17OCP2.SGM
17OCP2
61340
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
§ 50.10(c)(2) must be included in the
site safety analysis report.
Section 51.107 Public hearings in
proceedings for issuance of combined
licenses; limited work authorizations
Section 51.107 of the March 2006
proposed rule would be modified in two
respects. The title of this section would
be modified to add a reference to LWAs,
reflecting the expanded scope of matters
addressed in this section. A new
paragraph (d) would also be added to
specify the determinations which must
be made by the presiding officer in an
LWA hearing associated with a
combined license. This paragraph is
essentially the same as § 51.105(c).
Part 52
Section 52.1
Definitions
A new definition of limited work
authorization would be added to § 52.1
of the March 2006 proposed rule, which
would be defined as the authorization
provided under § 50.10(c). The
Commission wishes to clarify that an
applicant of an early site permit who
requests authority to perform the
activities permitted by § 50.10(c), would
not, if the request were granted, receive
a limited work authorization separate
from its early site permit. Instead, the
early site permit itself would authorize
the activities permitted by § 50.10(c).
This regulatory approach is consistent
with the current language of § 52.17(c)
and 52.25(b). However, once an ESP is
issued, the holder could apply for, and
would be issued an LWA directly under
§ 50.10(c).
Section 52.17 Contents of applications;
technical information
Paragraph (c) of § 52.17 of the March
2006 proposed rule would be modified
by removing the proposed language
with respect to limited work
authorizations, and instead specify that
if the applicant wishes to obtain an
LWA, then the information required by
Section 52.24 Issuance of early site
permit
This section would be removed from
the March 2006 proposed rule. The
requirements applicable to the holder of
an early site permit with respect to
limited work authorization activities are
set forth in proposed § 50.10(f).
chapter if a limited work authorization
is requested in conjunction with the
combined license application.
IV. Specific Request for Comments
Section 52.25 Limited Work
Authorization After Issuance of Early
Site Permit
Section 52.25 is a new section that
allows an early site permit holder to
request a LWA in accordance with
§ 50.10.
Section 52.79 Contents of Application;
Technical Information in Final Safety
Analysis Report
Section 52.79 of the March 2006
proposed rule would be modified by
removing the proposed language in
paragraph (a)(23) with respect to limited
work authorizations. Instead, this
paragraph would specify that if the
applicant wishes to obtain a LWA, then
the applicant must include the
information required by § 50.10, either
as part of a complete application under
§ 2.101(a)(1) through (4), or as a phased
application under § 2.101(a)(9).
As explained above, this
supplemental proposed rule would
impact the types of activities that could
be undertaken without prior approval
from the NRC, with NRC approval in the
form of a LWA, and with NRC approval
in the form of a construction permit or
combined license.
Therefore, in addition to the general
invitation to submit comments on the
proposed rule, the NRC also requests
comments on the following questions:
1. What types of activities should be
permitted without prior NRC approval?
2. What types of activities should be
permitted under a LWA?
3. What types of activities should only
be permitted after issuance of a
construction permit or combined
license?
V. Availability of Documents
Section 52.80 Content of Applications;
Additional Technical Information
Paragraph (c) of § 52.80(c) of the
March 2006 proposed rule would be
modified to require that a combined
license application containing a request
for a LWA must contain an
environmental report, either: (i) In
accordance with 10 CFR 51.50(c) if a
limited work authorization under 10
CFR 50.10 is not requested in
conjunction with the combined license
application; or (ii) in accordance with
§§ 51.49 and 51.50(c) of part 51 of this
The NRC is making the documents
identified below available to interested
persons through one or more of the
following methods as indicated.
Public Document Room (PDR). The
NRC Public Document Room is located
at 11555 Rockville Pike, Rockville,
Maryland.
Rulemaking Web site (Web). The
NRC’s interactive rulemaking Web site
is located at https://ruleforum.llnl.gov.
These documents may be viewed and
downloaded electronically via this Web
site.
NRC’s Public Electronic Reading
Room (EPDR). The NRC’s electronic
public reading room is located at
https://www.nrc.gov/reading-rm.html.
The NRC staff contact. Geary Mizuno,
Mail Stop O–15D21, Washington, DC
20555, 301–415–1639.
Document
PDR
Web
2006/5/25—Comment (4) submitted by Nuclear Energy Institute, Adrian P. Heymer on
Proposed Rules ..............................................................................................................
SECY–98–282, Part 52 Rulemaking Plan .........................................................................
Staff Requirements—SECY–98–282—Part 52 Rulemaking Plan .....................................
Regulatory Analysis ...........................................................................................................
X
................
................
X
X
................
................
X
pwalker on PROD1PC61 with PROPOSALS2
VI. Plain Language
The Presidential memorandum dated
June 1, 1998, entitled ‘‘Plain Language
in Government Writing’’ directed that
the Government’s writing be in plain
language. This memorandum was
published on June 10, 1998 (63 FR
31883). In complying with this
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
directive, the NRC made editorial
changes to improve the organization and
readability of the existing language of
the paragraphs being revised. These
types of changes are not discussed
further in this document. The NRC
requests comments on this proposed
rule specifically with respect to the
clarity and effectiveness of the language
PO 00000
Frm 00012
Fmt 4701
Sfmt 4702
EPDR
ML061510471
ML032801416
ML032801439
ML062750434
NRC
Staff
................
................
................
X
used. Comments should be submitted
using one of the methods described
under the ADDRESSES heading of the
preamble to this proposed rule.
VII. Agreement State Compatibility
Under the ‘‘Policy Statement on
Adequacy and Compatibility of
Agreement States Programs,’’ approved
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
by the Commission on June 20, 1997,
and published in the Federal Register
(62 FR 46517; September 3, 1997), this
rule is classified as compatibility ‘‘NRC’’
regulations. The NRC program elements
in this category are those that relate
directly to areas of regulation reserved
to the NRC by the AEA or provisions of
Title 10 of the Code of Federal
Regulations, and although an Agreement
State may not adopt program elements
reserved to NRC, it may wish to inform
its licensees of certain requirements via
a mechanism that is consistent with the
particular State’s administrative
procedure laws, but does not confer
regulatory authority on the State.
pwalker on PROD1PC61 with PROPOSALS2
VIII. Voluntary Consensus Standards
(Public Law 104)
The National Technology Transfer
and Advancement Act of 1995, Public
Law 104–113, requires that Federal
agencies use technical standards that are
developed or adopted by voluntary
consensus standards bodies unless
using such a standard is inconsistent
with applicable law or is otherwise
impractical. In this rule, the NRC is
proposing to: (i) Redefine the scope of
activities constituting ‘‘construction’’ for
which NRC approval is required; (ii)
redefine the scope of activities
constituting construction which the
NRC may approve in a limited work
authorization granted in advance of the
issuance of a construction permit or
combined license, or which may be
conducted by a holder of an early site
permit; and (iii) revise the NRC’s
procedures for granting limited work
authorizations. This rulemaking does
not establish standards or substantive
requirements with which all applicants
and licensees must comply. For the
reasons set forth in the preamble and
under the authority of the Atomic
Energy Act of 1954, as amended; the
Energy Reorganization Act of 1974, as
amended; and 5 U.S.C. 552 and 553, the
NRC is adopting the following
amendments to 10 CFR parts 2, 50, 51
and 52.
IX. Environmental Impact—Categorical
Exclusion
The NRC has determined that the
changes made in this rule fall within the
types of actions described in categorical
exclusions described in 10 CFR
51.22(c)(1) and (c)(3). Specifically, the
conforming changes made to 10 CFR
part 2 would qualify for the categorical
exclusion described in § 51.22(c)(1). The
changes to parts 50, 51 and 52 that
describe procedures for filing and
reviewing applications for limited work
authorizations would qualify for the
categorical exclusion described in
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
§ 51.22(c)(3)(i). All other changes would
qualify for the categorical exemption
described in § 51.22(c)(3)(iv).13
Therefore, neither an environmental
impact statement nor an environmental
assessment has been prepared for this
regulation.
X. Paperwork Reduction Act Statement
The proposed rule published on
March 13, 2006 imposed new or
amended information collection
requirements contained in 10 CFR parts
21, 25, 50, 52, and 54 that are subject
to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.). These new and
amended information collection
requirements were submitted to the
Office of Management and Budget for
review and approval. The existing
requirements were approved by the
Office of Management and Budget,
approval numbers 3150–0044, 3150–
0014, 3150–0146, 3150–0018, 3150–
0132, 3150–0002, 3150–0055, 3150–
0047, and 3150–0039.
This supplement would reduce the
proposed rule burden by eliminating the
requirement to obtain NRC permission
to engage in site preparation activities
that do not have a direct impact on
radiological health and safety or
common defense and security at sites
where new nuclear power plants are to
be constructed. Specifically, the burden
associated with the preparation of
applications for permission to engage in
these activities, as well as the burden of
responding to requests for additional
information associated with these
applications, would be eliminated by
the supplement. The burden reduction
for information collections contained in
10 CFR part 52 (OMB approval number
3150–0151), is estimated to be 50 hours
per application. The burden reduction
associated with this proposed rule
supplement will be included in the
revised OMB clearance package
prepared for the final rule.
13 Although the industry’s request came in the
form of a comment on the proposed Part 52 rule (71
FR 12782; March 13, 2006), the comment letter
stated; ‘‘To the extent the NRC determines that
these LWA issues cannot be addressed in the
current rulemaking, we ask that the Commission
initiate an expedited rulemaking.’’ The NRC has
determined that the changes suggested by the
industry in Comment 4 (docketed on May 30, 2006,
4:50 PM) could not be incorporated into the final
Part 52 rule without re-noticing. Therefore, the
Commission has decided to treat the comments
submitted by the industry as a petition for
expedited rulemaking and is publishing this
supplemental proposed rule for public comment.
The NRC has determined that Comment 4 meets the
sufficiency requirements described in 10 CFR
2.802(c) and that it is appropriate to seek public
comment on the petition by publishing this
proposed rule developed in response to the
petition, as allowed under 10 CFR 2.802(e).
PO 00000
Frm 00013
Fmt 4701
Sfmt 4702
61341
This supplement also contains a new
information collection requirement in
§ 51.49, however this new information
collection is not expected to result in a
net increase in the burden for LWA
applicants because the information to be
submitted under this new requirement
was formerly submitted by such
applicants as part of a complete
environmental report for the underlying
construction permit or combined license
under § 51.50, or for the ESP application
(or amendment) under part 52. The
primary effect of the new information
collection requirement in part 51 of the
supplemental proposed rule would be to
delay submission of most of the
environmental information to the time
that the underlying construction permit
or combined license application and
environmental report is submitted.
Thus, changes in burden for information
collections contained in 10 CFR part 51
(OMB approval number 3150–0021) are
expected to be minimal.
The U.S. Nuclear Regulatory
Commission is seeking public comment
on the potential impact of the
information collections contained in the
proposed rule supplement and on the
following issues:
1. Is the proposed information
collection necessary for the proper
performance of the functions of the
NRC, including whether the information
will have practical utility?
2. Is the estimate of burden accurate?
3. Is there a way to enhance the
quality, utility, and clarity of the
information to be collected?
4. How can the burden of the
information collection be minimized,
including the use of automated
collection techniques?
Send comments on any aspect of this
proposed information collection,
including suggestions for reducing the
burden and on the above issues, by
December 18, 2006 to the Records and
FOIA/Privacy Services Branch (T–5
F52), U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, or by Internet electronic mail to
INFOCOLLECTS@NRC.GOV and to the
Desk Officer, John A. Asalone, Office of
Information and Regulatory Affairs,
NEOB–10202, (3150–0021, 3150–0151),
Office of Management and Budget,
Washington, DC 20503. Comments
received after this date will be
considered if it is practical to do so, but
assurance of consideration cannot be
given to comments received after this
date. You may also e-mail comments to
John_A._Asalone@omb.eop.gov or
comment by telephone at (202) 395–
4650.
E:\FR\FM\17OCP2.SGM
17OCP2
61342
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
Public Protection Notification
List of Subjects
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a request for information or an
information collection requirement
unless the requesting document
displays a currently valid OMB control
number.
10 CFR Part 2
Administrative practice and
procedure, Antitrust, Byproduct
material, Classified information,
Environmental protection, Nuclear
materials, Nuclear power plants and
reactors, Penalties, Sex discrimination,
Source material, Special nuclear
material, Waste treatment and disposal.
XI. Regulatory Analysis
The commission has prepared a draft
regulatory analysis on this proposed
regulation. The analysis examines the
costs and benefits of the alternatives
considered by the Commission. The
Commission requests public comment
on the draft regulatory analysis.
Availability of the regulatory analysis is
provided in Section V. Comments on
the draft analysis may be submitted to
the NRC as indicated under the
ADDRESSES heading.
XII. Regulatory Flexibility Act
Certification
In accordance with the Regulatory
Flexibility Act (5 U.S.C. 605(b)), the
Commission certifies that this rule will
not, if promulgated, have a significant
economic impact on a substantial
number of small entities. This proposed
rule affects only the licensing of nuclear
power plants. The companies that will
apply for an approval, certification,
permit, site report, or license in
accordance with the regulations affected
by this proposed rule do not fall within
the scope of the definition of ‘‘small
entities’’ set forth in the Regulatory
Flexibility Act or the size standards
established by the NRC (10 CFR 2.810).
pwalker on PROD1PC61 with PROPOSALS2
XIII. Backfit Analysis
The NRC has determined that the
backfit rule does not apply to this
proposed rule and, therefore, a backfit
analysis is not required, because the
proposed rule does not contain any
provisions that would impose
backfitting as defined in the backfit rule,
10 CFR 50.109.
There are no current holders of early
site permits, construction permits, or
combined licenses for nuclear power
plants that would be protected by the
backfitting restrictions in § 50.109. To
the extent that the proposed rule would
revise the requirements for future early
site permits, construction permits, or
combined licenses for nuclear power
plants, these revisions would not
constitute backfits because they are
prospective in nature and the backfit
rule was not intended to apply to every
NRC action which substantially changes
the expectations of future applicants.
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
10 CFR Part 50
Antitrust, Classified information,
Criminal penalties, Emergency
Planning, Fire protection,
Intergovernmental relations, Nuclear
power plants and reactors, Radiation
protection, Reactor siting criteria,
Reporting and recordkeeping
requirements.
10 CFR Part 51
Administrative practice and
procedure, Environmental impact
statement, Nuclear materials, Nuclear
power plants and reactors, Reporting
and recordkeeping requirements.
10 CFR Part 52
Administrative practice and
procedure, Antitrust, Backfitting,
Combined license, Early site permit,
Emergency planning, Fees, Inspection,
Limited work authorization, Nuclear
power plants and reactors, Probabilistic
risk assessment, Prototype, Reactor
siting criteria, Redress of site, Reporting
and recordkeeping requirements,
Standard design, Standard design
certification.
For the reasons set forth in the
preamble and under the authority of the
Atomic Energy Act of 1954, as amended,
the Energy Reorganization Act of 1974,
as amended, and 5 U.S.C. 553, the NRC
is proposing to adopt the following
amendments to 10 CFR parts 2, 50, 51
and 52.
PART 2—RULES OF PRACTICE FOR
DOMESTIC LICENSING PROCEEDINGS
AND ISSUANCE OF ORDERS
1. The authority citation for part 2
continues to read as follows:
Authority: Secs. 161, 181, 68 Stat. 948,
953, as amended (42 U.S.C. 2201, 2231); sec.
191, as amended, Pub. L. 87–615, 76 Stat. 409
(42 U.S.C. 2241); sec. 201, 88 Stat. 1242, as
amended (42 U.S.C. 5841); 5 U.S.C. 552; sec.
1704, 112 Stat. 2750 (44 U.S.C. 3504 note).
Section 2.101 also issued under secs. 53, 62,
63, 81, 103, 104, 105, 68 Stat. 930, 932, 933,
935, 936, 937, 938, as amended (42 U.S.C.
2073, 2092, 2093, 2111, 2133, 2134, 2135);
sec. 114(f), Pub. L. 97–425, 96 Stat. 2213, as
amended (42 U.S.C. 10143(f)), sec. 102, Pub.
L. 91–190, 83 Stat. 853, as amended (42
U.S.C. 4332); sec. 301, 88 Stat. 1248 (42
U.S.C. 5871). Sections 2.102, 2.103, 2.104,
PO 00000
Frm 00014
Fmt 4701
Sfmt 4702
2.105, 2.721 also issued under secs. 102, 103,
104, 105, 183i, 189, 68 Stat. 936, 937, 938,
954, 955, as amended (42 U.S.C. 2132, 2133,
2134, 2135, 2233, 2239). Sections 2.105 also
issued under Pub. L. 97–415, 96 Stat. 2073
(42 U.S.C. 2239). Sections 2.200–2.206 also
issued under secs. 161 b, I, o, 182, 186, 234,
68 Stat. 948–951, 955, 83 Stat. 444, as
amended (42 U.S.C. 2201 (b), (I), (o), 2236,
2282); sec. 206, 88 Stat. 1246 (42 U.S.C.
5846). Section 2.205(j) also issued under Pub.
L. 101–410, 104 Stat. 90, as amended by
section 3100(s), Pub. L. 104–134, 110 Stat.
1321–373 (28 U.S.C. 2461 note). Sections
2.600–2.606 also issued under sec. 102, Pub.
L. 91–190, 83 Stat. 853, as amended (42
U.S.C. 4332). Sections 2.700a, 2.719 also
issued under 5 U.S.C. 554. Sections 2.754,
2.760, 2.770, 2.780 also issued under 5 U.S.C.
557. Section 2.764 also issued under secs.
135, 141, Pub. L. 97–425, 96 Stat. 2232, 2241
(42 U.S.C. 10155, 10161). Section 2.790 also
issued under sec. 103, 68 Stat. 936, as
amended (42 U.S.C. 2133), and 5 U.S.C. 552.
Sections 2.800 and 2.808 also issued under
5 U.S.C. 553. Section 2.809 also issued under
5 U.S.C. 553, and sec. 29, Pub. L. 85–256, 71
Stat. 579, as amended (42 U.S.C. 2039).
Subpart K also issued under sec. 189, 68 Stat.
955 (42 U.S.C. 2239); sec. 134, Pub. L. 97–
425, 96 Stat. 2230 (42 U.S.C. 10154). Subpart
L also issued under sec. 189, 68 Stat. 955 (42
U.S.C. 2239). Subpart M also issued under
sec. 184 (42 U.S.C. 2234) and sec. 189, 68
Stat. 955 (42 U.S.C. 2239). Appendix A also
issued under sec. 6, Pub. L. 91–560, 84 Stat.
1473 (42 U.S.C. 2135).
2. In § 2.101, paragraphs (a)(1) and
(a)(2) are revised, the introductory text
of paragraph (a)(3) is revised, paragraph
(a)(3)(ii) is revised, paragraph (a)(4) is
revised, paragraphs (a)(6) through (a)(8)
are added and reserved, and a paragraph
(a)(9) is added to read as follows:
§ 2.101
Filing of application.
(a)(1) An application for a permit, a
license, a license transfer, a license
amendment, a license renewal, and a
standard design approval, shall be filed
with the Director of Nuclear Reactor
Regulation or Director of Nuclear
Material Safety and Safeguards, as
prescribed by the applicable provisions
of this chapter. A prospective applicant
may confer informally with the NRC
staff before filing an application.
(2) Each application for a license for
a facility or for receipt of waste
radioactive material from other persons
for the purpose of commercial disposal
by the waste disposal licensee will be
assigned a docket number. However, to
allow a determination as to whether an
application for a construction permit,
operating license, early site permit,
standard design approval, combined
license, or manufacturing license for a
production or utilization facility is
complete and acceptable for docketing,
it will be initially treated as a tendered
application. A copy of the tendered
application will be available for public
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
inspection at the NRC Web site,
https://www.nrc.gov, and/or at the NRC
Public Document Room. Generally, the
determination on acceptability for
docketing will be made within a period
of 30 days. However, in selected
applications, the Commission may
decide to determine acceptability based
on the technical adequacy of the
application as well as its completeness.
In these cases, the Commission, under
§ 2.104(a), will direct that the notice of
hearing be issued as soon as practicable
after the application has been tendered,
and the determination of acceptability
will be made generally within a period
of 60 days. For docketing and other
requirements for applications under part
61 of this chapter, see paragraph (g) of
this section.
(3) If the Director of Nuclear Reactor
Regulation or Director of Nuclear
Material Safety and Safeguards, as
appropriate, determines that a tendered
application for a construction permit,
operating license, early site permit,
standard design approval, combined
license, or manufacturing license for a
production or utilization facility, and/or
any environmental report required
under subpart A of part 51 of this
chapter, or part thereof as provided in
paragraphs (a)(5) or (a–1) of this section
are complete and acceptable for
docketing, a docket number will be
assigned to the application or part
thereof, and the applicant will be
notified of the determination. With
respect to the tendered application and/
or environmental report or part thereof
that is acceptable for docketing, the
applicant will be requested to:
*
*
*
*
*
(ii) Serve a copy on the chief
executive of the municipality in which
the facility or site which is the subject
of an early site permit is to be located
or, if the facility or site which is the
subject of an early site permit is not to
be located within a municipality, on the
chief executive of the county, and serve
a notice of availability of the application
or environmental report on the chief
executives of the municipalities or
counties which have been identified in
the application or environmental report
as the location of all or part of the
alternative sites, containing the
following information, as applicable:
Docket number of the application, a
brief description of the proposed site
and facility; the location of the site and
facility as primarily proposed and
alternatively listed; the name, address,
telephone number, and e-mail address
(if available) of the applicant’s
representative who may be contacted for
further information; notification that a
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
draft environmental impact statement
will be issued by the Commission and
will be made available upon request to
the Commission; and notification that if
a request is received from the
appropriate chief executive, the
applicant will transmit a copy of the
application and environmental report,
and any changes to these documents
which affect the alternative site
location, to the executive who makes
the request. In complying with the
requirements of this paragraph, the
applicant should not make public
distribution of those parts of the
application subject to § 2.390(d). The
applicant shall submit to the Director of
Nuclear Reactor Regulation an affidavit
that service of the notice of availability
of the application or environmental
report has been completed along with a
list of names and addresses of those
executives upon whom the notice was
served; and
*
*
*
*
*
(4) The tendered application for a
construction permit, operating license,
early site permit, standard design
approval, combined license, or
manufacturing license will be formally
docketed upon receipt by the Director of
Nuclear Reactor Regulation or Director
of Nuclear Material Safety and
Safeguards, as appropriate, of the
required additional copies. Distribution
of the additional copies shall be deemed
to be complete as of the time the copies
are deposited in the mail or with a
carrier prepaid for delivery to the
designated addresses. The date of
docketing shall be the date when the
required copies are received by the
Director of Nuclear Reactor Regulation
or Director of Nuclear Material Safety
and Safeguards, as appropriate. Within
10 days after docketing, the applicant
shall submit to the Director of Nuclear
Reactor Regulation or Director of
Nuclear Material Safety and Safeguards,
as appropriate, an affidavit that
distribution of the additional copies to
Federal, State, and local officials has
been completed in accordance with the
requirements of this chapter and written
instructions furnished to the applicant
by the Director of Nuclear Reactor
Regulation or Director of Nuclear
Material Safety and Safeguards, as
appropriate. Amendments to the
application and environmental report
shall be filed and distributed and an
affidavit shall be furnished to the
Director of Nuclear Reactor Regulation
or Director of Nuclear Material Safety
and Safeguards, as appropriate, in the
same manner as for the initial
application and environmental report. If
it is determined that all or any part of
PO 00000
Frm 00015
Fmt 4701
Sfmt 4702
61343
the tendered application and/or
environmental report is incomplete and
therefore not acceptable for processing,
the applicant will be informed of this
determination, and the respects in
which the document is deficient.
*
*
*
*
*
(6)–(8) Reserved.
(9) Limited work authorization. An
applicant for a construction permit for
a utilization facility which is subject to
§ 51.20(b) of this chapter and is of the
type specified in § 50.21(b)(2) or (3) or
§ 50.22 of this chapter, an applicant for
or holder of an early site permit under
part 52 of this chapter, or an applicant
for a combined license under part 52 of
this chapter, who seeks to conduct the
activities authorized under § 50.10(c) of
this chapter may submit a complete
application under paragraphs (a)(1)–(4)
of this section which includes the
information required by § 50.10(c) of
this chapter. Alternatively, the applicant
(other than a holder of an early site
permit) may submit its application in
two parts:
(i) Part one must include the
information required by § 50.33(a)
through (f) of this chapter, and the
information required by § 50.10(c)(2)
and (3) of this chapter.
(ii) Part two must include the
remaining information required by the
Commission’s regulations in this
chapter which was not submitted in part
one, provided, however, that this
information may be submitted in
accordance with the applicable
provisions of paragraph (a–1) of this
section.
(iii) Part two of the application must
be submitted no later than twelve (12)
months after submission of part one.
*
*
*
*
*
3. In § 2.104, the introductory text of
paragraph (a) is revised, current
paragraphs (d) and (e) are redesignated
as paragraphs (l) and (m), respectively,
and revised, new paragraphs (d), (e),
and (f) are added, and paragraphs (g)
through (k) are added and reserved, and
footnote 1 is revised to read as follows:
§ 2.104
Notice of hearing.
(a) In the case of an application on
which a hearing is required by the Act
or this chapter, or in which the
Commission finds that a hearing is
required in the public interest, the
Secretary will issue a notice of hearing
to be published in the Federal Register
as required by law at least 15 days, and
in the case of an application concerning
a construction permit, early site permit,
or combined license for a facility of the
type described in § 50.21(b) or § 50.22 of
this chapter or a testing facility, at least
E:\FR\FM\17OCP2.SGM
17OCP2
61344
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
pwalker on PROD1PC61 with PROPOSALS2
30 days, before the date set for hearing
in the notice.1 In addition, in the case
of an application for an early site
permit, construction permit or
combined license for a facility of the
type described in § 50.22 of this chapter,
or a testing facility, the notice (other
than a notice under paragraph (d) of this
section) must be issued as soon as
practicable after the application has
been docketed. However, if the
Commission, under § 2.101(a)(2),
decides to determine the acceptability of
the application based on its technical
adequacy as well as completeness, the
notice must be issued as soon as
practicable after the application has
been tendered. The notice will state:
*
*
*
*
*
(d) In the case of an application for an
early site permit under subpart A of part
52 of this chapter, the notice of hearing
will state, in implementation of
paragraph (a)(3) of this section:
(1) If the proceeding is a contested
proceeding, the presiding officer will
consider the following issues:
(i) Whether applicable standards and
requirements of the Act and the
Commission’s regulations have been
met;
(ii) Whether any required
notifications to other agencies or bodies
have been duly made;
(iii) If the applicant requests, under
§ 52.17(c) of this chapter, a limited work
authorization under § 50.10 of this
chapter, whether there is reasonable
assurance that the proposed site is a
suitable location for a reactor of the
general size and type described in the
application from the standpoint of
radiological health and safety
considerations under the Act and
regulations issued by the Commission;
(iv) Whether there is reasonable
assurance that the site is in conformity
with the provisions of the Act, and the
Commission’s regulations;
(v) Whether the applicant is
technically qualified to engage in any
activities authorized;
(vi) Whether the proposed
inspections, tests, analyses and
acceptance criteria, including any on
emergency planning, are necessary and
sufficient within the scope of the early
1 If the notice of hearing concerning an
application for a construction permit, early site
permit, or combined license for a facility of the type
described in § 50.21(b) or § 50.22 of this chapter or
a testing facility does not specify the time and place
of initial hearing, a subsequent notice will be
published in the Federal Register which will
provide at least 30 days notice of the time and place
of that hearing. After this notice is given the
presiding officer may reschedule the
commencement of the initial hearing for a later date
or reconvene a recessed hearing without again
providing at least 30 days notice.
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
site permit to provide reasonable
assurance that the facility has been
constructed and will be operated in
conformity with the license, the
provisions of the Act, and the
Commission’s regulations;
(vii) Whether issuance of the early site
permit will be inimical to the common
defense and security or to the health
and safety of the public; and
(viii) Whether, in accordance with the
requirements of subpart A of part 52 of
this chapter and subpart A of part 51 of
this chapter, the early site permit should
be issued as proposed.
(2) If the proceeding is not a contested
proceeding, the presiding officer will
determine, without conducting a de
novo evaluation of the application,
whether:
(i) The application and the record of
the proceeding contain sufficient
information, and the review of the
application by the NRC staff has been
adequate to support affirmative findings
on paragraphs (d)(1)(i) through (v) and
(viii) of this section, and a negative
finding on paragraph (d)(1)(vii) of this
section; and
(ii) The review conducted under part
51 of this chapter under the National
Environmental Policy Act (NEPA) has
been adequate.
(3) Regardless of whether the
proceeding is contested or uncontested,
the presiding officer will, in accordance
with subpart A of part 51 of this
chapter:
(i) Determine whether the
requirements of section 102(2) (A), (C),
and (E) of the NEPA and subpart A of
part 51 of this chapter have been
complied with in the proceeding;
(ii) Independently consider the final
balance among conflicting factors
contained in the record of the
proceeding with a view to determine the
appropriate action to be taken; and
(iii) If the applicant requests
authorization to perform the activities
under § 52.17(c) of this chapter, whether
there is reasonable assurance that the
proposed site is a suitable location for
a reactor of the general size and type
described in the application from the
standpoint of radiological health and
safety considerations under the Act and
regulations issued by the Commission.
(iv) Determine whether the combined
license should be issued, denied or
appropriately conditioned to protect
environmental values.
(e) In the case of an application for a
combined license under subpart C of
part 52 of this chapter, the notice of
hearing will state, in implementation of
paragraph (a)(3) of this section:
PO 00000
Frm 00016
Fmt 4701
Sfmt 4702
(1) If the proceeding is a contested
proceeding, the presiding officer will
consider the following issues:
(i) Whether applicable standards and
requirements of the Act and the
Commission’s regulations have been
met;
(ii) Whether any required
notifications to other agencies or bodies
have been duly made;
(iii) Whether there is reasonable
assurance that the facility will be
constructed and will operate in
conformity with the license, the
provisions of the Act, and the
Commission’s regulations;
(iv) Whether the applicant is
technically and financially qualified to
engage in the activities authorized;
(v) Whether the proposed inspections,
tests, analyses, and acceptance criteria,
including those applicable to emergency
planning, are necessary and sufficient to
provide reasonable assurance that the
facility has been constructed and will be
operated in conformity with the license,
the provisions of the Act, and the
Commission’s regulations;
(vi) Whether any inspections, tests, or
analyses have been successfully
completed and the acceptance criteria in
a referenced early site permit, standard
design certification or for a
manufactured reactor have been met,
but only to the extent that the combined
license application represents that those
inspections, tests and analyses have
been successfully completed and the
acceptance criteria have been met;
(vii) Whether the issuance of the
combined license will be inimical to the
common defense and security or to the
health and safety of the public; and
(viii) Whether, in accordance with the
requirements of subpart C of part 52 of
this chapter and subpart A of part 51 of
this chapter, the combined license
should be issued as proposed.
(2) If the proceeding is not a contested
proceeding, the presiding officer will
determine, without conducting a de
novo evaluation of the application, if:
(i) The application and the record of
the proceeding contain sufficient
information, and the review of the
application by the NRC staff has been
adequate to support affirmative findings
on paragraphs (e)(1)(i) through (vii) and
(e)(1)(ix) of this section, and a negative
finding on paragraph (e)(1)(viii) of this
section; and
(ii) The review conducted under part
51 of this chapter under NEPA has been
adequate.
(3) Regardless of whether the
proceeding is contested or uncontested,
the presiding officer will, in accordance
with subpart A of part 51 of this
chapter:
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
(i) Determine whether the
requirements of section 102(2) (A), (C),
and (E) of the NEPA and subpart A of
part 51 of this chapter have been
complied with in the proceeding;
(ii) Independently consider the final
balance among conflicting factors
contained in the record of the
proceeding with a view to determine the
appropriate action to be taken; and
(iii) Determine whether the combined
license should be issued, denied or
appropriately conditioned to protect
environmental values.
(f) In the case of an application for a
manufacturing license under subpart F
of part 52 of this chapter, the issues
stated in the notice of hearing under
paragraph (a)(3) of this section will not
involve consideration of the particular
sites at which any of the nuclear power
reactors to be manufactured may be
located and operated. Unless the
Commission determines otherwise, the
notice of hearing will state:
(1) If the proceeding is a contested
proceeding, the presiding officer will
consider the following issues:
(i) Whether applicable standards and
requirements of the Act and the
Commission’s regulations have been
met;
(ii) Whether there is reasonable
assurance that the reactor(s) will be
manufactured, and can be transported,
incorporated into a nuclear power plant,
and operated in conformity with the
manufacturing license, the provisions of
the Act, and the Commission’s
regulations;
(iii) Whether the proposed reactor(s)
to be manufactured can be incorporated
into a nuclear power plant at sites
having characteristics that fall within
the site parameters postulated for the
design of the manufactured reactor(s)
without undue risk to the health and
safety of the public;
(iv) Whether the applicant is
technically qualified to design and
manufacture the proposed nuclear
power reactor(s);
(v) Whether the proposed inspections,
tests, analyses, and acceptance criteria
are necessary and sufficient, within the
scope of the manufacturing license, to
provide reasonable assurance that the
reactor has been manufactured and will
be operated in conformity with the
license, the provisions of the Act, and
the Commission’s regulations;
(vi) Whether the issuance of a license
for manufacture of the reactor(s) will be
inimical to the common defense and
security or to the health and safety of
the public; and
(vii) Whether, in accordance with the
requirements of subpart F of part 52 and
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
subpart A of part 51 of this chapter, the
license should be issued as proposed.
(2) If the proceeding is not a contested
proceeding, the presiding officer will
determine, without conducting a de
novo evaluation of the application,
whether:
(i) The application and the record of
the proceeding contain sufficient
information, and the review of the
application by the NRC staff has been
adequate to support affirmative findings
on paragraphs (f)(1)(i) through (v) and
(f)(1)(vii) of this section proposed to be
made and a negative finding on
paragraph (f)(1)(vi) of this section; and
(ii) The review conducted under part
51 of this chapter under NEPA has been
adequate.
(3) Regardless of whether the
proceeding is contested or uncontested,
the presiding officer will, in accordance
with subpart A of part 51 of this
chapter:
(i) Determine whether the
requirements of section 102(2) (A), (C),
and (E) of the National Environmental
Policy Act and subpart A of part 51 of
this chapter have been complied with in
the proceeding;
(ii) Independently consider the final
balance among conflicting factors
contained in the record of the
proceeding with a view to determine the
appropriate action to be taken; and
(iii) Determine whether the
manufacturing license should be issued,
denied or appropriately conditioned to
protect environmental values.
(4) The place of hearing on an
application for a manufacturing license
will be Rockville, Maryland, or such
other location as the Commission deems
appropriate.
(g)–(k) Reserved
(l) In an application for a construction
permit or an operating license for a
facility on which a hearing is required
by the Act or this chapter, the notice of
hearing will, unless the Commission
determines otherwise, state:
(1) A time of the hearing, which will
be as soon as practicable after
compliance with section 189a of the Act
and this part;
(2) The presiding officer for the
hearing who shall be either an
administrative law judge or an atomic
safety and licensing board established
by the Commission or by the Chief
Administrative Judge of the Atomic
Safety and Licensing Board Panel; and
(3) That matters of radiological health
and safety and common defense and
security, and matters raised under
NEPA, will be considered at another
hearing if otherwise required or ordered
to be held, for which a notice will be
published under paragraphs (a) and (b)
PO 00000
Frm 00017
Fmt 4701
Sfmt 4702
61345
of this section, unless otherwise
authorized by the Commission.
(m)(1) The Secretary will transmit a
notice of hearing on an application for
a license for a production or utilization
facility including an early site permit,
combined license (but not for a
manufacturing license), for a license for
receipt of waste radioactive material
from other persons for the purpose of
commercial disposal by the waste
disposal licensee, for a license under
part 61 of this chapter, for a
construction authorization for a HLW
repository at a geologic repository
operations area under parts 60 or 63 of
this chapter, for a license to receive and
possess high-level radioactive waste at a
geologic repository operations area
under parts 60 or 63 of this chapter, and
for a license under part 72 of this
chapter to acquire, receive or possess
spent fuel for the purpose of storage in
an independent spent fuel storage
installation (ISFSI) to the governor or
other appropriate official of the State
and to the chief executive of the
municipality in which the facility is to
be located or the activity is to be
conducted or, if the facility is not to be
located or the activity conducted within
a municipality, to the chief executive of
the county (or to the Tribal organization,
if it is to be located or conducted within
an Indian reservation).
(2) The Secretary will transmit a
notice of opportunity for hearing under
§ 52.103 of this chapter on whether the
facility as constructed complies, or on
completion will comply, with the
acceptance criteria in the combined
license, except for those ITAAC that the
Commission found were met under
§ 52.97 of this chapter, to the governor
or other appropriate official of the State
and to the chief executive of the
municipality in which the facility is to
be located or the activity is to be
conducted or, if the facility is not to be
located or the activity conducted within
a municipality, to the chief executive of
the county (or to the Tribal organization,
if it is to be located or conducted within
an Indian reservation).
(3) The Secretary will transmit a
notice of hearing on an application for
a license under part 72 of this chapter
to acquire, receive or possess spent fuel,
high-level radioactive waste or
radioactive material associated with
high-level radioactive waste for the
purpose of storage in a monitored
retrievable storage installation (MRS) to
the same persons who received the
notice of docketing under § 72.16(e) of
this chapter.
4. The heading of subpart F is revised
to read as follows:
E:\FR\FM\17OCP2.SGM
17OCP2
61346
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
Subpart F—Additional Procedures
Applicable to Early Partial Decisions
on Site Suitability Issues in
Connection With an Application for a
Construction Permit or Combined
License To Construct Certain
Utilization Facilities; and Advance
Issuance of Limited Work
Authorizations
5. Section 2.600 is revised to read as
follows:
§ 2.600
Scope of Subpart.
This subpart prescribes procedures
applicable to licensing proceedings
which involve an early submittal of site
suitability information in accordance
with § 2.101(a–1), and a hearing and
early partial decision on issues of site
suitability, in connection with an
application for a permit to construct a
utilization facility which is subject to
§ 51.20(b) of this chapter and is of the
type specified in § 50.21(b) (2) or (3) or
§ 50.22 of this chapter or is a testing
facility. This subpart also prescribes
procedures applicable to proceedings
for a construction permit for a
utilization facility which is subject to
§ 51.20(b) of this chapter and is of the
type specified in § 50.21(b)(2) or (3) or
§ 50.22 of this chapter, or an applicant
for a combined license under part 52 of
this chapter, who seeks to conduct the
activities authorized under § 50.10(c) of
part 50 of this chapter in advance of
issuance of the construction permit or
combined license, and submits an
application in accordance with
§ 2.101(a)(9).
6. Section 2.601 is revised to read as
follows:
§ 2.601
Applicability of other sections.
The provisions of subparts A, C, G, L
and N of this part relating to
applications for construction permits
and proceedings thereon apply,
respectively, to applications and
proceedings in accordance with this
subpart, except as specifically provided
otherwise by the provisions of this
subpart.
7. Preceding § 2.602, an undesignated
center heading is added to read as
follows:
pwalker on PROD1PC61 with PROPOSALS2
Early Partial Decisions on Site
Suitability
8. In § 2.606, paragraph (a) is revised
to read as follows:
§ 2.606 Partial decision on site suitability
issues.
(a) The provisions of §§ 2.331, 2.339,
2.340(b), 2.343, 2.712, and 2.713 apply
to any partial initial decision rendered
in accordance with this subpart. Section
2.340(c) does not apply to any partial
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
initial decision rendered in accordance
with this subpart. No construction
permit may be issued without
completion of the full review required
by section 102(2) of the National
Environmental Policy Act of 1969, as
amended, and subpart A of part 51 of
this chapter. The authority of the
Commission to review such a partial
initial decision sua sponte, or to raise
sua sponte an issue that has not been
raised by the parties, will be exercised
within the same time period as in the
case of a full decision relating to the
issuance of a construction permit.
*
*
*
*
*
9. Following § 2.606, an undesignated
center heading and §§ 2.641 through
2.649 are added to read as follows:
Phased Applications Involving Limited
Work Authorizations
Sec.
2.641 Filing Fees.
2.643 Acceptance and docketing of
applications for limited work
authorization.
2.645 Notice of hearing.
2.647 [Reserved]
2.649 Partial decisions on limited work
authorization.
§ 2.641
Filing fees.
Each application which contains a
request for limited work authorization
under the procedures of § 2.101(a)(9)
and this subpart shall be accompanied
by any fee required by § 50.30(e) and
part 170 of this chapter.
§ 2.643 Acceptance and docketing of
application for limited work authorization.
(a) Each part of an application
submitted in accordance with
§ 2.101(a)(9) will be initially treated as
a tendered application. If it is
determined that any one of the parts as
described in § 2.101(a)(9) is incomplete
and not acceptable for processing, the
Director of Nuclear Reactor Regulation
will inform the applicant of this
determination and the respects in which
the document is deficient. A
determination of completeness will
generally be made within a period of
thirty (30) days.
(b) The Director will accept for
docketing part one of an application for
a construction permit for a utilization
facility which is subject to § 51.20(b) of
this chapter and is of the type specified
in § 50.21(b) (2) or (3) or § 50.22 of this
chapter or an application for a
combined license where part one of the
application as described in § 2.101(a)(9)
is complete. Part one will not be
considered complete unless it contains
the information required by § 50.10(c) of
this chapter. Upon assignment of a
docket number, the procedures in
PO 00000
Frm 00018
Fmt 4701
Sfmt 4702
§ 2.101(a)(3) and (4) relating to formal
docketing and the submission and
distribution of additional copies of the
application must be followed.
(c) If part one of the application is
docketed, the Director will cause to be
published in the Federal Register and
send to the Governor or other
appropriate official of the State in which
the site is located, a notice of docketing
of the application which states the
purpose of the application, states the
location of the proposed site, states that
a notice of hearing will be published,
and requests comments on the limited
work authorization from Federal, State,
and local agencies and interested
persons. The notice will state that
comments must be submitted to the
NRC within 60 days or such other time
as may be specified in the notice.
(d) Part two of the application will be
docketed upon a determination by the
Director that it is complete.
(e) If part two of the application is
docketed, the Director will cause to be
published in the Federal Register and
sent to the Governor or other
appropriate official of the State in which
the site is located, a notice of docketing
of part two of the application which
states the purpose of the application,
states that a notice of hearing will be
published, and requests comments on
the construction permit or combined
license application, as applicable, from
Federal, State, and local agencies and
interested persons. The notice will state
that comments must be submitted to the
NRC within 60 days or such other time
as may be specified in the notice.
2.645
Notice of hearing.
(a) The notice of hearing on part one
of the application must set forth the
matters of fact and law to be considered,
as required by § 2.104, which will be
modified to state that the hearing will
relate only to the matters related to
§ 50.33(a) through (f) of this chapter,
and the limited work authorization.
(b) After docketing of part two of the
application, as provided in
§§ 2.101(a)(9) and 2.643(d), a
supplementary notice of hearing will be
published under § 2.104 with respect to
the remaining unresolved issues in the
proceeding within the scope of § 2.104.
The supplementary notice of hearing
will provide that any person whose
interest may be affected by the
proceeding and who desires to
participate as a party in the resolution
of the remaining issues shall file a
petition for leave to intervene within the
time prescribed in the notice. The
petition to intervene must meet the
applicable requirements in subpart C of
part 2 of this chapter, including § 2.309.
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
This supplementary notice will also
provide appropriate opportunities for
participation by a representative of an
interested State under § 2.315(c) and for
limited appearances under § 2.315(a).
(c) Any person who was permitted to
intervene under the initial notice of
hearing on the limited work
authorization and who was not
dismissed or did not withdraw as a
party, may continue to participate as a
party with respect to the remaining
unresolved issues only if, within the
time prescribed for filing of petitions for
leave to intervene in the supplementary
notice of hearing, that person files a
petition for intervention which meets
the applicable requirements in subpart
C of part 2, including § 2.309, provided,
however, that the petition need not
address § 2.309(d). However, a person
who was granted discretionary
intervention under § 2.309(e) must
address in its petition the factors in
§ 2..309(e) as they apply to the
supplementary hearing.
(d) A party who files a non-timely
petition for intervention under
subsection (c) of this section to continue
as a party may be dismissed from the
proceeding, absent a determination that
the party has made a substantial
showing of good cause for failure to file
on time, and with particular reference to
the factors specified in §§ 2.309(c)(1)(i)
through (iv) and 2.309(d). The notice
will be ruled upon by the Commission
or presiding officer designated to rule
on petitions for leave to intervene.
(e) To the maximum extent
practicable, the membership of the
atomic safety and licensing board, or the
individual presiding officer, as
applicable, designated to preside in the
proceeding on the remaining unresolved
issues pursuant to the supplemental
notice of hearing will be the same as the
membership or individual designated to
preside in the initial notice of hearing.
§ 2.647
[Reserved].
pwalker on PROD1PC61 with PROPOSALS2
§ 2.649 Partial decisions on limited work
authorization.
The provisions of §§ 2.331, 2.339,
2.340(b), 2.343, 2.712, and 2.713 apply
to any partial initial decision rendered
in accordance with this subpart. Section
2.340(c) does not apply to any partial
initial decision rendered in accordance
with this subpart. A limited work
authorization may not be issued under
10 CFR 50.10(c) without completion of
the review for limited work
authorizations required by subpart A of
part 51 of this chapter. The authority of
the Commission to review such a partial
initial decision sua sponte, or to raise
sua sponte an issue that has not been
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
raised by the parties, will be exercised
within the same time period as in the
case of a full decision relating to the
issuance of a construction permit or
combined license.
PART 50—DOMESTIC LICENSING OF
PRODUCTION AND UTILIZATION
FACILITIES
10. The authority citation for Part 50
continues to read as follows:
Authority: Secs. 102, 103, 104, 105, 161,
182, 183, 186, 189, 68 Stat. 936, 937, 938,
948, 953, 954, 955, 956, as amended, sec.
234, 83 Stat. 444, as amended (42 U.S.C.
2132, 2133, 2134, 2135, 2201, 2232, 2233,
2236, 2239, 2282); secs. 201, as amended,
202, 206, 88 Stat. 1242, as amended, 1244,
1246 (42 U.S.C. 5841, 5842, 5846); sec. 1704,
112 Stat. 2750 (44 U.S.C. 3504 note).
Section 50.7 also issued under Pub. L. 95–
601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5841).
Section 50.10 also issued under secs. 101,
185, 68 Stat. 955, as amended (42 U.S.C.
2131, 2235); sec. 102, Pub. L. 91–190, 83 Stat.
853 (42 U.S.C. 4332). Sections 50.13,
50.54(dd), and 50.103 also issued under sec.
108, 68 Stat. 939, as amended (42 U.S.C.
2138). Sections 50.23, 50.35, 50.55, and 50.56
also issued under sec. 185, 68 Stat. 955 (42
U.S.C. 2235). Sections 50.33a, 50.55a and
Appendix Q also issued under sec. 102, Pub.
L. 91–190, 83 Stat. 853 (42 U.S.C. 4332).
Sections 50.34 and 50.54 also issued under
sec. 204, 88 Stat. 1245 (42 U.S.C. 5844).
Sections 50.58, 50.91, and 50.92 also issued
under Pub. L. 97–415, 96 Stat. 2073 (42
U.S.C. 2239). Section 50.78 also issued under
sec. 122, 68 Stat. 939 (42 U.S.C. 2152).
Sections 50.80–50.81 also issued under sec.
184, 68 Stat. 954, as amended (42 U.S.C.
2234). Appendix F also issued under sec.
187, 68 Stat. 955 (42 U.S.C. 2237).
11. Section 50.10 is revised to read as
follows:
§ 50.10 License required; limited work
authorization.
(a) Requirement for license. Except as
provided in § 50.11, no person within
the United States shall transfer or
receive in interstate commerce,
manufacture, produce, transfer, acquire,
possess, or use any production or
utilization facility except as authorized
by a license issued by the Commission.
(b) Requirement for construction
permit, early site permit, combined
license, or limited work authorization.
No person may begin the construction of
a production or utilization facility on a
site on which the facility is to be
operated until that person has been
issued either a construction permit
under this part or a combined license
under part 52 of this chapter, or a
limited work authorization under
paragraph (c) of this section. As used in
this paragraph, the term ‘‘construction’’
includes excavation, subsurface
preparation, including the driving of
PO 00000
Frm 00019
Fmt 4701
Sfmt 4702
61347
piles, installation of the foundation,
including the placement of concrete,
and on-site, in-place fabrication,
erection, integration or testing, for any
structure, system or component of a
facility required by the Commission’s
rules and regulations to be described in
the site safety analysis report or
preliminary or final safety analysis
report. The term ‘‘construction’’
excludes:
(1) Changes for the temporary use of
the land for public recreational
purposes;
(2) Site exploration, including:
necessary borings to determine
foundation conditions or other
preconstruction monitoring to establish
background information related to the
suitability of the site, the environmental
impacts of construction or operation, or
the protection of environmental values;
(3) Preparation of the site for
construction of a facility, including
clearing of the site, grading, installation
of drainage, erosion and other
environmental mitigation measures, and
construction of temporary roads and
borrow areas;
(4) Construction of fencing and other
access control measures;
(5) Construction of temporary
construction support buildings (such as
construction equipment storage sheds,
warehouse and shop facilities, utilities,
concrete mixing plants, docking and
unloading facilities, and construction
support buildings and offices) for use in
connection with the construction of the
facility;
(6) Construction of permanent service
facilities, such as paved roads, parking
lots, railroad spurs, exterior utility and
lighting systems, potable water systems,
sanitary sewerage treatment facilities,
transmission lines, support buildings,
and office buildings;
(7) Procurement or manufacture of the
components of the proposed facility, or
the manufacture of a nuclear power
reactor under a manufacturing license
under subpart F of this part to be
installed at the proposed site and be
part of the proposed facility; and
(8) With respect to production or
utilization facilities, other than testing
facilities and nuclear power plants,
required to be licensed pursuant to
section 104.a or section 104.c of the Act,
the construction of buildings which will
be used for activities other than
operation of a facility and which may
also be used to house a facility (for
example, the construction of a college
laboratory building with space for
installation of a training reactor).
(c) Request for limited work
authorization. (1) Any person to whom
the Commission may otherwise issue
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
61348
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
either a license or permit under Sections
103, 104.b, or 185 of the Act for a
facility of the type specified in
§ 50.21(b)(2) or (3), § 50.22, or a testing
facility, may request a limited work
authorization allowing that person to
perform excavation, subsurface
preparation, including the driving of
piles, and installation of the foundation,
including placement of concrete, for any
structure, system or component of the
facility.
(2) An application for a limited work
authorization may be submitted as part
of a complete application for a
construction permit or combined license
in accordance with 10 CFR 2.101(a)(1)
through (4), or as a partial application
in accordance with 10 CFR 2.101(a)(9).
An application for a limited work
authorization must be submitted by an
applicant for or holder of an early site
permit as a complete application in
accordance with 10 CFR 2.101(a)(1)
through (4).
(3) The application must include:
(i) A safety analysis report required by
10 CFR 50.34, 10 CFR 52.17 or 10 CFR
52.79, as applicable, a description of the
activities requested to be performed,
and the design and construction
information otherwise required by the
Commission’s rules and regulations to
be submitted for a construction permit
or combined license, but limited to
those portions of the facility that are
within the scope of the limited work
authorization. The safety analysis report
must demonstrate that activities
conducted under the limited work
authorization will be conducted in
compliance with the technicallyrelevant Commission requirements in 10
CFR Chapter I applicable to the design
of those portions of the facility within
the scope of the limited work
authorization;
(ii) An environmental report in
accordance with § 51.49 of this chapter;
and
(iii) A plan for redress of the site to
achieve an environmentally stable and
aesthetically acceptable site suitable for
whatever non-nuclear use may conform
with local zoning laws, should limited
work activities be terminated by the
holder, the limited work authorization
is revoked by the NRC, or upon
effectiveness of the Commission’s final
decision denying the associated
construction permit or combined license
application, as applicable.
(d) Issuance of limited work
authorization. (1) The Director of the
Office of Nuclear Reactor Regulation
may issue a limited work authorization
only after:
(i) The NRC staff issues the final
environmental impact statement for the
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
limited work authorization in
accordance with subpart A of part 51 of
this chapter;
(ii) The presiding officer makes the
finding in § 51.105(c) or § 51.107(d) of
this chapter, as applicable;
(iii) The Director determines that the
applicable standards and requirements
of the Act and the Commission’s
regulations applicable to the activities to
be conducted under the limited work
authorization have been met; the
applicant is technically qualified to
engage in the activities authorized; and
issuance of the limited work
authorization will provide reasonable
assurance of adequate protection to
public health and safety and will not be
inimical to the common defense and
security; and
(iv) The presiding officer finds that
there are no unresolved safety issues
relating to the activities to be conducted
under the limited work authorization
that would constitute good cause for
withholding the authorization.
(2) Each limited work authorization
will specify the activities that the holder
is authorized to perform. The limited
work authorization will include a
condition requiring the holder to redress
the site in accordance with the redress
plan required by § 52.17(c) of this
chapter, if construction is terminated by
the holder, the LWA is revoked by the
NRC, or upon effectiveness of the
Commission’s final decision denying
the associated operating license
application or the underlying combined
license application, as applicable.
(e) Effect of limited work
authorization. Any activities
undertaken under a limited work
authorization are entirely at the risk of
the applicant and, except as to the
matters determined under paragraph
(d)(1) of this section, the issuance of the
limited work authorization has no
bearing on the issuance of a
construction permit or combined license
with respect to the requirements of the
Act, and rules, regulations, or orders
promulgated pursuant thereto. The
environmental impact statement for a
construction permit or combined license
application for which a limited work
authorization was previously issued
will not address, and the presiding
officer will not consider, the sunk costs
of the holder of limited work
authorization in determining the
proposed action (i.e., issuance of the
construction permit or combined
license).
(f) Implementation of redress plan. If
construction is terminated by the
holder, the underlying application is
withdrawn by the applicant or denied
by the NRC, or the LWA is revoked by
PO 00000
Frm 00020
Fmt 4701
Sfmt 4702
the NRC, then the holder must begin
implementation of the redress plan in a
reasonable time, and complete the
redress of the site no later than eighteen
(18) months after termination of
construction, revocation of the LWA,
upon effectiveness of the Commission’s
final decision denying the associated
operating license application or the
underlying combined license
application, as applicable.
PART 51—ENVIRONMENTAL
PROTECTION REGULATIONS FOR
DOMESTIC LICENSING AND RELATED
REGULATORY FUNCTIONS
12. The authority citation for Part 51
continues to read as follows:
Authority: Sec. 161, 68 Stat. 948, as
amended, sec. 1701, 106 Stat. 2951, 2952,
2953 (42 U.S.C. 2201, 2297f); secs. 201, as
amended, 202, 88 Stat. 1242, as amended,
1244 (42 U.S.C. 5841, 5842); sec. 1704, 112
Stat. 2750 (44 U.S.C. 3504 note). Subpart A
also issued under National Environmental
Policy Act of 1969, secs. 102, 104, 105, 83
Stat. 853–854, as amended (42 U.S.C. 4332,
4334, 4335); and Pub. L. 95–604, Title II, 92
Stat. 3033–3041; and sec. 193, Pub. L. 101–
575, 104 Stat. 2835 (42 U.S.C. 2243). Sections
51.20, 51.30, 51.60, 51.80, and 51.97 also
issued under secs. 135, 141, Pub. L. 97–425,
96 Stat. 2232, 2241, and sec. 148, Pub. L.
100–203, 101 Stat. 1330–223 (42 U.S.C.
10155, 10161, 10168). Section 51.22 also
issued under sec. 274, 73 Stat. 688, as
amended by 92 Stat. 3036–3038 (42 U.S.C.
2021) and under Nuclear Waste Policy Act of
1982, sec. 121, 96 Stat. 2228 (42 U.S.C.
10141). Sections 51.43, 51.67, and 51.109
also issued under Nuclear Waste Policy Act
of 1982, sec. 114(f), 96 Stat. 2216, as
amended (42 U.S.C. 10134(f)).
13. In § 51.4, a new definition of
construction is added to read as follows:
§ 51.4
Definitions.
*
*
*
*
*
Construction includes excavation,
subsurface preparation, including the
driving of piles, installation of the
foundation, including the placement of
concrete, and on-site, in-place
fabrication, erection, integration or
testing, for any structure, system or
component of a facility required by the
Commission’s rules and regulations to
be described in the site safety analysis
report or preliminary or final safety
analysis report. The term ‘‘construction’’
excludes:
(1) Changes for the temporary use of
the land for public recreational
purposes;
(2) Site exploration, including:
Necessary borings to determine
foundation conditions or other
preconstruction monitoring to establish
background information related to the
suitability of the site, the environmental
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
impacts of construction or operation, or
the protection of environmental values;
(3) Preparation of the site for
construction of a facility, including
clearing of the site, grading, installation
of drainage, erosion and other
environmental mitigation measures, and
construction of temporary roads and
borrow areas;
(4) Construction of fencing and other
access control measures;
(5) Construction of temporary
construction support buildings (such as
construction equipment storage sheds,
warehouse and shop facilities, utilities,
concrete mixing plants, docking and
unloading facilities, and construction
support buildings and offices) for use in
connection with the construction of the
facility;
(6) Construction of permanent service
facilities, such as paved roads, parking
lots, railroad spurs, exterior utility and
lighting systems, potable water systems,
sanitary sewerage treatment facilities,
transmission lines, support buildings,
and office buildings;
(7) Procurement or manufacture of the
components of the proposed facility, or
the manufacture of a nuclear power
reactor under a manufacturing license
under subpart F of this part to be
installed at the proposed site and be
part of the proposed facility; and
(8) With respect to production or
utilization facilities, other than testing
facilities and nuclear power plants,
required to be licensed pursuant to
section 104.a or section 104.c of the Act,
the construction of buildings which will
be used for activities other than
operation of a facility and which may
also be used to house a facility (for
example, the construction of a college
laboratory building with space for
installation of a training reactor).
14. In § 51.17, paragraph (b) is revised
to read as follows:
§ 51.17 Information collection
requirements; OMB approval.
pwalker on PROD1PC61 with PROPOSALS2
*
*
*
*
*
(b) The approved information
collection requirements in this part
appear in §§ 51.6, 51.16, 51.41, 51.45,
51.49, 51.50, 51.51, 51.52, 51.53, 51.54,
51.58, 51.60, 51.61, 51.62, 51.66, 51.68,
and 51.69.
15. In § 51.20, the introductory text of
paragraph (b) is republished and a new
paragraph (b)(5) is added to read as
follows:
§ 51.20 Criteria for and identification of
licensing and regulatory actions requiring
environmental impact statements.
*
*
*
*
*
(b) The following types of actions
require an environmental impact
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
statement or a supplement to an
environmental impact statement:
*
*
*
*
*
(5) Issuance of a limited work
authorization under 10 CFR 50.10 of the
chapter.
*
*
*
*
*
16. A new § 51.49 is added under the
heading Environmental Reports—
Production and Utilization Facilities to
read as follows:
§ 51.49 Environmental report—limited
work authorization.
(a) Limited work authorization
submitted as part of complete
construction permit or combined license
application. Each applicant for
construction permit or combined license
who applies for a limited work
authorization under § 50.10(c) of part 50
of this chapter in a complete application
under 10 CFR 2.101(a)(1) through (4),
shall submit with its application a
separate document, entitled,
‘‘Applicant’s Environmental Report—
Limited Work Authorization Stage,’’
which is in addition to the
Environmental Report required by
§ 51.50 of this section. The Applicant’s
Environmental Report—Limited Work
Authorization Stage must contain the
following information:
(1) A description of the activities
proposed to be conducted under the
limited work authorization;
(2) A statement of the need for the
activities; and
(3) A description of the environmental
impacts that may reasonably be
expected to result from the activities,
the mitigation measures that the
applicant proposes to implement in
order to achieve the level of
environmental impacts described, and a
discussion of the reasons for rejecting
mitigation measures that could be
employed by the applicant to further
reduce environmental impacts.
(b) Phased application for limited
work authorization and construction
permit or combined license. If the
construction permit or combined license
application is filed in accordance with
§ 2.101(a)(9) of this chapter, then the
environmental report for part one of the
application may be limited to a
discussion of the activities proposed to
be conducted under the limited work
authorization, and the proposed redress
plan. If the scope of the environmental
report for part one is so limited, then
part two of the application must include
the information required by § 51.50, as
applicable.
(c) Limited work authorization
submitted as part of early site permit
application. Each applicant for an early
site permit under subpart A of part 51
PO 00000
Frm 00021
Fmt 4701
Sfmt 4702
61349
who is requesting a limited work
authorization shall submit with its
application the environmental report
required by § 51.50(b), provided,
however, that the report must also
contain the following information:
(1) A description of the activities
proposed to be conducted under the
limited work authorization;
(2) A statement of the need for the
activities; and
(3) A description of the environmental
impacts that may reasonably be
expected to result from the activities,
the mitigation measures that the
applicant proposes to implement in
order to achieve the level of
environmental impacts described, and a
discussion of the reasons for rejecting
mitigation measures that could be
employed by the applicant to further
reduce environmental impacts.
(d) Limited work authorization
request submitted by early site permit
holder. Each holder of an early site
permit who requests a limited work
authorization shall submit with its
application the environmental report
containing the following information:
(1) A description of the activities
proposed to be conducted under the
limited work authorization;
(2) A statement of the need for the
activities;
(3) A description of the environmental
impacts that may reasonably be
expected to result from the activities,
the mitigation measures that the
applicant proposes to implement in
order to achieve the level of
environmental impacts described, and a
discussion of the reasons for rejecting
mitigation measures that could be
employed by the applicant to further
reduce environmental impacts; and
(4) A discussion of any new and
significant information on the
environmental impacts of construction
as determined in the environmental
impact statement for the early site
permit, which may materially affect the
conclusions of the early site permit with
respect to the environmental impacts of
the activities to be conducted under the
limited work authorization.
(e) Limited work authorization for site
where EIS was prepared, but the facility
was not constructed. If the limited work
authorization is for activities to be
conducted at a site for which the
Commission has previously prepared an
environmental impact statement for the
construction and operation of a nuclear
power plant, and a construction permit
was issued but construction of the plant
was never completed, then the
applicant’s environmental report may
reference the earlier environmental
impact statement. In the event of such
E:\FR\FM\17OCP2.SGM
17OCP2
61350
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
referencing, the environmental report
must identify whether there is new and
significant information material to the
matters required to be addressed in
paragraph (a) of this section.
(f) Environmental Report. An
environmental report submitted in
accordance with this section must
separately evaluate the environmental
impacts and proposed alternatives
attributable to the activities proposed to
be conducted under the limited work
authorization. At the option of the
applicant, the Applicant’s
Environmental Report—Limited Work
Authorization Stage may contain the
information required to be submitted in
the environmental report required under
§ 51.50, which addresses the impacts of
construction and operation for the
proposed facility (including the
environmental impacts attributable to
the limited work authorization), and
discusses the overall costs and benefits
balancing for the proposed action.
17. Section 51.50 is revised to read as
follows:
pwalker on PROD1PC61 with PROPOSALS2
§ 51.50 Environmental report—
construction permit, early site permit, or
combined license stage.
(a) Construction permit stage. Each
applicant for a permit to construct a
production or utilization facility
covered by § 51.20 shall submit with its
application a separate document,
entitled ‘‘Applicant’s Environmental
Report—Construction Permit Stage,’’
which shall contain the information
specified in §§ 51.45, 51.51 and 51.52.
Each environmental report shall identify
procedures for reporting and keeping
records of environmental data, and any
conditions and monitoring requirements
for protecting the non-aquatic
environment, proposed for possible
inclusion in the license as
environmental conditions in accordance
with § 50.36b of this chapter.
(b) Early site permit stage. Each
applicant for an early site permit shall
submit with its application a separate
document, entitled ‘‘Applicant’s
Environmental Report—Early Site
Permit Stage,’’ which shall contain the
information specified in §§ 51.45, 51.51,
and 51.52, as modified in this
paragraph. Environmental reports need
not include an assessment of the
economic, technical, and other benefits
and costs of the proposed action or an
analysis of other energy alternatives.
Environmental reports must focus on
the environmental effects of
construction and operation of a reactor,
or reactors, which have characteristics
that fall within the postulated site
parameters. Environmental reports must
include an evaluation of alternative sites
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
to determine whether there is any
obviously superior alternative to the site
proposed. For other than light-watercooled nuclear power reactors, the
environmental report shall contain the
basis for evaluating the contribution of
the environmental effects of fuel cycle
activities for the nuclear power reactor.
Each environmental report shall identify
procedures for reporting and keeping
records of environmental data, and any
conditions and monitoring requirements
for protecting the non-aquatic
environment, proposed for possible
inclusion in the license as
environmental conditions in accordance
with § 50.36b of this chapter.
(c) Combined license stage. Each
applicant for a combined license shall
submit with its application a separate
document, entitled ‘‘Applicant’s
Environmental Report—Combined
License Stage.’’ Each environmental
report shall contain the information
specified in §§ 51.45, 51.51 and 51.52,
for other than light-water-cooled nuclear
power reactors, the environmental
report shall contain the basis for
evaluating the contribution of the
environmental effects of fuel cycle
activities for the nuclear power reactor.
Each environmental report shall identify
procedures for reporting and keeping
records of environmental data, and any
conditions and monitoring requirements
for protecting the non-aquatic
environment, proposed for possible
inclusion in the license as
environmental conditions in accordance
with § 50.36b of this chapter. The
combined license environmental report
may reference information contained in
a final environmental document
previously prepared by the NRC staff.
(1) Application referencing an early
site permit. The applicant must have a
reasonable process for identifying any
new and significant information
regarding the NRC’s conclusions in the
early site permit environmental impact
statement. If the combined license
application references an early site
permit, then the ‘‘Applicant’s
Environmental Report—Combined
License Stage’’ need not contain
information or analyses submitted to the
Commission in ‘‘Applicant’s
Environmental Report—Early Site
Permit Stage,’’ but must contain, in
addition to the environmental
information and analyses otherwise
required:
(i) Information to demonstrate that the
design of the facility falls within the site
characteristics and design parameters
specified in the early site permit;
(ii) Information to resolve any other
significant environmental issue not
considered in the early site permit
PO 00000
Frm 00022
Fmt 4701
Sfmt 4702
proceeding, either for the site or design;
and
(iii) Any new and significant
information on the site or design to the
extent that it differs from, or is in
addition to, that discussed in the early
site permit environmental impact
statement.
(2) Application referencing standard
design certification. If the combined
license references a standard design
certification, then the combined license
environmental report may incorporate
by reference the environmental
assessment previously prepared by the
NRC for the referenced design
certification. If the design certification
environmental assessment is referenced,
then the combined license
environmental report must contain
information to demonstrate that the site
characteristics for the combined license
site fall within the site parameters in the
design certification environmental
assessment.
(3) Application referencing a
manufactured reactor. If the combined
license application proposes to use a
manufactured reactor, then the
combined license environmental report
may incorporate by reference the
environmental assessment previously
prepared by the NRC for the underlying
manufacturing license. If the
manufacturing license environmental
assessment is referenced, then the
combined license environmental report
must contain information to
demonstrate that the site characteristics
for the combined license site fall within
the site parameters in the manufacturing
license environmental assessment. The
environmental report need not address
the environmental impacts associated
with manufacturing the reactor under
the manufacturing license.
*
*
*
*
*
18. In § 51.71, paragraph (d) and
footnote 3 are revised, paragraph (e) is
redesignated as paragraph (f), and a new
paragraph (e) is added to read as
follows:
§ 51.71 Draft environmental impact
statement-contents.
*
*
*
*
*
(d) Analysis. (1) Unless excepted in
this paragraph, the draft environmental
impact statement will include a
preliminary analysis that considers and
weighs the environmental effects of the
proposed action; the environmental
impacts of alternatives to the proposed
action; and alternatives available for
reducing or avoiding adverse
environmental effects and consideration
of the economic, technical, and other
benefits and costs of the proposed
action and alternatives and indicate
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
what other interests and considerations
of Federal policy, including factors not
related to environmental quality if
applicable, are relevant to the
consideration of environmental effects
of the proposed action identified under
paragraph (a) of this section.
(2) The draft environmental impact
statement prepared at the early site
permit stage must focus on the
environmental effects of construction
and operation of a reactor, or reactors,
which have characteristics that fall
within the postulated site parameters,
and will not include an assessment of
the benefits (for example, need for
power) of the proposed action or an
evaluation of other alternative energy
sources unless considered by the
applicant, but must include an
evaluation of alternative sites to
determine whether there is any
obviously superior alternative to the site
proposed.
(3) The draft supplemental
environmental impact statement
prepared at the combined license stage
when an early site permit is referenced
need not include detailed information
or analyses that were resolved in the
final environmental impact statement
prepared by the Commission in
connection with the early site permit, if:
(i) The design of the facility falls
within the design parameters specified
in the early site permit;
(ii) The site falls within the site
characteristics specified within the early
site permit; and
(iii) There is no significant new
environmental issue or information not
considered on the site or the design only
to the extent that they differ from that
discussed in the final environmental
impact statement prepared by the
Commission in connection with the
early site permit.
(4) The draft supplemental
environmental impact statement
prepared at the license renewal stage
under § 51.95(c) need not discuss the
economic or technical benefits and costs
of either the proposed action or
alternatives except if benefits and costs
are either essential for a determination
regarding the inclusion of an alternative
in the range of alternatives considered
or relevant to mitigation. In addition,
the supplemental environmental impact
statement prepared at the license
renewal stage need not discuss other
issues not related to the environmental
effects of the proposed action and
associated alternatives. The draft
supplemental environmental impact
statement for license renewal prepared
under § 51.95(c) will rely on
conclusions as amplified by the
supporting information in the GEIS for
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
issues designated as Category 1 in
appendix B to subpart A of this part.
The draft supplemental environmental
impact statement must contain an
analysis of those issues identified as
Category 2 in appendix B to subpart A
of this part that are open for the
proposed action.
(5) The analysis for all draft
environmental impact statements will,
to the fullest extent practicable, quantify
the various factors considered. To the
extent that there are important
qualitative considerations or factors that
cannot be quantified, these
considerations or factors will be
discussed in qualitative terms.
(6) Due consideration will be given to
compliance with environmental quality
standards and requirements that have
been imposed by Federal, State,
regional, and local agencies having
responsibility for environmental
protection, including applicable zoning
and land-use regulations and water
pollution limitations or requirements
issued or imposed under the Federal
Water Pollution Control Act. The
environmental impact of the proposed
action will be considered in the analysis
with respect to matters covered by
environmental quality standards and
requirements irrespective of whether a
certification or license from the
appropriate authority has been
obtained.3 While satisfaction of
Commission standards and criteria
pertaining to radiological effects will be
necessary to meet the licensing
requirements of the Atomic Energy Act,
3 Compliance with the environmental quality
standards and requirements of the Federal Water
Pollution Control Act (imposed by EPA or
designated permitting states) is not a substitute for,
and does not negate the requirement for NRC to
weigh all environmental effects of the proposed
action, including the degradation, if any, of water
quality, and to consider alternatives to the proposed
action that are available for reducing adverse
effects. Where an environmental assessment of
aquatic impact from plant discharges is available
from the permitting authority, the NRC will
consider the assessment in its determination of the
magnitude of environmental impacts for striking an
overall cost-benefit balance at the construction
permit and operating license and early site permit
and combined license stages, and in its
determination of whether the adverse
environmental impacts of license renewal are so
great that preserving the option of license renewal
for energy planning decision-makers would be
unreasonable at the license renewal stage. When the
assessment of aquatic impacts is not available from
the permitting authority, NRC will establish on its
own, or in conjunction with the permitting
authority and other agencies having relevant
expertise, the magnitude of potential impacts for
striking an overall cost-benefit balance for the
facility at the construction permit and operating
license and early site permit and combined license
stages, and in its determination of whether the
adverse environmental impacts of license renewal
are so great that preserving the option of license
renewal for energy planning decision-makers would
be unreasonable at the license renewal stage.
PO 00000
Frm 00023
Fmt 4701
Sfmt 4702
61351
the analysis will, for the purposes of
NEPA, consider the radiological effects
of the proposed action and alternatives.
(e) Effect of limited work
authorization. If a limited work
authorization was issued either in
connection with or subsequent to an
early site permit, or in connection with
a construction permit or combined
license application, then the
environmental impact statement for the
construction permit or combined license
application will not address or consider
the sunk costs associated with the
limited work authorization.
*
*
*
*
*
19. Section 51.76 is revised to read as
follows:
§ 51.76 Draft environmental impact
statement-limited work authorization.
The NRC will prepare a draft
environmental impact statement relating
to issuance of a limited work
authorization in accordance with the
procedures and measures described in
§§ 51.70, 51.71, and 51.73, as further
supplemented or modified in the
following paragraphs.
(a) Limited work authorization
submitted as part of complete
construction permit or combined license
application. If the application for a
limited work authorization is submitted
as part of a complete construction
permit or combined license application,
then the NRC may prepare a partial draft
environmental impact statement,
provided, however, that the analysis
called for by § 51.71(d) will be limited
to the activities proposed to be
conducted under the limited work
authorization. Alternatively, the NRC
may prepare a complete draft
environmental impact statement
prepared in accordance with § 51.75(a)
or (c), as applicable.
(b) Phased application for limited
work authorization under § 2.101(a)(9)
of this chapter. If the application for a
limited work authorization is submitted
in accordance with § 2.101(a)(9) of this
chapter, then the draft environmental
impact statement for part one of the
application may be limited to
consideration of the activities proposed
to be conducted under the limited work
authorization, and the proposed redress
plan. However, if the environmental
report contains the full set of
information required to be submitted
under § 51.50(a) or (c), then the draft
environmental impact statement will be
prepared in accordance with § 51.75(a)
or (c), as applicable. Siting issues,
including whether there is an obviously
superior alternative site, or issues
related to operation of the proposed
nuclear power plant at the site,
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
61352
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
including need for power may not be
considered. After part two of the
application is docketed, the NRC will
prepare a draft supplement to the final
environmental impact statement for part
two of the application under § 51.72. No
updating of the information contained
in the final environmental statement
prepared for part one is necessary in
preparation of the supplemental
environmental impact statement. The
draft supplement must consider all
environmental impacts associated with
the prior issuance of the limited work
authorization, but may not address or
consider the sunk costs associated with
the limited work authorization.
(c) Limited work authorization
submitted as part of an early site permit
application. If the application for a
limited work authorization is submitted
as part of an application for an early site
permit, then the NRC will prepare an
environmental impact statement in
accordance with § 51.75(b). However,
the analysis called for by § 51.71(d)
must also address the activities
proposed to be conducted under the
limited work authorization.
(d) Limited work authorization
request submitted by early site permit
holder. If the application for a limited
work authorization is submitted by a
holder of an early site permit, then the
NRC will prepare a prepare a draft
supplement to the environmental
impact statement for the early site
permit. The supplement is limited to
consideration of the activities proposed
to be conducted under the limited work
authorization, the adequacy of the
proposed redress plan, and whether
there is significant new information on
the impacts of construction which
materially affect the conclusions of the
early site permit with respect to the
environmental impacts of the activities
to be conducted under the limited work
authorization. No other updating of the
information contained in the final
environmental statement prepared for
the early site permit is required.
(e) Limited work authorization for site
where EIS was prepared, but the facility
was not constructed. If the limited work
authorization is for activities to be
conducted at a site for which the
Commission has previously prepared an
environmental impact statement for the
construction and operation of a nuclear
power plant, a construction permit was
issued but construction of the plant (as
defined in § 50.10 of this chapter) was
never commenced, the draft
environmental impact statement shall
incorporate by reference the earlier
environmental impact statement. The
draft environmental impact statement
will be limited to a consideration of
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
whether there is significant new
information with respect to the
environmental impacts of construction,
relevant to the activities to be conducted
under the limited work authority, such
that the conclusion of the referenced
environmental impact statement on the
impacts of construction would, when
analyzed in accordance with § 51.71,
lead to the conclusion that the limited
work authorization should not be issued
or should be issued with appropriate
conditions.
(f) A draft environmental impact
statement prepared under this section
must separately evaluate the
environmental impacts and proposed
alternatives attributable to the activities
proposed to be conducted under the
limited work authorization. However, if
the Applicant’s Environmental Report—
Limited Work Authorization Stage also
contains the information required to be
submitted in the environmental report
required under § 51.50, then the
environmental impact statement must
address the impacts of construction and
operation for the proposed facility
(including the environmental impacts
attributable to the limited work
authorization), and discuss the overall
costs and benefits balancing for the
underlying proposed action, in
accordance with § 51.71, and § 51.75(a)
or (c), as applicable.
20. In § 51.103, a new paragraph (a)(6)
is added to read as follows:
§ 51.103
Record of decision—general.
(a) * * *
(6) In a construction permit or the
combined license proceeding, where a
limited work authorization under 10
CFR 50.10 was issued, the
Commission’s decision on the
construction permit or combined license
application will not address or consider
the sunk costs associated with the
limited work authorization in
determining the proposed action.
*
*
*
*
*
21. In § 51.104, a new paragraph (c) is
added to read as follows:
§ 51.104 NRC proceedings using public
hearings; consideration of environmental
impact statement.
*
*
*
*
*
(c) Limited work authorization. In any
proceeding in which a limited work
authorization is requested, unless the
Commission orders otherwise, a party to
the proceeding may take a position and
offer evidence only on the aspects of the
proposed action within the scope of
NEPA and this subpart which are within
the scope of that party’s admitted
contention, in accordance with the
provisions of part 2 of this chapter
PO 00000
Frm 00024
Fmt 4701
Sfmt 4702
applicable to the limited work
authorization or in accordance with the
terms of any notice of hearing
applicable to the limited work
authorization. In the proceeding, the
presiding officer will decide any such
matters in controversy among the
parties.
22. Section 51.105, is revised to read
as follows:
§ 51.105 Public hearings in proceedings
for issuance of construction permits or
early site permits; limited work
authorizations.
(a) In addition to complying with
applicable requirements of § 51.104, in
a proceeding for the issuance of a
construction permit or early site permit
for a nuclear power reactor, testing
facility, fuel reprocessing plant or
isotopic enrichment plant, the presiding
officer will:
(1) Determine whether the
requirements of section 102(2) (A), (C),
and (E) of NEPA and the regulations in
this subpart have been met;
(2) Independently consider the final
balance among conflicting factors
contained in the record of the
proceeding with a view to determining
the appropriate action to be taken;
(3) Determine, after weighing the
environmental, economic, technical,
and other benefits against
environmental and other costs, and
considering reasonable alternatives,
whether the construction permit or early
site permit should be issued, denied, or
appropriately conditioned to protect
environmental values;
(4) Determine, in an uncontested
proceeding, whether the NEPA review
conducted by the NRC staff has been
adequate; and
(5) Determine, in a contested
proceeding, whether in accordance with
the regulations in this subpart, the
construction permit or early site permit
should be issued as proposed.
(b) The presiding officer in an early
site permit hearing shall not admit
contentions proffered by any party
concerning the benefits assessment (e.g.,
need for power) or alternative energy
sources if those issues were not
addressed by the applicant in the early
site permit application.
(c)(1) In addition to complying with
the applicable provisions of § 51.104, in
any proceeding for the issuance of a
construction permit for a nuclear power
plant or an early site permit under part
52 of this chapter where the applicant
requests a limited work authorization
under § 50.10(c) of this chapter, the
presiding officer shall—–
(i) Determine whether the
requirements of section 102(2)(A), (C)
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
and (E) of NEPA and the regulations in
the subpart have been met, with respect
to the activities to be conducted under
the limited work authorization;
(ii) Independently consider the
balance among conflicting factors with
respect to the limited work
authorization which is contained in the
record of the proceeding, with a view to
determining the appropriate action to be
taken;
(iii) In an uncontested proceeding,
determine whether the NEPA review
conducted by the NRC staff for the
limited work authorization has been
adequate; and
(iv) In a contested proceeding,
determine whether in accordance with
the regulations in this subpart, the
limited work authorization should be
issued as proposed.
(2) If the limited work authorization is
for activities to be conducted at a site for
which the Commission has previously
prepared an environmental impact
statement for the construction and
operation of a nuclear power plant, and
a construction permit was issued but
construction of the plant was never
completed, then in making the
determinations in paragraph (c)(1) of
this section, the presiding officer shall
be limited to a consideration whether
there is, with respect to construction
activities encompassed by the
environmental impact statement which
are analogous to the activities to be
conducted under the limited work
authorization, significant new
information on the environmental
impacts of those activities, such that the
limited work authorization should not
be issued as proposed.
(3) The presiding officer’s
determination in this paragraph shall be
made in a partial initial decision to be
issued separately from, and in advance
of, the presiding officer’s decision in
paragraph (a) of this section.
23. Section 51.107 is added to read as
follows:
pwalker on PROD1PC61 with PROPOSALS2
§ 51.107 Public hearings in proceedings
for issuance of combined licenses; limited
work authorizations.
(a) In addition to complying with
applicable requirements of § 51.104, in
a proceeding for the issuance of a
combined license for a nuclear power
reactor, the presiding officer will:
(1) Determine whether the
requirements of section 102(2) (A), (C),
and (E) of NEPA and the regulations in
this subpart have been met;
(2) Independently consider the final
balance among conflicting factors
contained in the record of the
proceeding with a view to determining
the appropriate action to be taken;
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
(3) Determine, after weighing the
environmental, economic, technical,
and other benefits against
environmental and other costs, and
considering reasonable alternatives,
whether the combined license should be
issued, denied, or appropriately
conditioned to protect environmental
values;
(4) Determine, in an uncontested
proceeding, whether the NEPA review
conducted by the NRC staff has been
adequate; and
(5) Determine, in a contested
proceeding, whether in accordance with
the regulations in this subpart, the
combined license should be issued as
proposed by the NRC’s Director of
Nuclear Reactor Regulation.
(b) If the combined license
application references an early site
permit, then the presiding officer in a
combined license hearing shall not
admit contentions proffered by any
party on environmental issues which
have been accorded finality under
§ 52.39 of this chapter, unless this
contention—
(1) Demonstrates that the design of the
facility falls outside the design
parameters specified in the early site
permit;
(2) Demonstrates that the site no
longer falls within the site
characteristics specified in the early site
permit; or
(3) Raises any other significant
environmental issue not considered
which is material to the site or the
design only to the extent that it differs
from those discussed or it reflects
significant new information in addition
to that discussed in the final
environmental impact statement
prepared by the Commission in
connection with the early site permit.
(c) If the combined license application
references a standard design
certification, or proposes to use a
manufactured reactor, then the
presiding officer in a combined license
hearing may not admit contentions
proffered by any party concerning
severe accident mitigation design
alternatives unless the contention
demonstrates that the site characteristics
fall outside of the site parameters in the
standard design certification or
underlying manufacturing license for
the manufactured reactor.
(d)(1) In addition to complying with
the applicable provisions of § 51.104, in
any proceeding for the issuance of a
combined license where the applicant
requests a limited work authorization
under § 50.10(c) of this chapter, the
presiding officer shall—
(i) Determine whether the
requirements of section 102(2)(A), (C)
PO 00000
Frm 00025
Fmt 4701
Sfmt 4702
61353
and (E) of NEPA and the regulations in
the subpart have been met, with respect
to the activities to be conducted under
the limited work authorization;
(ii) Independently consider the
balance among conflicting factors with
respect to the limited work
authorization which is contained in the
record of the proceeding, with a view to
determining the appropriate action to be
taken;
(iii) In an uncontested proceeding,
determine whether the NEPA review
conducted by the NRC staff for the
limited work authorization has been
adequate; and
(iv) In a contested proceeding,
determine whether in accordance with
the regulations in this subpart, the
limited work authorization should be
issued as proposed by the NRC’s
Director of Nuclear Reactor Regulation.
(2) If the limited work authorization is
for activities to be conducted at a site for
which the Commission has previously
prepared an environmental impact
statement for the construction and
operation of a nuclear power plant, and
a construction permit was issued but
construction of the plant was never
completed, then in making the
determinations in paragraph (c)(1) of
this section, the presiding officer shall
be limited to a consideration whether
there is, with respect to construction
activities encompassed by the
environmental impact statement which
are analogous to the activities to be
conducted under the limited work
authorization, significant new
information on the environmental
impacts of those activities, such that the
limited work authorization should not
be issued as proposed by the Director of
Nuclear Reactor Regulation.
(3) In making the determination
required by this section, the presiding
officer may not address or consider the
sunk costs associated with the limited
work authorization.
(4) The presiding officer’s
determination in this paragraph shall be
made in a partial initial decision to be
issued separately from, and in advance
of, the presiding officer’s decision in
paragraph (a) of this section on the
combined license.
PART 52—EARLY SITE PERMITS;
STANDARD DESIGN
CERTIFICATIONS; AND COMBINED
LICENSES FOR NUCLEAR POWER
PLANTS
24. The authority citation for part 52
continues to read as follows:
Authority: Secs. 103, 104, 161, 182, 183,
186, 189, 68 Stat. 936, 948, 953, 954, 955,
956, as amended, sec. 234, 83 Stat. 444, as
E:\FR\FM\17OCP2.SGM
17OCP2
61354
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
amended (42 U.S.C. 2133, 2201, 2232, 2233,
2236, 2239, 2282); secs. 201, 202, 206, 88
Stat. 1242, 1244, 1246, as amended (42 U.S.C.
5841, 5842, 5846); sec. 1704, 112 Stat. 2750
(44 U.S.C. 3504 note).
25. Section 52.1 is removed.
26. Section 52.3 is redesignated as
§ 52.1 and revised to read as follows:
pwalker on PROD1PC61 with PROPOSALS2
§ 52.1
Definitions.
(a) As used in this part—
Combined license means a combined
construction permit and operating
license with conditions for a nuclear
power facility issued under subpart C of
this part.
Decommission means to remove a
facility or site safely from service and
reduce residual radioactivity to a level
that permits—
(i) Release of the property for
unrestricted use and termination of the
license; or
(ii) Release of the property under
restricted conditions and termination of
the license.
Design characteristics are the actual
features of a reactor or reactors. Design
characteristics are specified in a
standard design approval, a standard
design certification, or a combined
license application.
Design parameters are the postulated
features of a reactor or reactors that
could be built at a proposed site. Design
parameters are specified in an early site
permit.
Early site permit means a Commission
approval, issued under subpart A of this
part, for a site or sites for one or more
nuclear power facilities.
License means a license, including an
early site permit, combined license or
manufacturing license under this part or
a renewed license issued by the
Commission under this part or part 54
of this chapter.
Licensee means a person who is
authorized to conduct activities under a
license issued by the Commission.
Limited work authorization means the
authorization provided by the Director
of Nuclear Reactor Regulation under
§ 50.10 of this chapter.
Manufacturing license means a
license, issued under subpart F of this
part, authorizing the manufacture of
nuclear power reactors but not their
construction, installation, or operation
at the sites on which the reactors are to
be operated.
Modular design means a nuclear
power station that consists of two or
more essentially identical nuclear
reactors (modules) and each module is
a separate nuclear reactor capable of
being operated independent of the state
of completion or operating condition of
any other module co-located on the
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
same site, even though the nuclear
power station may have some shared or
common systems.
Prototype plant means a nuclear
power plant that is used to test new
safety features, such as the testing
required under 10 CFR 50.43(e). The
prototype plant is similar to a first-of-akind or standard plant design in all
features and size, but may include
additional safety features to protect the
public and the plant staff from the
possible consequences of accidents
during the testing period.
Site characteristics are the actual
physical, environmental and
demographic features of a site. Site
characteristics are specified in an early
site permit or in a final safety analysis
report for a combined license.
Site parameters are the postulated
physical, environmental and
demographic features of an assumed
site. Site parameters are specified in a
standard design approval, standard
design certification, or a manufacturing
license.
Standard design means a design
which is sufficiently detailed and
complete to support certification in
accordance with subpart B or E of this
part, and which is usable for a multiple
number of units or at a multiple number
of sites without reopening or repeating
the review.
Standard design approval or design
approval means an NRC staff approval,
issued under subpart E of this part, of
a final standard design for a nuclear
power reactor of the type described in
10 CFR 50.22. The approval may be for
either the final design for the entire
reactor facility or the final design of
major portions thereof.
Standard design certification or
design certification means a
Commission approval, issued under
subpart B of this part, of a final standard
design for a nuclear power facility. This
design may be referred to as a certified
standard design.
(b) All other terms in this part have
the meaning set out in 10 CFR 50.2, or
Section 11 of the Atomic Energy Act, as
applicable.
27. Section 52.17 is revised to read as
follows:
§ 52.17 Contents of applications; technical
information.
(ii) The anticipated maximum levels
of radiological and thermal effluents
each facility will produce;
(iii) The type of cooling systems,
intakes, and outflows that may be
associated with each facility;
(iv) The boundaries of the site;
(v) The proposed general location of
each facility on the site;
(vi) The seismic, meteorological,
hydrologic, and geologic characteristics
of the proposed site with appropriate
consideration of the most severe of the
natural phenomena that have been
historically reported for the site and
surrounding area and with sufficient
margin for the limited accuracy,
quantity, and period of time in which
the historical data have been
accumulated;
(vii) The location and description of
any nearby industrial, military, or
transportation facilities and routes;
(viii) The existing and projected
future population profile of the area
surrounding the site;
(ix) A description and safety
assessment of the site on which a
facility is to be located. The assessment
must contain an analysis and evaluation
of the major structures, systems, and
components of the facility that bear
significantly on the acceptability of the
site under the radiological consequence
evaluation factors identified in
paragraphs (a)(1)(ix)(A) and (a)(1)(ix)(B)
of this section. In performing this
assessment, an applicant shall assume a
fission product release 1 from the core
into the containment assuming that the
facility is operated at the ultimate power
level contemplated. The applicant shall
perform an evaluation and analysis of
the postulated fission product release,
using the expected demonstrable
containment leak rate and any fission
product cleanup systems intended to
mitigate the consequences of the
accidents, together with applicable site
characteristics, including site
meteorology, to evaluate the offsite
radiological consequences. Site
characteristics must comply with part
100 of this chapter. The evaluation must
determine that:
(A) An individual located at any point
on the boundary of the exclusion area
for any 2 hour period following the
onset of the postulated fission product
release, would not receive a radiation
(a) The application must contain:
(1) A site safety analysis report. The
site safety analysis report must include
the following:
(i) The specific number, type, and
thermal power level of the facilities, or
range of possible facilities, for which the
site may be used;
1 The fission product release assumed for this
evaluation should be based upon a major accident,
hypothesized for purposes of site analysis or
postulated from considerations of possible
accidental events. Such accidents have generally
been assumed to result in substantial meltdown of
the core with subsequent release into the
containment of appreciable quantities of fission
products.
PO 00000
Frm 00026
Fmt 4701
Sfmt 4702
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
pwalker on PROD1PC61 with PROPOSALS2
dose in excess of 25 rem 2 total effective
dose equivalent (TEDE).
(B) An individual located at any point
on the outer boundary of the low
population zone, who is exposed to the
radioactive cloud resulting from the
postulated fission product release
(during the entire period of its passage)
would not receive a radiation dose in
excess of 25 rem TEDE;
(x) For nuclear power facilities to be
sited on multi-unit sites, an evaluation
of the potential hazards to the
structures, systems, and components
important to safety of operating units
resulting from construction activities, as
well as a description of the managerial
and administrative controls to be used
to provide assurance that the limiting
conditions for operation are not
exceeded as a result of construction
activities at the multi-unit sites;
(xi) Information demonstrating that
site characteristics are such that
adequate security plans and measures
can be developed;
(xii) For applications submitted after
[effective date of final rule], a
description of the quality assurance
program applied to site-related activities
for the future design, fabrication,
construction, and testing of the
structures, systems, and components of
a facility or facilities that may be
constructed on the site. Appendix B to
10 CFR part 50 contains requirements
for quality assurance programs for
nuclear power plants. The description
of the quality assurance program for a
nuclear power plant site must include a
discussion of how the applicable
requirements of appendix B to 10 CFR
part 50 will be satisfied; and
(xiii) An evaluation of the site against
applicable sections of the Standard
Review Plan (SRP) revision in effect 6
months before the docket date of the
application. The evaluation required by
this section must include an
identification and description of all
differences in analytical techniques and
procedural measures proposed for a site
and those corresponding techniques and
measures given in the SRP acceptance
criteria. Where such a difference exists,
2 A whole body dose of 25 rem has been stated
to correspond numerically to the once in a lifetime
accidental or emergency dose for radiation workers
which, according to NCRP recommendations at the
time could be disregarded in the determination of
their radiation exposure status (see NBS Handbook
69 dated June 5, 1959). However, its use is not
intended to imply that this number constitutes an
acceptable limit for an emergency dose to the public
under accident conditions. Rather, this dose value
has been set forth in this section as a reference
value, which can be used in the evaluation of plant
design features with respect to postulated reactor
accidents, to assure that these designs provide
assurance of low risk of public exposure to
radiation, in the event of an accident.
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
the evaluation must discuss how the
proposed alternative provides an
acceptable method of complying with
the Commission’s regulations, or
portions thereof, that underlie the
corresponding SRP acceptance criteria.
The SRP was issued to establish criteria
that the NRC staff intends to use in
evaluating whether an applicant/
licensee meets the Commission’s
regulations. The SRP is not a substitute
for the regulations, and compliance is
not a requirement.
(2) A complete environmental report
as required by 10 CFR 51.50(b).
(b)(1) The application must identify
physical characteristics of the proposed
site, such as egress limitations from the
area surrounding the site, that could
pose a significant impediment to the
development of emergency plans. If
physical characteristics are identified
that could pose a significant
impediment to the development of
emergency plans, the application must
identify measures that would, when
implemented, mitigate or eliminate the
significant impediment.
(2) The application may also:
(i) Propose major features of the
emergency plans in the site safety
analysis report, in accordance with the
pertinent standards of 10 CFR 50.47,
and the requirements of appendix E to
10 CFR part 50, such as the exact size
and configuration of the emergency
planning zones, that can be reviewed
and approved by NRC in consultation
with the Federal Emergency
Management Agency (FEMA) in the
absence of complete and integrated
emergency plans; or
(ii) Propose complete and integrated
emergency plans in the site safety
analysis report for review and approval
by the NRC, in consultation with FEMA,
in accordance with the applicable
standards of 10 CFR 50.47, and the
requirements of appendix E to 10 CFR
part 50. To the extent approval of
emergency plans is sought, the
application must contain the
information required by §§ 50.33(g) and
(j) of this chapter.
(3) Emergency plans, and each major
feature of an emergency plan, submitted
under paragraph (b)(2) of this section
must include the proposed inspections,
tests, and analyses that the holder of a
combined license referencing the early
site permit shall perform, and the
acceptance criteria that are necessary
and sufficient to provide reasonable
assurance that, if the inspections, tests,
and analyses are performed and the
acceptance criteria met, the facility has
been constructed and will operate in
conformity with the license, the
PO 00000
Frm 00027
Fmt 4701
Sfmt 4702
61355
provisions of the Atomic Energy Act,
and the NRC’s regulations.
(4) Under paragraphs (b)(1) and
(b)(2)(i) of this section, the application
must include a description of contacts
and arrangements made with Federal,
State, and local governmental agencies
with emergency planning
responsibilities. The application must
contain any certifications that have been
obtained. If these certifications cannot
be obtained, the application must
contain information, including a utility
plan, sufficient to show that the
proposed plans provide reasonable
assurance that adequate protective
measures can and will be taken in the
event of a radiological emergency at the
site. Under the option set forth in
paragraph (b)(2)(ii) of this section, the
applicant shall make good faith efforts
to obtain from the same governmental
agencies certifications that:
(i) The proposed emergency plans are
practicable;
(ii) These agencies are committed to
participating in any further
development of the plans, including any
required field demonstrations; and
(iii) That these agencies are
committed to executing their
responsibilities under the plans in the
event of an emergency.
(c) An applicant may request that a
limited work authorization under 10
CFR 50.10 be issued in conjunction with
the early site permit. The application
must include the information otherwise
required by 10 CFR 50.10.
(d) The NRC staff will advise the
applicant on whether any information
beyond that required by this section
must be submitted.
28. Section 52.24 is revised to read as
follows:
§ 52.24
Issuance of early site permit.
(a) After conducting a hearing under
§ 52.21 and receiving the report to be
submitted by the ACRS under § 52.23,
the Commission may issue an early site
permit, in the form the Commission
deems appropriate, if the Commission
finds that:
(1) An application for an early site
permit meets the applicable standards
and requirements of the Act and the
Commission’s regulations;
(2) Notifications, if any, to other
agencies or bodies have been duly
made;
(3) There is reasonable assurance that
the site is in conformity with the
provisions of the Act, and the
Commission’s regulations;
(4) The applicant is technically
qualified to engage in any activities
authorized;
(5) The proposed inspections, tests,
analyses and acceptance criteria,
E:\FR\FM\17OCP2.SGM
17OCP2
61356
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
including any on emergency planning,
are necessary and sufficient, within the
scope of the early site permit, to provide
reasonable assurance that the facility
has been constructed and will be
operated in conformity with the license,
the provisions of the Act, and the
Commission’s regulations;
(6) Issuance of the permit will not be
inimical to the common defense and
security or to the health and safety of
the public;
(7) Any significant adverse
environmental impact resulting from
activities requested under § 52.17(c) can
be redressed; and
(8) The findings required by subpart
A of 10 CFR part 51 have been made.
(b) The early site permit must specify
the site characteristics, design
parameters, and terms and conditions of
the early site permit the Commission
deems appropriate. Before issuance of
either a construction permit or
combined license referencing an early
site permit, the Commission shall find
that any relevant terms and conditions
of the early site permit have been met.
29. Section 52.25 is revised to read as
follows:
§ 52.25 Limited work authorization after
issuance of early site permit.
A holder of an early site permit may
request a limited work authorization in
accordance with 10 CFR 50.10 of this
chapter.
30. Section 52.79 is revised to read as
follows:
pwalker on PROD1PC61 with PROPOSALS2
§ 52.79 Contents of applications; technical
information in final safety analysis report.
(a) The application must contain a
final safety analysis report that
describes the facility, presents the
design bases and the limits on its
operation, and presents a safety analysis
of the structures, systems, and
components of the facility as a whole.
The final safety analysis report must
include the following information, at a
level of information sufficient to enable
the Commission to reach a final
conclusion on all safety matters that
must be resolved by the Commission
before issuance of a combined license:
(1)(i) The boundaries of the site;
(ii) The proposed general location of
each facility on the site;
(iii) The seismic, meteorological,
hydrologic, and geologic characteristics
of the proposed site with appropriate
consideration of the most severe of the
natural phenomena that have been
historically reported for the site and
surrounding area and with sufficient
margin for the limited accuracy,
quantity, and time in which the
historical data have been accumulated;
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
(iv) The location and description of
any nearby industrial, military, or
transportation facilities and routes;
(v) The existing and projected future
population profile of the area
surrounding the site;
(vi) A description and safety
assessment of the site on which the
facility is to be located. The assessment
must contain an analysis and evaluation
of the major structures, systems, and
components of the facility that bear
significantly on the acceptability of the
site under the radiological consequence
evaluation factors identified in
paragraphs (a)(1)(vi)(A) and (a)(1)(vi)(B)
of this section. In performing this
assessment, an applicant shall assume a
fission product release 1 from the core
into the containment assuming that the
facility is operated at the ultimate power
level contemplated. The applicant shall
perform an evaluation and analysis of
the postulated fission product release,
using the expected demonstrable
containment leak rate and any fission
product cleanup systems intended to
mitigate the consequences of the
accidents, together with applicable site
characteristics, including site
meteorology, to evaluate the offsite
radiological consequences. Site
characteristics must comply with part
100 of this chapter. The evaluation must
determine that:
(A) An individual located at any point
on the boundary of the exclusion area
for any 2 hour period following the
onset of the postulated fission product
release, would not receive a radiation
dose in excess of 25 rem 2 total effective
dose equivalent (TEDE).
(B) An individual located at any point
on the outer boundary of the low
population zone, who is exposed to the
radioactive cloud resulting from the
postulated fission product release
1 The fission product release assumed for this
evaluation should be based upon a major accident,
hypothesized for purposes of site analysis or
postulated from considerations of possible
accidental events. Such accidents have generally
been assumed to result in substantial meltdown of
the core with subsequent release into the
containment of appreciable quantities of fission
products.
2 A whole body dose of 25 rem has been stated
to correspond numerically to the once in a lifetime
accidental or emergency dose for radiation workers
which, according to NCRP recommendations at the
time could be disregarded in the determination of
their radiation exposure status (see NBS Handbook
69 dated June 5, 1959). However, its use is not
intended to imply that this number constitutes an
acceptable limit for an emergency dose to the public
under accident conditions. Rather, this dose value
has been set forth in this section as a reference
value, which can be used in the evaluation of plant
design features with respect to postulated reactor
accidents, to assure that these designs provide
assurance of low risk of public exposure to
radiation, in the event of an accident.
PO 00000
Frm 00028
Fmt 4701
Sfmt 4702
(during the entire period of its passage)
would not receive a radiation dose in
excess of 25 rem TEDE; and
(2) A description and analysis of the
structures, systems, and components of
the facility with emphasis upon
performance requirements, the bases,
with technical justification, upon which
these requirements have been
established, and the evaluations
required to show that safety functions
will be accomplished. It is expected that
reactors will reflect through their
design, construction and operation an
extremely low probability for accidents
that could result in the release of
significant quantities of radioactive
fission products. The descriptions must
be sufficient to permit understanding of
the system designs and their
relationship to safety evaluations. Items
as the reactor core, reactor coolant
system, instrumentation and control
systems, electrical systems, containment
system, other engineered safety features,
auxiliary and emergency systems, power
conversion systems, radioactive waste
handling systems, and fuel handling
systems must be discussed insofar as
they are pertinent. The following power
reactor design characteristics and
proposed operation will be taken into
consideration by the Commission:
(i) Intended use of the reactor
including the proposed maximum
power level and the nature and
inventory of contained radioactive
materials;
(ii) The extent to which generally
accepted engineering standards are
applied to the design of the reactor;
(iii) The extent to which the reactor
incorporates unique, unusual or
enhanced safety features having a
significant bearing on the probability or
consequences of accidental release of
radioactive materials;
(iv) The safety features that are to be
engineered into the facility and those
barriers that must be breached as a
result of an accident before a release of
radioactive material to the environment
can occur. Special attention must be
directed to plant design features
intended to mitigate the radiological
consequences of accidents. In
performing this assessment, an
applicant shall assume a fission product
release 3 from the core into the
containment assuming that the facility
3 The fission product release assumed for this
evaluation should be based upon a major accident,
hypothesized for purposes of site analysis or
postulated from considerations of possible
accidental events. These accidents have generally
been assumed to result in substantial meltdown of
the core with subsequent release into the
containment of appreciable quantities of fission
products.
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
is operated at the ultimate power level
contemplated;
(3) The kinds and quantities of
radioactive materials expected to be
produced in the operation and the
means for controlling and limiting
radioactive effluents and radiation
exposures within the limits set forth in
part 20 of this chapter;
(4) The design of the facility
including:
(i) The principal design criteria for the
facility. Appendix A to part 50 of this
chapter, ‘‘General Design Criteria for
Nuclear Power Plants,’’ establishes
minimum requirements for the principal
design criteria for water-cooled nuclear
power plants similar in design and
location to plants for which
construction permits have previously
been issued by the Commission and
provides guidance to applicants in
establishing principal design criteria for
other types of nuclear power units;
(ii) The design bases and the relation
of the design bases to the principal
design criteria;
(iii) Information relative to materials
of construction, arrangement, and
dimensions, sufficient to provide
reasonable assurance that the design
will conform to the design bases with
adequate margin for safety.
(5) An analysis and evaluation of the
design and performance of structures,
systems, and components with the
objective of assessing the risk to public
health and safety resulting from
operation of the facility and including
determination of the margins of safety
during normal operations and transient
conditions anticipated during the life of
the facility, and the adequacy of
structures, systems, and components
provided for the prevention of accidents
and the mitigation of the consequences
of accidents. Analysis and evaluation of
ECCS cooling performance and the need
for high-point vents following
postulated loss-of-coolant accidents
must be performed in accordance with
the requirements of §§ 50.46 and 50.46a
of this chapter;
(6) A description and analysis of the
fire protection design features for the
reactor necessary to comply with 10
CFR part 50, appendix A, GDC 3, and
§ 50.48 of this chapter;
(7) A description of protection
provided against pressurized thermal
shock events, including projected values
of the reference temperature for reactor
vessel beltline materials as defined in
§§ 50.60, and 50.61(b)(1) and (b)(2) of
this chapter;
(8) The analyses and the descriptions
of the equipment and systems required
by § 50.44 of this chapter for
combustible gas control;
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
(9) The coping analyses required, and
any necessary design features necessary
to address station blackout, as described
in § 50.63 of this chapter;
(10) A description of the program
required by § 50.49(a) of this chapter for
the environmental qualification of
electric equipment important to safety
and the list of electric equipment
important to safety that is required by
10 CFR 50.49(d);
(11) A description of the program(s)
necessary to ensure that the systems and
components meet the requirements of
the ASME Boiler and Pressure Vessel
Code in accordance with § 50.55a of this
chapter;
(12) A description of the primary
containment leakage rate testing
program necessary to ensure that the
containment meets the requirements of
Appendix J to 10 CFR part 50;
(13) A description of the reactor
vessel material surveillance program
required by Appendix H to 10 CFR part
50;
(14) A description of the operator
training program necessary to meet the
requirements of 10 CFR part 55;
(15) A description of the program for
monitoring the effectiveness of
maintenance necessary to meet the
requirements of § 50.65 of this chapter;
(16) The information with respect to
the design of equipment to maintain
control over radioactive materials in
gaseous and liquid effluents produced
during normal reactor operations, as
described in § 50.34a(d) of this chapter;
(17) The information with respect to
compliance with technically relevant
positions of the Three Mile Island
requirements in § 50.34(f) of this
chapter, with the exception of
§§ 50.34(f)(1)(xii), (f)(2)(ix), and (f)(3)(v);
(18) If the applicant seeks to use riskinformed treatment of SSCs in
accordance with § 50.69 of this chapter,
the information required by § 50.69(b)(2)
of this chapter;
(19) Information necessary to
demonstrate that the SSCs important to
safety comply with the earthquake
engineering criteria in 10 CFR part 50,
appendix S;
(20) Proposed technical resolutions of
those unresolved safety issues and
medium- and high-priority generic
safety issues that are identified in the
version of NUREG–0933 current on the
date 6 months before application and
that are technically relevant to the
design;
(21) Emergency plans complying with
the requirements of § 50.47 of this
chapter, and 10 CFR part 50, appendix
E;
(22)(i) All emergency plan
certifications that have been obtained
PO 00000
Frm 00029
Fmt 4701
Sfmt 4702
61357
from the State and local governmental
agencies with emergency planning
responsibilities must state that:
(A) The proposed emergency plans
are practicable;
(B) These agencies are committed to
participating in any further
development of the plans, including any
required field demonstrations; and
(C) These agencies are committed to
executing their responsibilities under
the plans in the event of an emergency;
(ii) If certifications cannot be obtained
after sustained, good faith efforts by the
applicant, then the application must
contain information, including a utility
plan, sufficient to show that the
proposed plans provide reasonable
assurance that adequate protective
measures can and will be taken in the
event of a radiological emergency at the
site.
(23) An applicant may request that a
limited work authorization under 10
CFR 50.10 be issued in advance of
issuance of the combined license. The
application must include the
information otherwise required by 10
CFR 50.10, in accordance with either 10
CFR 2.101(a)(1) through (4), or 10 CFR
2.101(a)(9).
(24) If the application is for a nuclear
power reactor design which differs
significantly from light-water reactor
designs that were licensed before 1997
or use simplified, inherent, passive, or
other innovative means to accomplish
their safety functions, the application
must describe how the design meets the
requirements in § 50.43(e) of this
chapter;
(25) A description of the quality
assurance program to be applied to the
design, fabrication, construction, and
testing of the structures, systems, and
components of the facility. Appendix B
to 10 CFR part 50 sets forth the
requirements for quality assurance
programs for nuclear power plants. The
description of the quality assurance
program for a nuclear power plant shall
include a discussion of how the
applicable requirements of appendix B
to 10 CFR part 50 will be satisfied;
(26) The applicant’s organizational
structure, allocations or responsibilities
and authorities, and personnel
qualifications requirements for
operation;
(27) Managerial and administrative
controls to be used to assure safe
operation. Appendix B to 10 CFR part
50 sets forth the requirements for these
controls for nuclear power plants. The
information on the controls to be used
for a nuclear power plant shall include
a discussion of how the applicable
requirements of appendix B to 10 CFR
part 50 will be satisfied;
E:\FR\FM\17OCP2.SGM
17OCP2
pwalker on PROD1PC61 with PROPOSALS2
61358
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
(28) Plans for preoperational testing
and initial operations;
(29) Plans for conduct of normal
operations, including maintenance,
surveillance, and periodic testing of
structures, systems, and components;
(30) Proposed technical specifications
prepared in accordance with the
requirements of §§ 50.36 and 50.36a of
this chapter;
(31) For nuclear power plants to be
operated on multi-unit sites, an
evaluation of the potential hazards to
the structures, systems, and components
important to safety of operating units
resulting from construction activities, as
well as a description of the managerial
and administrative controls to be used
to provide assurance that the limiting
conditions for operation are not
exceeded as a result of construction
activities at the multi-unit sites;
(32) The technical qualifications of
the applicant to engage in the proposed
activities in accordance with the
regulations in this chapter;
(33) A description of the training
program required by § 50.120 of this
chapter;
(34) A description and plans for
implementation of an operator
requalification program. The operator
requalification program must as a
minimum, meet the requirements for
those programs contained in § 55.59 of
this chapter;
(35) A physical security plan,
describing how the applicant will meet
the requirements of 10 CFR part 73 (and
10 CFR part 11, if applicable, including
the identification and description of
jobs as required by § 11.11(a) of this
chapter, at the proposed facility). The
plan must list tests, inspections, audits,
and other means to be used to
demonstrate compliance with the
requirements of 10 CFR parts 11 and 73,
if applicable;
(36)(i) A safeguards contingency plan
in accordance with the criteria set forth
in appendix C to 10 CFR part 73. The
safeguards contingency plan shall
include plans for dealing with threats,
thefts, and radiological sabotage, as
defined in part 73 of this chapter,
relating to the special nuclear material
and nuclear facilities licensed under
this chapter and in the applicant’s
possession and control. Each
application for this type of license shall
include the information contained in
the applicant’s safeguards contingency
plan.4 (Implementing procedures
4 A physical security plan that contains all the
information required in both §§ 73.55 of this
chapter and appendix C to 10 CFR part 73 satisfies
the requirement for a contingency plan.
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
required for this plan need not be
submitted for approval.)
(ii) Each applicant who prepares a
physical security plan, a safeguards
contingency plan, or a guard
qualification and training plan, shall
protect the plans and other related
Safeguards Information against
unauthorized disclosure in accordance
with the requirements of § 73.21 of this
chapter, as appropriate.
(37) The information which
demonstrates how operating experience
insights from generic letters and
bulletins issued up to 6 months before
the docket date of the application, or
comparable international operating
experience, have been incorporated into
the plant design;
(38) A description and analysis of
design features for the prevention and
mitigation of severe accidents (core-melt
accidents), including challenges to
containment integrity caused by coreconcrete interaction, steam explosion,
high-pressure core melt ejection,
hydrogen detonation, and containment
bypass;
(39) The earliest and latest dates for
completion of the construction;
(40) [Reserved]
(41) For applications for light-water
cooled nuclear power plant combined
licenses, an evaluation of the facility
against the Standard Review Plan (SRP)
in effect 6 months before the docket date
of the application. The evaluation
required by this section must include an
identification and description of all
differences in design features, analytical
techniques and procedural measures
proposed for a facility and those
corresponding features, techniques and
measures given in the SRP acceptance
criteria. Where a difference exists, the
evaluation must discuss how the
proposed alternative provides an
acceptable method of complying with
the Commission’s regulations, or
portions thereof, that underlie the
corresponding SRP acceptance criteria.
The SRP was issued to establish criteria
that the NRC staff intends to use in
evaluating whether an applicant/
licensee meets the Commission’s
regulations. The SRP is not a substitute
for the regulations, and compliance is
not a requirement;
(42) Information demonstrating how
the applicant will comply with
requirements for reduction of risk from
anticipated transients without scram
(ATWS) events in § 50.62 of this
chapter;
(43) Information demonstrating how
the applicant will comply with
requirements for criticality accidents in
§ 50.68 of this chapter;
PO 00000
Frm 00030
Fmt 4701
Sfmt 4702
(44) The NRC staff will advise the
applicant on whether any information
beyond that required by this section
must be submitted.
(b) If the application for a final safety
analysis report references an early site
permit, then the following requirements
apply:
(1) The final safety analysis report
need not contain information or
analyses submitted to the Commission
in connection with the early site permit,
but must contain, in addition to the
information and analyses otherwise
required, information sufficient to
demonstrate that the design of the
facility falls within the site
characteristics and design parameters
specified in the early site permit.
(2) If the final safety analysis report
does not demonstrate that design of the
facility falls within the site
characteristics and design parameters,
the application must include a request
for a variance that complies with the
requirements of §§ 52.39 and 52.93.
(3) The final safety analysis report
must demonstrate that all terms and
conditions that have been included in
the early site permit will be satisfied by
the date of issuance of the combined
license.
(4) If the early site permit approves
complete and integrated emergency
plans, or major features of emergency
plans, then the final safety analysis
report must include any new or
additional information that updates and
corrects the information that was
provided under § 52.17(b), and discuss
whether the new or additional
information materially changes the
bases for compliance with the
applicable requirements. If the proposed
facility emergency plans incorporate
existing emergency plans or major
features of emergency plans, the
application must identify changes to the
emergency plans or major features of
emergency plans that have been
incorporated into the proposed facility
emergency plans and that constitute a
decrease in effectiveness under
§ 50.54(q) of this chapter.
(5) If complete and integrated
emergency plans are approved as part of
the early site permit, new certifications
meeting the requirements of paragraph
(a)(22) of this section are not required.
(c) If the combined license application
references a standard design approval,
then the following requirements apply:
(1) The final safety analysis report
need not contain information or
analyses submitted to the Commission
in connection with the design approval,
but must contain, in addition to the
information and analyses otherwise
required, information sufficient to
E:\FR\FM\17OCP2.SGM
17OCP2
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 / Proposed Rules
pwalker on PROD1PC61 with PROPOSALS2
demonstrate that the characteristics of
the site fall within the site parameters
specified in the design approval.
(2) The final safety analysis report
must demonstrate that the interface
requirements established for the design
under § 52.137 have been met.
(3) The final safety analysis report
must demonstrate that all terms and
conditions that have been included in
the final design approval will be
satisfied by the date of issuance of the
combined license.
(d) If the combined license
application references a standard design
certification, then the following
requirements apply:
(1) The final safety analysis report
need not contain information or
analyses submitted to the Commission
in connection with the design
certification, but must contain, in
addition to the information and analyses
otherwise required, information
sufficient to demonstrate that the
characteristics of the site fall within the
site parameters specified in the design
certification.
(2) The final safety analysis report
must demonstrate that the interface
requirements established for the design
under § 52.47 have been met.
(3) The final safety analysis report
must demonstrate that all requirements
and restrictions set forth in the
referenced design certification rule must
be satisfied by the date of issuance of
the combined license.
(e) If the combined license application
references the use of one or more
manufactured nuclear power reactors
licensed under subpart F of this part,
then the following requirements apply:
(1) The final safety analysis report
need not contain information or
analyses submitted to the Commission
in connection with the manufacturing
VerDate Aug<31>2005
06:26 Oct 17, 2006
Jkt 211001
license, but must contain, in addition to
the information and analyses otherwise
required, information sufficient to
demonstrate that the site parameters for
the manufactured reactor are bounded
by the site where the manufactured
reactor is to be installed and used.
(2) The final safety analysis report
must demonstrate that the interface
requirements established for the design
have been met.
(3) The final safety analysis report
must demonstrate that all terms and
conditions that have been included in
the manufacturing license will be
satisfied by the date of issuance of the
combined license.
31. Section 52.80 is added to read as
follows:
§ 52.80 Contents of applications;
additional technical information.
The application must contain:
(a) A plant-specific probabilistic risk
assessment (PRA). If the application
references a standard design
certification or standard design
approval, or if the application proposes
to use a nuclear power reactor
manufactured under a manufacturing
license under subpart F of this part, the
plant-specific PRA must use the PRA for
the design certification, design
approval, or manufactured reactor, as
applicable, and must be updated to
account for site-specific design
information and any design changes,
departures, or variances.
(b) The proposed inspections, tests,
and analyses, including those applicable
to emergency planning, that the licensee
shall perform, and the acceptance
criteria which are necessary and
sufficient to provide reasonable
assurance that, if the inspections, tests,
and analyses are performed and the
acceptance criteria met, the facility has
PO 00000
Frm 00031
Fmt 4701
Sfmt 4702
61359
been constructed and will operate in
conformity with the combined license,
the provisions of the Atomic Energy
Act, and the NRC’s regulations.
(1) If the application references an
early site permit with ITAAC, the early
site permit ITAAC must apply to those
aspects of the combined license which
are approved in the early site permit.
(2) If the application references a
standard design certification, the ITAAC
contained in the certified design must
apply to those portions of the facility
design which are approved in the design
certification.
(3) If the application references an
early site permit with ITAAC or a
standard design certification or both, the
application may include a notification
that a required inspection, test, or
analysis in the ITAAC has been
successfully completed and that the
corresponding acceptance criterion has
been met. The Federal Register
notification required by § 52.85 must
indicate that the application includes
this notification.
(c) An environmental report, in
accordance with 10 CFR 51.50(c) if a
limited work authorization under 10
CFR 50.10 is not requested in
conjunction with the combined license
application, or in accordance with
§§ 51.49 and 51.50(c) of this chapter if
a limited work authorization is
requested in conjunction with the
combined license application.
Dated at Rockville, Maryland, this 6th day
of October 2006.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 06–8656 Filed 10–16–06; 8:45 am]
BILLING CODE 7590–01–P
E:\FR\FM\17OCP2.SGM
17OCP2
Agencies
[Federal Register Volume 71, Number 200 (Tuesday, October 17, 2006)]
[Proposed Rules]
[Pages 61330-61359]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 06-8656]
[[Page 61329]]
-----------------------------------------------------------------------
Part IV
Nuclear Regulatory Commission
-----------------------------------------------------------------------
10 CFR Parts 2, 50, 51 and 52
Licenses, Certifications, and Approvals for Nuclear Power Plants;
Supplemental Proposed Rule
Federal Register / Vol. 71, No. 200 / Tuesday, October 17, 2006 /
Proposed Rules
[[Page 61330]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Parts 2, 50, 51 and 52
RIN 3150-AG24
Licenses, Certifications, and Approvals for Nuclear Power Plants;
Supplemental Proposed Rule
AGENCY: Nuclear Regulatory Commission.
ACTION: Supplemental proposed rule.
-----------------------------------------------------------------------
SUMMARY: The Nuclear Regulatory Commission (NRC) is proposing to
supplement its proposed rule entitled ``Licenses, Certifications, and
Approvals for Nuclear Power Plants,'' which was published on March 13,
2006 (71 FR 12782). The NRC is proposing to supplement that proposed
rule by amending the regulations applicable to limited work
authorizations (LWA), which allow limited construction activities on
nuclear power plants to commence before a construction permit or
combined license is issued. This supplemental proposed rule would
modify the scope of activities that are considered construction
requiring a LWA and would also make changes to the review and approval
process for LWA requests. The NRC is proposing these changes to enhance
the efficiency of its licensing and approval process for new nuclear
reactors.
DATES: Submit comments by November 16, 2006. Comments received after
this date will be considered if it is practical to do so, but the
Commission is able to ensure consideration only for comments received
on or before this date.
ADDRESSES: You may submit comments by any one of the following methods.
Please include the following number RIN 3150-AG24 in the subject line
of your comments. Comments on rulemakings submitted in writing or in
electronic form will be made available to the public in their entirety
on the NRC rulemaking Web site. Personal information will not be
removed from your comments.
Mail comments to: Secretary, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, Attn: Rulemakings and Adjudications Staff.
E-mail comments to: SECY@nrc.gov. If you do not receive a reply e-
mail confirming that we have received your comments, contact us
directly at (301) 415-1966. You may also submit comments via the NRC's
rulemaking Web site at https://ruleforum.llnl.gov. Address questions
about our rulemaking Web site to Carol Gallagher (301) 415-5905; e-mail
cag@nrc.gov. Comments may also be submitted via the Federal eRulemaking
portal https://www.regulations.gov.
Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m. Federal workdays. (Telephone
(301) 415-1966).
Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at
(301) 415-1101.
Publicly available documents related to this rulemaking may be
examined and copied for a fee at the NRC's Public Document Room (PDR),
Public File Area O1 F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland. Selected documents, including comments, can be
viewed and downloaded electronically via the NRC rulemaking Web site at
https://ruleforum.llnl.gov.
Publicly available documents created or received at the NRC after
November 1, 1999, are available electronically at the NRC's Electronic
Reading Room at https://www.nrc.gov/NRC/ADAMS/. From this
site, the public can gain entry into the NRC's Agencywide Document
Access and Management System (ADAMS), which provides text and image
files of NRC's public documents. If you do not have access to ADAMS or
if there are problems in accessing the documents located in ADAMS,
contact the NRC Public Document Room (PDR) Reference staff at 1-800-
397-4209, 301-415-4737 or by e-mail to pdr@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Mr. Geary Mizuno, Office of the
General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone (301) 415-1639; e-mail: GSM@nrc.gov.
SUPPLEMENTARY INFORMATION:
I.. Background
A. History of the Part 52 Rulemaking Proceeding
II. Discussion
A. History of the NRC's Concept of Construction and the LWA
B. NRC's Proposed Concept of Construction and the LWA (PRM-50-
82)
C. NRC's Proposed Concept of Construction and the AEA
D. Proposed Supplement Complies With NEPA
1. NRC's Proposed Concept of Construction Is Consistent With the
Legal Effect of NEPA
2. NRC's Proposed Concept of the ``Major Federal Action'' Is
Consistent With NEPA Law
3. NRC's Phased Approval Approach Is not Illegal Segmentation
Under NEPA
E. Inclusion of Additional Activities as ``Construction'' under
Sec. 50.10(b)
F. Phased Application and Approval Process
G. EIS Prepared, but Facility Never Constructed
III. Section-by-Section Analysis
IV. Specific Request for Comments
V. Availability of Documents
VI. Plain Language
VII. Agreement State Compatibility
VIII. Voluntary Consensus Standards
IX. Environmental Impact--Categorical Exclusion
X. Paperwork Reduction Act Statement
XI. Regulatory Analysis
XII. Regulatory Flexibility Act Certification
XIII. Backfit Analysis
I. Background
A. History of the Part 52 Rulemaking Proceeding
The NRC issued 10 CFR part 52 on April 18, 1989 (54 FR 15372), to
reform its licensing process for future nuclear power plants. The rule
added alternative licensing processes in 10 CFR part 52 for early site
permits, standard design certifications, and combined licenses. These
were additions to the two-step licensing process that already existed
in 10 CFR part 50. The processes in 10 CFR part 52 allow for resolving
safety and environmental issues early in the licensing proceedings and
were intended to enhance the safety and reliability of nuclear power
plants through standardization.
The NRC had planned to update 10 CFR part 52 after using the
standard design certification process. The proposed rulemaking action
began with the issuance of SECY-98-282, ``Part 52 Rulemaking Plan,'' on
December 4, 1998. The Commission issued a staff requirements memorandum
on January 14, 1999 (SRM on SECY-98-282), approving the NRC staff's
plan for revising 10 CFR part 52. Subsequently, the NRC obtained
considerable stakeholder comment on its planned action, conducted three
public meetings on the proposed rulemaking, and twice posted draft rule
language on the NRC's rulemaking Web site before issuance of the
initial proposed rule on July 3, 2003 (68 FR 40026). However, a number
of factors led the NRC to question whether the July 2003 proposed rule
would meet the NRC's objective of improving the effectiveness of its
processes for licensing future nuclear power plants (71 FR 12782). As a
result, the NRC decided that a substantial rewrite and expansion of the
original proposed rulemaking was desirable so that the agency may more
effectively and efficiently implement the licensing and approval
processes for future nuclear power plants under part 52. Accordingly,
the Commission decided to revise the July 2003 proposed rule and
published the revised proposed rule for public comment on March 13,
2006
[[Page 61331]]
(71 FR 12782). The public comment period on the March 2006 proposed
rule ended on May 30, 2006.
II. Discussion
A. History of the NRC's Concept of Construction and the LWA
Section 101 of the Atomic Energy Act of 1954, as amended (AEA)
prohibits the manufacture, production, or use of a commercial nuclear
power reactor, except where the manufacture, production or use is
conducted under a license issued by the Commission. While construction
of a nuclear power reactor is not mentioned in section 101, section 185
of the AEA requires that the Commission grant construction permits to
applicants for licenses to construct or modify production or
utilization facilities, if the applications for such permits are
acceptable to the Commission. However, the term construction is not
defined anywhere in the AEA or in the legislative history of the Act.
To prevent the construction of production or utilization facilities
before a construction permit is issued, the NRC proposed a regulatory
definition of construction in 1960 (25 FR 1224; February 11, 1960). The
definition of construction was adopted in a final rule that same year
and codified in 10 CFR 50.10(b) (25 FR 8712; September 9, 1960). As
promulgated, Sec. 50.10(b) stated that no person shall begin the
construction of a production or utilization facility on a site on which
the facility is to be operated until a construction permit had been
issued. Construction was defined in Sec. 50.10(b) as including:
pouring the foundation for, or the installation of, any portion of
the permanent facility on the site; but [not to] include: (1) Site
exploration, site excavation, preparation of the site for
construction of the facility and construction of roadways, railroad
spurs and transmission lines; (2) Procurement or manufacture of
components of the facility; (3) Construction of non-nuclear
facilities (such as turbo-generators and turbine buildings) and
temporary buildings (such as construction equipment storage sheds)
for use in connection with the construction of the facility; and (4)
with respect to production or utilization facilities, other than
testing facilities, required to be licensed pursuant to section
104a. or section 104c. of the Act, the construction of buildings
which will be used for activities other than operation of a facility
and which may also be used to house a facility. (For example, the
construction of a college laboratory building with space for
installation of a training reactor is not affected by this
paragraph). (25 FR 8712; September 9, 1960)
The definition of construction remained unchanged until 1968, when
the driving of piles was specifically excluded from the definition (33
FR 2381; January 31, 1968). This change was implemented by amending
Sec. 50.10(b)(1) to read: ``Site exploration, site excavation,
preparation of the site for construction of the reactor, including the
driving of piles, and construction of roadways, railroad spurs, and
transmission lines.'' The rationale for this change, as articulated in
the proposed rule (32 FR 11278; August 3, 1967), seems to have been
that the driving of piles was closely related to ``preparation of the
site for construction'' and that the performance of this type of site
preparation activity would not affect the NRC's subsequent decision to
grant or deny the construction permit. With the exception of the
exclusion of the driving of piles from the definition of construction
in 1968, the NRC's interpretation of the scope of activities requiring
a construction permit under the AEA has remained largely unchanged.
However, following the enactment of the National Environmental
Policy Act of 1969, as amended (NEPA), the Commission adopted a major
amendment to the definition of construction in Sec. 50.10 (37 FR 5745;
March 21, 1972). In that rulemaking, the Commission adopted a much more
expansive concept of construction. Specifically, a new Sec. 50.10(c)
was adopted stating that no person shall effect ``commencement of
construction'' of a production or utilization facility on the site on
which such facility will be constructed until a construction permit has
been issued. ``Commencement of construction'' was defined as
any clearing of land, excavation or other substantial action that
would adversely affect the natural environment of a site and
construction of nonnuclear facilities (such as turbogenerators and
turbine buildings) for use in connection with the facility, but does
not mean: (1) Changes desirable for the temporary use of the land
for public recreational uses, necessary boring to determine
foundation conditions or other preconstruction monitoring to
establish background information related to the suitability of the
site or to the protection of environmental values; (2) Procurement
or manufacture of components of the facility; and (3) With respect
to production or utilization facilities, other than testing
facilities, required to be licensed pursuant to section 104a or
section 104c of the Act, the construction of buildings which will be
used for activities other than operation of a facility and which may
also be used to house a facility * * * . (37 FR 5748)
The Commission explained that expansion of the NRC's permitting
authority was:
[C]onsistent with the direction of the Congress, as expressed in
section 102 of the National Environmental Policy Act of 1969, that,
to the fullest extent possible, the policies, regulations and public
laws of the United States shall be interpreted and administered in
accordance with the policies set forth in that Act. Since site
preparation constitutes a key point from the standpoint of
environmental impact, in connection with the licensing of nuclear
facilities and materials, these amendments will facilitate
consideration and balancing of a broader range of realistic
alternatives and provide a more significant mechanism for protecting
the environment during the earlier stages of a project for which a
facility or materials license is being sought. (37 FR 5746)
Thus, the Commission's interpretation of its responsibilities under
NEPA, not the AEA, was the driving factor leading to its adoption of
Sec. 50.10(c).\1\
---------------------------------------------------------------------------
\1\ See The Carolina Power and Light Company (Shearon Harris
Nuclear Power Plant, Units 1, 2, 3 and 4), 7 AEC 939, 943 (June 11,
1974) (hereinafter Shearon Harris) (``The regulations were revised
in 1972, not because of any requirements of the Atomic Energy Act,
but rather to implement the precepts of NEPA which had then recently
been enacted.''); Kansas Gas and Electric Company (Wolf Creek
Nuclear Generating Station, Unit No. 1), 5 NRC 1, 5 (Jan. 12, 1977)
(explaining that NEPA led the AEC to amend its regulations in
several respects, including the changes to 50.10(c)).
---------------------------------------------------------------------------
Two years after the expansion of the Commission's permitting
authority resulting from the promulgation of Sec. 50.10(c), the NRC
promulgated Sec. 50.10(e) (39 FR 14506; April 24, 1974). This
provision created the current LWA process, which was added to allow
site preparation, excavation and certain other on-site activities to
proceed before issuance of a construction permit. Prior to the
promulgation of Sec. 50.10(e), NRC permission to engage in site
preparation activities before a construction permit was issued could
only be obtained via an exemption issued under Sec. 50.12. The
provisions of Sec. 50.10(e) allowed the NRC to authorize the
commencement of both safety-related (known as ``LWA-II'' activities)
and non safety-related (known as ``LWA-I'' activities) on-site
construction activities before issuance of a construction permit if the
NRC had completed a final environmental impact statement (FEIS) on the
issuance of the construction permit and the presiding officer in the
construction permit proceeding had made the requisite environmental
and, in the case of an LWA-II, safety-related findings.
B. NRC's Proposed Concept of Construction and the LWA (PRM-50-82)
The NRC received several comments in response to its Part 52
proposed rule revision published on March 13, 2006 (71 FR 12782),
including comments submitted by the Nuclear Energy Institute (NEI)
dated May 25, 2006.\2\
[[Page 61332]]
NEI's comments suggested modifications to the NRC's LWA process
including: (1) That non-safety related ``LWA-I'' activities, currently
reflected in Sec. 50.10(c) and Sec. 50.10(e)(1), be allowed to
proceed without prior authorization from the NRC, and (2) that the
approval process for safety-related ``LWA-II'' activities be
accelerated. NEI's comment also stated that the current definition of
construction in Sec. 50.10(b) reflects the correct interpretation of
the Commission's licensing authority under the AEA.
---------------------------------------------------------------------------
\2\ See Letter from Adrian P. Heymer, Nuclear Energy Institute
to Annette L. Vietti-Cook, Secretary, U.S. Nuclear Regulatory
Commission, Pre-Licensing Construction Activity and Limited Work
Authorization Issues relating to NRC Proposed Rule, ``Licenses,
Certifications and Approvals for Nuclear Power Plants,'' 71 FR 12,
782 (March 13, 2006) (RIN 3150-AG24) (May 25, 2006).
---------------------------------------------------------------------------
Further, NEI's comment letter stated that ``[t]o the extent the NRC
determines that these LWA issues cannot be addressed in the current
rulemaking, we ask that the Commission initiate an expedited
rulemaking.'' The NRC has determined that the changes suggested in the
NEI comment could not be incorporated into the final Part 52 rule
without re-noticing. Therefore, the Commission has decided that the NEI
letter meets the sufficiency requirements described in 10 CFR 2.802(c)
and is docketing the letter as a petition for rulemaking (PRM-50-82).
Furthermore, the NRC has determined that it is appropriate to seek
public comment on the action requested by petitioner within the context
of this supplemental proposed rule, which has been developed in
response to NEI's request, as allowed under 10 CFR 2.802(e).
NEI supported its suggested changes to the LWA process, stating
that the business environment requires that new plant applicants seek
to minimize the time interval between a decision to proceed with a
combined license application and the start of commercial operation. In
order to achieve this goal, NEI states that non safety-related ``LWA-
I'' activities would need to be initiated up to two years before the
activities currently defined as ``construction'' in Sec. 50.10(b). In
NEI's view, the current LWA approval process would constrain the
industry's ability to use modern construction practices and needlessly
add eighteen (18) months to estimated construction schedules for new
plants that did not reference an early site permit (ESP) with LWA
authority.
The NRC agrees, in part, with NEI's comments and is now issuing
this supplement to the March 13, 2006 proposed rule.\3\ This
supplemental proposed rule would narrow the scope of activities
requiring permission from the NRC in the form of limited work
authorizations (LWA) by eliminating the concept of ``commencement of
construction'' currently described in Sec. 50.10(c) and the
authorization described in Sec. 50.10(e)(1). Instead, under the
supplemental proposed rule, NRC authorization would only be required
before undertaking activities that have a reasonable nexus to
radiological health and safety and/or common defense and security (i.e.
excavation, subsurface preparation, installation of the foundation, and
on-site, in-place fabrication, erection, integration or testing, for
any structure, system or component of a facility required by the
Commission's rules and regulations to be described in the site safety
analysis report or preliminary or final safety analysis report). While
this redefinition of ``construction'' would result in fewer activities
requiring NRC permission in the form of a LWA, it also redefines
certain activities (such as the driving of piles), that are currently
excluded from the regulatory definition of construction given in Sec.
50.10(b), as construction requiring a LWA.
---------------------------------------------------------------------------
\3\ Industry stakeholders did not raise issues relating to
perceived problems either with the LWA process or, more generally,
with the definition of construction during the period leading to the
March 2006 proposed rule and no such changes were suggested in the
proposed rule. Therefore, the NRC is providing notice and an
opportunity for public comment on the changes proposed in this
supplement. The Commission may adopt this supplemental proposed rule
either as part of the final rule promulgating the changes to Part 52
(see 71 FR 12782; March 13, 2006), or in a separate final rule.
---------------------------------------------------------------------------
Further, this proposed rule would provide an optional, phased
application and approval procedure for construction permit and combined
license applicants to obtain limited work authorizations. Specifically,
the proposed rule would provide an environmental review and approval
process for LWA requests that would allow the NRC to grant an applicant
permission to engage in LWA activities after completion of a limited
environmental impact statement addressing those activities, but before
completion of the comprehensive environmental impact statement
addressing the underlying request for a construction permit or combined
license. Finally, this proposed rule would specifically address the
environmental review required in situations where the LWA activities
are to be conducted at sites for which the Commission has previously
prepared an environmental impact statement for the construction and
operation of a nuclear power plant, and for which a construction permit
was issued, but construction of the plant was never completed.
C. NRC's Proposed Concept of Construction and the AEA
This change is fully consistent with the Commission's radiological
health and safety and common defense and security responsibilities
under the AEA.\4\ Specifically, the Commission has determined that the
site-preparation activities that would no longer be considered
construction under this proposed rule do not have a reasonable nexus to
radiological health and safety, or the common defense and security.
Further, as previously mentioned, the term ``construction'' is not
defined in the AEA or in the Act's legislative history. Instead of
expressly defining the term in the AEA, Congress entrusted the agency
with the responsibility of determining what activities constitute
construction.\5\ The Commission believes that its proposed definition
of the term ``construction'' is reasonable.
---------------------------------------------------------------------------
\4\ See State of New Hampshire v. Atomic Energy Commission, 406
F.2d 170, 174-75 (1st Cir. 1969).
\5\ Shearon Harris, 7 AEC 939.
---------------------------------------------------------------------------
D. Proposed Supplement Complies With NEPA
1. NRC's Proposed Concept of Construction is Consistent with the Legal
Effect of NEPA
The proposed change in the definition of construction is also
consistent with the legal effect of NEPA. Section 50.10(c) was
originally added to part 50 due to the interpretation that the
enactment of NEPA, not a change in the powers delegated to the agency
in the AEA, required the NRC to expand its permitting/licensing
authority. However, subsequent judicial decisions have made it clear
that NEPA is a procedural statute and does not expand the jurisdiction
delegated to an agency by its organic statute.\6\ Therefore, while NEPA
may require the NRC to consider the environmental effects caused by the
exercise of its permitting/licensing authority, the statute cannot be
the source of the expansion of the NRC's authority to require
construction permits, combined licenses, or other forms of permission
for activities that are not reasonably related to radiological health
and safety or protection of the common defense and security. Since NEPA
cannot expand the
[[Page 61333]]
Commission's permitting/licensing authority under the AEA, the
elimination of the blanket inclusion of site preparation activities in
the definition of construction under Sec. 50.10(c) does not violate
NEPA.
---------------------------------------------------------------------------
\6\ See, e.g., Robertson v. Methow Valley Citizens Council, 490
U.S. 332, 350-52 (1989); Natural Resources Defense Counsel v. U.S.
Environmental Protection Agency, 822 F.2d 104, 129 (D.C. Cir 1987);
Kitchen v. Federal Communications Commission, 464 F.2d 801, 802
(D.C. Cir. 1972).
---------------------------------------------------------------------------
2. NRC's Proposed Concept of the ``Major Federal Action'' is Consistent
with NEPA Law
Because the AEA does not authorize NRC to require an applicant to
obtain permission before undertaking site preparation activities that
do not implicate radiological health and safety or common defense and
security, as a general matter the Commission considers these activities
``non-Federal action'' for the purposes of implementing its NEPA
responsibilities. Generally, non-Federal actions are not subject to the
requirements of NEPA.\7\
---------------------------------------------------------------------------
\7\ Save the Bay, Inc. v. U.S. Army Corps of Engineers, 610 F.2d
322, 326 (5th Cir. 1980).
---------------------------------------------------------------------------
Further, the Commission believes that these non-Federal site
preparation activities would not generally be ``federalized'' if the
Commission were to ultimately grant a combined license or construction
permit. The grant of a construction permit or combined license by the
Commission is not a legal condition precedent to these non-Federal,
site preparation activities. While the Commission recognizes that there
may be a ``but for'' causal relationship between certain non-Federal
site preparation activities and the major Federal action of issuing a
construction permit or combined license, such a ``but for'' causal
relationship is not sufficient to require non-Federal site preparation
activities to be treated as Federal action for the purposes of NEPA.\8\
---------------------------------------------------------------------------
\8\ See Landmark West! v. U.S. Postal Service, 840 F.Supp. 994,
1006 (S.D.N.Y. 1993) (citing cases).
---------------------------------------------------------------------------
In addition, under the proposed definition of construction, the
Commission does not believe that it has sufficient ability or
discretion to influence or control the non-Federal, site preparation
activities to the extent that its influence or control would constitute
practical or factual veto power over the non-Federal action. Further,
the Commission does not believe that allowing the non-Federal, site
preparation activities to be undertaken would restrict its
consideration of alternative sites or the need to assess whether there
is an ``obviously superior'' site. Specifically, while the Commission
recognizes that narrowing the definition of construction may result in
substantial changes to the physical properties of a site, many of the
fundamental elements that enter into a determination of the existence
of an ``obviously superior'' site would not be affected by the changes
to those physical properties. For example, meteorology and seismology
would not be affected in any significant way by the non-Federal site
preparation activities.
However, while the effects caused by the non-Federal, site
preparation activities would not be considered effects of the
Commission's licensing action, the effects of the non-Federal
activities would be considered during any subsequent ``cumulative
impacts'' analysis. Specifically, the effects of the non-Federal
activities would be considered in order to establish a baseline against
which the incremental effect of the Commission's major Federal action
(i.e. issuing a LWA, construction permit or combined license) would be
measured. These incremental impacts may be additive or synergistic.
3. NRC's Phased Approval Approach is not Illegal Segmentation Under
NEPA
The phased application and approval of LWAs does not raise the
concerns underlying the prohibition of segmentation under NEPA law.
Generally, the NEPA segmentation problem arises when the environmental
impacts of projects are evaluated in a piecemeal fashion and, as a
result, the comprehensive environmental impacts of the entire Federal
action are never considered or are only considered after the agency has
committed itself to continuation of the project. Another associated
segmentation problem arises when pieces of a Federal action are
evaluated separately and, as a result, none of the individual pieces
are considered ``major federal actions'' requiring an EIS.\9\
---------------------------------------------------------------------------
\9\ Daniel R. Mandelker, NEPA Law and Litigation, 9-25 (2nd ed.
2004).
---------------------------------------------------------------------------
Neither of these segmentation concerns are presented by the
approach proposed here. First, under both LWA application options, the
environmental effects associated with the LWA activities and the
project as a whole (i.e. issuance of a construction permit or combined
license) would be evaluated in an EIS. Therefore, the segmentation
problem of considering a project in phases, thereby avoiding completion
of an EIS, is not an issue. In addition, all of the environmental
impacts associated with the construction and operation of the proposed
plant, including the impacts associated with the LWA activities, would
be considered together, through incorporation by reference, in the EIS
prepared on the construction permit or combined license application.
This comprehensive consideration of environmental impacts would take
place before the NRC is committed to issuing any construction permit or
combined license. The fact that the NRC will not have prejudged the
ultimate decision of whether to grant a construction permit or a
combined license by issuing the LWA, coupled with the requirement that
the site redress plan be implemented in the event that the permit or
license is ultimately not issued, also ensures that issuance of the LWA
would not foreclose reasonable alternatives.
In addition, the proposed application and approval process is
consistent with the Commission's previously expressed position that
NEPA does not, as a general matter, prohibit an agency from undertaking
part of a project without a complete environmental analysis of the
whole project.\10\ The key factors used to support the Commission's
position in Clinch River were; (1) That the site preparation activities
in that case would not result in irreversible or irretrievable
commitments to the remaining portions of the project and (2) the
environmental impacts of the site preparation activities allowed in
that case were substantially redressable.\11\
---------------------------------------------------------------------------
\10\ See Tennessee Valley Authority (Clinch River Breeder
Reactor Plant), 16 NRC 412, 424 (Aug. 17, 1982) (hereinafter Clinch
River).
\11\ Id.
---------------------------------------------------------------------------
These considerations are reflected in the provisions of the
supplemental proposed rule. Specifically, Sec. 50.10(c)(6) of the
proposed rule states that any activity undertaken pursuant to a LWA are
entirely at the risk of the applicant, that the issuance of the LWA has
no bearing on whether the construction permit or combined license
should be issued, and that the environmental impact statement
associated with the underlying request will not consider the sunk costs
associated with the LWA activities. In addition, Sec. 50.10(c)(3)
would require an applicant requesting a LWA to submit a plan for
redress of the site to be implemented in the event that the LWA holder
is ultimately not issued a construction permit or combined license.
This site redress plan must ``achieve an environmentally stable and
aesthetically acceptable site suitable for whatever non-nuclear use may
conform with local zoning laws'' in the event that the LWA holder is
not ultimately issued a construction permit or combined license. The
redress plan would achieve this objective by addressing site impacts
resulting from LWA activities. Impacts associated with pre-LWA
activities would not be addressed in the redress plan. Further,
[[Page 61334]]
Sec. 50.10(c)(7) would require that the site redress plan be
implemented within a reasonable time and that the redress of the site
occur within eighteen (18) months of the Commission's final decision
denying a construction permit or combined license.
It should be noted that while redress of site impacts may have the
practical effect of mitigating some environmental impacts, the redress
plan is not a substitute for a thorough evaluation of environmental
impacts, or development of mitigation measures that may be necessary to
provide relief from environmental impacts associated with the proposed
LWA activities. The primary purpose of the site redress plan is to
ensure that impacts associated with any LWA activities performed at the
site will not prevent the site from being utilized for a permissible,
non-nuclear alternative use. In this way, the redress plan helps to
preserve the Commission's ability to objectively evaluate an
application for a construction permit or combined license, despite the
fact that LWA activities have been undertaken at the site.
E. Inclusion of Additional Activities as ``Construction'' Under Sec.
50.10(b)
A significant change proposed in this supplemental proposed rule is
the inclusion of activities--such as the driving of piles and
excavation of foundations for safety-related structures--in the
definition of construction that are not currently defined as
construction in Sec. 50.10(b).
Although the driving of piles was not expressly included in the
definition of ``construction'' contained in Sec. 50.10(b) before the
amendment of Sec. 50.10(b)(1) in 1968, this activity was generally
considered to be encompassed in the existing definition of construction
at that time (See 33 FR 2381; January 31, 1968). The proposed rule
suggesting that the driving of piles be expressly excluded from the
definition of construction simply states that the ``activity is closely
related to, and may be appropriately included in'' site preparation
activities, which were not considered construction (32 FR 11278; August
3, 1967).\12\ The rationale for not including the driving of piles, and
site preparation activities generally, in the definition of
construction seems to have been that these activities would have no
effect on the NRC's ultimate decision to grant or deny a construction
permit and that these activities were undertaken entirely at the
applicant's risk (32 FR 11278).
---------------------------------------------------------------------------
\12\ The proposed rule language was promulgated without
modification in the final rule. 33 FR 2381.
---------------------------------------------------------------------------
The NRC does not currently believe that the exclusion of a site
preparation activity from the definition of construction should hinge
on this factor. The Commission believes that the site preparation
activities described in Sec. 50.10(b) of this supplement, including
the driving of piles and excavation of foundations in certain
situations, have a reasonable nexus to radiological health and safety,
and/or common defense and security and, therefore, are properly
considered ``construction'' as that term is used in Sec. 185 of the
AEA. In addition, the inclusion of these activities in the definition
of construction (i.e. requiring an LWA before they are undertaken),
coupled with the phased approval process suggested in this supplemental
proposed rule, would allow for early resolution of the safety issues
associated with these activities. Early resolution of safety issues is
consistent with the general rationale underlying the licensing and
permitting processes provided in 10 CFR part 52.
F. Phased Application and Approval Process
Another significant change suggested in this supplemental proposed
rule is the modification of the procedure for obtaining LWA approval by
implementing an optional phased application and approval process.
Specifically, as proposed, Sec. 2.101(a)(9) would allow applicants for
construction permits and combined licenses the option of submitting
either: (1) A complete application or (2) a two part application with
part one including information required for the NRC to make a decision
on the applicant's request to undertake LWA activities and part two
containing all other information required to obtain the underlying
license or permit. The proposed rule would allow the NRC to consider
the environmental impacts attributable to the requested LWA activities
separately, either as part of a comprehensive environmental impact
statement (EIS) in the case where a complete application is submitted,
or in a separate EIS addressing only the LWA activities in the case of
a two-part application. After consideration of the environmental
impacts and the relevant safety-related issues associated with the LWA
activities, the NRC would be permitted to allow the applicant to
undertake the LWA activities, even if the EIS on the underlying request
(i.e. construction permit or combined license) is not complete.
The NRC believes that this phased application/approval process
would add efficiencies to the licensing/construction process by
preventing unnecessary delay in construction schedules, which would
result if issuance of an LWA for safety-related activities were delayed
until the final environmental impact statement and adjudicatory hearing
on the entire underlying license application were complete. In
addition, the proposed application/approval process would result in the
timely resolution of relevant safety and environmental issues at an
earlier stage in the licensing process. As previously discussed, the
NRC believes that these efficiencies can be gained without compromising
the agency's NEPA responsibilities, as the phased approach presented in
this supplemental proposed rule does not constitute illegal
segmentation.
G. EIS Prepared, but Facility Never Constructed
The supplemental proposed rule also specifically addresses the
situation where a request is made to perform LWA activities at a site
for which an EIS has previously been prepared for the construction and
operation of a nuclear power plant, and a construction permit has been
issued, but construction of the plant was never completed. In this
special situation, the proposed supplement would allow an applicant to
reference the previous EIS in its environmental report, but requires
that the applicant identify any new and significant information
material to the matters required to be addressed in the proposed Sec.
51.49(a). Further, in these special cases the proposed supplement would
allow the NRC to incorporate the previous EIS by reference when
preparing its draft EIS on the LWA activities. The draft EIS on the LWA
request would be limited to the consideration of any significant new
information dealing with the environmental impacts of construction,
relevant to the activities to be carried out under the LWA. Further, in
a hearing on issuance of an LWA at such sites, the presiding officer
would be limited to determining whether there is significant new
information pertaining to the environmental impacts of the construction
activities encompassed by the previous EIS that are analogous to the
activities to be conducted under the LWA. The presiding officer would
evaluate significant new information indetermining whether an LWA
should be issued as proposed by the Director of Nuclear Reactor
Regulation.
This provision is designed to gain efficiency by using existing
environmental impact statements to evaluate the environmental impacts
of
[[Page 61335]]
activities to be performed under an LWA. The Commission believes that
this practice is appropriate because the referenced environmental
review will come in the form of a FEIS prepared by NRC staff for sites
on which permission to construct a nuclear power plant was ultimately
granted by the Commission. The Commission understands that the
activities proposed in a current LWA request may be different from the
activities proposed and analyzed in the previous FEIS referenced by an
applicant and relied upon by NRC staff. However, it is the Commission's
intent that if such differences will likely result in significant
changes to the environmental impacts caused by the LWA activities
currently proposed by the applicant, then the differences should be
considered ``new and significant information'' material to the
environmental impacts that may reasonably be expected to result from
the LWA activities and, therefore, should be addressed in the
applicant's environmental report, analyzed by the staff in a supplement
to the existing FEIS, and considered by the presiding officer.
Further, for the reasons previously discussed in section D.3, the
Commission does not believe that authorizing LWA activities before
completion of the FEIS on the combined license or construction permit
would have the effect of prejudging the license/permit, or foreclosing
reasonable alternatives.
III. Section-by-Section Analysis
Part 2
Section 2.101 Filing of Application
Section 2.101 would be revised to add a new paragraph (a)(9), which
would state that an applicant for a construction permit or combined
license may submit a request for an LWA either as part of a complete
application under paragraphs (a)(1) through (4), or in two parts under
this paragraph (i.e., a ``phased LWA application''). If the LWA
application is submitted as part of a complete construction permit or
operating license application, the application must include the
information required by Sec. 50.10(c).
If the application is a phased LWA application, the first part must
contain the information required by Sec. 50.10(c) on the LWA, as well
as the general information required of all production and utilization
facility applicants under Sec. 50.33(a) through (f). The second part
of the application would contain the remaining information otherwise
required to be filed in a complete application under Sec. 2.101(a)(1)
thorough (4). However, the applicant would have the further option of
submitting part two in additional subparts in accordance with Sec.
2.101(a-1). The second part (or the first subpart of multiple subparts
under Sec. 2.101(a-1)) must be filed no later than twelve (12) months
after the filing of part one. Part two of the application (or the first
subpart of any additional subparts submitted in accordance with Sec.
2.101(a-1)) must be submitted no later that twelve (12) months after
submission of part one of the application.
An applicant for an early site permit may not submit its LWA
application in advance of the underlying early site permit application,
and therefore is not permitted to use the procedures of Subpart F.
Section 2.104 Notice of Hearing
Paragraph (d)(1)(iii) of Sec. 2.104 would be modified to more
clearly refer to the authority requested under Sec. 52.17(c) as the
limited work authorization under Sec. 50.10.
Subpart F
The title of Subpart F would be revised to reflect the broader
scope of matters covered under this section, as described under Sec.
2.600.
Section 2.600 Scope of Subpart
The statement of scope in Sec. 2.600 would be revised to reflect
the new set of procedures for phased LWA applications in proposed
Sec. Sec. 2.641 through 2.649.
Section 2.601 Applicability of Other Sections
Section 2.601 would be corrected to add references to subparts C, L
and N of part 2, in order to make clear that these subparts (in
addition to subparts A and G) apply to applications and proceedings
under subpart F, except as specifically provided in subpart F.
Section 2.606 Partial Decision on Site Suitability Issues
Paragraph (a) of Sec. 2.606, which provides that a LWA may not be
issued without completion of the ``full review'' required by NEPA,
would be revised to remove the reference to a LWA, inasmuch as LWAs
would now be covered in Sec. Sec. 2.641 through 2.649.
Section 2.641 Filing Fees
Section 2.641, which is comparable to current Sec. 2.602, provides
that a phased LWA application shall be accompanied by the applicable
filing fees in Sec. 50.30(e) and part 170 of this chapter.
Section 2.643 Acceptance and Docketing of Application for Limited Work
Authorization
Section 2.643, which is comparable to current Sec. 2.603,
describes the acceptance and docketing requirements for phased LWA
applications, and the requirement for publication in the Federal
Register of a notice of docketing. Paragraph (a) provides that each
part of the application, when first received, will be treated as a
tendered application and assessed for sufficiency. If the submitted
part of the application is determined to be incomplete, the Director of
NRR (Director) will inform the applicant. The determination of
completeness will generally be made in 30 days, barring unusual
circumstances.
Under paragraph (b), the Director will docket part one of the
application only if that part is ``complete.'' The NRC would use the
existing guidelines and practices for determining the completeness of
applications under this section, as are used in determining
completeness under Sec. 2.101. Upon docketing, the Director will
assign a docket number that will be used throughout the entire
proceeding (including that part of the proceeding on part two of the
application). Under paragraph (c), the Director would make the
designated distributions to the Governor of the state in which the
nuclear power plant will be located, and publish a notice of docketing
in the Federal Register. Often in practice, the notice of hearing
required by the AEA is included in the notice of docketing, but as with
existing applications, this will remain a matter of discretion by the
NRC, who will determine what is the most efficient course of action in
this regard.
Paragraph (d) provides that part two of the application will be
docketed, as with part one, when it is determined to be complete. The
Commission reiterates that ``part two'' could be submitted in several
subparts, if the applicant chose to take advantage of the provisions of
Sec. 2.101(a-1), which provides for submission of applications in
three parts.
Finally, under paragraph (e), the Director will publish a second
notice of docketing in the Federal Register, in this case for part two
of the application. As with the notice of docketing for part one, the
notice of docketing for part two may also include a notice of hearing
on the second part of the application.
The Commission notes that nothing in Sec. 2.101(a)(9), or any part
of subpart F, requires that the hearing on part one of the application
be completed and an initial decision issued by the presiding
[[Page 61336]]
officer, before part two of the application is filed.
Section 2.645 Notice of Hearing
Section 2.645, which is comparable to current Sec. 2.604, sets
forth the content of the notice of hearing for each of the two parts of
the proceeding. Paragraph (a) provides that the notice of hearing for
part one specify that the hearing will relate only to consideration of
the matters related to Sec. 50.33(a) through (f), and the limited work
authorization issues under review. Although not explicitly stated in
this paragraph, interested persons who seek to intervene in the hearing
on part one of the application must file a petition to intervene in
accordance with the notice of hearing, and Sec. 2.309.
Under paragraph (b), a supplementary notice of hearing will be
published in the Federal Register when part two of the application is
docketed. This provides a second opportunity for interested persons to
file petitions to intervene with respect to the matters relevant to
part two of the application. These petitions must be filed within the
time period specified in the notice of hearing, and must meet the
applicable requirements of subpart C of part 2, including the
contention requirements in Sec. 2.309.
Paragraph (c) of the proposed rule differs somewhat from Sec.
2.604, in that the Commission proposes not to allow a party admitted in
part one of the proceeding, who did not withdraw or was not otherwise
dismissed, to automatically continue as a party in phase two of the
proceeding. Instead, each party who wishes to participate in the second
phase must submit a second petition to intervene in accordance with
Sec. 2.309, but the petition need not address the interest and
standing requirements in Sec. 2.309(d). The petition must be filed
within the time period provided by the supplementary notice of hearing
published in the Federal Register for part two of the application.
As noted in the section-by-section analysis for Sec. 2.643,
nothing in Sec. 2.101(a)(9) or subpart F requires that the hearing on
part one of the application be completed and an initial decision issued
by the presiding officer, before part two of the application is filed.
Thus, there may be simultaneous hearings on parts one and two of the
application. However, as reflected in paragraph (e), the Commission's
intent is that the membership of the Atomic Safety and Licensing Board
designated for hearings under part one be the same as for the hearings
under part two, to the extent practical and consistent with timely
completion of each hearing.
Section 2.647 [Reserved]
This section is reserved for future use by the Commission.
Section 2.649 Partial Decisions on Limited Work Authorization
Section 2.649, which is comparable to Sec. 2.606, denotes the
provisions in subparts C and G relative to issues such as oral
arguments, immediate effectiveness of the presiding officer's initial
decision, and petitions for Commission review, that apply to partial
initial decisions on a LWA rendered in accordance with this subpart.
This section also states that the LWA may not be issued without
completion of the environmental review required for LWAs under subpart
A of part 51. Finally, this section provides that the time periods for
the Commission to exercise its review and sua sponte authority are the
same time periods provided for in part 2 with respect to a final
decision on issuance of a construction permit or combined license.
Part 50
Section 50.10 License Required; Limited Work Authorization
Paragraph (a). This paragraph, which is unchanged from the current
rule, prohibits any person within the United States from transferring
or receiving in interstate commerce, manufacturing, producing,
transferring, acquiring, possessing, or using any production or
utilization facility except as authorized by a license issued by the
Commission, or as provided in Sec. 50.11.
Paragraph (b). This paragraph, which is substantially modified from
the current rule, prohibits any person from beginning the
``construction'' of a production or utilization facility on a site on
which the facility is to be operated until that person has been issued
a construction permit, a combined license under part 52, or a limited
work authorization under paragraph (c) of this section.
The remainder of this paragraph is devoted to specifying what
activities are, and are not, deemed to constitute ``construction'' for
purposes of this paragraph's prohibition. Activities, such as site
clearing, grading, site exploration, test boring, erection of temporary
buildings and erection of permanent structures which are not required
to be described in the site safety analysis report, preliminary safety
analysis report, or final safety analysis report, would not be regarded
as ``construction,'' and no NRC approval would be needed to conduct
those activities. The only work that would be considered construction
would be the excavation, subsurface preparation, and on-site, in-place
fabrication, erection, integration or testing (including the
installation of foundations) of any structure, system or component
required by the Commission's rules and regulations to be described in
the site safety analysis report, preliminary safety analysis report, or
final safety analysis report. The term, ``on-site, in place,
fabrication, erection, integration or testing'' is intended to describe
the historical process of constructing a nuclear power plant in its
final, on-site location, where components or modules are integrated
into the final, in-plant location and elevation. The definition is
intended to exclude persons from having to obtain a LWA, construction
permit, or combined license, in order to fabricate, assemble and test
components and modules in a shop building, warehouse, or laydown area
located on-site.
Thus, the proposed redefinition of construction for the most part
returns to the pre-1972 definition of ``construction'' in Sec.
50.10(b), and removes the need for NRC approval to conduct the
activities currently described in Sec. 50.10(e)(1), except in two
important respects. First, whereas existing Sec. 50.10(b) allows the
driving of piles for the facility, proposed Sec. 50.10(b) would not
permit driving of piles for any structure, system or component required
to be described in an SSAR, PSAR, or FSAR unless NRC permission is
obtained in the form of a LWA, construction permit, or combined
license. Second, existing Sec. 50.10(e)(1) allows a person, with NRC
permission in the form of a LWA, to excavate and install the structural
foundations for any structure, systems and components ``which do not
prevent or mitigate the consequences of postulated accidents that could
cause undue risk to the health and safety of the public.'' The proposed
redefinition would not remove the need for NRC approval, but
substitutes a slightly different scope of structures, systems and
components whose excavation and foundation installation may be allowed
under an LWA, viz., those which are required to be described in the
FSAR.
``Excavation,'' as used in paragraph (b), excludes initial site
grading to attain the final ground elevation, and erosion control
measures to preclude run-off, at the location where further excavation
will be required for a structure, systems or component required by the
Commission's regulations to be described in the FSAR. By contrast, the
removal of any soil, rock, gravel or other material below the final
ground
[[Page 61337]]
elevation, in preparation for the placement of the foundation and
associated retaining walls, is excavation that may not be performed
without an LWA, construction permit, or combined license under part 52.
The ``driving of piles'' not related to ensuring the structural
stability or integrity of any structure, systems or component required
by the Commission's regulations to be described in the FSAR does not
fall within the definition of construction in this paragraph.
Therefore, piles driven to support the erection of a bridge for a
temporary or permanent access road would not be considered
``construction'' under this section and may be performed without a LWA,
construction permit, or combined license. ``Installation of the
foundation,'' means soil compaction; the installation of drainage
systems and geofabric; the placement of concrete (e.g., ``mudmats'') or
other materials which will not be removed prior to placement of the
foundation of a structure; the placement and compaction of a subbase;
the installation of reinforcing bars to be incorporated into the
foundation of the structure; the erection of concrete forms for the
foundations that will remain in-place permanently (even if non-
structural); and placement of concrete or other material constituting
the foundation of any structure, systems or component required by the
Commission's regulations to be described in the FSAR. Foundation
installation activities will require a LWA, construction permit, or
combined license.
Construction is deemed to also include the ``on-site, in-place,''
fabrication, erection, integration or testing activities for any
structure, system or component required by the Commission's regulations
to be described in the FSAR. The use of the term, ``on-site, in
place,'' is intended to allow such structures, systems and components,
including any ``modules'' and subassemblies, to be fabricated,
assembled and tested in a shop building, warehouse, or laydown area
located on-site without a LWA, construction permit, or combined
license. However, the installation or integration of that structure,
system, or component into its final location in the reactor would
require either a construction permit or combined license. The
Commission notes that this paragraph does not apply to manufacturing,
inasmuch as ``manufacturing'' is not ``construction.'' Moreover,
paragraph (b) refers to construction ``on a site on which the facility
is to be operated;'' which is not within the scope of a ``manufacturing
license'' under subpart F of part 52. Accordingly, manufacturing is not
covered by paragraph (b).
Paragraph (c). This paragraph, which is substantially modified from
the current rule, addresses the need for, nature and contents of an
application for a LWA. Paragraph (c)(1) allows the Commission to issue
an LWA in advance of a construction permit or combined license,
authorizing the holder to perform certain delineated construction
requirements.
Paragraph (c)(2) provides that an LWA application may be submitted
as:
--Part of a complete application for a construction permit or combined
license under Sec. 2.101(a)(1) through (4).
--Part one of a phased application under Sec. 2.101(a)(9).
--Part of a complete application for an early site permit under Sec.
2.101(a)(1) through (4).
--An amendment to an already-issued early site permit
Paragraph (c)(3) establishes the requirements for the content of an
LWA application. The application must include a safety analysis report,
an environmental report, and a redress plan. The safety analysis
report, which may be a stand-alone document or incorporated into the
construction permit or combined license application's preliminary or
final safety analysis report, as applicable, must describe the LWA
activities that the applicant seeks to perform, provide the final
design for the structures to be constructed under the LWA and a safety
analysis for those portions of the structure, and provide a safety
analysis of the design demonstrating that the activities will be
conducted in accordance with applicable Commission safety requirements.
The environmental report must meet the requirements of 10 CFR
51.49, which is discussed in more detail in the section by section
analysis for that provision.
The redress plan must describe the activities that would be
implemented by the LWA holder, should construction be terminated by the
holder, the LWA is revoked by the NRC, or upon effectiveness of the
Commission's final decision denying the associated operating license
application or the underlying combined license application, as
applicable. The primary purpose of the redress plan is to return the
site to an environmentally stable and aesthetically acceptable
condition that would allow the site to be utilized for alternative,
non-nuclear uses that conform with local zoning laws. This will be
accomplished through redress of site impacts resulting from LWA
activities performed at the site. Redress of site impacts resulting
from pre-LWA activities will not be required under the redress plan. In
addition, while redress of site impacts may have the practical effect
of mitigating some environmental impacts, the redress plan is not a
substitute for a thorough evaluation of environmental impacts, or
development of mitigation measures that may be necessary to provide
relief from environmental impacts associated with the proposed LWA
activities.
Paragraph (d). This paragraph, which is substantially modified from
the current rule, generally addresses the requirements associated with
issuance of a LWA. Paragraph (d)(1) sets forth the requirements for the
appropriate Director to issue an LWA under this section. The Director
may issue an LWA only after making the appropriate findings on: (i)
Necessary technical qualifications, and the matter of foreign ownership
or control relevant to the information required by Sec. 50.33(a)
through (f), as mandated by sections 103.d. and 182.a. of the AEA; (ii)
making the necessary findings on public health and safety and common
defense and security with respect to the activities to be carried out
under the LWA; (iii) NRC staff issuance of a final EIS on the LWA in
accordance with the applicable requirements of part 51; and (iv) the
presiding officer finding on the environmental issues relevant to the
LWA in accordance with the applicable requirements of part 51, and a
finding on the safety issues relevant to the LWA.
Paragraph (d)(2) requires that the LWA specify the activities that
the holder is authorized to perform, consistent with the LWA
application and as modified based upon the NRC's review. In addition,
each LWA will be issued with a condition requiring implementation of
the redress plan if the LWA holder terminates construction, the LWA is
revoked, or upon effectiveness of the Commission's final decision
denying the associated operating license application or the underlying
combined license application, as applicable. As discussed in the
analysis of paragraph (e), this condition survives the merging of the
LWA into the underlying construction permit, early site permit, or
combined license.
Paragraph (e). This paragraph, which is substantially modified from
the current rule, addresses the legal effect of an issued LWA.
Paragraph (e)(1)
[[Page 61338]]
provides that any activities undertaken under a limited work
authorization shall be entirely at the risk of the applicant and, with
exception of the matters determined under paragraph (c)(4)(ii) and
(iii), the issuance of the limited work authorization shall have no
bearing on the issuance of a construction permit or combined license
with respect to the requirements of the Act, and rules, regulations, or
orders promulgated pursuant thereto. Thus, this paragraph states that
the environmental impact statement for a construction permit or
combined license application for which a limited work authorization was
previously issued will not address, and the presiding officer will not
consider, the sunk costs of the holder of limited work authorization in
determining the proposed action (i.e., issuance of the construction
permit or combined license).
Paragraph (f). This new paragraph would require the LWA holder to
begin implementation of the redress plan in a reasonable time, and
complete the redress no later than eighteen (18) months after
termination of construction by the holder, revocation of the LWA, or
upon effectiveness of the Commission's final decision denying the
associated operating license application or the underlying combined
license application, as applicable.
Part 51
Section 51.4 Definitions
Section 51.4 would be revised by adding a new definition of
``construction,'' which would make applicable throughout part 51 the
definition of construction in proposed Sec. 50.10(b). This would have
the effect of excluding from an EIS for any early site permit,
construction permit, combined license, or LWA issued under Sec.
50.10(c), any discussion, evaluation or consideration of the
environmental impacts or benefits associated with non-construction
activities as effectively defined in Sec. 50.10(b). This would also
remove the need for the NRC decision maker, including a presiding
officer, to make a NEPA finding with respect to the environmental
impacts or benefits associated with those non-construction activities.
Section 51.17 Information collection requirements; OMB approval
Paragraph (b) of Sec. 51.17 of the March 2006 proposed rule w