AP1000 Design Certification, 4464-4482 [06-788]
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4464
§ 319.56–2
Federal Register / Vol. 71, No. 18 / Friday, January 27, 2006 / Rules and Regulations
[Amended]
30. In § 319.56–2, paragraph (k) is
amended by removing the words ‘‘11
species of fruit flies and one species of
seed weevil’’ and adding the words
‘‘plant pests’’ in their place.
I 31. Section 319.74–2 is amended as
follows by redesignating paragraph (d)
as paragraph (e) and by adding a new
paragraph (d) to read as follows:
I
§ 319.74–2 Conditions governing the entry
of cut flowers.
of the Federal Register as of February
27, 2006.
FOR FURTHER INFORMATION CONTACT:
Lauren Quinones-Navarro or Jerry N.
Wilson, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone (301) 415–2007 or (301)
415–3145; e-mail: lnq@nrc.gov or
jnw@nrc.gov.
SUPPLEMENTARY INFORMATION:
Done in Washington, DC, this 20th day of
January 2006.
Kevin Shea,
Acting Administrator, Animal and Plant
Health Inspection Service.
[FR Doc. 06–746 Filed 1–26–06; 8:45 am]
I. Background.
II. Comment Analysis
A. Design Control Document
B. Design Certification Rule
III. Section-by-Section Analysis
A. Introduction (Section I)
B. Definitions (Section II)
C. Scope and Contents (Section III)
D. Additional Requirements and
Restrictions (Section IV)
E. Applicable Regulations (Section V)
F. Issue Resolution (Section VI)
G. Duration of this Appendix (Section VII)
H. Processes for Changes and Departures
(Section VIII)
I. Inspections, Tests, Analyses, and
Acceptance Criteria (Section IX)
J. Records and Reporting (Section X)
IV. Availability of Documents
V. Voluntary Consensus Standards
VI. Finding of No Significant Environmental
Impact: Availability
VII. Paperwork Reduction Act Statement
VIII. Regulatory Analysis
IX. Regulatory Flexibility Certification
X. Backfit Analysis
XI. Congressional Review Act
BILLING CODE 3410–34–P
I. Background
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*
(d) Irradiation. Cut flowers and foliage
that are required under this part to be
treated or subjected to inspection to
control one or more of the plant pests
listed in § 305.31(a) of this chapter may
instead be treated with irradiation.
Commodities treated with irradiation for
plant pests listed in § 305.31(a) must be
irradiated at the doses listed in
§ 305.31(a), and the irradiation
treatment must be conducted in
accordance with the other requirements
of § 305.34 of this chapter. There is a
possibility that some cut flowers could
be damaged by such irradiation.
*
*
*
*
*
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 52
RIN 3150–AH56
AP1000 Design Certification
Nuclear Regulatory
Commission.
ACTION: Final rule.
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AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC or Commission) is
amending its regulations to certify the
AP1000 standard plant design. This
action is necessary so that applicants or
licensees intending to construct and
operate an AP1000 design may do so by
referencing this regulation [AP1000
design certification rule (DCR)]. The
applicant for certification of the AP1000
design was Westinghouse Electric
Company, LLC (Westinghouse).
DATES: Effective Date: The effective date
of this rule is February 27, 2006. The
incorporation by reference of certain
material specified in this regulation is
approved by the Director of the Office
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Subpart B of 10 CFR part 52 sets forth
the process for obtaining standard
design certifications. On March 28, 2002
(67 FR 20845; April 26, 2002),
Westinghouse tendered its application
for certification of the AP1000 standard
plant design with the NRC.
Westinghouse submitted this
application in accordance with subpart
B and appendix O of 10 CFR part 52.
The NRC formally accepted the
application as a docketed application
for design certification (Docket No. 52–
006) on June 25, 2002 (67 FR 43690;
June 28, 2002). The pre-application
information submitted before the NRC
formally accepted the application can be
found in the NRC’s Agencywide
Documents Access and Management
System (ADAMS) under Docket Number
PROJ0711 (Project No. 711).
The NRC staff issued a final safety
evaluation report (FSER) for the AP1000
design in September 2004 (NUREG–
1793). The FSER provides the bases for
issuance of a final design approval
(FDA) under appendix O to part 52,
which is a prerequisite to a design
certification. The FDA for the AP1000
design was issued on September 13,
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2004, and published in the Federal
Register on September 17, 2004 (69 FR
56101). A proposed rule to certify the
AP1000 was published on April 18,
2005 (70 FR 20062).
Subsequently, Westinghouse
submitted editorial and minor technical
changes and clarifications to the
inspections, tests, analyses, and
acceptance criteria (ITAAC) in revision
15 to the design control document
(DCD). The NRC staff evaluated these
changes in a supplement to the FSER
(NUREG–1793, Supplement No. 1).
Supplement No. 1 is being made
available to the public as part of this
rulemaking. The FSER and Supplement
No. 1 provide the bases for the
Commission’s approval of the AP1000
standard plant design. An FDA, which
incorporates the changes to the DCD,
will be issued to supersede the current
FDA after issuance of this final design
certification rule.
II. Comment Analysis
The period for submitting comments
on the proposed DCR, AP1000 DCD, or
draft environmental assessment (EA)
expired on July 5, 2005. The NRC
received three letters from two private
citizens and one letter from the Nuclear
Energy Institute (NEI). The comments
addressed three categories of
information: Environmental Assessment
(EA), Design Control Document, and
Design Certification Rule. The responses
to the comments on the EA are
discussed in section 7.0 of the EA
(ML053630176). Responses to the
comments in the second and third
categories are discussed below.
A. Design Control Document (DCD)
Comment summary. There is an overreliance on passive systems in the
AP1000.
Response. The NRC disagrees with
this comment. The NRC required tests of
the new passive safety systems to
demonstrate that they will perform as
predicted in the safety analysis (see
Chapter 21 of the AP1000 FSER). The
NRC also required higher availability for
certain active backup systems to
compensate for any remaining
uncertainties in the performance of the
passive safety systems (see Chapter 22
of the AP1000 FSER). As a result of
these reviews, the NRC concluded that
the use of passive safety systems in the
AP1000 design is acceptable.
Comment Summary. The AP1000 is
an unnecessary and unsafe variation on
AP600.
Response. The NRC disagrees with the
comment. The NRC has determined that
the AP1000 design can be built and
operated safely (see AP1000 FSER). The
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NRC does not determine which designs
are necessary for future deployment.
Comment Summary. The AP1000
DCD referenced in the proposed rule
does not meet the requirement of 10
CFR part 52 that the plant design be
complete except for site-specific
elements and other specific exemptions.
Response. The NRC disagrees with
this comment. The requirement for a
complete scope of design [10 CFR
52.47(b)(2)(i)(A)(4)] was met by the
applicant (see discussion in section
1.2.1 of AP1000 FSER). The comment
appears to be directed at the
requirement for an application to
contain a sufficient level of design
information for the Commission to reach
a conclusion on all safety questions
associated with the design [10 CFR
52.47(a)(2)], which was also met by the
applicant (see discussion in section 1.5
of AP1000 FSER).
Comment Summary. The
appropriateness of the process used to
derive the AP1000 design from the
AP600 design has not been given
sufficient attention in the NRC’s review.
Response. The NRC disagrees with
this comment, which appears to apply
to the NRC’s review of the applicant’s
quality assurance (QA) program. In its
application for design certification of
the AP1000 plant, Westinghouse stated
that a continuous QA program spanning
the AP600 design and the AP1000
design has been used. Since March 31,
1996, activities affecting the quality of
items and services for the AP1000
project during design, procurement,
fabrication, inspection, and/or testing
have been performed under the quality
plan described in ‘‘Westinghouse
Energy Systems Business Unit—Quality
Management System.’’ The Quality
Management System (QMS) establishes
design control measures for preparing,
reviewing, and approving design
documentation for safety-related
structures, systems, and components
(SSCs). As documented in an NRC
evaluation letter, dated February 23,
1996, from S. Black (NRC) to N.J.
Liparulo, the Westinghouse QMS was
reviewed by the NRC and found to meet
the requirements of 10 CFR part 50,
appendix B. Subsequent revisions to the
QMS have also been reviewed by the
NRC and found to be acceptable. To
provide additional assurance that
Westinghouse implemented the
measures described in the QMS, the
NRC staff performed a QA
implementation inspection at the
Westinghouse engineering offices in
Monroeville, Pennsylvania, which was
documented in NRC Inspection Report
No. 99900404/03–01, dated November
4, 2003 (ADAMS Accession No.
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ML033090510). Therefore, the NRC
concludes that the applicant’s QA
program for the AP1000 design was
acceptable.
Comment Summary. The decision by
the NRC not to require Westinghouse to
build and test a prototype for the
automatic depressurization system
(ADS) 4th stage squib valve was made
under pressure of the accelerated
AP1000 schedule.
Response. The NRC disagrees that the
AP1000 schedule affected the decision
not to require Westinghouse to build
and test a prototype for the ADS 4th
stage squib valve. The need for a
prototype test was evaluated by the NRC
staff during the AP1000 design review.
Also, the ability to design and build the
ADS valve for AP1000 was discussed
with the Advisory Committee on
Reactor Safeguards (ACRS) at its future
plant subcommittee meeting on July 17–
18, 2003. In addition, in a letter to ACRS
dated May 18, 2004, the NRC staff stated
that the ADS–4 squib valves will be
designed, constructed, and tested under
Section III of the Boiler and Pressure
Vessel Code promulgated by the
American Society of Mechanical
Engineers and are actuated by
redundant and diverse instrumentation
and control systems. The staff also
performed a sensitivity study by
increasing the failure probability and
the common-cause failure probability of
the ADS–4 squib valves by an order of
magnitude. This sensitivity study
indicated that the CDF increased by
only a factor of three (to 6 × 10¥7/
year)and was not large enough to impact
the probabilistic risk assessment (PRA)
conclusions and insights about the
AP1000 design.
Comment Summary. The effect of heat
of solar radiation on the performance of
the AP1000 passive containment
cooling system (PCS) has not been
resolved, and geographical latitude
ought to be a site parameter, unless it
can be shown that the PCS is effective
at all geographical latitudes, even when
heat of solar radiation is taken into
account.
Response. The NRC disagrees with
these comments. The site parameters for
the AP1000 design include minimum
and maximum air temperatures (see
DCD Table 2–1). The safety maximum
temperature is 115 °F, which is based on
historical site data and excludes peaks
of less than 2-hour durations.
The operational limits for the AP1000
containment include a technical
specification (TS) limit on the
temperature of the air inside
containment, TS 3.6.5, ‘‘Containment
Air Temperature,’’ of less than or equal
to 120 °F. In addition, there is a limit
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on the water temperature in the PCS
storage tank specified in TS 3.6.6,
‘‘Passive Containment Cooling System—
Operating,’’ of greater than or equal to
¥40 °F and less than or equal to 120 °F.
If the water temperature is at or below
50 °F, or at or above 100 °F, the
surveillance frequency to check the
temperature is reduced from 7 days to
24 hours. The operational limits and the
site parameters provide reasonable
assurance that the AP1000 can be
operated without undue risk to the
public health and safety. Conservative
evaluations of the potential effect of
solar radiation on the operation and
performance of the AP1000 PCS show
that the AP1000 TS provide reasonable
assurance that off-normal conditions
can be detected and appropriate actions
taken to preclude operations outside the
current design-base assumptions. Based
on the estimated time needed to exceed
the current operational temperature
limits (10 days of uninterrupted extreme
environmental conditions), it is
reasonable to conclude that the AP1000
operational limits will not be exceeded
even for sites with high solar radiation.
In the unlikely event that the shield
building might heat up, a containment
response analysis showed the pressure
increase to be small, 0.75 pounds per
square inch (psi), and based on the
current margin of 1.2 psi (DCD Table
6.2.1.1–1), the design pressure limit of
73.7 pounds per square inch absolute
(psia) would not be exceeded.
Therefore, the effect of heat of solar
radiation on the performance of the PCS
has been resolved.
Comment Summary. The accelerated
schedule for the AP1000 led to cutting
regulatory corners and was further
accelerated by granting the FDA before
the FSER was made available to the
public.
Response. The NRC disagrees with
this comment. In a letter to Mr. W.E.
Cummins (Westinghouse), dated July
12, 2002, it is true that the NRC
provided an expected schedule for the
AP1000 review, which was significantly
shorter than previous DCRs. However,
the shorter schedule was due to
efficiencies that the NRC expected to
achieve as a result of the similarities
between the previously-approved
AP600 design and the AP1000 design.
Also, the AP1000 FSER was made
available to the public on September 20,
2004, the same day that the FDA was
made available to the public.
B. Design Certification Rule
It is the Commission’s goal to
maintain as much consistency as
possible in the rule language for all of
the DCRs. Many of the following
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comments from NEI appear to be
applicable to all of the DCRs but some
repeat comments NEI submitted
previously during the 2003 proposed
rule to amend 10 CFR part 52 (68 FR
40025; July 3, 2003).
Comment Summary. NEI recommends
that Section III.B of the Supplementary
Information (70 FR 20064) be revised to
delete the phrase ‘‘not just incorporate
by reference.’’
Response. The NRC disagrees with
this request. The NRC does agree that
the plant-specific DCD should be part of
the final safety analysis report (FSAR)
for a combined license (COL)
application. The NRC believes that the
generic DCD should also be part of the
FSAR, not just incorporated by
reference, in order to facilitate the NRC
staff’s review of any departures or
exemptions. However, any changes
made to existing DCRs if part 52 is
revised would also be made to the
AP1000 DCR.
Comment Summary. NEI recommends
clarification of the review status of
‘‘operational requirements’’ in Section
III.F of the Supplementary Information
(70 FR 20067).
Response. The NRC agrees that the
special backfit provisions of 10 CFR
52.63 do not apply to operational
requirements in the DCD. However, the
NRC believes that the discussion in
Section III.F of the Supplementary
Information section of the proposed rule
document accurately states the review
status of operational requirements and
does not need to be revised.
Comment Summary. NEI recommends
modification of the definition of generic
TS in section II.B of the AP1000 DCR.
Response. The NRC disagrees with
this comment. The NRC stated in the
Supplementary Information (70 FR
20063) that the values in brackets are
neither part of the AP1000 DCR nor are
they binding. The NRC believes that
amending the definition of generic TS is
not necessary and also wants to
maintain consistent rule language for all
DCRs.
Comment Summary. NEI recommends
replacement of the term ‘‘investment
protection’’ in section II.E of the AP1000
DCR and elsewhere in the DCD by the
term ‘‘non-safety-related severe accident
equipment.’’ In addition, NEI
recommends that the AP1000 DCR and
Supplementary Information be revised
so that bracketed information in the
investment protection short-term
availability controls will be treated like
bracketed information in generic TS.
Response. The NRC disagrees with
NEI’s request to change this
terminology. Use of the term
‘‘investment protection short-term
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availability controls’’ was requested by
the applicant (Westinghouse Electric
Company, LLC) and was also used in
the AP600 DCR. Furthermore, the origin
of investment protection short-term
availability controls comes from
implementing the regulatory treatment
of non-safety systems process, which
typically results in requirements to
achieve higher reliability for certain
active, non-safety systems. These
systems are not limited to severe
accident design features. Therefore,
even if the NRC agreed to a generic
change to the term ‘‘investment
protection,’’ the proposed term ‘‘nonsafety-related severe accident
equipment’’ would not be an acceptable
replacement.
The NRC agrees that the bracketed
values in the investment protection
short-term availability controls have the
same status as the bracketed values in
the generic TS. As a result, the NRC
refers to the availability controls in
section III.H of the Supplementary
Information in this Federal Register
notice.
Comment Summary. NEI recommends
that the phrase ‘‘or licensees’’ be deleted
from the rule language in section
VIII.C.2 of the AP1000 DCR.
Response. The NRC agrees with this
comment and section VIII.C.2 of the
AP1000 DCR has been amended as
suggested by NEI. The Commission may
consider amending the DCRs to adopt
the language recommended by NEI if 10
CFR part 52 is revised.
Comment Summary. NEI recommends
amending the rule language in section
VIII.C.6 of the AP1000 DCR to delete the
requirement that changes to the plantspecific TS be treated as license
amendments.
Response. The NRC disagrees with
this request. The requirement that
changes to the plant-specific TS be
treated as license amendments is
correct. If the Commission decides to
clarify this issue for the DCRs in any
potential revision to 10 CFR part 52, the
NRC will also clarify the AP1000 DCR
accordingly as part of that rulemaking.
Comment Summary. NEI recommends
amending the rule language in section
IX.B.1 of the AP1000 DCR to restore the
phrase ‘‘based solely thereon.’’
Response. The NRC agrees to amend
section IX.B.1 of the AP1000 DCR, in
order to make all of the DCRs consistent.
However, the NRC notes that inclusion
of the phrase ‘‘based solely thereon,’’
does not change the meaning of section
IX.B.1. The determination of inspection,
test, analysis, and acceptance criteria
(ITAAC) completion will always be
based on information that is material to
the acceptance criteria.
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Comment Summary. NEI recommends
amending the rule language in section
X.A.1 of the AP1000 DCR to require the
design certification applicant to include
all generic changes to the generic TS
and other operational requirements in
the generic DCD.
Response. The NRC agrees with this
comment, section X.A.1 of the AP1000
DCR has been amended as suggested by
NEI. The Commission may consider
amending the DCRs to adopt the
language recommended by NEI if 10
CFR part 52 is revised.
Comment Summary. NEI recommends
that sections IV.A.2 and IV.A.3 of the
AP1000 DCR be amended to be
consistent with respect to inclusion of
information in the plant-specific DCD or
explain the difference between the
terms ‘‘include’’ and ‘‘physically
include’’ in section IV.A (70 FR 20076).
Response. The NRC agrees that use of
the terms ‘‘include’’ and ‘‘physically
include’’ in section IV.A of the AP1000
DCR should be clarified. The
Commission may consider amending all
of the DCRs to clarify this issue if 10
CFR part 52 is revised.
Comment Summary. NEI recommends
amending the definition of Tier 2 in
section II.E.1 of the AP1000 DCR to
exclude the design-specific PRA and the
evaluation of SAMDAs.
Response. The NRC agrees with this
comment, section II.E.1 of the AP1000
DCR has been amended as suggested by
NEI. The NRC notes that NEI submitted
the same comment during the 2003
proposed rule to amend 10 CFR part 52.
The Commission may consider
amending the DCRs to adopt the
language recommended by NEI if 10
CFR part 52 is revised.
Comment Summary. NEI recommends
amending the rule language in section
III.E of the AP1000 DCR to use the
terminology for ‘‘site characteristics’’
consistently.
Response. The NRC agrees with this
comment, section III.E of the AP1000
DCR has been amended to be consistent
with the other DCRs in the proposed
part 52 rule. The NRC notes that NEI
submitted the same comment during the
2003 proposed rule to amend 10 CFR
part 52.
Comment Summary. NEI recommends
clarifying the rule language in section
IV.A.2 of the AP1000 DCR regarding
‘‘same’’ information and ‘‘generic DCD.’’
Response. The NRC agrees with this
comment, section IV.A.2 of the AP1000
DCR has been amended to be consistent
with the other DCRs in the proposed
part 52 rule. The NRC notes that NEI
submitted the same comment during the
2003 proposed rule to amend 10 CFR
part 52.
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Comment Summary. NEI recommends
amending section VIII.B.6.a of the
AP1000 DCR to be consistent with
section VI.B.5 regarding plant-specific
departures.
Response. The NRC disagrees with
this request. It was determined during
the first two DCRs that departures from
Tier 2* information would not receive
finality or be treated as a resolved issue
within the meaning of section VI of the
DCR. The NRC notes that NEI submitted
the same comment during the 2003
proposed rule to amend 10 CFR part 52.
If the Commission decides to adopt
NEI’s proposed language for the DCRs in
any potential revision to 10 CFR part 52,
the NRC will also amend the AP1000
DCR accordingly as part of that
rulemaking.
Comment Summary. NEI recommends
amending section VIII.C.3 of the AP1000
DCR to require the NRC to meet the
backfit requirements of 10 CFR 50.109
in addition to the special circumstances
in 10 CFR 2.758(b) for plant-specific
departures from operational
requirements.
Response. The NRC disagrees with
this request. In the first two DCRs, the
Commission decided on different
standards for changes made under
section VIII.C of the DCRs (see the
discussion at 62 FR 25800; May 12,
1997). The NRC notes that NEI
submitted the same comment during the
2003 proposed rule to amend 10 CFR
part 52. If the Commission decides to
adopt NEI’s proposed language for the
DCRs in any potential revision to 10
CFR part 52, the NRC will also amend
the AP1000 DCR accordingly as part of
that rulemaking.
Comment Summary. NEI recommends
amending section VIII.C.4 of the AP1000
DCR to revise the standards for making
changes to operational requirements.
Response. The NRC disagrees with
this request. In the first two DCRs, the
Commission decided on different
standards for changes made under
section VIII.C of the DCRs (see the
discussion at 62 FR 25800; May 12,
1997). In addition, the Commission
determined that exemptions from
operational requirements would not
receive finality or be treated as a
resolved issue within the meaning of
section VI of the DCR. The NRC notes
that NEI submitted the same comment
during the 2003 proposed rule to amend
10 CFR part 52. If the Commission
decides to adopt NEI’s proposed
language for the DCRs in any potential
revision to 10 CFR part 52, the NRC will
also amend the AP1000 DCR
accordingly as part of that rulemaking.
Comment Summary. NEI recommends
amending section IX.B.1 of the AP1000
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DCR to specify the type of action to be
performed by the NRC staff regarding
ITAAC.
Response. The NRC disagrees with
this request. Individual DCRs should
not address the scope of the NRC staff’s
activities with respect to ITAAC
verification. This is a generic matter
that, if it is to be addressed in a
rulemaking, is more appropriate for
inclusion in subpart C of part 52 dealing
generally with combined licenses.
The NRC notes that NEI submitted the
same comment during the 2003
proposed rule to amend 10 CFR part 52.
If the Commission decides to adopt
NEI’s proposed language for the DCRs in
any potential revision to 10 CFR part 52,
the NRC will also amend the AP1000
DCR accordingly as part of that
rulemaking.
Comment Summary. NEI recommends
amending section IX.B.3 of the AP1000
DCR to clarify the rule language.
Response. The NRC disagrees with
this editorial request and has decided to
maintain the original rule language for
this provision. The NRC notes that NEI
submitted the same comment during the
2003 proposed rule to amend 10 CFR
part 52. If the Commission decides to
adopt NEI’s proposed language for the
DCRs in any potential revision to 10
CFR part 52, the NRC will also amend
the AP1000 DCR accordingly as part of
that rulemaking.
Comment Summary. NEI recommends
amending sections X.B.1 and X.B.3 of
the AP1000 DCR to clarify the rule
language regarding DCDs.
Response. The NRC agrees with this
comment and section X.B of the AP1000
DCR has been amended to clarify the
language. The NRC notes that NEI
submitted the same comment during the
2003 proposed rule to amend 10 CFR
part 52. The Commission may consider
amending the existing DCRs in any
potential revision to 10 CFR part 52.
III. Section-by-Section Analysis
The following discussion sets forth
the purpose and key aspects of each
section and paragraph of the final
AP1000 DCR. All section and paragraph
references are to the provisions in
appendix D to 10 CFR part 52. The final
DCR for the AP1000 standard plant
design is nearly identical to the AP600
DCR, which the NRC previously
codified in 10 CFR part 52, appendix C
(Design Certification Rule for the AP600
Design, 64 FR 72015, December 23,
1999). Many of the procedural issues
and their resolutions for the AP600
DCR, as well as the initial two DCRs for
the ABWR and ABB–CE System 80+,
(e.g., the two-tier structure, Tier 2*, the
scope of issue resolution) were
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developed after extensive public
discussions with stakeholders,
including Westinghouse. Also,
Westinghouse requested that policy
resolutions for the AP600 design review
be applied to the AP1000. Accordingly,
the NRC has modeled the AP1000 DCR
on the existing DCRs, with certain
departures where necessary, to account
for differences in the AP1000 design
documentation, design features, and
environmental assessment (including
severe accident mitigation design
alternatives (SAMDAs).
A. Introduction
The purpose of section I of appendix
D to 10 CFR part 52 (this appendix) is
to identify the standard plant design
that is approved by this DCR, and the
applicant for certification of the
standard design. Identification of the
design certification applicant is
necessary to implement this appendix,
for two reasons. First, the
implementation of 10 CFR 52.63(c)
depends on whether an applicant for a
COL contracts with the design
certification applicant to provide the
generic DCD and supporting design
information. If the COL applicant does
not use the design certification
applicant to provide this information,
then the COL applicant must meet the
requirements in 10 CFR 52.63(c). Also,
paragraph X.A.1 of this appendix
requires the design certification
applicant to maintain the generic DCD
throughout the time this appendix may
be referenced.
B. Definitions
During development of the first two
DCRs, the Commission decided that
there would be both generic (master)
DCDs maintained by the NRC and the
design certification applicant, as well as
individual plant-specific DCDs
maintained by each applicant and
licensee that reference this appendix.
This distinction is necessary in order to
specify the relevant plant-specific
requirements to applicants and
licensees referencing the appendix. The
master DCDs would include generic
changes to the version of the DCD
approved in this design certification
rulemaking. These changes would occur
as the result of generic rulemaking by
the Commission, under the change
criteria in section VIII of this appendix.
The Commission also requires each
applicant and licensee referencing this
appendix to submit and maintain a
plant-specific DCD.
This plant-specific DCD would
contain (not just incorporate by
reference) the information in the generic
DCD. The plant-specific DCD would be
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updated as necessary to reflect the
generic changes to the DCD that the
Commission may adopt through
rulemaking, plant-specific departures
from the generic DCD that the
Commission imposed on the licensee by
order, and any plant-specific departures
that the licensee chooses to make in
accordance with the relevant processes
in section VIII of this appendix. Thus,
the plant-specific DCD would function
like an updated FSAR because it would
provide the most complete and accurate
information on a plant’s licensing basis
for that part of the plant within the
scope of this appendix. Therefore, this
appendix would define both a generic
DCD and a plant-specific DCD.
Also, the Commission decided to treat
the TS in section 16.1 of the generic
DCD as a special category of information
and to designate them as generic TS in
order to facilitate the special treatment
of this information under this appendix.
A COL applicant must submit plantspecific TS that consist of the generic
TS, which may be modified under
paragraph VIII.C of this appendix, and
the remaining plant-specific information
needed to complete the TS. The FSAR
that is required by 10 CFR 52.79(b) will
consist of the plant-specific DCD, the
site-specific portion of the FSAR, and
the plant-specific TS.
The terms Tier 1, Tier 2, Tier 2*, and
COL action items (license information)
are defined in this appendix because
these concepts were not envisioned
when 10 CFR part 52 was developed.
The design certification applicants and
the NRC used these terms in
implementing the two-tiered rule
structure that was proposed by
representatives of the nuclear industry
after issuance of 10 CFR part 52.
Therefore, appropriate definitions for
these additional terms are included in
this appendix. The nuclear industry
representatives requested a two-tiered
structure for the DCRs to achieve issue
preclusion for a greater amount of
information than was originally planned
for the DCRs, while retaining flexibility
for design implementation. The
Commission approved the use of a twotiered rule structure in its staff
requirements memorandum (SRM),
dated February 14, 1991, on SECY–90–
377, ‘‘Requirements for Design
Certification Under 10 CFR Part 52,’’
dated November 8, 1990. This document
and others are available in the
Regulatory History of Design
Certification (see section IV, Availability
of Documents, of this Statement of
Consideration (SOC)).
The Tier 1 portion of the designrelated information contained in the
DCD is certified by this appendix and,
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therefore, is subject to the special
backfit provisions in paragraph VIII.A of
this appendix. An applicant who
references this appendix is required to
incorporate by reference and comply
with Tier 1, under paragraphs III.B and
IV.A.1 of this appendix. This
information consists of an introduction
to Tier 1, the system based and nonsystem based design descriptions and
corresponding ITAAC, significant
interface requirements, and significant
site parameters for the design. The
design descriptions, interface
requirements, and site parameters in
Tier 1 were derived from Tier 2, but
may be more general than the Tier 2
information. The NRC staff’s evaluation
of the Tier 1 information is provided in
section 14.3 of the FSER. Changes to or
departures from the Tier 1 information
must comply with section VIII.A of this
appendix.
The Tier 1 design descriptions serve
as commitments for the lifetime of a
facility referencing the design
certification. The ITAAC verifies that
the as-built facility conforms with the
approved design and applicable
regulations. Under 10 CFR 52.103(g), the
Commission must find that the
acceptance criteria in the ITAAC are
met before authorizing operation. After
the Commission has made the finding
required by 10 CFR 52.103(g), the
ITAAC do not constitute regulatory
requirements for licensees or for
renewal of the COL. However,
subsequent modifications to the facility
must comply with the design
descriptions in the plant-specific DCD
unless changes are made under the
change process in section VIII of this
appendix. The Tier 1 interface
requirements are the most significant of
the interface requirements for systems
that are wholly or partially outside the
scope of the standard design. Tier 1
interface requirements were submitted
in response to 10 CFR 52.47(a)(1)(vii)
and must be met by the site-specific
design features of a facility that
references this appendix. An
application that references this
appendix must demonstrate that the site
parameters (both Tier 1 and Tier 2) are
met at the proposed site (refer to
paragraph III.D of this SOC).
Tier 2 is the portion of the designrelated information contained in the
DCD that is approved by this appendix
but not certified. Tier 2 information is
subject to the backfit provisions in
paragraph VIII.B of this appendix. Tier
2 includes the information required by
10 CFR 52.47 (with the exception of
generic TS, conceptual design
information, and the evaluation of
SAMDAs) and the supporting
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information on inspections, tests, and
analyses that will be performed to
demonstrate that the acceptance criteria
in the ITAAC have been met. As with
Tier 1, paragraphs III.B and IV.A.1 of
this appendix require an applicant who
references this appendix to incorporate
Tier 2 by reference and to comply with
Tier 2, except for the COL action items,
including the investment protection
short-term availability controls in
section 16.3 of the generic DCD. The
definition of Tier 2 makes clear that Tier
2 information has been determined by
the Commission, by virtue of its
inclusion in this appendix and its
designation as Tier 2 information, to be
an approved sufficient method for
meeting Tier 1 requirements. However,
there may be other acceptable ways of
complying with Tier 1. The appropriate
criteria for departing from Tier 2
information are specified in paragraph
VIII.B of this appendix. Departures from
Tier 2 do not negate the requirement in
paragraph III.B to reference Tier 2.
A definition of ‘‘combined license
action items’’ (COL information), which
is part of the Tier 2 information, has
been added to clarify that COL
applicants who reference this appendix
are required to address COL action
items in their license application.
However, the COL action items are not
the only acceptable set of information.
An applicant may depart from or omit
COL action items, provided that the
departure or omission is identified and
justified in the FSAR. After issuance of
a construction permit or COL, these
items are not requirements for the
licensee unless they are restated in the
FSAR. For additional discussion, see
Section D.
The investment protection short-term
availability controls, which are set forth
in section 16.3 of the generic DCD, were
added to the information that is part of
Tier 2 to make it clear that the
availability controls are not operational
requirements for the purposes of
paragraph VIII.C of this appendix.
Rather, the availability controls are
associated with specific design features.
The availability controls may be
changed if the associated design feature
is changed under paragraph VIII.B of
this appendix. For additional
discussion, see section III.C of this SOC.
Certain Tier 2 information has been
designated in the generic DCD with
brackets and italicized text as ‘‘Tier 2*’’
information and, as discussed in greater
detail in the section-by-section
explanation for section H, a plantspecific departure from Tier 2*
information requires prior NRC
approval. However, the Tier 2*
designation expires for some of this
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information when the facility first
achieves full power after the finding
required by 10 CFR 52.103(g). The
process for changing Tier 2*
information and the time at which its
status as Tier 2* expires is set forth in
paragraph VIII.B.6 of this appendix.
Some Tier 2* requirements concerning
special pre-operational tests are
designated to be performed only for the
first plant or first three plants
referencing the AP1000 DCR. The Tier
2* designation for these selected tests
will expire after the first plant or first
three plants complete the specified
tests. However, a COL action item
requires that subsequent plants also
perform the tests or justify that the
results of the first-plant-only or firstthree-plants-only tests are applicable to
the subsequent plant.
In an earlier rulemaking (64 FR 53582;
October 4, 1999), the Commission
revised 10 CFR 50.59 to incorporate new
thresholds for permitting changes to a
plant as described in the FSAR without
NRC approval. For consistency and
clarity, the Commission proposes to use
these new thresholds in the proposed
AP1000 DCR. Inasmuch as § 50.59 is the
primary change mechanism for
operating nuclear plants, the
Commission believes that future plants
referencing the AP1000 DCR should
utilize thresholds as close to § 50.59 as
is practicable and appropriate. Because
of some differences in how the change
control requirements are structured in
the DCRs, certain definitions contained
in § 50.59 are not applicable to 10 CFR
part 52 and are not being included in
this rule. One definition that the
Commission is including is the
definition from the new § 50.59 for a
‘‘departure from a method of
evaluation,’’ (paragraph II.G), which is
appropriate to include in this
rulemaking so that the eight criteria in
paragraph VIII.B.5.b of the final rule
will be implemented as intended.
C. Scope and Contents
The purpose of section III of this
appendix is to describe and define the
scope and contents of this design
certification and to set forth how
documentation discrepancies or
inconsistencies are to be resolved.
Paragraph III.A is the required statement
of the Office of the Federal Register
(OFR) for approval of the incorporation
by reference of Tier 1, Tier 2, and the
generic TS into this appendix.
Paragraph III.B requires COL applicants
and licensees to comply with the
requirements of this appendix. The legal
effect of incorporation by reference is
that the incorporated material has the
same legal status as if it were published
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in the Code of Federal Regulations. This
material, like any other properly-issued
regulation, has the force and effect of
law. Tier 1 and Tier 2 information, as
well as the generic TS, have been
combined into a single document called
the generic DCD, in order to effectively
control this information and facilitate its
incorporation by reference into the rule.
The generic DCD was prepared to meet
the requirements of the OFR for
incorporation by reference (1 CFR part
51). One of the requirements of the OFR
for incorporation by reference is that the
design certification applicant must
make the generic DCD available upon
request after the final rule becomes
effective. Therefore, paragraph III.A of
this appendix identifies a Westinghouse
representative to be contacted in order
to obtain a copy of the generic DCD.
Paragraphs III.A and III.B also identify
the investment protection short-term
availability controls in section 16.3 of
the generic DCD as part of the Tier 2
information. During its review of the
AP1000 design, the NRC determined
that residual uncertainties associated
with passive safety system performance
increased the importance of non-safetyrelated active systems in providing
defense-in-depth functions that back-up
the passive systems. As a result,
Westinghouse developed administrative
controls to provide a high level of
confidence that active systems having a
significant safety role are available
when challenged. Westinghouse named
these additional controls ‘‘investment
protection short-term availability
controls.’’ The Commission included
this characterization in section III of this
appendix to ensure that these
availability controls are binding on
applicants and licensees that reference
this appendix and will be enforceable
by the NRC. The NRC’s evaluation of the
availability controls is provided in
Chapter 22 of the FSER.
The generic DCD (master copy) for
this design certification will be
electronically accessible in NRC’s
Agencywide Documents Access and
Management System (ADAMS) and at
the OFR. Copies of the generic DCD will
also be available at the NRC’s Public
Document Room (PDR). Questions
concerning the accuracy of information
in an application that references this
appendix will be resolved by checking
the master copy of the generic DCD in
ADAMS. If a generic change
(rulemaking) is made to the DCD by the
change process provided in section VIII
of this appendix, then at the completion
of the rulemaking the NRC would
request approval of the Director, OFR,
for the changed incorporation by
reference and change its copies of the
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4469
generic DCD and notify the OFR and the
design certification applicant to change
their copies. The Commission is
requiring that the design certification
applicant maintain an up-to-date copy
under paragraph X.A.1 of this appendix
because it is likely that most applicants
intending to reference the standard
design will obtain the generic DCD from
the design certification applicant. Plantspecific changes to and departures from
the generic DCD will be maintained by
the applicant or licensee that references
this appendix in a plant-specific DCD
under paragraph X.A.2 of this appendix.
In addition to requiring compliance
with this appendix, paragraph III.B
clarifies that the conceptual design
information and Westinghouse’s
evaluation of SAMDAs are not
considered to be part of this appendix.
The conceptual design information is
for those portions of the plant that are
outside the scope of the standard design
and are contained in Tier 2 information.
As provided by 10 CFR 52.47(a)(1)(ix),
these conceptual designs are not part of
this appendix and, therefore, are not
applicable to an application that
references this appendix. Therefore, the
applicant is not required to conform
with the conceptual design information
that was provided by the design
certification applicant. The conceptual
design information, which consists of
site-specific design features, was
required to facilitate the design
certification review. Conceptual design
information is neither Tier 1 nor Tier 2.
Section 1.8 of Tier 2 identifies the
location of the conceptual design
information. Westinghouse’s evaluation
of various design alternatives to prevent
and mitigate severe accidents does not
constitute design requirements. The
Commission’s assessment of this
information is discussed in Section VII
of this SOC on environmental impacts.
Paragraphs III.C and III.D set forth the
way potential conflicts are to be
resolved. Paragraph III.C establishes the
Tier 1 description in the DCD as
controlling in the event of an
inconsistency between the Tier 1 and
Tier 2 information in the DCD.
Paragraph III.D establishes the generic
DCD as the controlling document in the
event of an inconsistency between the
DCD and the FSER for the certified
standard design.
Paragraph III.E makes it clear that
design activities that are wholly outside
the scope of this design certification
may be performed using site-specific
design parameters, provided the design
activities do not affect Tier 1 or Tier 2,
or conflict with the interface
requirements in the DCD. This provision
applies to site-specific portions of the
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plant, such as the administration
building. Because this statement is not
a definition, this provision has been
located in Section III of this appendix.
D. Additional Requirements and
Restrictions
Section IV of this appendix sets forth
additional requirements and restrictions
imposed upon an applicant who
references this appendix. Paragraph
IV.A sets forth the information
requirements for these applicants. This
paragraph distinguishes between
information and/or documents which
must actually be included in the
application or the DCD, versus those
which may be incorporated by reference
(i.e., referenced in the application as if
the information or documents were
included in the application). Any
incorporation by reference in the
application should be clear and should
specify the title, date, edition, or version
of a document, the page number(s), and
table(s) containing the relevant
information to be incorporated.
Paragraph IV.A.1 requires an
applicant who references this appendix
to incorporate by reference this
appendix in its application. The legal
effect of such an incorporation by
reference is that this appendix is legally
binding on the applicant or licensee.
Paragraph IV.A.2.a requires that a plantspecific DCD be included in the initial
application to ensure that the applicant
commits to complying with the DCD.
This paragraph also requires the plantspecific DCD to use the same format as
the generic DCD and reflect the
applicant’s proposed departures and
exemptions from the generic DCD as of
the time of submission of the
application. The Commission expects
that the plant-specific DCD will become
the plant’s FSAR, by including
information, i.e., site-specific
information, for the portions of the plant
outside the scope of the referenced
design, including related ITAAC, and
other matters required to be included in
an FSAR by 10 CFR 50.34 and 52.79.
Integration of the plant-specific DCD
and remaining site-specific information
into the plant’s FSAR, will result in an
application that is easier to use and
should minimize ‘‘duplicate
documentation’’ and the attendant
possibility for confusion. Paragraph
IV.A.2.a also requires that the initial
application include the reports on
departures and exemptions as of the
time of submission of the application.
Paragraph IV.A.2.b requires that an
application referencing this appendix
include the reports required by
paragraph X.B of this appendix for
exemptions and departures proposed by
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the applicant as of the date of
submission of its application. Paragraph
IV.A.2.c requires submission of plantspecific TS for the plant that consists of
the generic TS from section 16.1 of the
DCD, with any changes made under
paragraph VIII.C of this appendix, and
the TS for the site-specific portions of
the plant that are either partially or
wholly outside the scope of this design
certification. The applicant must also
provide the plant-specific information
designated in the generic TS, such as
bracketed values.
Paragraph IV.A.2.d requires the
applicant referencing this appendix to
provide information demonstrating that
the proposed site falls within the site
parameters for this appendix and that
the plant-specific design complies with
the interface requirements, as required
by 10 CFR 52.79(b). If the proposed site
has a characteristic that exceeds one or
more of the site parameters in the DCD,
then the proposed site is unacceptable
for this design unless the applicant
seeks an exemption under section VIII
of this appendix and provides adequate
justification for locating the certified
design on the proposed site. Paragraph
IV.A.2.e requires submission of
information addressing COL action
items, identified in the generic DCD as
COL information in the application. The
COL information identifies matters that
need to be addressed by an applicant
who references this appendix, as
required by subpart C of 10 CFR part 52.
An applicant may depart from or omit
these items, provided that the departure
or omission is identified and justified in
its application (FSAR). Paragraph
IV.A.2.f requires that the application
include the information specified by 10
CFR 52.47(a) that is not within the
scope of this rule, such as generic issues
that must be addressed, in whole or in
part, by an applicant that references this
rule. Paragraph IV.A.3 requires the
applicant to physically include, not
simply reference, the proprietary and
safeguards information referenced in the
DCD, or its equivalent, to ensure that the
applicant has actual notice of these
requirements.
Paragraph IV.B reserves to the
Commission the right to determine in
what manner this DCR may be
referenced by an applicant for a
construction permit or operating license
under 10 CFR part 50. This
determination may occur in the context
of a subsequent rulemaking modifying
10 CFR part 52 or this design
certification rule, or on a case-by-case
basis in the context of a specific
application for a 10 CFR part 50
construction permit or operating
license. This provision is necessary
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because the previous DCRs were not
implemented in the manner that was
originally envisioned at the time that 10
CFR part 52 was promulgated. The
Commission’s concern is with the way
ITAAC were developed and the lack of
experience with design certifications in
license proceedings. Therefore, it is
appropriate that the Commission retain
some discretion regarding the way this
appendix could be referenced in a 10
CFR part 50 licensing proceeding.
E. Applicable Regulations
The purpose of section V of this
appendix is to specify the regulations
that were applicable and in effect at the
time this design certification was
approved. These regulations consist of
the technically relevant regulations
identified in paragraph V.A, except for
the regulations in paragraph V.B that are
not applicable to this certified design.
Paragraph V.A identifies the
regulations in 10 CFR parts 20, 50, 73,
and 100 that are applicable to the
AP1000 design. After the NRC staff
issued its FSER for the AP1000 design
(NUREG–1793, September 2004), the
Commission amended several existing
regulations and adopted new
regulations. The Commission reviewed
these regulations to determine if they
are applicable to this design and, if so,
to determine if the design meets these
regulations. The Commission finds that
none of these new regulations are
applicable to the AP1000 design. The
Commission’s determination of the
applicable regulations was made as of
the date specified in paragraph V.A of
this appendix, which is the date that
this appendix was approved by the
Commission and signed by the Secretary
of the Commission.
In paragraph V.B of this appendix, the
Commission identifies the regulations
that do not apply to the AP1000 design.
The Commission has determined that
the AP1000 design should be exempt
from portions of 10 CFR 50.34, 50.62,
and Appendix A to part 50, as described
in the FSER (NUREG–1793) and
summarized below:
(1) Paragraph (f)(2)(iv) of 10 CFR
50.34—Plant Safety Parameter Display
Console. Under 10 CFR 52.47(a)(ii), an
applicant for design certification must
demonstrate compliance with any
technically relevant Three Mile Island
(TMI) requirements in 10 CFR 50.34(f).
The requirement in 10 CFR
50.34(f)(2)(iv) states that an application
must provide a plant safety parameter
display console that will display a
minimum set of parameters defining the
safety status of the plant, be capable of
displaying a full range of important
plant parameters and data trends on
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demand, and be capable of indicating
when process limits are being
approached or exceeded. Westinghouse
addresses this requirement, in section
18.8.2 of the DCD, with an integrated
design rather than a stand-alone, add-on
system, as is used at most current
operating plants. Specifically,
Westinghouse integrated the safety
parameter display system (SPDS)
requirements into the design
requirements for the alarm and display
systems. The NRC staff has determined
that the function of a separate SPDS
may be integrated into the overall
control room design. Therefore, the
Commission has determined that the
special circumstances for allowing an
exemption as described in 10 CFR
50.12(a)(2)(ii) exist because the
requirement for an SPDS console need
not be applied in this particular
circumstance to achieve the underlying
purpose because Westinghouse has
provided an acceptable alternative that
accomplishes the intent of the
regulation. On this basis, the
Commission concludes that an
exemption from the requirements of 10
CFR 50.34(f)(2)(iv) is authorized by law,
will not present an undue risk to public
health and safety, and is consistent with
the common defense and security.
(2) Paragraph (c)(1) of 10 CFR 50.62—
Auxiliary Feedwater System. The
AP1000 design relies on the passive
residual heat removal system (PRHR) in
lieu of an auxiliary or emergency
feedwater system as its safety-related
method of removing decay heat.
Westinghouse requested an exemption
from a portion of 10 CFR 50.62(c)(1),
which requires auxiliary or emergency
feedwater as an alternate system for
decay heat removal during an
anticipated transient without scram
(ATWS) event. The NRC staff concluded
that Westinghouse met the intent of the
rule by relying on the PRHR system to
remove the decay heat and, thereby, met
the underlying purpose of the rule.
Therefore, the Commission has
determined that the special
circumstances for allowing an
exemption described in 10 CFR
50.12(a)(2)(ii) exist because the
requirement for an auxiliary or
emergency feedwater system is not
necessary to achieve the underlying
purpose of 10 CFR 50.62(c)(1). This is
because Westinghouse has adopted
acceptable alternatives that accomplish
the intent of this regulation, and the
exemption is authorized by law, will not
present an undue risk to public health
and safety, and is consistent with the
common defense and security.
(3) Appendix A to 10 CFR part 50,
GDC 17—Second Offsite Power Supply
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Circuit. Westinghouse requested a
partial exemption from the requirement
in General Design Criteria (GDC) 17 for
a second offsite power supply circuit.
The AP1000 plant design supports an
exemption to this requirement by
providing safety-related ‘‘passive’’
systems. These passive safety-related
systems only require electric power for
valves and the related instrumentation.
The onsite Class 1E batteries and
associated dc and ac distribution
systems can provide the power for these
valves and instrumentation. In addition,
if no offsite power is available, it is
expected that the non-safety-related
onsite diesel generators would be
available for important plant functions.
However, this non-safety-related ac
power is not relied on to maintain core
cooling or containment integrity.
Therefore, the Commission has
determined that the special
circumstances for allowing an
exemption as described in 10 CFR
50.12(a)(2)(ii) exist because the
requirement need not be applied in this
particular circumstance to achieve the
underlying purpose of having two
offsite power sources. This is because
the AP1000 design includes an
acceptable alternative approach to
accomplish safety functions that do not
rely on power from the offsite system
and, therefore, accomplishes the intent
of the regulation. On this basis, the
Commission concludes that a partial
exemption from the requirements of
GDC 17 is authorized by law, will not
present an undue risk to public health
and safety, and is consistent with the
common defense and security.
F. Issue Resolution
The purpose of section VI of this
appendix is to identify the scope of
issues that are resolved by the
Commission in this rulemaking and;
therefore, are ‘‘matters resolved’’ within
the meaning and intent of 10 CFR
52.63(a)(4). The section is divided into
five parts: (A) The Commission’s safety
findings in adopting this appendix, (B)
the scope and nature of issues which are
resolved by this rulemaking, (C) issues
which are not resolved by this
rulemaking, (D) the backfit restrictions
applicable to the Commission with
respect to this appendix, and (E) the
availability of secondary references.
Paragraph VI.A describes the nature of
the Commission’s findings in general
terms and makes the finding required by
10 CFR 52.54 for the Commission’s
approval of this DCR. Furthermore,
paragraph VI.A explicitly states the
Commission’s determination that this
design provides adequate protection of
the public health and safety.
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Paragraph VI.B sets forth the scope of
issues that may not be challenged as a
matter of right in subsequent
proceedings. The introductory phrase of
paragraph VI.B clarifies that issue
resolution as described in the remainder
of the paragraph extends to the
delineated NRC proceedings referencing
this appendix. The remainder of
paragraph VI.B describes the categories
of information for which there is issue
resolution. Specifically, paragraph
VI.B.1 provides that all nuclear safety
issues arising from the Atomic Energy
Act of 1954, as amended, that are
associated with the information in the
NRC staff’s FSER (NUREG–1793) and
Supplement No. 1, the Tier 1 and Tier
2 information (including the availability
controls in Section 16.3 of the generic
DCD), and the rulemaking record for
this appendix are resolved within the
meaning of 10 CFR 52.63(a)(4). These
issues include the information
referenced in the DCD that are
requirements (i.e., ‘‘secondary
references’’), as well as all issues arising
from proprietary and safeguards
information which are intended to be
requirements.
Paragraph VI.B.2 provides for issue
preclusion of proprietary and safeguards
information. Paragraphs VI.B.3, VI.B.4,
VI.B.5, and VI.B.6 clarify that approved
changes to and departures from the DCD
which are accomplished in compliance
with the relevant procedures and
criteria in section VIII of this appendix
continue to be matters resolved in
connection with this rulemaking.
Paragraphs VI.B.4, VI.B.5, and VI.B.6,
which characterize the scope of issue
resolution in three situations, use the
phrase ‘‘but only for that plant.’’
Paragraph VI.B.4 describes how issues
associated with a design certification
rule are resolved when an exemption
has been granted for a plant referencing
the design certification rule. Paragraph
VI.B.5 describes how issues are resolved
when a plant referencing the design
certification rule obtains a license
amendment for a departure from Tier 2
information.
Paragraph VI.B.6 describes how issues
are resolved when the applicant or
licensee departs from the Tier 2
information on the basis of paragraph
VIII.B.5, which will waive the
requirement for NRC approval. In all
three situations, after a matter (e.g., an
exemption in the case of paragraph
VI.B.4) is addressed for a specific plant
referencing a design certification rule,
the adequacy of that matter for that
plant will not ordinarily be subject to
challenge in any subsequent proceeding
or action for that plant (e.g., an
enforcement action) listed in the
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introductory portion of paragraph IV.B.
There will not, by contrast, be any issue
resolution on that subject matter for any
other plant.
Paragraph VI.B.7 provides that, for
those plants located on sites whose site
parameters do not exceed those
assumed in Westinghouse’s evaluation
of SAMDAs, all issues with respect to
SAMDAs arising under the National
Environmental Policy Act of 1969, as
amended (NEPA), associated with the
information in the environmental
assessment for this design and the
information regarding SAMDAs in
Appendix 1B of the generic DCD are
also resolved within the meaning and
intent of 10 CFR 52.63(a)(4). If an
exemption from a site parameter is
granted, the exemption applicant has
the initial burden of demonstrating that
the original SAMDA analysis still
applies to the actual site parameters but;
if the exemption is approved, requests
for litigation at the COL stage must meet
the requirements of 10 CFR 2.309 and
present sufficient information to create
a genuine controversy in order to obtain
a hearing on the site parameter
exemption.
Paragraph VI.C reserves the right of
the Commission to impose operational
requirements on applicants that
reference this appendix. This provision
reflects the fact that operational
requirements, including generic TS in
section 16.1 of the DCD, were not
completely or comprehensively
reviewed at the design certification
stage. Therefore, the special backfit
provisions of 10 CFR 52.63 do not apply
to operational requirements. However,
all design changes will be controlled by
the appropriate provision in section VIII
of this appendix. Although the
information in the DCD that is related to
operational requirements is necessary to
support the NRC’s safety review of this
design, the review of this information
was not sufficient to conclude that the
operational requirements are fully
resolved and ready to be assigned
finality under 10 CFR 52.63. As a result,
if the NRC wanted to change a
temperature limit and that operational
change required a consequential change
to a design feature, then the temperature
limit backfit would be controlled by
paragraph VIII.A or VIII.B of this
appendix. However, changes to other
operational requirements, such as
inservice testing and inservice
inspection programs, post-fuel load
verification activities, and requirements
governing shutdown risk that do not
require a design change would not be
restricted by 10 CFR 52.63 (see
paragraph VIII.C of this appendix).
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Paragraph VI.C allows the NRC to
impose future operational requirements
(distinct from design matters) on
applicants who reference this design
certification. Also, license conditions
for portions of the plant within the
scope of this design certification, e.g.,
start-up and power ascension testing,
are not restricted by 10 CFR 52.63. The
requirement to perform these testing
programs is contained in Tier 1
information. However, ITAAC cannot be
specified for these subjects because the
matters to be addressed in these license
conditions cannot be verified prior to
fuel load and operation, when the
ITAAC are satisfied. Therefore, another
regulatory vehicle is necessary to ensure
that licensees comply with the matters
contained in the license conditions.
License conditions for these areas
cannot be developed now because this
requires the type of detailed design
information that will be developed
during a combined license review. In
the absence of detailed design
information to evaluate the need for and
develop specific post-fuel load
verifications for these matters, the
Commission is reserving the right to
impose license conditions by rule for
post-fuel load verification activities for
portions of the plant within the scope of
this design certification.
Paragraph VI.D reiterates the
restrictions (contained in section VIII of
this appendix) placed upon the
Commission when ordering generic or
plant-specific modifications, changes or
additions to structures, systems, or
components, design features, design
criteria, and ITAAC (paragraph VI.D.3
would address ITAAC) within the scope
of the certified design.
Paragraph VI.E provides the
procedure for an interested member of
the public to obtain access to
proprietary or safeguards information
for the AP1000 design, in order to
request and participate in proceedings
identified in paragraph VI.B of this
appendix, viz., proceedings involving
licenses and applications which
reference this appendix. Paragraph VI.E
specifies that access must first be sought
from the design certification applicant.
If Westinghouse refuses to provide the
information, the person seeking access
shall request access from the
Commission or the presiding officer, as
applicable. Access to the proprietary or
safeguards information may be ordered
by the Commission, but must be subject
to an appropriate non-disclosure
agreement.
G. Duration of This Appendix
The purpose of section VII of this
appendix is in part, to specify the
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period during which this design
certification may be referenced by an
applicant for a COL, under 10 CFR
52.55. This section also states that the
design certification remains valid for an
applicant or licensee that references the
design certification until the application
is withdrawn or the license expires.
Therefore, if an application references
this design certification during the 15year period, then the design certification
will be effective until the application is
withdrawn or the license issued on that
application expires. Also, the design
certification will be effective for the
referencing licensee if the license is
renewed. The Commission intends for
this appendix to remain valid for the life
of the plant that references the design
certification to achieve the benefits of
standardization and licensing stability.
This means that changes to, or plantspecific departures from, information in
the plant-specific DCD must be made
under the change processes in section
VIII of this appendix for the life of the
plant.
H. Processes for Changes and
Departures
The purpose of section VIII of this
appendix is to set forth the processes for
generic changes to or plant-specific
departures (including exemptions) from
the DCD. The Commission adopted this
restrictive change process in order to
achieve a more stable licensing process
for applicants and licensees that
reference this DCR. Section VIII is
divided into three paragraphs, which
correspond to Tier 1, Tier 2, and
operational requirements. The language
of section VIII of this appendix
distinguishes between generic changes
to the DCD versus plant-specific
departures from the DCD. Generic
changes must be accomplished by
rulemaking because the intended
subject of the change is this DCR itself,
as is contemplated by 10 CFR
52.63(a)(1). Consistent with 10 CFR
52.63(a)(2), any generic rulemaking
changes are applicable to all plants,
absent circumstances which render the
change [‘‘modification’’ in the language
of 10 CFR 52.63(a)(2)] ‘‘technically
irrelevant.’’ By contrast, plant-specific
departures could be either a
Commission-issued order to one or more
applicants or licensees; or an applicant
or licensee-initiated departure
applicable only to that applicant’s or
licensee’s plant(s), similar to a 10 CFR
50.59 departure or an exemption.
Because these plant-specific departures
will result in a DCD that is unique for
that plant, section X of this appendix
requires an applicant or licensee to
maintain a plant-specific DCD. For
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purposes of brevity, this discussion
refers to both generic changes and plantspecific departures as ‘‘change
processes.’’
Section VIII of this appendix refers to
an exemption from one or more
requirements of this appendix and the
criteria for granting an exemption. The
Commission cautions that when the
exemption involves an underlying
substantive requirement (applicable
regulation), then the applicant or
licensee requesting the exemption must
also show that an exemption from the
underlying applicable requirement
meets the criteria of 10 CFR 50.12.
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Tier 1 information
The change processes for Tier 1
information are covered in paragraph
VIII.A. Generic changes to Tier 1 are
accomplished by rulemakings that
amend the generic DCD and are
governed by the standards in 10 CFR
52.63(a)(1). This provision provides that
the Commission may not modify,
change, rescind, or impose new
requirements by rulemaking except
when necessary either to bring the
certification into compliance with the
Commission’s regulations applicable
and in effect at the time of approval of
the design certification or to ensure
adequate protection of the public health
and safety or common defense and
security. The rulemakings must provide
for notice and opportunity for public
comment on the proposed change, as
required by 10 CFR 52.63(a)(1).
Departures from Tier 1 may occur in
two ways: (1) The Commission may
order a licensee to depart from Tier 1,
as provided in paragraph VIII.A.3; or (2)
an applicant or licensee may request an
exemption from Tier 1, as provided in
paragraph VIII.A.4. If the Commission
seeks to order a licensee to depart from
Tier 1, paragraph VIII.A.3 requires that
the Commission find both that the
departure is necessary for adequate
protection or for compliance, and that
special circumstances are present.
Paragraph VIII.A.4 provides that
exemptions from Tier 1 requested by an
applicant or licensee are governed by
the requirements of 10 CFR 52.63(b)(1)
and 52.97(b), which provide an
opportunity for a hearing. In addition,
the Commission will not grant requests
for exemptions that may result in a
significant decrease in the level of safety
otherwise provided by the design.
Tier 2 information
The change processes for the three
different categories of Tier 2
information, namely, Tier 2, Tier 2*,
and Tier 2* with a time of expiration,
are set forth in paragraph VIII.B. The
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change process for Tier 2 has the same
elements as the Tier 1 change process,
but some of the standards for plantspecific orders and exemptions are
different. As stated in section III, of this
SOC, it is the Commission’s intent that
this appendix emulates Appendix C to
10 CFR part 52. However, the
Commission has revised the 10 CFR
50.59-like change process in paragraph
VIII.B.5 of this appendix to be
commensurate with the new 10 CFR
50.59 (64 FR 53613, October 4, 1999).
The process for generic Tier 2 changes
(including changes to Tier 2* and Tier
2* with a time of expiration) tracks the
process for generic Tier 1 changes. As
set forth in paragraph VIII.B.1, generic
Tier 2 changes are accomplished by
rulemaking amending the generic DCD
and are governed by the standards in 10
CFR 52.63(a)(1). This provision provides
that the Commission may not modify,
change, rescind, or impose new
requirements by rulemaking except
when necessary, either to bring the
certification into compliance with the
Commission’s regulations applicable
and in effect at the time of approval of
the design certification or to ensure
adequate protection of the public health
and safety or common defense and
security. If a generic change is made to
Tier 2* information, then the category
and expiration, if necessary, of the new
information would also be determined
in the rulemaking and the appropriate
change process for that new information
would apply.
Departures from Tier 2 may occur in
five ways: (1) The Commission may
order a plant-specific departure, as set
forth in paragraph VIII.B.3; (2) an
applicant or licensee may request an
exemption from a Tier 2 requirement as
set forth in paragraph VIII.B.4; (3) a
licensee may make a departure without
prior NRC approval under paragraph
VIII.B.5 [similar to the process in 10
CFR 50.59]; (4) the licensee may request
NRC approval for proposed departures
which do not meet the requirements in
paragraph VIII.B.5 as provided in
paragraph VIII.B.5.d; and (5) the
licensee may request NRC approval for
a departure from Tier 2* information
under paragraph VIII.B.6.
Similar to Commission-ordered Tier 1
departures and generic Tier 2 changes,
Commission-ordered Tier 2 departures
cannot be imposed except when
necessary either to bring the
certification into compliance with the
Commission’s regulations applicable
and in effect at the time of approval of
the design certification or to ensure
adequate protection of the public health
and safety or common defense and
security, as set forth in paragraph
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4473
VIII.B.3. However, the special
circumstances for the Commissionordered Tier 2 departures do not have
to outweigh any decrease in safety that
may result from the reduction in
standardization caused by the plantspecific order, as required by 10 CFR
52.63(a)(3). The Commission
determined that it was not necessary to
impose an additional limitation similar
to that imposed on Tier 1 departures by
10 CFR 52.63(a)(3) and (b)(1). This type
of additional limitation for
standardization would unnecessarily
restrict the flexibility of applicants and
licensees with respect to Tier 2
information.
An applicant or licensee may request
an exemption from Tier 2 information as
set forth in paragraph VIII.B.4. The
applicant or licensee must demonstrate
that the exemption complies with one of
the special circumstances in 10 CFR
50.12(a). In addition, the Commission
will not grant requests for exemptions
that may result in a significant decrease
in the level of safety otherwise provided
by the design. However, the special
circumstances for the exemption do not
have to outweigh any decrease in safety
that may result from the reduction in
standardization caused by the
exemption. If the exemption is
requested by an applicant for a license,
the exemption is subject to litigation in
the same manner as other issues in the
license hearing, consistent with 10 CFR
52.63(b)(1). If the exemption is
requested by a licensee, then the
exemption is subject to litigation in the
same manner as a license amendment.
Paragraph VIII.B.5 allows an applicant
or licensee to depart from Tier 2
information, without prior NRC
approval, if the proposed departure does
not involve a change to, or departure
from, Tier 1 or Tier 2* information, TS,
or does not require a license amendment
under paragraphs VIII.B.5.b or
VIII.B.5.c. The TS referred to in
VIII.B.5.a of this paragraph are the TS in
section 16.1 of the generic DCD,
including bases, for departures made
prior to issuance of the COL. After
issuance of the COL, the plant-specific
TS are controlling under paragraph
VIII.B.5. The bases for the plant-specific
TS will be controlled by the bases
control procedures for the plant-specific
TS (analogous to the bases control
provision in the Improved Standard
Technical Specifications). The
requirement for a license amendment in
paragraph VIII.B.5.b will be similar to
the definition in the new 10 CFR 50.59
and apply to all information in Tier 2
except for the information that resolves
the severe accident issues.
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The Commission believes that the
resolution of severe accident issues
should be preserved and maintained in
the same fashion as all other safety
issues that were resolved during the
design certification review (refer to SRM
on SECY–90–377). However, because of
the increased uncertainty in severe
accident issue resolutions, the
Commission has adopted separate
criteria in paragraph VIII.B.5.c for
determining if a departure from
information that resolves severe
accident issues would require a license
amendment. For purposes of applying
the special criteria in paragraph
VIII.B.5.c, severe accident resolutions
are limited to design features where the
intended function of the design feature
is relied upon to resolve postulated
accidents when the reactor core has
melted and exited the reactor vessel,
and the containment is being
challenged. These design features are
identified in section 1.9.5 and Appendix
19B of the DCD, with other issues, and
are described in other sections of the
DCD. Therefore, the location of design
information in the DCD is not important
to the application of this special
procedure for severe accident issues.
However, the special procedure in
paragraph VIII.B.5.c does not apply to
design features that resolve so-called
‘‘beyond design-basis accidents’’ or
other low-probability events. The
important aspect of this special
procedure is that it is limited to severe
accident design features, as defined
above. Some design features may have
intended functions to meet ‘‘design
basis’’ requirements and to resolve
‘‘severe accidents.’’ If these design
features are reviewed under paragraph
VIII.B.5, then the appropriate criteria
from either paragraphs VIII.B.5.b or
VIII.B.5.c are selected depending upon
the function being changed.
An applicant or licensee that plans to
depart from Tier 2 information, under
paragraph VIII.B.5, is required to
prepare an evaluation which provides
the bases for the determination that the
proposed change does not require a
license amendment or involve a change
to Tier 1 or Tier 2* information, or a
change to the TS, as explained above. In
order to achieve the Commission’s goals
for design certification, the evaluation
needs to consider all of the matters that
were resolved in the DCD, such as
generic issue resolutions that are
relevant to the proposed departure. The
benefits of the early resolution of safety
issues would be lost if departures from
the DCD were made that violated these
resolutions without appropriate review.
The evaluation of the relevant matters
needs to consider the proposed
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departure over the full range of power
operation from startup to shutdown, as
it relates to anticipated operational
occurrences, transients, design-basis
accidents, and severe accidents. The
evaluation must also include a review of
all relevant secondary references from
the DCD because Tier 2 information,
which is intended to be treated as a
requirement, is contained in the
secondary references. The evaluation
should consider Tables 14.3–1 through
14.3–8 and 19.59–18 of the generic DCD
to ensure that the proposed change does
not impact Tier 1 information. These
tables contain cross-references from the
safety analyses and probabilistic risk
assessment in Tier 2 to the important
parameters that were included in Tier 1.
A party to an adjudicatory proceeding
(e.g., for issuance of a COL) who
believes that an applicant or licensee
has not complied with paragraph
VIII.B.5 when departing from Tier 2
information, is permitted to petition to
admit such a contention into the
proceeding under paragraph VIII.B.5.f.
This provision was included because an
incorrect departure from the
requirements of this appendix
essentially places the departure outside
of the scope of the Commission’s safety
finding in the design certification
rulemaking. Therefore, it follows that
properly founded contentions alleging
such incorrectly implemented
departures cannot be considered
‘‘resolved’’ by this rulemaking. As set
forth in paragraph VIII.B.5.f, the petition
must comply with the requirements of
10 CFR 2.309 and show that the
departure does not comply with
paragraph VIII.B.5. Any other party may
file a response to the petition. If on the
basis of the petition and any responses,
the presiding officer in the proceeding
determines that the required showing
has been made, the matter shall be
certified to the Commission for its final
determination. In the absence of a
proceeding, petitions alleging
nonconformance with paragraph
VIII.B.5 requirements applicable to Tier
2 departures will be treated as petitions
for enforcement action under 10 CFR
2.206.
Paragraph VIII.B.6 provides a process
for departing from Tier 2* information.
The creation of and restrictions on
changing Tier 2* information resulted
from the development of the Tier 1
information for ABWR design
certification (Appendix A to part 52)
and the ABB–CE System 80+ design
certification (Appendix B to part 52).
During this development process, these
applicants requested that the amount of
information in Tier 1 be minimized to
provide additional flexibility for an
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applicant or licensee who references
these appendices. Also, many codes,
standards, and design processes, which
were not specified in Tier 1 that are
acceptable for meeting ITAAC, were
specified in Tier 2. The result of these
actions is that certain significant
information only exists in Tier 2 and the
Commission does not want this
significant information to be changed
without prior NRC approval. This Tier
2* information is identified in the
generic DCD with italicized text and
brackets (See Table 1–1 of AP1000 DCD
Introduction).
Although the Tier 2* designation was
originally intended to last for the
lifetime of the facility, like Tier 1
information, the NRC determined that
some of the Tier 2* information could
expire when the plant first achieves full
(100 percent) power, after the finding
required by 10 CFR 52.103(g), while
other Tier 2* information must remain
in effect throughout the life of the
facility. The factors determining
whether Tier 2* information could
expire after the first full power was
achieved were whether the Tier 1
information would govern these areas
after first full power and the NRC’s
determination that prior approval was
required before implementation of the
change due to the significance of the
information. Therefore, certain Tier 2*
information listed in paragraph
VIII.B.6.c ceases to retain its Tier 2*
designation after full-power operation is
first achieved following the Commission
finding under 10 CFR 52.103(g).
Thereafter, that information is deemed
to be Tier 2 information that is subject
to the departure requirements in
paragraph VIII.B.5. By contrast, the Tier
2* information identified in paragraph
VIII.B.6.b retains its Tier 2* designation
throughout the duration of the license,
including any period of license renewal.
Certain preoperational tests in
paragraph VIII.B.6.c are designated to be
performed only for the first plant or first
three plants that reference this
appendix. Westinghouse’s basis for
performing these ‘‘first-plant-only’’ and
‘‘first-three-plants-only’’ preoperational
tests is provided in section 14.2.5 of the
DCD. The NRC found Westinghouse’s
basis for performing these tests and its
justification for only performing the
tests on the first plant or first three
plants acceptable. The NRC’s decision
was based on the need to verify that
plant-specific manufacturing and/or
construction variations do not adversely
impact the predicted performance of
certain passive safety systems, while
recognizing that these special tests will
result in significant thermal transients
being applied to critical plant
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components. The NRC believes that the
range of manufacturing or construction
variations that could adversely affect the
relevant passive safety systems would
be adequately disclosed after performing
the designated tests on the first plant, or
the first three plants, as applicable. The
COL action item in section 14.4.6 of the
DCD states that subsequent plants shall
either perform these preoperational tests
or justify that the results of the firstplant-only or first-three-plant-only tests
are applicable to the subsequent plant.
The Tier 2* designation for these tests
will expire after the first plant or first
three plants complete these tests, as
indicated in paragraph VIII.B.6.c.
If Tier 2* information is changed in a
generic rulemaking, the designation of
the new information (Tier 1, 2*, or 2)
would also be determined in the
rulemaking and the appropriate process
for future changes would apply. If a
plant-specific departure is made from
Tier 2* information, then the new
designation would apply only to that
plant. If an applicant who references
this design certification makes a
departure from Tier 2* information, the
new information is subject to litigation
in the same manner as other plantspecific issues in the licensing hearing.
If a licensee makes a departure from
Tier 2* information, it will be treated as
a license amendment under 10 CFR
50.90 and the finality will be
determined under paragraph VI.B.5 of
this appendix. Any requests for
departures from Tier 2* information that
affects Tier 1 must also comply with the
requirements in paragraph VIII.A of this
appendix.
Operational Requirements
The change process for TS and other
operational requirements in the DCD is
set forth in paragraph VIII.C. This
change process has elements similar to
the Tier 1 and Tier 2 change process in
paragraphs VIII.A and VIII.B, but with
significantly different change standards.
Because of the different finality status
for TS and other operational
requirements (refer to paragraph III.F of
this SOC), the Commission designated a
special category of information,
consisting of the TS and other
operational requirements, with its own
change process in proposed paragraph
VIII.C. The key to using the change
processes proposed in section VIII is to
determine if the proposed change or
departure requires a change to a design
feature described in the generic DCD. If
a design change is required, then the
appropriate change process in paragraph
VIII.A or VIII.B applies. However, if a
proposed change to the TS or other
operational requirements does not
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require a change to a design feature in
the generic DCD, then paragraph VIII.C
applies. The language in paragraph
VIII.C also distinguishes between
generic (section 16.1 of DCD) and plantspecific TS to account for the different
treatment and finality accorded TS
before and after a license is issued.
The process in paragraph VIII.C.1 for
making generic changes to the generic
TS in section 16.1 of the DCD or other
operational requirements in the generic
DCD is accomplished by rulemaking
and governed by the backfit standards in
10 CFR 50.109. The determination of
whether the generic TS and other
operational requirements were
completely reviewed and approved in
the design certification rulemaking is
based upon the extent to which an NRC
safety conclusion in the FSER is being
modified or changed. If it cannot be
determined that the TS or operational
requirement was comprehensively
reviewed and finalized in the design
certification rulemaking, then there is
no backfit restriction under 10 CFR
50.109 because no prior position was
taken on this safety matter. Generic
changes made under proposed
paragraph VIII.C.1 are applicable to all
applicants or licensees (refer to
paragraph VIII.C.2), unless the change is
irrelevant because of a plant-specific
departure.
Some generic TS and investment
protection short-term availability
controls contain values in brackets [].
The brackets are placeholders indicating
that the NRC’s review is not complete,
and represent a requirement that the
applicant for a combined license
referencing the AP1000 DCR must
replace the values in brackets with final
plant-specific values. The values in
brackets are neither part of the design
certification rule nor are they binding.
Therefore, the replacement of bracketed
values with final plant-specific values
does not require an exemption from the
generic TS or investment protection
short-term availability controls.
Plant-specific departures may occur
by either a Commission order under
paragraph VIII.C.3 or an applicant’s
exemption request under paragraph
VIII.C.4. The basis for determining if the
TS or operational requirement was
completely reviewed and approved for
these processes is the same as for
paragraph VIII.C.1 above. If the TS or
operational requirement is
comprehensively reviewed and
finalized in the design certification
rulemaking, then the Commission must
demonstrate that special circumstances
are present before ordering a plantspecific departure. If not, there is no
restriction on plant-specific changes to
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4475
the TS or operational requirements,
prior to the issuance of a license,
provided a design change is not
required. Although the generic TS were
reviewed and approved by the NRC staff
in support of the design certification
review, the Commission intends to
consider the lessons learned from
subsequent operating experience during
its licensing review of the plant-specific
TS. The process for petitioning to
intervene on a TS or operational
requirement contained in paragraph
VIII.C.5 is similar to other issues in a
licensing hearing, except that the
petitioner must also demonstrate why
special circumstances are present.
Finally, the generic TS will have no
further effect on the plant-specific TS
after the issuance of a license that
references this appendix. The bases for
the generic TS will be controlled by the
change process in paragraph VIII.C of
this appendix. After a license is issued,
the bases will be controlled by the bases
change provision set forth in the
administrative controls section of the
plant-specific TS.
I. Inspections, Tests, Analyses, and
Acceptance Criteria (ITAAC)
The purpose of section IX of this
appendix is to set forth how the ITAAC
in Tier 1 of this design certification rule
are to be treated in a license proceeding.
Paragraph IX.A restates the
responsibilities of an applicant or
licensee for performing and successfully
completing ITAAC, and notifying the
NRC of such completion. Paragraph
IX.A.1 clarifies that an applicant may
proceed at its own risk with design and
procurement activities subject to
ITAAC, and that a licensee may proceed
at its own risk with design,
procurement, construction, and
preoperational testing activities subject
to an ITAAC, even though the NRC may
not have found that any particular
ITAAC has been successfully
completed. Paragraph IX.A.2 requires
the licensee to notify the NRC that the
required inspections, tests, and analyses
in the ITAAC have been completed and
that the acceptance criteria have been
met.
Paragraphs IX.B.1 and IX.B.2 reiterate
the NRC’s responsibilities with respect
to ITAAC as set forth in 10 CFR 52.99
and 52.103(g).1 Finally, paragraph
IX.B.3 states that ITAAC do not, by
virtue of their inclusion in the DCD,
constitute regulatory requirements after
the licensee has received authorization
to load fuel or has been granted a
1 For discussion of the verification of ITAAC, see
SECY–00––92, ‘‘Combined License Review
Process,’’ dated April 20, 2000.
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renewal of its license. However,
subsequent modifications to the terms of
the COL must comply with the design
descriptions in the DCD unless the
applicable requirements in 10 CFR
52.97 and section VIII of this appendix
have been met. As discussed in
paragraph III.D of this SOC, the
Commission will defer a determination
of the applicability of ITAAC and its
effect in terms of issue resolution in 10
CFR part 50 licensing proceedings until
a part 50 applicant decides to reference
this appendix.
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J. Records and Reporting
The purpose of section X of this
appendix is to set forth the requirements
that will apply to maintaining records of
changes to and departures from the
generic DCD, which are to be reflected
in the plant-specific DCD. Section X
also sets forth the requirements for
submitting reports (including updates to
the plant-specific DCD) to the NRC. This
section of the appendix is similar to the
requirements for records and reports in
10 CFR part 50, except for minor
differences in information collection
and reporting requirements.
Paragraph X.A.1 of this appendix
requires that a generic DCD and the
proprietary and safeguards information
referenced in the generic DCD be
maintained by the applicant for this
rule. The generic DCD was developed,
in part, to meet the requirements for
incorporation by reference, including
availability requirements. Therefore, the
proprietary and safeguards information
could not be included in the generic
DCD because they are not publicly
available. However, the proprietary and
safeguards information was reviewed by
the NRC and, as stated in paragraph
VI.B.2 of this appendix, the Commission
considers the information resolved
within the meaning of 10 CFR
52.63(a)(4). Because this information is
not in the generic DCD, the proprietary
and safeguards information, or its
equivalent, is required to be provided by
an applicant for a license. Therefore, to
ensure that this information will be
available, a requirement for the design
certification applicant to maintain the
proprietary and safeguards information
was added to proposed paragraph X.A.1
of this appendix. The acceptable version
of the proprietary and safeguards
information is identified (referenced) in
the version of the DCD that is
incorporated into this rule. The generic
DCD and the acceptable version of the
proprietary and safeguards information
must be maintained for the period of
time that this appendix may be
referenced.
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Paragraphs X.A.2 and X.A.3 place
recordkeeping requirements on the
applicant or licensee that references this
design certification so that its plantspecific DCD accurately reflects both
generic changes to the generic DCD and
plant-specific departures made under
Section VIII of this appendix. The term
‘‘plant-specific’’ was added to paragraph
X.A.2 and other sections of this
appendix to distinguish between the
generic DCD that is incorporated by
reference into this appendix, and the
plant-specific DCD that the applicant is
required to submit under paragraph
IV.A of this appendix. The requirement
to maintain changes to the generic DCD
is explicitly stated to ensure that these
changes are not only reflected in the
generic DCD, which will be maintained
by the applicant for design certification,
but also in the plant-specific DCD.
Therefore, records of generic changes to
the DCD will be required to be
maintained by both entities to ensure
that both entities have up-to-date DCDs.
Paragraph X.A of this appendix does
not place recordkeeping requirements
on site-specific information that is
outside the scope of this rule. As
discussed in paragraph III.D of this SOC,
the FSAR required by 10 CFR 52.79 will
contain the plant-specific DCD and the
site-specific information for a facility
that references this rule. The phrase
‘‘site-specific portion of the final safety
analysis report’’ in paragraph X.B.3.c of
this appendix refers to the information
that is contained in the FSAR for a
facility (required by 10 CFR 52.79) but
is not part of the plant-specific DCD
(required by paragraph IV.A of this
appendix). Therefore, this rule does not
require that duplicate documentation be
maintained by an applicant or licensee
that references this rule, because the
plant-specific DCD is part of the FSAR
for the facility.
Paragraph X.B.1 requires applicants or
licensees that reference this rule to
submit reports, which describe
departures from the DCD and include a
summary of the written evaluations. The
requirements for the written evaluations
are set forth in paragraph X.A.1. The
frequency of the report submittals is set
forth in paragraph X.B.3. The
requirement for submitting a summary
of the evaluations is similar to the
requirement in 10 CFR 50.59(d)(2).
Paragraph X.B.2 requires applicants or
licensees that reference this rule to
submit updates to the DCD, which
include both generic changes and plantspecific departures. The frequency for
submitting updates is set forth in
paragraph X.B.3. The requirements in
paragraph X.B.3 for submitting the
reports and updates will vary according
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to certain time periods during a
facility’s lifetime. If a potential
applicant for a combined license who
references this rule decides to depart
from the generic DCD prior to
submission of the application, then
paragraph X.B.3.a will require that the
updated DCD be submitted as part of the
initial application for a license. Under
paragraph X.B.3.b, the applicant may
submit any subsequent updates to its
plant-specific DCD along with its
amendments to the application
provided that the submittals are made at
least once per year. Because
amendments to an application are
typically made more frequently than
once a year, this should not be an
excessive burden on the applicant.
Paragraph X.B.3.b also requires that
the reports required by paragraph X.B.1
be submitted semi-annually. This
increase in reporting frequency during
the period of construction and
application review is consistent with
Commission guidance. Also, more
frequent reporting of design changes
during the period of detailed design and
construction is necessary to closely
monitor the status and progress of the
facility. In order to make the finding
under 10 CFR 52.103(g), the NRC must
monitor the design changes made under
proposed section VIII of this appendix.
Frequent reporting of design changes
would be particularly important when
the number of design changes could be
significant, such as during the
procurement of components and
equipment, detailed design of the plant
before and during construction, and
during preoperational testing. After the
facility begins operation, the frequency
of reporting will revert to the
requirement in paragraph X.B.3.c,
which is consistent with the
requirements for plants licensed under
10 CFR 50.57.
IV. Availability of Documents
The NRC is making the documents
identified below available to interested
persons through one or more of the
following:
Public Document Room (PDR). The
NRC’s Public Document Room is located
at 11555 Rockville Pike, Public File
Area O–1 F21, Rockville, Maryland
20852. Copies of publicly available
documents related to this rulemaking
can be viewed electronically on public
computers in the PDR. The PDR
reproduction contractor will make
copies of documents for a fee.
Rulemaking Web site (Web). The
NRC’s interactive rulemaking Web site
is located at https://ruleforum.llnl.gov.
Selected documents may be viewed and
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downloaded electronically via this Web
site.
Public Electronic Reading Room
(ADAMS). The NRC’s Public Electronic
Reading Room (PERR) is located at
https://www.nrc.gov/reading-rm/
adams.html. Through this site, the
4477
public can gain access to ADAMS,
which provides text and image files of
NRC’s public documents.
Document
PDR
Web
ADAMS
AP1000 Design Control Document, Revision 15 .........................................................................................
AP1000 Final Environmental Assessment ...................................................................................................
AP1000 Final Safety Evaluation Report [NUREG–1793] ............................................................................
NUREG–1793, Supplement 1, AP1000 FSER ............................................................................................
SECY–05–0227, Final Rule—AP1000 Design Certification ........................................................................
Regulatory History of Design Certification 2 .................................................................................................
X
X
X
X
X
X
................
................
................
................
X
................
ML053460400
ML053630176
ML043570339
ML053410203
ML053250288
ML003761550
V. Voluntary Consensus Standards
The National Technology Transfer
and Advancement Act of 1995 (Act),
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 final rule,
the NRC is approving the AP1000
standard plant design for use in nuclear
power plant licensing under 10 CFR
parts 50 or 52. Design certifications are
not generic rulemakings establishing a
generally applicable standard with
which all parts 50 and 52 nuclear power
plant licensees must comply. Design
certifications are Commission approvals
of specific nuclear power plant designs
by rulemaking. Furthermore, design
certifications are initiated by an
applicant for rulemaking, rather than by
the NRC. For these reasons, the NRC
concludes that the Act does not apply
to this final rule.
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VI. Finding of No Significant
Environmental Impact: Availability
The Commission has determined
under NEPA, and the Commission’s
regulations in 10 CFR part 51, subpart
A, that this design certification rule is
not a major Federal action significantly
affecting the quality of the human
environment and, therefore, an
Environmental Impact Statement (EIS)
is not required. The basis for this
determination, as documented in the
environmental assessment (EA), is that
this amendment to 10 CFR part 52 does
not authorize the siting, construction, or
operation of a facility using the AP1000
design; it only codifies the AP1000
design in a rule. The NRC will evaluate
the environmental impacts and issue an
EIS as appropriate under NEPA as part
of the application(s) for the construction
and operation of a facility referencing
the AP1000 design certification rule.
2 The regulatory history of the NRC’s design
certification reviews is a package of 100 documents
that is available in NRC’s PERR and in the PDR.
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In addition, as part of the
environmental assessment for the
AP1000 design, the NRC reviewed
Westinghouse’s evaluation of various
design alternatives to prevent and
mitigate severe accidents in Appendix
1B of the AP1000 DCD Tier 2. Based
upon review of Westinghouse’s
evaluation, the Commission finds that:
(1) Westinghouse identified a
reasonably complete set of potential
design alternatives to prevent and
mitigate severe accidents for the AP1000
design; (2) none of the potential design
alternatives are justified on the basis of
cost-benefit considerations; and (3) it is
unlikely that other design changes
would be identified and justified in the
future on the basis of cost-benefit
considerations, because the estimated
core damage frequencies for the AP1000
are very low on an absolute scale. These
issues are considered resolved for the
AP1000 design.
The EA, upon which the
Commission’s Finding of No Significant
Impact is based, and the AP1000 DCD
are available for examination and
copying at the NRC Public Document
Room, One White Flint North, 11555
Rockville Pike, Rockville, Maryland
20852. The NRC sent a copy of the EA
and proposed rule to every State Liaison
Officer and no comments were received.
Single copies of the EA are also
available from Lauren M. QuinonesNavarro, Mailstop O–4D9A, Office of
Nuclear Reactor Regulation, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555.
The burden to the public for these
information collections is estimated to
average 8 hours per response, including
the time for reviewing instructions,
searching existing data sources,
gathering and maintaining the data
needed, and completing and reviewing
the information collection. Send
comments on any aspect of these
information collections, including
suggestions for reducing the burden, to
the Records and FOIA/Privacy Services
Branch (T5 F52), U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, or by Internet
electronic mail to
INFOCOLLECTS@NRC.GOV; and to the
Desk Officer, Office of Information and
Regulatory Affairs, NEOB–10202,
(3150–0151), Office of Management and
Budget, Washington, DC 20503.
Public Protection Notification
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.
VII. Paperwork Reduction Act
Statement
This final rule contains new or
amended information collection
requirements that are subject to the
Paperwork Reduction Act of 1995 (44
U.S.C. 3501 et seq.). These requirements
were approved by the Office of
Management and Budget, approval
number 3150–0151.
VIII. Regulatory Analysis
The NRC has not prepared a
regulatory analysis for this final rule.
The NRC prepares regulatory analyses
for rulemakings that establish generic
regulatory requirements applicable to all
licensees. Design certifications are not
generic rulemakings in the sense that
design certifications do not establish
standards or requirements with which
all licensees must comply. Rather,
design certifications are Commission
approvals of specific nuclear power
plant designs by rulemaking, which
then may be voluntarily referenced by
applicants for COLs. Furthermore,
design certification rulemakings are
initiated by an applicant for a design
certification, rather than the NRC.
Preparation of a regulatory analysis in
This history spans a 15-year period during which
the NRC simultaneously developed the regulatory
standards for reviewing these designs and the form
and content of the rules that certified the designs.
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this circumstance would not be useful
because the design to be certified is
proposed by the applicant rather than
the NRC. For these reasons, the
Commission concludes that preparation
of a regulatory analysis is neither
required nor appropriate.
IX. Regulatory Flexibility Certification
Under the Regulatory Flexibility Act
of 1980, 5 U.S.C. 605(b), the
Commission certifies that this final rule
will not have a significant economic
impact upon a substantial number of
small entities. The final rule provides
for certification of a nuclear power plant
design. Neither the design certification
applicant, nor prospective nuclear
power plant licensees who reference
this design certification rule, fall within
the scope of the definition of ‘‘small
entities’’ set forth in the Regulatory
Flexibility Act, or the Small Business
Size Standards set out in regulations
issued by the Small Business
Administration in 13 CFR part 121.
Thus, this rule does not fall within the
purview of the Regulatory Flexibility
Act.
X. Backfit Analysis
The Commission has determined that
this final rule does not constitute a
backfit as defined in the backfit rule (10
CFR 50.109), because this design
certification does not impose new or
changed requirements on existing 10
CFR part 50 licensees, nor does it
impose new or change requirements on
existing DCRs in appendices A–C of part
52. Therefore, a backfit analysis was not
prepared for this rule.
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XI. Congressional Review Act
In accordance with the Congressional
Review Act of 1996, the NRC has
determined that this action is not a
major rule and has verified this
determination with the Office of
Information and Regulatory Affairs of
OMB.
List of Subjects in 10 CFR Part 52
Administrative practice and
procedure, Antitrust, Backfitting,
Combined license, Early site permit,
Emergency planning, Fees,
Incorporation by reference, 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.
I For the reasons set out in this SOC
and under the authority of the Atomic
Energy Act of 1954, as amended; the
Energy Reorganization Act of 1974, as
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15:14 Jan 26, 2006
Jkt 208001
amended; and 5 U.S.C. 552 and 553; the
NRC is adopting the following
amendments to 10 CFR part 52.
PART 52—EARLY SITE PERMITS;
STANDARD DESIGN
CERTIFICATIONS; AND COMBINED
LICENSES FOR NUCLEAR POWER
PLANTS
1. The authority citation for 10 CFR
part 52 continues to read as follows:
I
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
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).
2. In § 52.8, paragraph (b) is revised to
read as follows:
I
§ 52.8 Information collection
requirements: OMB approval.
*
*
*
*
*
(b) The approved information
collection requirements contained in
this part appear in §§ 52.15, 52.17,
52.29, 52.35, 52.45, 52.47, 52.51, 52.57,
52.63, 52.75, 52.77, 52.78, 52.79, 52.89,
52.91, 52.99, and appendices A, B, C,
and D to this part.
I 3. A new Appendix D to 10 CFR part
52 is added to read as follows:
Appendix D to Part 52—Design
Certification Rule for the AP1000
Design
I. Introduction
Appendix D constitutes the standard
design certification for the AP1000 3 design,
in accordance with 10 CFR part 52, subpart
B. The applicant for certification of the
AP1000 design is Westinghouse Electric
Company LLC.
II. Definitions
A. Generic design control document
(generic DCD) means the document
containing the Tier 1 and Tier 2 information
and generic technical specifications that is
incorporated by reference into this appendix.
B. Generic technical specifications means
the information required by 10 CFR 50.36
and 50.36a for the portion of the plant that
is within the scope of this appendix.
C. Plant-specific DCD means the document
maintained by an applicant or licensee who
references this appendix consisting of the
information in the generic DCD as modified
and supplemented by the plant-specific
departures and exemptions made under
section VIII of this appendix.
D. Tier 1 means the portion of the designrelated information contained in the generic
DCD that is approved and certified by this
appendix (Tier 1 information). The design
descriptions, interface requirements, and site
3 AP1000 is a trademark of Westinghouse Electric
Company LLC.
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parameters are derived from Tier 2
information. Tier 1 information includes:
1. Definitions and general provisions;
2. Design descriptions;
3. Inspections, tests, analyses, and
acceptance criteria (ITAAC);
4. Significant site parameters; and
5. Significant interface requirements.
E. Tier 2 means the portion of the designrelated information contained in the generic
DCD that is approved but not certified by this
appendix (Tier 2 information). Compliance
with Tier 2 is required, but generic changes
to and plant-specific departures from Tier 2
are governed by section VIII of this appendix.
Compliance with Tier 2 provides a sufficient,
but not the only acceptable, method for
complying with Tier 1. Compliance methods
differing from Tier 2 must satisfy the change
process in section VIII of this appendix.
Regardless of these differences, an applicant
or licensee must meet the requirement in
paragraph III.B to reference Tier 2 when
referencing Tier 1. Tier 2 information
includes:
1. Information required by 10 CFR 52.47,
with the exception of generic TS, the designspecific PRA, the evaluation of SAMDAs, and
conceptual design information;
2. Information required for a final safety
analysis report under 10 CFR 50.34;
3. Supporting information on the
inspections, tests, and analyses that will be
performed to demonstrate that the acceptance
criteria in the ITAAC have been met; and
4. COL action items (COL information),
which identify certain matters that shall be
addressed in the site-specific portion of the
FSAR by an applicant who references this
appendix. These items constitute information
requirements but are not the only acceptable
set of information in the FSAR. An applicant
may depart from or omit these items,
provided that the departure or omission is
identified and justified in the FSAR. After
issuance of a construction permit or COL,
these items are not requirements for the
licensee unless such items are restated in the
FSAR.
5. The investment protection short-term
availability controls in section 16.3 of the
DCD.
F. Tier 2* means the portion of the Tier 2
information, designated as such in the
generic DCD, which is subject to the change
process in paragraph VIII.B.6 of this
appendix. This designation expires for some
Tier 2* information under paragraph VIII.B.6.
G. Departure from a method of evaluation
described in the plant-specific DCD used in
establishing the design bases or in the safety
analyses means:
1. Changing any of the elements of the
method described in the plant-specific DCD
unless the results of the analysis are
conservative or essentially the same; or
2. Changing from a method described in
the plant-specific DCD to another method
unless that method has been approved by the
NRC for the intended application.
H. All other terms in this appendix have
the meaning set out in 10 CFR 50.2, 10 CFR
52.3, or section 11 of the Atomic Energy Act
of 1954, as amended, as applicable.
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III. Scope and Contents
A. Tier 1, Tier 2 (including the investment
protection short-term availability controls in
Section 16.3), and the generic TS in the
AP1000 DCD (Revision 15, dated December
8, 2005) are approved for incorporation by
reference by the Director of the Office of the
Federal Register on February 27, 2006 under
5 U.S.C. 552(a) and 1 CFR part 51. Copies of
the generic DCD may be obtained from
Ronald P. Vijuk, Manager, Passive Plant
Engineering, Westinghouse Electric
Company, P.O. Box 355, Pittsburgh,
Pennsylvania 15230–0355. A copy of the
generic DCD is also available for examination
and copying at the NRC Public Document
Room, One White Flint North, 11555
Rockville Pike, Rockville, Maryland, 20852.
Copies are available for examination at the
NRC Library, Two White Flint North, 11545
Rockville Pike, Rockville, Maryland,
telephone (301) 415–5610, e-mail
LIBRARY@NRC.GOV or at the National
Archives and Records Administration
(NARA). For information on the availability
of this material at NARA, call (202) 741–6030
or go to https://www.archives.gov/
federal_register/code_of_federal_regulations/
ibr_locations.html.
B. An applicant or licensee referencing this
appendix, in accordance with Section IV of
this appendix, shall incorporate by reference
and comply with the requirements of this
appendix, including Tier 1, Tier 2 (including
the investment protection short-term
availability controls in section 16.3 of the
DCD), and the generic TS except as otherwise
provided in this appendix. Conceptual
design information in the generic DCD and
the evaluation of SAMDAs in appendix 1B of
the generic DCD are not part of this
appendix.
C. If there is a conflict between Tier 1 and
Tier 2 of the DCD, then Tier 1 controls.
D. If there is a conflict between the generic
DCD and either the application for design
certification of the AP1000 design or
NUREG–1793, ‘‘Final Safety Evaluation
Report Related to Certification of the AP1000
Standard Design,’’ (FSER) and Supplement
No. 1, then the generic DCD controls.
E. Design activities for structures, systems,
and components that are wholly outside the
scope of this appendix may be performed
using site characteristics, provided the design
activities do not affect the DCD or conflict
with the interface requirements.
IV. Additional Requirements and
Restrictions
A. An applicant for a license that wishes
to reference this appendix shall, in addition
to complying with the requirements of 10
CFR 52.77, 52.78, and 52.79, comply with the
following requirements:
1. Incorporate by reference, as part of its
application, this appendix.
2. Include, as part of its application:
a. A plant-specific DCD containing the
same type of information and using the same
organization and numbering as the generic
DCD for the AP1000 design, as modified and
supplemented by the applicant’s exemptions
and departures;
b. The reports on departures from and
updates to the plant-specific DCD required by
paragraph X.B of this appendix;
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c. Plant-specific TS, consisting of the
generic and site-specific TS that are required
by 10 CFR 50.36 and 50.36a;
d. Information demonstrating compliance
with the site parameters and interface
requirements;
e. Information that addresses the COL
action items; and
f. Information required by 10 CFR 52.47(a)
that is not within the scope of this appendix.
3. Physically include, in the plant-specific
DCD, the proprietary and safeguards
information referenced in the AP1000 DCD.
B. The Commission reserves the right to
determine in what manner this appendix
may be referenced by an applicant for a
construction permit or operating license
under part 50 of this chapter.
V. Applicable Regulations
A. Except as indicated in paragraph B of
this section, the regulations that apply to the
AP1000 design are in 10 CFR parts 20, 50,
73, and 100, codified as of January 23, 2006,
that are applicable and technically relevant,
as described in the FSER (NUREG–1793) and
Supplement No. 1.
B. The AP1000 design is exempt from
portions of the following regulations:
1. Paragraph (f)(2)(iv) of 10 CFR 50.34—
Plant Safety Parameter Display Console;
2. Paragraph (c)(1) of 10 CFR 50.62—
Auxiliary (or emergency) feedwater system;
and
3. Appendix A to 10 CFR part 50, GDC
17—Second offsite power supply circuit.
VI. Issue Resolution
A. The Commission has determined that
the structures, systems, components, and
design features of the AP1000 design comply
with the provisions of the Atomic Energy Act
of 1954, as amended, and the applicable
regulations identified in section V of this
appendix; and therefore, provide adequate
protection to the health and safety of the
public. A conclusion that a matter is resolved
includes the finding that additional or
alternative structures, systems, components,
design features, design criteria, testing,
analyses, acceptance criteria, or justifications
are not necessary for the AP1000 design.
B. The Commission considers the
following matters resolved within the
meaning of 10 CFR 52.63(a)(4) in subsequent
proceedings for issuance of a COL,
amendment of a COL, or renewal of a COL,
proceedings held under to 10 CFR 52.103,
and enforcement proceedings involving
plants referencing this appendix:
1. All nuclear safety issues, except for the
generic TS and other operational
requirements, associated with the
information in the FSER and Supplement No.
1, Tier 1, Tier 2 (including referenced
information, which the context indicates is
intended as requirements, and the
investment protection short-term availability
controls in section 16.3 of the DCD), and the
rulemaking record for certification of the
AP1000 design;
2. All nuclear safety and safeguards issues
associated with the information in
proprietary and safeguards documents,
referenced and in context, are intended as
requirements in the generic DCD for the
AP1000 design;
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3. All generic changes to the DCD under
and in compliance with the change processes
in sections VIII.A.1 and VIII.B.1 of this
appendix;
4. All exemptions from the DCD under and
in compliance with the change processes in
sections VIII.A.4 and VIII.B.4 of this
appendix, but only for that plant;
5. All departures from the DCD that are
approved by license amendment, but only for
that plant;
6. Except as provided in paragraph
VIII.B.5.f of this appendix, all departures
from Tier 2 under and in compliance with
the change processes in paragraph VIII.B.5 of
this appendix that do not require prior NRC
approval, but only for that plant;
7. All environmental issues concerning
SAMDAs associated with the information in
the NRC’s EA for the AP1000 design and
Appendix 1B of the generic DCD, for plants
referencing this appendix whose site
parameters are within those specified in the
SAMDA evaluation.
C. The Commission does not consider
operational requirements for an applicant or
licensee who references this appendix to be
matters resolved within the meaning of 10
CFR 52.63(a)(4). The Commission reserves
the right to require operational requirements
for an applicant or licensee who references
this appendix by rule, regulation, order, or
license condition.
D. Except under the change processes in
section VIII of this appendix, the
Commission may not require an applicant or
licensee who references this appendix to:
1. Modify structures, systems, components,
or design features as described in the generic
DCD;
2. Provide additional or alternative
structures, systems, components, or design
features not discussed in the generic DCD; or
3. Provide additional or alternative design
criteria, testing, analyses, acceptance criteria,
or justification for structures, systems,
components, or design features discussed in
the generic DCD.
E.1. Persons who wish to review
proprietary and safeguards information or
other secondary references in the AP1000
DCD, in order to request or participate in the
hearing required by 10 CFR 52.85 or the
hearing provided under 10 CFR 52.103, or to
request or participate in any other hearing
relating to this appendix in which interested
persons have adjudicatory hearing rights,
shall first request access to such information
from Westinghouse. The request must state
with particularity:
a. The nature of the proprietary or other
information sought;
b. The reason why the information
currently available to the public in the NRC’s
public document room is insufficient;
c. The relevance of the requested
information to the hearing issue(s) which the
person proposes to raise; and
d. A showing that the requesting person
has the capability to understand and utilize
the requested information.
2. If a person claims that the information
is necessary to prepare a request for hearing,
the request must be filed no later than 15
days after publication in the Federal Register
of the notice required either by 10 CFR 52.85
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or 10 CFR 52.103. If Westinghouse declines
to provide the information sought,
Westinghouse shall send a written response
within ten (10) days of receiving the request
to the requesting person setting forth with
particularity the reasons for its refusal. The
person may then request the Commission (or
presiding officer, if a proceeding has been
established) to order disclosure. The person
shall include copies of the original request
(and any subsequent clarifying information
provided by the requesting party to the
applicant) and the applicant’s response. The
Commission and presiding officer shall base
their decisions solely on the person’s original
request (including any clarifying information
provided by the requesting person to
Westinghouse), and Westinghouse’s
response. The Commission and presiding
officer may order Westinghouse to provide
access to some or all of the requested
information, subject to an appropriate nondisclosure agreement.
VII. Duration of This Appendix
This appendix may be referenced for a
period of 15 years from February 27, 2006,
except as provided for in 10 CFR 52.55(b)
and 52.57(b). This appendix remains valid
for an applicant or licensee who references
this appendix until the application is
withdrawn or the license expires, including
any period of extended operation under a
renewed license.
VIII. Processes for Changes and Departures
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A. Tier 1 Information
1. Generic changes to Tier 1 information
are governed by the requirements in 10 CFR
52.63(a)(1).
2. Generic changes to Tier 1 information
are applicable to all applicants or licensees
who reference this appendix, except those for
which the change has been rendered
technically irrelevant by action taken under
paragraphs A.3 or A.4 of this section.
3. Departures from Tier 1 information that
are required by the Commission through
plant-specific orders are governed by the
requirements in 10 CFR 52.63(a)(3).
4. Exemptions from Tier 1 information are
governed by the requirements in 10 CFR
52.63(b)(1) and 52.97(b). The Commission
will deny a request for an exemption from
Tier 1, if it finds that the design change will
result in a significant decrease in the level of
safety otherwise provided by the design.
B. Tier 2 Information
1. Generic changes to Tier 2 information
are governed by the requirements in 10 CFR
52.63(a)(1).
2. Generic changes to Tier 2 information
are applicable to all applicants or licensees
who reference this appendix, except those for
which the change has been rendered
technically irrelevant by action taken under
paragraphs B.3, B.4, B.5, or B.6 of this
section.
3. The Commission may not require new
requirements on Tier 2 information by plantspecific order while this appendix is in effect
under 10 CFR 52.55 or 52.61, unless:
a. A modification is necessary to secure
compliance with the Commission’s
regulations applicable and in effect at the
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time this appendix was approved, as set forth
in Section V of this appendix, or to ensure
adequate protection of the public health and
safety or the common defense and security;
and
b. Special circumstances as defined in 10
CFR 50.12(a) are present.
4. An applicant or licensee who references
this appendix may request an exemption
from Tier 2 information. The Commission
may grant such a request only if it determines
that the exemption will comply with the
requirements of 10 CFR 50.12(a). The
Commission will deny a request for an
exemption from Tier 2, if it finds that the
design change will result in a significant
decrease in the level of safety otherwise
provided by the design. The grant of an
exemption to an applicant must be subject to
litigation in the same manner as other issues
material to the license hearing. The grant of
an exemption to a licensee must be subject
to an opportunity for a hearing in the same
manner as license amendments.
5.a. An applicant or licensee who
references this appendix may depart from
Tier 2 information, without prior NRC
approval, unless the proposed departure
involves a change to or departure from Tier
1 information, Tier 2* information, or the TS,
or requires a license amendment under
paragraphs B.5.b or B.5.c of this section.
When evaluating the proposed departure, an
applicant or licensee shall consider all
matters described in the plant-specific DCD.
b. A proposed departure from Tier 2, other
than one affecting resolution of a severe
accident issue identified in the plant-specific
DCD, requires a license amendment if it
would:
(1) Result in more than a minimal increase
in the frequency of occurrence of an accident
previously evaluated in the plant-specific
DCD;
(2) Result in more than a minimal increase
in the likelihood of occurrence of a
malfunction of a structure, system, or
component (SSC) important to safety and
previously evaluated in the plant-specific
DCD;
(3) Result in more than a minimal increase
in the consequences of an accident
previously evaluated in the plant-specific
DCD;
(4) Result in more than a minimal increase
in the consequences of a malfunction of an
SSC important to safety previously evaluated
in the plant-specific DCD;
(5) Create a possibility for an accident of
a different type than any evaluated
previously in the plant-specific DCD;
(6) Create a possibility for a malfunction of
an SSC important to safety with a different
result than any evaluated previously in the
plant-specific DCD;
(7) Result in a design basis limit for a
fission product barrier as described in the
plant-specific DCD being exceeded or altered;
or
(8) Result in a departure from a method of
evaluation described in the plant-specific
DCD used in establishing the design bases or
in the safety analyses.
c. A proposed departure from Tier 2
affecting resolution of a severe accident issue
identified in the plant-specific DCD, requires
a license amendment if:
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(1) There is a substantial increase in the
probability of a severe accident such that a
particular severe accident previously
reviewed and determined to be not credible
could become credible; or
(2) There is a substantial increase in the
consequences to the public of a particular
severe accident previously reviewed.
d. If a departure requires a license
amendment under paragraph B.5.b or B.5.c of
this section, it is governed by 10 CFR 50.90.
e. A departure from Tier 2 information that
is made under paragraph B.5 of this section
does not require an exemption from this
appendix.
f. A party to an adjudicatory proceeding for
either the issuance, amendment, or renewal
of a license or for operation under 10 CFR
52.103(a), who believes that an applicant or
licensee who references this appendix has
not complied with paragraph VIII.B.5 of this
appendix when departing from Tier 2
information, may petition to admit into the
proceeding such a contention. In addition to
compliance with the general requirements of
10 CFR 2.309, the petition must demonstrate
that the departure does not comply with
paragraph VIII.B.5 of this appendix. Further,
the petition must demonstrate that the
change bears on an asserted noncompliance
with an ITAAC acceptance criterion in the
case of a 10 CFR 52.103 preoperational
hearing, or that the change bears directly on
the amendment request in the case of a
hearing on a license amendment. Any other
party may file a response. If, on the basis of
the petition and any response, the presiding
officer determines that a sufficient showing
has been made, the presiding officer shall
certify the matter directly to the Commission
for determination of the admissibility of the
contention. The Commission may admit such
a contention if it determines the petition
raises a genuine issue of material fact
regarding compliance with paragraph VIII.B.5
of this appendix.
6.a. An applicant who references this
appendix may not depart from Tier 2*
information, which is designated with
italicized text or brackets and an asterisk in
the generic DCD, without NRC approval. The
departure will not be considered a resolved
issue, within the meaning of Section VI of
this appendix and 10 CFR 52.63(a)(4).
b. A licensee who references this appendix
may not depart from the following Tier 2*
matters without prior NRC approval. A
request for a departure will be treated as a
request for a license amendment under 10
CFR 50.90.
(1) Maximum fuel rod average burn-up.
(2) Fuel principal design requirements.
(3) Fuel criteria evaluation process.
(4) Fire areas.
(5) Human factors engineering.
(6) Small-break loss-of-coolant accident
(LOCA) analysis methodology.
c. A licensee who references this appendix
may not, before the plant first achieves full
power following the finding required by 10
CFR 52.103(g), depart from the following Tier
2* matters except under paragraph B.6.b of
this section. After the plant first achieves full
power, the following Tier 2* matters revert
to Tier 2 status and are subject to the
departure provisions in paragraph B.5 of this
section.
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(1) Nuclear Island structural dimensions.
(2) American Society of Mechanical
Engineers Boiler & Pressure Vessel Code
(ASME Code), Section III, and Code Case284.
(3) Design Summary of Critical Sections.
(4) American Concrete Institute (ACI) 318,
ACI 349, American National Standards
Institute/American Institute of Steel
Construction (ANSI/AISC)–690, and
American Iron and Steel Institute (AISI),
‘‘Specification for the Design of Cold Formed
Steel Structural Members, Part 1 and 2,’’
1996 Edition and 2000 Supplement.
(5) Definition of critical locations and
thicknesses.
(6) Seismic qualification methods and
standards.
(7) Nuclear design of fuel and reactivity
control system, except burn-up limit.
(8) Motor-operated and power-operated
valves.
(9) Instrumentation and control system
design processes, methods, and standards.
(10) Passive residual heat removal (PRHR)
natural circulation test (first plant only).
(11) Automatic depressurization system
(ADS) and core make-up tank (CMT)
verification tests (first three plants only).
(12) Polar crane parked orientation.
(13) Piping design acceptance criteria.
(14) Containment vessel design parameters.
d. Departures from Tier 2* information that
are made under paragraph B.6 of this section
do not require an exemption from this
appendix.
C. Operational Requirements
1. Generic changes to generic TS and other
operational requirements that were
completely reviewed and approved in the
design certification rulemaking and do not
require a change to a design feature in the
generic DCD are governed by the
requirements in 10 CFR 50.109. Generic
changes that require a change to a design
feature in the generic DCD are governed by
the requirements in paragraphs A or B of this
section.
2. Generic changes to generic TS and other
operational requirements are applicable to all
applicants who reference this appendix,
except those for which the change has been
rendered technically irrelevant by action
taken under paragraphs C.3 or C.4 of this
section.
3. The Commission may require plantspecific departures on generic TS and other
operational requirements that were
completely reviewed and approved, provided
a change to a design feature in the generic
DCD is not required and special
circumstances as defined in 10 CFR 2.335 are
present. The Commission may modify or
supplement generic TS and other operational
requirements that were not completely
reviewed and approved or require additional
TS and other operational requirements on a
plant-specific basis, provided a change to a
design feature in the generic DCD is not
required.
4. An applicant who references this
appendix may request an exemption from the
generic TS or other operational requirements.
The Commission may grant such a request
only if it determines that the exemption will
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comply with the requirements of 10 CFR
50.12(a). The grant of an exemption must be
subject to litigation in the same manner as
other issues material to the license hearing.
5. A party to an adjudicatory proceeding
for either the issuance, amendment, or
renewal of a license, or for operation under
10 CFR 52.103(a), who believes that an
operational requirement approved in the
DCD or a TS derived from the generic TS
must be changed may petition to admit such
a contention into the proceeding. The
petition must comply with the general
requirements of 10 CFR 2.309 and must
demonstrate why special circumstances as
defined in 10 CFR 2.335 are present, or
demonstrate compliance with the
Commission’s regulations in effect at the time
this appendix was approved, as set forth in
section V of this appendix. Any other party
may file a response to the petition. If, on the
basis of the petition and any response, the
presiding officer determines that a sufficient
showing has been made, the presiding officer
shall certify the matter directly to the
Commission for determination of the
admissibility of the contention. All other
issues with respect to the plant-specific TS
or other operational requirements are subject
to a hearing as part of the license proceeding.
6. After issuance of a license, the generic
TS have no further effect on the plantspecific TS. Changes to the plant-specific TS
will be treated as license amendments under
10 CFR 50.90.
IX. Inspections, Tests, Analyses, and
Acceptance Criteria (ITAAC)
A.1 An applicant or licensee who
references this appendix shall perform and
demonstrate conformance with the ITAAC
before fuel load. With respect to activities
subject to an ITAAC, an applicant for a
license may proceed at its own risk with
design and procurement activities. A licensee
may also proceed at its own risk with design,
procurement, construction, and
preoperational activities, even though the
NRC may not have found that any particular
ITAAC has been satisfied.
2. The licensee who references this
appendix shall notify the NRC that the
required inspections, tests, and analyses in
the ITAAC have been successfully completed
and that the corresponding acceptance
criteria have been met.
3. If an activity is subject to an ITAAC and
the applicant or licensee who references this
appendix has not demonstrated that the
ITAAC has been satisfied, the applicant or
licensee may either take corrective actions to
successfully complete that ITAAC, request an
exemption from the ITAAC under section
VIII of this appendix and 10 CFR 52.97(b), or
petition for rulemaking to amend this
appendix by changing the requirements of
the ITAAC, under 10 CFR 2.802 and 52.97(b).
Such rulemaking changes to the ITAAC must
meet the requirements of paragraph VIII.A.1
of this appendix.
B.1 The NRC shall ensure that the required
inspections, tests, and analyses in the ITAAC
are performed. The NRC shall verify that the
inspections, tests, and analyses referenced by
the licensee have been successfully
completed and, based solely thereon, find
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4481
that the prescribed acceptance criteria have
been met. At appropriate intervals during
construction, the NRC shall publish notices
of the successful completion of ITAAC in the
Federal Register.
2. Under 10 CFR 52.99 and 52.103(g), the
Commission shall find that the acceptance
criteria in the ITAAC for the license are met
before fuel load.
3. After the Commission has made the
finding required by 10 CFR 52.103(g), the
ITAAC do not, by virtue of their inclusion
within the DCD, constitute regulatory
requirements either for licensees or for
renewal of the license; except for specific
ITAAC, which are the subject of a section
103(a) hearing, their expiration will occur
upon final Commission action in such a
proceeding. However, subsequent
modifications must comply with the Tier 1
and Tier 2 design descriptions in the plantspecific DCD unless the licensee has
complied with the applicable requirements of
10 CFR 52.97 and section VIII of this
appendix.
X. Records and Reporting
A. Records
1. The applicant for this appendix shall
maintain a copy of the generic DCD that
includes all generic changes to Tier 1, Tier
2, and the generic TS and other operational
requirements. The applicant shall maintain
the proprietary and safeguards information
referenced in the generic DCD for the period
that this appendix may be referenced, as
specified in section VII of this appendix.
2. An applicant or licensee who references
this appendix shall maintain the plantspecific DCD to accurately reflect both
generic changes to the generic DCD and
plant-specific departures made under section
VIII of this appendix throughout the period
of application and for the term of the license
(including any period of renewal).
3. An applicant or licensee who references
this appendix shall prepare and maintain
written evaluations which provide the bases
for the determinations required by section
VIII of this appendix. These evaluations must
be retained throughout the period of
application and for the term of the license
(including any period of renewal).
B. Reporting
1. An applicant or licensee who references
this appendix shall submit a report to the
NRC containing a brief description of any
plant-specific departures from the DCD,
including a summary of the evaluation of
each. This report must be filed in accordance
with the filing requirements applicable to
reports in 10 CFR 50.4.
2. An applicant or licensee who references
this appendix shall submit updates to its
DCD, which reflect the generic changes to
and plant-specific departures from the
generic DCD made under section VIII of this
appendix. These updates shall be filed under
the filing requirements applicable to final
safety analysis report updates in 10 CFR 50.4
and 50.71(e).
3. The reports and updates required by
paragraphs X.B.1 and X.B.2 must be
submitted as follows:
a. On the date that an application for a
license referencing this appendix is
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submitted, the application must include the
report and any updates to the generic DCD.
b. During the interval from the date of
application for a license to the date the
Commission makes its findings under 10 CFR
52.103(g), the report must be submitted semiannually. Updates to the plant-specific DCD
must be submitted annually and may be
submitted along with amendments to the
application.
c. After the Commission has made its
finding under 10 CFR 52.103(g), the reports
and updates to the plant-specific DCD must
be submitted, along with updates to the sitespecific portion of the final safety analysis
report for the facility, at the intervals
required by 10 CFR 50.59(d)(2) and
50.71(e)(4), respectively, or at shorter
intervals as specified in the license.
DATES:
Dated at Rockville, Maryland, this 23rd day
of January 2006.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 06–788 Filed 1–26–06; 8:45 am]
FOR FURTHER INFORMATION CONTACT:
BILLING CODE 7590–01–P
This AD becomes effective
March 3, 2006.
You may examine the AD
docket on the Internet at https://
dms.dot.gov or in person at the Docket
Management Facility, U.S. Department
of Transportation, 400 Seventh Street
SW., Nassif Building, Room PL–401,
Washington, DC.
Contact Boeing Commercial
Airplanes, Long Beach Division, 3855
Lakewood Boulevard, Long Beach,
California 90846, Attention: Data and
Service Management, Dept. C1–L5A
(D800–0024), for service information
identified in this AD.
ADDRESSES:
Brett Portwood, Aerospace Engineer,
Systems and Equipment Branch, ANM–
130L, FAA, Los Angeles Aircraft
Certification Office, 3960 Paramount
Boulevard, Lakewood, California
90712–4137; telephone (562) 627–5350;
fax (562) 627–5210.
SUPPLEMENTARY INFORMATION:
DEPARTMENT OF TRANSPORTATION
Examining the Docket
Federal Aviation Administration
You may examine the airworthiness
directive (AD) docket on the Internet at
https://dms.dot.gov or in person at the
Docket Management Facility office
between 9 a.m. and 5 p.m., Monday
through Friday, except Federal holidays.
The Docket Management Facility office
(telephone (800) 647–5227) is located on
the plaza level of the Nassif Building at
the street address stated in the
ADDRESSES section.
14 CFR Part 39
[Docket No. FAA–2005–20034; Directorate
Identifier 2004–NM–178–AD; Amendment
39–14463; AD 2006–02–11]
RIN 2120–AA64
Airworthiness Directives; McDonnell
Douglas Model DC–10–10, DC–10–10F,
DC–10–15, DC–10–30, DC–10–30F (KC–
10A and KDC–10), DC–10–40, DC–10–
40F, MD–10–10F, MD–10–30F, MD–11,
and MD–11F Airplanes
Federal Aviation
Administration (FAA), Department of
Transportation (DOT).
ACTION: Final rule.
rmajette on PROD1PC67 with RULES
AGENCY:
SUMMARY: The FAA is adopting a new
airworthiness directive (AD) for certain
McDonnell Douglas transport category
airplanes. This AD requires doing
repetitive detailed inspections for
accumulation of debris (blockage) in the
drain holes of the pitot tubes, and
cleaning the hole if any evidence of
debris is found. This AD results from
reports of blocked drain holes of the
pitot tubes. We are issuing this AD to
prevent blocked drain holes of the pitot
tubes, which could result in the
accumulation of water in the pitot-static
system and consequent failure of that
system. Failure of the pitot-static system
could result in erroneous airspeed
indications in the cockpit and
consequent loss of airspeed control.
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Discussion
The FAA issued a notice of proposed
rulemaking (NPRM) to amend 14 CFR
part 39 to include an AD that would
apply to certain McDonnell Douglas
Model DC–10–10, DC–10–10F, DC–10–
15, DC–10–30, DC–10–30F (KC–10A
and KDC–10), DC–10–40, DC–10–40F,
MD–10–10F, MD–10–30F, MD–11, and
MD–11F airplanes. That NPRM was
published in the Federal Register on
January 12, 2005 (70 FR 2062). That
NPRM proposed to require doing
repetitive detailed inspections for
accumulation of debris (blockage) of the
drain holes of the pitot tubes, and
cleaning the hole if any evidence of
debris is found.
Comments
We provided the public the
opportunity to participate in the
development of this AD. We have
considered the comments received.
Support for the NPRM
One commenter supports the NPRM.
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Requests To Extend Repetitive Interval
Three commenters request that the
650-flight-hour interval for the
repetitive detailed inspections in
paragraph (f) of the NPRM be increased.
One commenter, the airplane
manufacturer, states that it originally
recommended an interval of 650 flight
hours because that was believed to be
greater than the A-check interval in use
at that time. The commenter points out
that an A-check for some operators is
now approaching 1,000 flight hours and
recommends that interval. The
commenter also states that inspection
data, which cover as much as ten years,
show that there have been no findings
of blockage of the holes of the pitot tube
drain tube since implementation of
repetitive inspections.
A second commenter states that it has
performed the proposed repetitive
inspections on its fleet every 2,000 flight
hours since July 1999. The results of an
analysis conducted by the commenter
revealed no events of all three pitot tube
drains being blocked and only two
events where the drain holes on one of
the three pitot tubes were blocked.
Based on this service history, the
commenter does not support a repetitive
interval of less than 2,000 flight hours.
A third commenter states that an
interval shorter than an A-check would
require operators to perform the
proposed visual and forced-air
inspections during turnaround of the
airplane. The commenter’s normal
turnaround time is 2 hours. The
commenter further states that the
proposed visual and forced air
inspections take at least one hour, and
that it takes at least an additional 20
minutes for the pitot probes to cool
down. In addition, the commenter states
that its airplanes have never had
blockage through calcium build-up;
however, it has heard from other
operators that calcium blockage takes
more than a year to build up. Therefore,
the commenter concludes that it would
be costly to do the proposed inspections
during a turnaround and suggests an
interval of at least 850 flight hours,
preferably 1,000 flight hours.
We agree that the repetitive
inspection interval can be extended
somewhat. Since issuance of the NPRM,
we have analyzed further in-service data
from the airplane manufacturer and
failure rate data for a blocked pitot tube
from DC–10, MD–10, and MD–11
service history, which included 22
reported events.
The airplane manufacturer performed
an analysis using four maintenance
intervals: 650, 700, 1,000, and 1,500
flight hours. The results of the analysis
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27JAR1
Agencies
[Federal Register Volume 71, Number 18 (Friday, January 27, 2006)]
[Rules and Regulations]
[Pages 4464-4482]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 06-788]
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NUCLEAR REGULATORY COMMISSION
10 CFR Part 52
RIN 3150-AH56
AP1000 Design Certification
AGENCY: Nuclear Regulatory Commission.
ACTION: Final rule.
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SUMMARY: The Nuclear Regulatory Commission (NRC or Commission) is
amending its regulations to certify the AP1000 standard plant design.
This action is necessary so that applicants or licensees intending to
construct and operate an AP1000 design may do so by referencing this
regulation [AP1000 design certification rule (DCR)]. The applicant for
certification of the AP1000 design was Westinghouse Electric Company,
LLC (Westinghouse).
DATES: Effective Date: The effective date of this rule is February 27,
2006. The incorporation by reference of certain material specified in
this regulation is approved by the Director of the Office of the
Federal Register as of February 27, 2006.
FOR FURTHER INFORMATION CONTACT: Lauren Quinones-Navarro or Jerry N.
Wilson, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001; telephone (301) 415-2007 or
(301) 415-3145; e-mail: lnq@nrc.gov or jnw@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background.
II. Comment Analysis
A. Design Control Document
B. Design Certification Rule
III. Section-by-Section Analysis
A. Introduction (Section I)
B. Definitions (Section II)
C. Scope and Contents (Section III)
D. Additional Requirements and Restrictions (Section IV)
E. Applicable Regulations (Section V)
F. Issue Resolution (Section VI)
G. Duration of this Appendix (Section VII)
H. Processes for Changes and Departures (Section VIII)
I. Inspections, Tests, Analyses, and Acceptance Criteria
(Section IX)
J. Records and Reporting (Section X)
IV. Availability of Documents
V. Voluntary Consensus Standards
VI. Finding of No Significant Environmental Impact: Availability
VII. Paperwork Reduction Act Statement
VIII. Regulatory Analysis
IX. Regulatory Flexibility Certification
X. Backfit Analysis
XI. Congressional Review Act
I. Background
Subpart B of 10 CFR part 52 sets forth the process for obtaining
standard design certifications. On March 28, 2002 (67 FR 20845; April
26, 2002), Westinghouse tendered its application for certification of
the AP1000 standard plant design with the NRC. Westinghouse submitted
this application in accordance with subpart B and appendix O of 10 CFR
part 52. The NRC formally accepted the application as a docketed
application for design certification (Docket No. 52-006) on June 25,
2002 (67 FR 43690; June 28, 2002). The pre-application information
submitted before the NRC formally accepted the application can be found
in the NRC's Agencywide Documents Access and Management System (ADAMS)
under Docket Number PROJ0711 (Project No. 711).
The NRC staff issued a final safety evaluation report (FSER) for
the AP1000 design in September 2004 (NUREG-1793). The FSER provides the
bases for issuance of a final design approval (FDA) under appendix O to
part 52, which is a prerequisite to a design certification. The FDA for
the AP1000 design was issued on September 13, 2004, and published in
the Federal Register on September 17, 2004 (69 FR 56101). A proposed
rule to certify the AP1000 was published on April 18, 2005 (70 FR
20062).
Subsequently, Westinghouse submitted editorial and minor technical
changes and clarifications to the inspections, tests, analyses, and
acceptance criteria (ITAAC) in revision 15 to the design control
document (DCD). The NRC staff evaluated these changes in a supplement
to the FSER (NUREG-1793, Supplement No. 1). Supplement No. 1 is being
made available to the public as part of this rulemaking. The FSER and
Supplement No. 1 provide the bases for the Commission's approval of the
AP1000 standard plant design. An FDA, which incorporates the changes to
the DCD, will be issued to supersede the current FDA after issuance of
this final design certification rule.
II. Comment Analysis
The period for submitting comments on the proposed DCR, AP1000 DCD,
or draft environmental assessment (EA) expired on July 5, 2005. The NRC
received three letters from two private citizens and one letter from
the Nuclear Energy Institute (NEI). The comments addressed three
categories of information: Environmental Assessment (EA), Design
Control Document, and Design Certification Rule. The responses to the
comments on the EA are discussed in section 7.0 of the EA
(ML053630176). Responses to the comments in the second and third
categories are discussed below.
A. Design Control Document (DCD)
Comment summary. There is an over-reliance on passive systems in
the AP1000.
Response. The NRC disagrees with this comment. The NRC required
tests of the new passive safety systems to demonstrate that they will
perform as predicted in the safety analysis (see Chapter 21 of the
AP1000 FSER). The NRC also required higher availability for certain
active backup systems to compensate for any remaining uncertainties in
the performance of the passive safety systems (see Chapter 22 of the
AP1000 FSER). As a result of these reviews, the NRC concluded that the
use of passive safety systems in the AP1000 design is acceptable.
Comment Summary. The AP1000 is an unnecessary and unsafe variation
on AP600.
Response. The NRC disagrees with the comment. The NRC has
determined that the AP1000 design can be built and operated safely (see
AP1000 FSER). The
[[Page 4465]]
NRC does not determine which designs are necessary for future
deployment.
Comment Summary. The AP1000 DCD referenced in the proposed rule
does not meet the requirement of 10 CFR part 52 that the plant design
be complete except for site-specific elements and other specific
exemptions.
Response. The NRC disagrees with this comment. The requirement for
a complete scope of design [10 CFR 52.47(b)(2)(i)(A)(4)] was met by the
applicant (see discussion in section 1.2.1 of AP1000 FSER). The comment
appears to be directed at the requirement for an application to contain
a sufficient level of design information for the Commission to reach a
conclusion on all safety questions associated with the design [10 CFR
52.47(a)(2)], which was also met by the applicant (see discussion in
section 1.5 of AP1000 FSER).
Comment Summary. The appropriateness of the process used to derive
the AP1000 design from the AP600 design has not been given sufficient
attention in the NRC's review.
Response. The NRC disagrees with this comment, which appears to
apply to the NRC's review of the applicant's quality assurance (QA)
program. In its application for design certification of the AP1000
plant, Westinghouse stated that a continuous QA program spanning the
AP600 design and the AP1000 design has been used. Since March 31, 1996,
activities affecting the quality of items and services for the AP1000
project during design, procurement, fabrication, inspection, and/or
testing have been performed under the quality plan described in
``Westinghouse Energy Systems Business Unit--Quality Management
System.'' The Quality Management System (QMS) establishes design
control measures for preparing, reviewing, and approving design
documentation for safety-related structures, systems, and components
(SSCs). As documented in an NRC evaluation letter, dated February 23,
1996, from S. Black (NRC) to N.J. Liparulo, the Westinghouse QMS was
reviewed by the NRC and found to meet the requirements of 10 CFR part
50, appendix B. Subsequent revisions to the QMS have also been reviewed
by the NRC and found to be acceptable. To provide additional assurance
that Westinghouse implemented the measures described in the QMS, the
NRC staff performed a QA implementation inspection at the Westinghouse
engineering offices in Monroeville, Pennsylvania, which was documented
in NRC Inspection Report No. 99900404/03-01, dated November 4, 2003
(ADAMS Accession No. ML033090510). Therefore, the NRC concludes that
the applicant's QA program for the AP1000 design was acceptable.
Comment Summary. The decision by the NRC not to require
Westinghouse to build and test a prototype for the automatic
depressurization system (ADS) 4th stage squib valve was made under
pressure of the accelerated AP1000 schedule.
Response. The NRC disagrees that the AP1000 schedule affected the
decision not to require Westinghouse to build and test a prototype for
the ADS 4th stage squib valve. The need for a prototype test was
evaluated by the NRC staff during the AP1000 design review. Also, the
ability to design and build the ADS valve for AP1000 was discussed with
the Advisory Committee on Reactor Safeguards (ACRS) at its future plant
subcommittee meeting on July 17-18, 2003. In addition, in a letter to
ACRS dated May 18, 2004, the NRC staff stated that the ADS-4 squib
valves will be designed, constructed, and tested under Section III of
the Boiler and Pressure Vessel Code promulgated by the American Society
of Mechanical Engineers and are actuated by redundant and diverse
instrumentation and control systems. The staff also performed a
sensitivity study by increasing the failure probability and the common-
cause failure probability of the ADS-4 squib valves by an order of
magnitude. This sensitivity study indicated that the CDF increased by
only a factor of three (to 6 x 10-7/year)and was not large
enough to impact the probabilistic risk assessment (PRA) conclusions
and insights about the AP1000 design.
Comment Summary. The effect of heat of solar radiation on the
performance of the AP1000 passive containment cooling system (PCS) has
not been resolved, and geographical latitude ought to be a site
parameter, unless it can be shown that the PCS is effective at all
geographical latitudes, even when heat of solar radiation is taken into
account.
Response. The NRC disagrees with these comments. The site
parameters for the AP1000 design include minimum and maximum air
temperatures (see DCD Table 2-1). The safety maximum temperature is 115
[deg]F, which is based on historical site data and excludes peaks of
less than 2-hour durations.
The operational limits for the AP1000 containment include a
technical specification (TS) limit on the temperature of the air inside
containment, TS 3.6.5, ``Containment Air Temperature,'' of less than or
equal to 120 [deg]F. In addition, there is a limit on the water
temperature in the PCS storage tank specified in TS 3.6.6, ``Passive
Containment Cooling System--Operating,'' of greater than or equal to -
40 [deg]F and less than or equal to 120 [deg]F. If the water
temperature is at or below 50 [deg]F, or at or above 100 [deg]F, the
surveillance frequency to check the temperature is reduced from 7 days
to 24 hours. The operational limits and the site parameters provide
reasonable assurance that the AP1000 can be operated without undue risk
to the public health and safety. Conservative evaluations of the
potential effect of solar radiation on the operation and performance of
the AP1000 PCS show that the AP1000 TS provide reasonable assurance
that off-normal conditions can be detected and appropriate actions
taken to preclude operations outside the current design-base
assumptions. Based on the estimated time needed to exceed the current
operational temperature limits (10 days of uninterrupted extreme
environmental conditions), it is reasonable to conclude that the AP1000
operational limits will not be exceeded even for sites with high solar
radiation. In the unlikely event that the shield building might heat
up, a containment response analysis showed the pressure increase to be
small, 0.75 pounds per square inch (psi), and based on the current
margin of 1.2 psi (DCD Table 6.2.1.1-1), the design pressure limit of
73.7 pounds per square inch absolute (psia) would not be exceeded.
Therefore, the effect of heat of solar radiation on the performance of
the PCS has been resolved.
Comment Summary. The accelerated schedule for the AP1000 led to
cutting regulatory corners and was further accelerated by granting the
FDA before the FSER was made available to the public.
Response. The NRC disagrees with this comment. In a letter to Mr.
W.E. Cummins (Westinghouse), dated July 12, 2002, it is true that the
NRC provided an expected schedule for the AP1000 review, which was
significantly shorter than previous DCRs. However, the shorter schedule
was due to efficiencies that the NRC expected to achieve as a result of
the similarities between the previously-approved AP600 design and the
AP1000 design. Also, the AP1000 FSER was made available to the public
on September 20, 2004, the same day that the FDA was made available to
the public.
B. Design Certification Rule
It is the Commission's goal to maintain as much consistency as
possible in the rule language for all of the DCRs. Many of the
following
[[Page 4466]]
comments from NEI appear to be applicable to all of the DCRs but some
repeat comments NEI submitted previously during the 2003 proposed rule
to amend 10 CFR part 52 (68 FR 40025; July 3, 2003).
Comment Summary. NEI recommends that Section III.B of the
Supplementary Information (70 FR 20064) be revised to delete the phrase
``not just incorporate by reference.''
Response. The NRC disagrees with this request. The NRC does agree
that the plant-specific DCD should be part of the final safety analysis
report (FSAR) for a combined license (COL) application. The NRC
believes that the generic DCD should also be part of the FSAR, not just
incorporated by reference, in order to facilitate the NRC staff's
review of any departures or exemptions. However, any changes made to
existing DCRs if part 52 is revised would also be made to the AP1000
DCR.
Comment Summary. NEI recommends clarification of the review status
of ``operational requirements'' in Section III.F of the Supplementary
Information (70 FR 20067).
Response. The NRC agrees that the special backfit provisions of 10
CFR 52.63 do not apply to operational requirements in the DCD. However,
the NRC believes that the discussion in Section III.F of the
Supplementary Information section of the proposed rule document
accurately states the review status of operational requirements and
does not need to be revised.
Comment Summary. NEI recommends modification of the definition of
generic TS in section II.B of the AP1000 DCR.
Response. The NRC disagrees with this comment. The NRC stated in
the Supplementary Information (70 FR 20063) that the values in brackets
are neither part of the AP1000 DCR nor are they binding. The NRC
believes that amending the definition of generic TS is not necessary
and also wants to maintain consistent rule language for all DCRs.
Comment Summary. NEI recommends replacement of the term
``investment protection'' in section II.E of the AP1000 DCR and
elsewhere in the DCD by the term ``non-safety-related severe accident
equipment.'' In addition, NEI recommends that the AP1000 DCR and
Supplementary Information be revised so that bracketed information in
the investment protection short-term availability controls will be
treated like bracketed information in generic TS.
Response. The NRC disagrees with NEI's request to change this
terminology. Use of the term ``investment protection short-term
availability controls'' was requested by the applicant (Westinghouse
Electric Company, LLC) and was also used in the AP600 DCR. Furthermore,
the origin of investment protection short-term availability controls
comes from implementing the regulatory treatment of non-safety systems
process, which typically results in requirements to achieve higher
reliability for certain active, non-safety systems. These systems are
not limited to severe accident design features. Therefore, even if the
NRC agreed to a generic change to the term ``investment protection,''
the proposed term ``non-safety-related severe accident equipment''
would not be an acceptable replacement.
The NRC agrees that the bracketed values in the investment
protection short-term availability controls have the same status as the
bracketed values in the generic TS. As a result, the NRC refers to the
availability controls in section III.H of the Supplementary Information
in this Federal Register notice.
Comment Summary. NEI recommends that the phrase ``or licensees'' be
deleted from the rule language in section VIII.C.2 of the AP1000 DCR.
Response. The NRC agrees with this comment and section VIII.C.2 of
the AP1000 DCR has been amended as suggested by NEI. The Commission may
consider amending the DCRs to adopt the language recommended by NEI if
10 CFR part 52 is revised.
Comment Summary. NEI recommends amending the rule language in
section VIII.C.6 of the AP1000 DCR to delete the requirement that
changes to the plant-specific TS be treated as license amendments.
Response. The NRC disagrees with this request. The requirement that
changes to the plant-specific TS be treated as license amendments is
correct. If the Commission decides to clarify this issue for the DCRs
in any potential revision to 10 CFR part 52, the NRC will also clarify
the AP1000 DCR accordingly as part of that rulemaking.
Comment Summary. NEI recommends amending the rule language in
section IX.B.1 of the AP1000 DCR to restore the phrase ``based solely
thereon.''
Response. The NRC agrees to amend section IX.B.1 of the AP1000 DCR,
in order to make all of the DCRs consistent. However, the NRC notes
that inclusion of the phrase ``based solely thereon,'' does not change
the meaning of section IX.B.1. The determination of inspection, test,
analysis, and acceptance criteria (ITAAC) completion will always be
based on information that is material to the acceptance criteria.
Comment Summary. NEI recommends amending the rule language in
section X.A.1 of the AP1000 DCR to require the design certification
applicant to include all generic changes to the generic TS and other
operational requirements in the generic DCD.
Response. The NRC agrees with this comment, section X.A.1 of the
AP1000 DCR has been amended as suggested by NEI. The Commission may
consider amending the DCRs to adopt the language recommended by NEI if
10 CFR part 52 is revised.
Comment Summary. NEI recommends that sections IV.A.2 and IV.A.3 of
the AP1000 DCR be amended to be consistent with respect to inclusion of
information in the plant-specific DCD or explain the difference between
the terms ``include'' and ``physically include'' in section IV.A (70 FR
20076).
Response. The NRC agrees that use of the terms ``include'' and
``physically include'' in section IV.A of the AP1000 DCR should be
clarified. The Commission may consider amending all of the DCRs to
clarify this issue if 10 CFR part 52 is revised.
Comment Summary. NEI recommends amending the definition of Tier 2
in section II.E.1 of the AP1000 DCR to exclude the design-specific PRA
and the evaluation of SAMDAs.
Response. The NRC agrees with this comment, section II.E.1 of the
AP1000 DCR has been amended as suggested by NEI. The NRC notes that NEI
submitted the same comment during the 2003 proposed rule to amend 10
CFR part 52. The Commission may consider amending the DCRs to adopt the
language recommended by NEI if 10 CFR part 52 is revised.
Comment Summary. NEI recommends amending the rule language in
section III.E of the AP1000 DCR to use the terminology for ``site
characteristics'' consistently.
Response. The NRC agrees with this comment, section III.E of the
AP1000 DCR has been amended to be consistent with the other DCRs in the
proposed part 52 rule. The NRC notes that NEI submitted the same
comment during the 2003 proposed rule to amend 10 CFR part 52.
Comment Summary. NEI recommends clarifying the rule language in
section IV.A.2 of the AP1000 DCR regarding ``same'' information and
``generic DCD.''
Response. The NRC agrees with this comment, section IV.A.2 of the
AP1000 DCR has been amended to be consistent with the other DCRs in the
proposed part 52 rule. The NRC notes that NEI submitted the same
comment during the 2003 proposed rule to amend 10 CFR part 52.
[[Page 4467]]
Comment Summary. NEI recommends amending section VIII.B.6.a of the
AP1000 DCR to be consistent with section VI.B.5 regarding plant-
specific departures.
Response. The NRC disagrees with this request. It was determined
during the first two DCRs that departures from Tier 2* information
would not receive finality or be treated as a resolved issue within the
meaning of section VI of the DCR. The NRC notes that NEI submitted the
same comment during the 2003 proposed rule to amend 10 CFR part 52. If
the Commission decides to adopt NEI's proposed language for the DCRs in
any potential revision to 10 CFR part 52, the NRC will also amend the
AP1000 DCR accordingly as part of that rulemaking.
Comment Summary. NEI recommends amending section VIII.C.3 of the
AP1000 DCR to require the NRC to meet the backfit requirements of 10
CFR 50.109 in addition to the special circumstances in 10 CFR 2.758(b)
for plant-specific departures from operational requirements.
Response. The NRC disagrees with this request. In the first two
DCRs, the Commission decided on different standards for changes made
under section VIII.C of the DCRs (see the discussion at 62 FR 25800;
May 12, 1997). The NRC notes that NEI submitted the same comment during
the 2003 proposed rule to amend 10 CFR part 52. If the Commission
decides to adopt NEI's proposed language for the DCRs in any potential
revision to 10 CFR part 52, the NRC will also amend the AP1000 DCR
accordingly as part of that rulemaking.
Comment Summary. NEI recommends amending section VIII.C.4 of the
AP1000 DCR to revise the standards for making changes to operational
requirements.
Response. The NRC disagrees with this request. In the first two
DCRs, the Commission decided on different standards for changes made
under section VIII.C of the DCRs (see the discussion at 62 FR 25800;
May 12, 1997). In addition, the Commission determined that exemptions
from operational requirements would not receive finality or be treated
as a resolved issue within the meaning of section VI of the DCR. The
NRC notes that NEI submitted the same comment during the 2003 proposed
rule to amend 10 CFR part 52. If the Commission decides to adopt NEI's
proposed language for the DCRs in any potential revision to 10 CFR part
52, the NRC will also amend the AP1000 DCR accordingly as part of that
rulemaking.
Comment Summary. NEI recommends amending section IX.B.1 of the
AP1000 DCR to specify the type of action to be performed by the NRC
staff regarding ITAAC.
Response. The NRC disagrees with this request. Individual DCRs
should not address the scope of the NRC staff's activities with respect
to ITAAC verification. This is a generic matter that, if it is to be
addressed in a rulemaking, is more appropriate for inclusion in subpart
C of part 52 dealing generally with combined licenses.
The NRC notes that NEI submitted the same comment during the 2003
proposed rule to amend 10 CFR part 52. If the Commission decides to
adopt NEI's proposed language for the DCRs in any potential revision to
10 CFR part 52, the NRC will also amend the AP1000 DCR accordingly as
part of that rulemaking.
Comment Summary. NEI recommends amending section IX.B.3 of the
AP1000 DCR to clarify the rule language.
Response. The NRC disagrees with this editorial request and has
decided to maintain the original rule language for this provision. The
NRC notes that NEI submitted the same comment during the 2003 proposed
rule to amend 10 CFR part 52. If the Commission decides to adopt NEI's
proposed language for the DCRs in any potential revision to 10 CFR part
52, the NRC will also amend the AP1000 DCR accordingly as part of that
rulemaking.
Comment Summary. NEI recommends amending sections X.B.1 and X.B.3
of the AP1000 DCR to clarify the rule language regarding DCDs.
Response. The NRC agrees with this comment and section X.B of the
AP1000 DCR has been amended to clarify the language. The NRC notes that
NEI submitted the same comment during the 2003 proposed rule to amend
10 CFR part 52. The Commission may consider amending the existing DCRs
in any potential revision to 10 CFR part 52.
III. Section-by-Section Analysis
The following discussion sets forth the purpose and key aspects of
each section and paragraph of the final AP1000 DCR. All section and
paragraph references are to the provisions in appendix D to 10 CFR part
52. The final DCR for the AP1000 standard plant design is nearly
identical to the AP600 DCR, which the NRC previously codified in 10 CFR
part 52, appendix C (Design Certification Rule for the AP600 Design, 64
FR 72015, December 23, 1999). Many of the procedural issues and their
resolutions for the AP600 DCR, as well as the initial two DCRs for the
ABWR and ABB-CE System 80+, (e.g., the two-tier structure, Tier 2*, the
scope of issue resolution) were developed after extensive public
discussions with stakeholders, including Westinghouse. Also,
Westinghouse requested that policy resolutions for the AP600 design
review be applied to the AP1000. Accordingly, the NRC has modeled the
AP1000 DCR on the existing DCRs, with certain departures where
necessary, to account for differences in the AP1000 design
documentation, design features, and environmental assessment (including
severe accident mitigation design alternatives (SAMDAs).
A. Introduction
The purpose of section I of appendix D to 10 CFR part 52 (this
appendix) is to identify the standard plant design that is approved by
this DCR, and the applicant for certification of the standard design.
Identification of the design certification applicant is necessary to
implement this appendix, for two reasons. First, the implementation of
10 CFR 52.63(c) depends on whether an applicant for a COL contracts
with the design certification applicant to provide the generic DCD and
supporting design information. If the COL applicant does not use the
design certification applicant to provide this information, then the
COL applicant must meet the requirements in 10 CFR 52.63(c). Also,
paragraph X.A.1 of this appendix requires the design certification
applicant to maintain the generic DCD throughout the time this appendix
may be referenced.
B. Definitions
During development of the first two DCRs, the Commission decided
that there would be both generic (master) DCDs maintained by the NRC
and the design certification applicant, as well as individual plant-
specific DCDs maintained by each applicant and licensee that reference
this appendix. This distinction is necessary in order to specify the
relevant plant-specific requirements to applicants and licensees
referencing the appendix. The master DCDs would include generic changes
to the version of the DCD approved in this design certification
rulemaking. These changes would occur as the result of generic
rulemaking by the Commission, under the change criteria in section VIII
of this appendix. The Commission also requires each applicant and
licensee referencing this appendix to submit and maintain a plant-
specific DCD.
This plant-specific DCD would contain (not just incorporate by
reference) the information in the generic DCD. The plant-specific DCD
would be
[[Page 4468]]
updated as necessary to reflect the generic changes to the DCD that the
Commission may adopt through rulemaking, plant-specific departures from
the generic DCD that the Commission imposed on the licensee by order,
and any plant-specific departures that the licensee chooses to make in
accordance with the relevant processes in section VIII of this
appendix. Thus, the plant-specific DCD would function like an updated
FSAR because it would provide the most complete and accurate
information on a plant's licensing basis for that part of the plant
within the scope of this appendix. Therefore, this appendix would
define both a generic DCD and a plant-specific DCD.
Also, the Commission decided to treat the TS in section 16.1 of the
generic DCD as a special category of information and to designate them
as generic TS in order to facilitate the special treatment of this
information under this appendix. A COL applicant must submit plant-
specific TS that consist of the generic TS, which may be modified under
paragraph VIII.C of this appendix, and the remaining plant-specific
information needed to complete the TS. The FSAR that is required by 10
CFR 52.79(b) will consist of the plant-specific DCD, the site-specific
portion of the FSAR, and the plant-specific TS.
The terms Tier 1, Tier 2, Tier 2*, and COL action items (license
information) are defined in this appendix because these concepts were
not envisioned when 10 CFR part 52 was developed. The design
certification applicants and the NRC used these terms in implementing
the two-tiered rule structure that was proposed by representatives of
the nuclear industry after issuance of 10 CFR part 52. Therefore,
appropriate definitions for these additional terms are included in this
appendix. The nuclear industry representatives requested a two-tiered
structure for the DCRs to achieve issue preclusion for a greater amount
of information than was originally planned for the DCRs, while
retaining flexibility for design implementation. The Commission
approved the use of a two-tiered rule structure in its staff
requirements memorandum (SRM), dated February 14, 1991, on SECY-90-377,
``Requirements for Design Certification Under 10 CFR Part 52,'' dated
November 8, 1990. This document and others are available in the
Regulatory History of Design Certification (see section IV,
Availability of Documents, of this Statement of Consideration (SOC)).
The Tier 1 portion of the design-related information contained in
the DCD is certified by this appendix and, therefore, is subject to the
special backfit provisions in paragraph VIII.A of this appendix. An
applicant who references this appendix is required to incorporate by
reference and comply with Tier 1, under paragraphs III.B and IV.A.1 of
this appendix. This information consists of an introduction to Tier 1,
the system based and non-system based design descriptions and
corresponding ITAAC, significant interface requirements, and
significant site parameters for the design. The design descriptions,
interface requirements, and site parameters in Tier 1 were derived from
Tier 2, but may be more general than the Tier 2 information. The NRC
staff's evaluation of the Tier 1 information is provided in section
14.3 of the FSER. Changes to or departures from the Tier 1 information
must comply with section VIII.A of this appendix.
The Tier 1 design descriptions serve as commitments for the
lifetime of a facility referencing the design certification. The ITAAC
verifies that the as-built facility conforms with the approved design
and applicable regulations. Under 10 CFR 52.103(g), the Commission must
find that the acceptance criteria in the ITAAC are met before
authorizing operation. After the Commission has made the finding
required by 10 CFR 52.103(g), the ITAAC do not constitute regulatory
requirements for licensees or for renewal of the COL. However,
subsequent modifications to the facility must comply with the design
descriptions in the plant-specific DCD unless changes are made under
the change process in section VIII of this appendix. The Tier 1
interface requirements are the most significant of the interface
requirements for systems that are wholly or partially outside the scope
of the standard design. Tier 1 interface requirements were submitted in
response to 10 CFR 52.47(a)(1)(vii) and must be met by the site-
specific design features of a facility that references this appendix.
An application that references this appendix must demonstrate that the
site parameters (both Tier 1 and Tier 2) are met at the proposed site
(refer to paragraph III.D of this SOC).
Tier 2 is the portion of the design-related information contained
in the DCD that is approved by this appendix but not certified. Tier 2
information is subject to the backfit provisions in paragraph VIII.B of
this appendix. Tier 2 includes the information required by 10 CFR 52.47
(with the exception of generic TS, conceptual design information, and
the evaluation of SAMDAs) and the supporting information on
inspections, tests, and analyses that will be performed to demonstrate
that the acceptance criteria in the ITAAC have been met. As with Tier
1, paragraphs III.B and IV.A.1 of this appendix require an applicant
who references this appendix to incorporate Tier 2 by reference and to
comply with Tier 2, except for the COL action items, including the
investment protection short-term availability controls in section 16.3
of the generic DCD. The definition of Tier 2 makes clear that Tier 2
information has been determined by the Commission, by virtue of its
inclusion in this appendix and its designation as Tier 2 information,
to be an approved sufficient method for meeting Tier 1 requirements.
However, there may be other acceptable ways of complying with Tier 1.
The appropriate criteria for departing from Tier 2 information are
specified in paragraph VIII.B of this appendix. Departures from Tier 2
do not negate the requirement in paragraph III.B to reference Tier 2.
A definition of ``combined license action items'' (COL
information), which is part of the Tier 2 information, has been added
to clarify that COL applicants who reference this appendix are required
to address COL action items in their license application. However, the
COL action items are not the only acceptable set of information. An
applicant may depart from or omit COL action items, provided that the
departure or omission is identified and justified in the FSAR. After
issuance of a construction permit or COL, these items are not
requirements for the licensee unless they are restated in the FSAR. For
additional discussion, see Section D.
The investment protection short-term availability controls, which
are set forth in section 16.3 of the generic DCD, were added to the
information that is part of Tier 2 to make it clear that the
availability controls are not operational requirements for the purposes
of paragraph VIII.C of this appendix. Rather, the availability controls
are associated with specific design features. The availability controls
may be changed if the associated design feature is changed under
paragraph VIII.B of this appendix. For additional discussion, see
section III.C of this SOC.
Certain Tier 2 information has been designated in the generic DCD
with brackets and italicized text as ``Tier 2*'' information and, as
discussed in greater detail in the section-by-section explanation for
section H, a plant-specific departure from Tier 2* information requires
prior NRC approval. However, the Tier 2* designation expires for some
of this
[[Page 4469]]
information when the facility first achieves full power after the
finding required by 10 CFR 52.103(g). The process for changing Tier 2*
information and the time at which its status as Tier 2* expires is set
forth in paragraph VIII.B.6 of this appendix. Some Tier 2* requirements
concerning special pre-operational tests are designated to be performed
only for the first plant or first three plants referencing the AP1000
DCR. The Tier 2* designation for these selected tests will expire after
the first plant or first three plants complete the specified tests.
However, a COL action item requires that subsequent plants also perform
the tests or justify that the results of the first-plant-only or first-
three-plants-only tests are applicable to the subsequent plant.
In an earlier rulemaking (64 FR 53582; October 4, 1999), the
Commission revised 10 CFR 50.59 to incorporate new thresholds for
permitting changes to a plant as described in the FSAR without NRC
approval. For consistency and clarity, the Commission proposes to use
these new thresholds in the proposed AP1000 DCR. Inasmuch as Sec.
50.59 is the primary change mechanism for operating nuclear plants, the
Commission believes that future plants referencing the AP1000 DCR
should utilize thresholds as close to Sec. 50.59 as is practicable and
appropriate. Because of some differences in how the change control
requirements are structured in the DCRs, certain definitions contained
in Sec. 50.59 are not applicable to 10 CFR part 52 and are not being
included in this rule. One definition that the Commission is including
is the definition from the new Sec. 50.59 for a ``departure from a
method of evaluation,'' (paragraph II.G), which is appropriate to
include in this rulemaking so that the eight criteria in paragraph
VIII.B.5.b of the final rule will be implemented as intended.
C. Scope and Contents
The purpose of section III of this appendix is to describe and
define the scope and contents of this design certification and to set
forth how documentation discrepancies or inconsistencies are to be
resolved. Paragraph III.A is the required statement of the Office of
the Federal Register (OFR) for approval of the incorporation by
reference of Tier 1, Tier 2, and the generic TS into this appendix.
Paragraph III.B requires COL applicants and licensees to comply with
the requirements of this appendix. The legal effect of incorporation by
reference is that the incorporated material has the same legal status
as if it were published in the Code of Federal Regulations. This
material, like any other properly-issued regulation, has the force and
effect of law. Tier 1 and Tier 2 information, as well as the generic
TS, have been combined into a single document called the generic DCD,
in order to effectively control this information and facilitate its
incorporation by reference into the rule. The generic DCD was prepared
to meet the requirements of the OFR for incorporation by reference (1
CFR part 51). One of the requirements of the OFR for incorporation by
reference is that the design certification applicant must make the
generic DCD available upon request after the final rule becomes
effective. Therefore, paragraph III.A of this appendix identifies a
Westinghouse representative to be contacted in order to obtain a copy
of the generic DCD.
Paragraphs III.A and III.B also identify the investment protection
short-term availability controls in section 16.3 of the generic DCD as
part of the Tier 2 information. During its review of the AP1000 design,
the NRC determined that residual uncertainties associated with passive
safety system performance increased the importance of non-safety-
related active systems in providing defense-in-depth functions that
back-up the passive systems. As a result, Westinghouse developed
administrative controls to provide a high level of confidence that
active systems having a significant safety role are available when
challenged. Westinghouse named these additional controls ``investment
protection short-term availability controls.'' The Commission included
this characterization in section III of this appendix to ensure that
these availability controls are binding on applicants and licensees
that reference this appendix and will be enforceable by the NRC. The
NRC's evaluation of the availability controls is provided in Chapter 22
of the FSER.
The generic DCD (master copy) for this design certification will be
electronically accessible in NRC's Agencywide Documents Access and
Management System (ADAMS) and at the OFR. Copies of the generic DCD
will also be available at the NRC's Public Document Room (PDR).
Questions concerning the accuracy of information in an application that
references this appendix will be resolved by checking the master copy
of the generic DCD in ADAMS. If a generic change (rulemaking) is made
to the DCD by the change process provided in section VIII of this
appendix, then at the completion of the rulemaking the NRC would
request approval of the Director, OFR, for the changed incorporation by
reference and change its copies of the generic DCD and notify the OFR
and the design certification applicant to change their copies. The
Commission is requiring that the design certification applicant
maintain an up-to-date copy under paragraph X.A.1 of this appendix
because it is likely that most applicants intending to reference the
standard design will obtain the generic DCD from the design
certification applicant. Plant-specific changes to and departures from
the generic DCD will be maintained by the applicant or licensee that
references this appendix in a plant-specific DCD under paragraph X.A.2
of this appendix.
In addition to requiring compliance with this appendix, paragraph
III.B clarifies that the conceptual design information and
Westinghouse's evaluation of SAMDAs are not considered to be part of
this appendix. The conceptual design information is for those portions
of the plant that are outside the scope of the standard design and are
contained in Tier 2 information. As provided by 10 CFR 52.47(a)(1)(ix),
these conceptual designs are not part of this appendix and, therefore,
are not applicable to an application that references this appendix.
Therefore, the applicant is not required to conform with the conceptual
design information that was provided by the design certification
applicant. The conceptual design information, which consists of site-
specific design features, was required to facilitate the design
certification review. Conceptual design information is neither Tier 1
nor Tier 2. Section 1.8 of Tier 2 identifies the location of the
conceptual design information. Westinghouse's evaluation of various
design alternatives to prevent and mitigate severe accidents does not
constitute design requirements. The Commission's assessment of this
information is discussed in Section VII of this SOC on environmental
impacts.
Paragraphs III.C and III.D set forth the way potential conflicts
are to be resolved. Paragraph III.C establishes the Tier 1 description
in the DCD as controlling in the event of an inconsistency between the
Tier 1 and Tier 2 information in the DCD. Paragraph III.D establishes
the generic DCD as the controlling document in the event of an
inconsistency between the DCD and the FSER for the certified standard
design.
Paragraph III.E makes it clear that design activities that are
wholly outside the scope of this design certification may be performed
using site-specific design parameters, provided the design activities
do not affect Tier 1 or Tier 2, or conflict with the interface
requirements in the DCD. This provision applies to site-specific
portions of the
[[Page 4470]]
plant, such as the administration building. Because this statement is
not a definition, this provision has been located in Section III of
this appendix.
D. Additional Requirements and Restrictions
Section IV of this appendix sets forth additional requirements and
restrictions imposed upon an applicant who references this appendix.
Paragraph IV.A sets forth the information requirements for these
applicants. This paragraph distinguishes between information and/or
documents which must actually be included in the application or the
DCD, versus those which may be incorporated by reference (i.e.,
referenced in the application as if the information or documents were
included in the application). Any incorporation by reference in the
application should be clear and should specify the title, date,
edition, or version of a document, the page number(s), and table(s)
containing the relevant information to be incorporated.
Paragraph IV.A.1 requires an applicant who references this appendix
to incorporate by reference this appendix in its application. The legal
effect of such an incorporation by reference is that this appendix is
legally binding on the applicant or licensee. Paragraph IV.A.2.a
requires that a plant-specific DCD be included in the initial
application to ensure that the applicant commits to complying with the
DCD. This paragraph also requires the plant-specific DCD to use the
same format as the generic DCD and reflect the applicant's proposed
departures and exemptions from the generic DCD as of the time of
submission of the application. The Commission expects that the plant-
specific DCD will become the plant's FSAR, by including information,
i.e., site-specific information, for the portions of the plant outside
the scope of the referenced design, including related ITAAC, and other
matters required to be included in an FSAR by 10 CFR 50.34 and 52.79.
Integration of the plant-specific DCD and remaining site-specific
information into the plant's FSAR, will result in an application that
is easier to use and should minimize ``duplicate documentation'' and
the attendant possibility for confusion. Paragraph IV.A.2.a also
requires that the initial application include the reports on departures
and exemptions as of the time of submission of the application.
Paragraph IV.A.2.b requires that an application referencing this
appendix include the reports required by paragraph X.B of this appendix
for exemptions and departures proposed by the applicant as of the date
of submission of its application. Paragraph IV.A.2.c requires
submission of plant-specific TS for the plant that consists of the
generic TS from section 16.1 of the DCD, with any changes made under
paragraph VIII.C of this appendix, and the TS for the site-specific
portions of the plant that are either partially or wholly outside the
scope of this design certification. The applicant must also provide the
plant-specific information designated in the generic TS, such as
bracketed values.
Paragraph IV.A.2.d requires the applicant referencing this appendix
to provide information demonstrating that the proposed site falls
within the site parameters for this appendix and that the plant-
specific design complies with the interface requirements, as required
by 10 CFR 52.79(b). If the proposed site has a characteristic that
exceeds one or more of the site parameters in the DCD, then the
proposed site is unacceptable for this design unless the applicant
seeks an exemption under section VIII of this appendix and provides
adequate justification for locating the certified design on the
proposed site. Paragraph IV.A.2.e requires submission of information
addressing COL action items, identified in the generic DCD as COL
information in the application. The COL information identifies matters
that need to be addressed by an applicant who references this appendix,
as required by subpart C of 10 CFR part 52. An applicant may depart
from or omit these items, provided that the departure or omission is
identified and justified in its application (FSAR). Paragraph IV.A.2.f
requires that the application include the information specified by 10
CFR 52.47(a) that is not within the scope of this rule, such as generic
issues that must be addressed, in whole or in part, by an applicant
that references this rule. Paragraph IV.A.3 requires the applicant to
physically include, not simply reference, the proprietary and
safeguards information referenced in the DCD, or its equivalent, to
ensure that the applicant has actual notice of these requirements.
Paragraph IV.B reserves to the Commission the right to determine in
what manner this DCR may be referenced by an applicant for a
construction permit or operating license under 10 CFR part 50. This
determination may occur in the context of a subsequent rulemaking
modifying 10 CFR part 52 or this design certification rule, or on a
case-by-case basis in the context of a specific application for a 10
CFR part 50 construction permit or operating license. This provision is
necessary because the previous DCRs were not implemented in the manner
that was originally envisioned at the time that 10 CFR part 52 was
promulgated. The Commission's concern is with the way ITAAC were
developed and the lack of experience with design certifications in
license proceedings. Therefore, it is appropriate that the Commission
retain some discretion regarding the way this appendix could be
referenced in a 10 CFR part 50 licensing proceeding.
E. Applicable Regulations
The purpose of section V of this appendix is to specify the
regulations that were applicable and in effect at the time this design
certification was approved. These regulations consist of the
technically relevant regulations identified in paragraph V.A, except
for the regulations in paragraph V.B that are not applicable to this
certified design.
Paragraph V.A identifies the regulations in 10 CFR parts 20, 50,
73, and 100 that are applicable to the AP1000 design. After the NRC
staff issued its FSER for the AP1000 design (NUREG-1793, September
2004), the Commission amended several existing regulations and adopted
new regulations. The Commission reviewed these regulations to determine
if they are applicable to this design and, if so, to determine if the
design meets these regulations. The Commission finds that none of these
new regulations are applicable to the AP1000 design. The Commission's
determination of the applicable regulations was made as of the date
specified in paragraph V.A of this appendix, which is the date that
this appendix was approved by the Commission and signed by the
Secretary of the Commission.
In paragraph V.B of this appendix, the Commission identifies the
regulations that do not apply to the AP1000 design. The Commission has
determined that the AP1000 design should be exempt from portions of 10
CFR 50.34, 50.62, and Appendix A to part 50, as described in the FSER
(NUREG-1793) and summarized below:
(1) Paragraph (f)(2)(iv) of 10 CFR 50.34--Plant Safety Parameter
Display Console. Under 10 CFR 52.47(a)(ii), an applicant for design
certification must demonstrate compliance with any technically relevant
Three Mile Island (TMI) requirements in 10 CFR 50.34(f). The
requirement in 10 CFR 50.34(f)(2)(iv) states that an application must
provide a plant safety parameter display console that will display a
minimum set of parameters defining the safety status of the plant, be
capable of displaying a full range of important plant parameters and
data trends on
[[Page 4471]]
demand, and be capable of indicating when process limits are being
approached or exceeded. Westinghouse addresses this requirement, in
section 18.8.2 of the DCD, with an integrated design rather than a
stand-alone, add-on system, as is used at most current operating
plants. Specifically, Westinghouse integrated the safety parameter
display system (SPDS) requirements into the design requirements for the
alarm and display systems. The NRC staff has determined that the
function of a separate SPDS may be integrated into the overall control
room design. Therefore, the Commission has determined that the special
circumstances for allowing an exemption as described in 10 CFR
50.12(a)(2)(ii) exist because the requirement for an SPDS console need
not be applied in this particular circumstance to achieve the
underlying purpose because Westinghouse has provided an acceptable
alternative that accomplishes the intent of the regulation. On this
basis, the Commission concludes that an exemption from the requirements
of 10 CFR 50.34(f)(2)(iv) is authorized by law, will not present an
undue risk to public health and safety, and is consistent with the
common defense and security.
(2) Paragraph (c)(1) of 10 CFR 50.62--Auxiliary Feedwater System.
The AP1000 design relies on the passive residual heat removal system
(PRHR) in lieu of an auxiliary or emergency feedwater system as its
safety-related method of removing decay heat. Westinghouse requested an
exemption from a portion of 10 CFR 50.62(c)(1), which requires
auxiliary or emergency feedwater as an alternate system for decay heat
removal during an anticipated transient without scram (ATWS) event. The
NRC staff concluded that Westinghouse met the intent of the rule by
relying on the PRHR system to remove the decay heat and, thereby, met
the underlying purpose of the rule. Therefore, the Commission has
determined that the special circumstances for allowing an exemption
described in 10 CFR 50.12(a)(2)(ii) exist because the requirement for
an auxiliary or emergency feedwater system is not necessary to achieve
the underlying purpose of 10 CFR 50.62(c)(1). This is because
Westinghouse has adopted acceptable alternatives that accomplish the
intent of this regulation, and the exemption is authorized by law, will
not present an undue risk to public health and safety, and is
consistent with the common defense and security.
(3) Appendix A to 10 CFR part 50, GDC 17--Second Offsite Power
Supply Circuit. Westinghouse requested a partial exemption from the
requirement in General Design Criteria (GDC) 17 for a second offsite
power supply circuit. The AP1000 plant design supports an exemption to
this requirement by providing safety-related ``passive'' systems. These
passive safety-related systems only require electric power for valves
and the related instrumentation. The onsite Class 1E batteries and
associated dc and ac distribution systems can provide the power for
these valves and instrumentation. In addition, if no offsite power is
available, it is expected that the non-safety-related onsite diesel
generators would be available for important plant functions. However,
this non-safety-related ac power is not relied on to maintain core
cooling or containment integrity. Therefore, the Commission has
determined that the special circumstances for allowing an exemption as
described in 10 CFR 50.12(a)(2)(ii) exist because the requirement need
not be applied in this particular circumstance to achieve the
underlying purpose of having two offsite power sources. This is because
the AP1000 design includes an acceptable alternative approach to
accomplish safety functions that do not rely on power from the offsite
system and, therefore, accomplishes the intent of the regulation. On
this basis, the Commission concludes that a partial exemption from the
requirements of GDC 17 is authorized by law, will not present an undue
risk to public health and safety, and is consistent with the common
defense and security.
F. Issue Resolution
The purpose of section VI of this appendix is to identify the scope
of issues that are resolved by the Commission in this rulemaking and;
therefore, are ``matters resolved'' within the meaning and intent of 10
CFR 52.63(a)(4). The section is divided into five parts: (A) The
Commission's safety findings in adopting this appendix, (B) the scope
and nature of issues which are resolved by this rulemaking, (C) issues
which are not resolved by this rulemaking, (D) the backfit restrictions
applicable to the Commission with respect to this appendix, and (E) the
availability of secondary references.
Paragraph VI.A describes the nature of the Commission's findings in
general terms and makes the finding required by 10 CFR 52.54 for the
Commission's approval of this DCR. Furthermore, paragraph VI.A
explicitly states the Commission's determination that this design
provides adequate protection of the public health and safety.
Paragraph VI.B sets forth the scope of issues that may not be
challenged as a matter of right in subsequent proceedings. The
introductory phrase of paragraph VI.B clarifies that issue resolution
as described in the remainder of the paragraph extends to the
delineated NRC proceedings referencing this appendix. The remainder of
paragraph VI.B describes the categories of information for which there
is issue resolution. Specifically, paragraph VI.B.1 provides that all
nuclear safety issues arising from the Atomic Energy Act of 1954, as
amended, that are associated with the information in the NRC staff's
FSER (NUREG-1793) and Supplement No. 1, the Tier 1 and Tier 2
information (including the availability controls in Section 16.3 of the
generic DCD), and the rulemaking record for this appendix are resolved
within the meaning of 10 CFR 52.63(a)(4). These issues include the
information referenced in the DCD that are requirements (i.e.,
``secondary references''), as well as all issues arising from
proprietary and safeguards information which are intended to be
requirements.
Paragraph VI.B.2 provides for issue preclusion of proprietary and
safeguards information. Paragraphs VI.B.3, VI.B.4, VI.B.5, and VI.B.6
clarify that approved changes to and departures from the DCD which are
accomplished in compliance with the relevant procedures and criteria in
section VIII of this appendix continue to be matters resolved in
connection with this rulemaking. Paragraphs VI.B.4, VI.B.5, and VI.B.6,
which characterize the scope of issue resolution in three situations,
use the phrase ``but only for that plant.'' Paragraph VI.B.4 describes
how issues associated with a design certification rule are resolved
when an exemption has been granted for a plant referencing the design
certification rule. Paragraph VI.B.5 describes how issues are resolved
when a plant referencing the design certification rule obtains a
license amendment for a departure from Tier 2 information.
Paragraph VI.B.6 describes how issues are resolved when the
applicant or licensee departs from the Tier 2 information on the basis
of paragraph VIII.B.5, which will waive the requirement for NRC
approval. In all three situations, after a matter (e.g., an exemption
in the case of paragraph VI.B.4) is addressed for a specific plant
referencing a design certification rule, the adequacy of that matter
for that plant will not ordinarily be subject to challenge in any
subsequent proceeding or action for that plant (e.g., an enforcement
action) listed in the
[[Page 4472]]
introductory portion of paragraph IV.B. There will not, by contrast, be
any issue resolution on that subject matter for any other plant.
Paragraph VI.B.7 provides that, for those plants located on sites
whose site parameters do not exceed those assumed in Westinghouse's
evaluation of SAMDAs, all issues with respect to SAMDAs arising under
the National Environmental Policy Act of 1969, as amended (NEPA),
associated with the information in the environmental assessment for
this design and the information regarding SAMDAs in Appendix 1B of the
generic DCD are also resolved within the meaning and intent of 10 CFR
52.63(a)(4). If an exemption from a site parameter is granted, the
exemption applicant has the initial burden of demonstrating that the
original SAMDA analysis still applies to the actual site parameters
but; if the exemption is approved, requests for litigation at the COL
stage must meet the requirements of 10 CFR 2.309 and present sufficient
information to create a genuine controversy in order to obtain a
hearing on the site parameter exemption.
Paragraph VI.C reserves the right of the Commission to impose
operational requirements on applicants that reference this appendix.
This provision reflects the fact that operational requirements,
including generic TS in section 16.1 of the DCD, were not completely or
comprehensively reviewed at the design certification stage. Therefore,
the special backfit provisions of 10 CFR 52.63 do not apply to
operational requirements. However, all design changes will be
controlled by the appropriate provision in section VIII of this
appendix. Although the information in the DCD that is related to
operational requirements is necessary to support the NRC's safety
review of this design, the review of this information was not
sufficient to conclude that the operational requirements are fully
resolved and ready to be assigned finality under 10 CFR 52.63. As a
result, if the NRC wanted to change a temperature limit and that
operational change required a consequential change to a design feature,
then the temperature limit backfit would be controlled by paragraph
VIII.A or VIII.B of this appendix. However, changes to other
operational requirements, such as inservice testing and inservice
inspection programs, post-fuel load verification activities, and
requirements governing shutdown risk that do not require a design
change would not be restricted by 10 CFR 52.63 (see paragraph VIII.C of
this appendix).
Paragraph VI.C allows the NRC to impose future operational
requirements (distinct from design matters) on applicants who reference
this design certification. Also, license conditions for portions of the
plant within the scope of this design certification, e.g., start-up and
power ascension testing, are not restricted by 10 CFR 52.63. The
requirement to perform these testing programs is contained in Tier 1
information. However, ITAAC cannot be specified for these subjects
because the matters to be addressed in these license conditions cannot
be verified prior to fuel load and operation, when the ITAAC are
satisfied. Therefore, another regulatory vehicle is necessary to ensure
that licensees comply with the matters contained in the license
conditions. License conditions for these areas cannot be developed now
because this requires the type of detailed design information that will
be developed during a combined license review. In the absence of
detailed design information to evaluate the need for and develop
specific post-fuel load verifications for these matters, the Commission
is reserving the right to impose license conditions by rule for post-
fuel load verification activities for portions of the plant within the
scope of this design certification.
Paragraph VI.D reiterates the restrictions (contained in section
VIII of this appendix) placed upon the Commission when ordering generic
or plant-specific modifications, changes or additions to structures,
systems, or components, design features, design criteria, and ITAAC
(paragraph VI.D.3 would address ITAAC) within the scope of the
certified design.
Paragraph VI.E provides the procedure for an interested member of
the public to obtain access to proprietary or safeguards information
for the AP1000 design, in order to request and participate in
proceedings identified in paragraph VI.B of this appendix, viz.,
proceedings involving licenses and applications which reference this
appendix. Paragraph VI.E specifies that access must first be sought
from the design certification applicant. If Westinghouse refuses to
provide the information, the person seeking access shall request access
from the Commission or the presiding officer, as applicable. Access to
the proprietary or safeguards information may be ordered by the
Commission, but must be subject to an appropriate non-disclosure
agreement.
G. Duration of This Appendix
The purpose of section VII of this appendix is in part, to specify
the period during which this design certification may be referenced by
an applicant for a COL, under 10 CFR 52.55. This section also states
that the design certification remains valid for an applicant or
licensee that references the design certification until the application
is withdrawn or the license expires. Therefore, if an application
references this design certification during the 15-year period, then
the design certification will be effective until the application is
withdrawn or the license issued on that application expires. Also, the
design certification will be effective for the referencing licensee if
the license is renewed. The Commission intends for this appendix to
remain valid for the life of the plant that references the design
certification to achieve the benefits of standardization and licensing
stability. This means that changes to, or plant-specific departures
from, information in the plant-specific DCD must be made under the
change processes in section VIII of this appendix for the life of the
plant.
H. Processes for Changes and Departures
The purpose of section VIII of this appendix is to set forth the
processes for generic changes to or plant-specific departures
(including exemptions) from the DCD. The Commission adopted this
restrictive change process