Maine Yankee Atomic Power Company; Maine Yankee Atomic Power Plant Issuance of Environmental Assessment and Finding of No Significant Impact Regarding an Exemption Request, 42556-42558 [2013-16988]
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Federal Register / Vol. 78, No. 136 / Tuesday, July 16, 2013 / Notices
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Docket No. NRC–2013–0131. Mail
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about the information collection
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Dated at Rockville, Maryland, this 10th day
of July, 2013.
For the Nuclear Regulatory Commission.
Tremaine Donnell,
NRC Clearance Officer, Office of Information
Services.
[FR Doc. 2013–16989 Filed 7–15–13; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–309 and 72–30; NRC–2013–
0156]
Maine Yankee Atomic Power
Company; Maine Yankee Atomic
Power Plant Issuance of
Environmental Assessment and
Finding of No Significant Impact
Regarding an Exemption Request
Nuclear Regulatory
Commission.
ACTION: Issuance of environmental
assessment and finding of no significant
impact.
AGENCY:
John
Goshen, Project Manager, Division of
Spent Fuel Storage and Transportation,
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555.
Telephone: 301–287–9250, Fax number:
301–287–9341; Email:
John.Goshen@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
emcdonald on DSK67QTVN1PROD with NOTICES
1.0
Introduction
On November 23, 2011, the U.S.
Nuclear Regulatory Commission (NRC)
issued a final rule amending certain
emergency planning (EP) requirements
in the regulations that govern domestic
licensing of production and utilization
facilities (76 FR 72560; November 23,
2011) (EP Final Rule). The EP Final Rule
was effective on December 23, 2011,
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18:49 Jul 15, 2013
Jkt 229001
with various implementation dates for
each of the rule changes.
Maine Yankee Atomic Power
Company (MYAPC) is holder of Facility
Operating License DPR–36 for the
Maine Yankee Atomic Power Plant
(MY). The license, issued pursuant to
the Atomic Energy Act of 1954, as
amended, and part 50 of Title 10 of the
Code of Federal Regulations (10 CFR),
allows MY to possess and store spent
nuclear fuel at the permanently shut
down and decommissioned facility
under the provision of 10 CFR part 72,
subpart K, ‘‘General License for Storage
of Spent Fuel at Power Reactor Sites.’’
In a letter dated August 7, 1997
(Agencywide Document Access and
Management System (ADAMS) Legacy
Accession No. 9708140225), MYAPC
informed the NRC that the MY facility
had permanently ceased power
operations and fuel had been removed
from the reactor and placed in the fuel
pool.
After ceasing operations at the reactor,
MYAPC began transferring spent
nuclear fuel from the spent fuel pool to
the MY independent spent fuel storage
installation (ISFSI) for long- term dry
storage. These activities were completed
in 2004, and final decommissioning of
the reactor site was completed in 2005.
The MY ISFSI is a vertical dry cask
storage facility for spent nuclear fuel.
The ISFSI is located on approximately
three acres of land that was not released
for unrestricted use after completion of
decommissioning of the reactor
(ADAMS Accession No. ML052380223).
On June 8, 2012, MYAPC submitted a
letter, ‘‘Request for Exemption to
Revised Emergency Planning
Regulations’’ (ADAMS Accession No.
ML12172A298 *), requesting exemption
from specific EP requirements of 10 CFR
50.47 and Appendix E to 10 CFR part
50 for the MY ISFSI.
MYAPC states that this exemption
request and its impact on the
corresponding emergency plan: (1) Is
authorized by law; (2) will not present
an undue risk to the public health and
safety; and (3) is consistent with the
common defense and security in
accordance with 10 CFR 50.12. MYAPC
states that its intent in submitting this
exemption request is to maintain the
regulatory structure in place prior to
issuance of the EP Final Rule and,
therefore, does not propose any changes
to the emergency plan or implementing
procedures other than simple regulatory
reference changes that can be
implemented under 10 CFR 50.54(q).
* Document contains sensitive security related
information and is not publically available.
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Fmt 4703
Sfmt 4703
2.0
Discussion
On August 7, 1997, MYAPC notified
the NRC that it had decided to cease
operating MY. On November 6, 1997
(ADAMS Legacy Accession No.
9711130334), MYAPC requested an
exemption from the provisions of 10
CFR 50.54(q) that required emergency
plans to meet all of the standards of 10
CFR 50.47(b) and all of the requirements
of Appendix E to 10 CFR part 50 so that
the licensee would have to meet only
certain EP standards and requirements.
Additionally, MYAPC requested
approval of a proposed MY Defueled
Emergency Plan (DEP) that proposed to
meet those limited standards and
requirements.
The NRC approved the requested
exemption and the DEP on September 3,
1998 (ADAMS Legacy Accession No.
9809140214). The safety evaluation
report (SER) established EP
requirements for MY as documented in
the DEP. The NRC staff concluded that
the licensee’s emergency plan was
acceptable in view of the greatly
reduced offsite radiological
consequences associated with the
decommissioning plant status. The staff
found that the postulated dose to the
general public from any reasonably
conceivable accident would not exceed
the U.S. Environmental Protection
Agency (EPA) Protective Action Guides
(PAGs), and for the bounding accident,
the length of time available to respond
to a loss of spent fuel cooling or
reduction in water level gave confidence
that offsite measures for the public
could be taken without preparation.
On August 28, 2002 (ADAMS
Accession No. ML022550037 *), the DEP
was revised under 10 CFR 50.54(q) to
include an emergency plan specific to
the onsite ISFSI as the licensee
commenced moving spent nuclear fuel
to the ISFSI. This ISFSI Emergency Plan
was included as an Attachment III to the
DEP.
According to MYAPC, the power
plant buildings have been dismantled
and the materials to be removed have
been shipped offsite. As part of
completing decommissioning, all spent
nuclear fuel and greater than class C
waste was ultimately transferred to the
ISFSI in February 2004.
On September 27, 2004 (ADAMS
Accession No. ML042790408 *), the DEP
was revised under 10 CFR 50.54(q) to
reflect that all spent nuclear fuel had
been transferred into the ISFSI, the
Spent Fuel Pool was drained, and all
evolutions that could produce a
radiological event serious enough to
trigger the declaration of an emergency
at the plant have been completed.
E:\FR\FM\16JYN1.SGM
16JYN1
emcdonald on DSK67QTVN1PROD with NOTICES
Federal Register / Vol. 78, No. 136 / Tuesday, July 16, 2013 / Notices
Therefore, the licensee terminated the
DEP but retained the MY ISFSI
Emergency Plan. This action eliminated
all facets of the emergency plan not
related to the ISFSI. The standalone MY
ISFSI Emergency Plan reflected the
emergency preparedness and response
requirements applicable to MYAPC in
light of the exemption granted in 1998.
The ISFSI Emergency Plan provides
reasonable assurance that adequate
protective measures can and will be
taken in the event of a radiological
emergency at the MY ISFSI for the same
reasons that the NRC found that the DEP
met the applicable EP requirements.
Since the approval and SER for the
original MY DEP, MYAPC has not
requested nor received substantive
exemptions from emergency planning
requirements.
Revision 1 of the MY ISFSI
Emergency Plan, February 17, 2011
(ADAMS Accession No.
ML110601310 *), reflects the current
conditions, where the only thing
remaining onsite is the ISFSI and its
related support systems, structures, and
components.
With the Final EP Rule, several
requirements in 10 CFR part 50 were
modified or added, including changes in
§ 50.47, § 50.54, and Appendix E.
Specific implementation dates were
provided for each EP rule change. The
Final EP Rule codified certain voluntary
protective measures contained in NRC
Bulletin 2005–02, ‘‘Emergency
Preparedness and Response Actions for
Security-Based Events,’’ and generically
applicable requirements similar to those
previously imposed by NRC Order EA–
02–026, ‘‘Order for Interim Safeguards
and Security Compensatory Measures,’’
dated February 25, 2002.
In addition, the EP Final Rule
amended other licensee emergency plan
requirements to: (1) Enhance the ability
of licensees in preparing for and in
taking certain protective actions in the
event of a radiological emergency; (2)
address, in part, security issues
identified after the terrorist events of
September 11, 2001; (3) clarify
regulations to effect consistent
emergency plan implementation among
licensees; and (4) modify certain EP
requirements to be more effective and
efficient. However, the EP Final Rule
was only an enhancement to the NRC’s
regulations and was not necessary for
adequate protection. On page 72563 of
the Federal Register notice for the EP
Final Rule, the Commission
‘‘determined that the existing regulatory
structure ensures adequate protection of
public health and safety and common
defense and security.’’
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3.0
Regulatory Evaluation
In the Final Rule for Storage of Spent
Fuel in NRC-Approved Storage Casks at
Power Reactor Sites (55 FR 29181; July
18, 1990), the NRC amended its
regulations to provide for the storage of
spent nuclear fuel under a general
license on the site of any nuclear power
reactor. In its Statement of
Considerations (SOC) for the Final Rule
(55 FR 29185), the Commission
responded to comments related to
emergency preparedness for spent fuel
dry storage, stating, ‘‘The new 10 CFR
72.32(c) . . . states that, ‘For an ISFSI
that is located on the site of a nuclear
power reactor licensed for operation by
the Commission, the emergency plan
required by 10 CFR 50.47 shall be
deemed to satisfy the requirements of
this section.’ One condition of the
general license is that the reactor
licensee must review the reactor
emergency plan and modify it as
necessary to cover dry cask storage and
related activities. If the emergency plan
is in compliance with 10 CFR 50.47,
then it is in compliance with the
Commission’s regulations with respect
to dry cask storage.’’
In the SOC for the Final Rule for EP
requirements for ISFSIs and Monitored
Retrievable Storage Installation (MRS)
(60 FR 32430; June 22, 1995), the
Commission stated, in part, that
‘‘current reactor emergency plans cover
all at- or near-reactor ISFSI’s. An ISFSI
that is to be licensed for a stand-alone
operation will need an emergency plan
established in accordance with the
requirements in this rulemaking’’ (60 FR
32431). The Commission responded to
comments (60 FR 32435) concerning
offsite emergency planning for ISFSIs or
an MRS and concluded that ‘‘the offsite
consequences of potential accidents at
an ISFSI or a MRS would not warrant
establishing Emergency Planning
Zones.’’
As part of the review for MYAPC’s
current exemption request, the staff also
used the EP regulations in 10 CFR 72.32
and Spent Fuel Project Office Interim
Staff Guidance (ISG)—16, ‘‘Emergency
Planning,’’ (ADAMS Accession No.
ML003724570) as references to ensure
consistency between specific-licensed
and general-licensed ISFSIs.
4.0
Technical Evaluation
Pursuant to 10 CFR 50.12, the
Commission may, upon application by
any interested person or upon its own
initiative, grant exemptions from the
requirements of 10 CFR part 50 when:
(1) The exemptions are authorized by
law, will not present an undue risk to
public health or safety, and are
PO 00000
Frm 00072
Fmt 4703
Sfmt 4703
42557
consistent with the common defense
and security; and (2) when special
circumstances are present. The staff
reviewed this request to determine
whether the specific exemptions should
be granted, and the safety evaluation
(SE) is provided in its letter to MYAPC,
dated May 2, 2013 (ADAMS Accession
No. ML13112A842). After evaluating the
exemption requests, the staff
determined MYAPC should be granted
the exemptions detailed in the SE.
The NRC has found that MYAPC
meets the criteria for an exemption in
§ 50.12. The Atomic Energy Act of 1954,
as amended, and the Commission’s
regulations permit the Commission to
grant exemptions from the regulations
in 10 CFR part 50. Granting exemptions
is consistent with the authority
provided to the Commission in the
Atomic Energy Act of 1954, as amended.
Therefore, the exemption is authorized
by law.
As noted in Section 2.0, ‘‘Discussion’’
above, MYAPC’s compliance with the
EP requirements in effect before the
effective date of the EP Final Rule
demonstrated reasonable assurance of
adequate protection of the public health
and safety and common defense and
security. In its SE, the NRC staff
explains that MYAPC’s implementation
of its ISFSI emergency plan, with the
exemptions, will continue to provide
this reasonable assurance of adequate
protection. Thus, granting the
exemptions will not present an undue
risk to public health or safety and is not
inconsistent with the common defense
and security.
For the Commission to grant an
exemption, special circumstances must
exist. Under § 50.12(a)(2)(ii), special
circumstances are present when
‘‘[a]pplication of the regulation in the
particular circumstances would not
serve the underlying purpose of the rule
or is not necessary to achieve the
underlying purpose of the rule.’’ These
special circumstances exist here. The
NRC has determined that MYAPC’s
compliance with the regulations
described in its SE is not necessary for
the licensee to demonstrate that, under
its emergency plan, there is reasonable
assurance that adequate protective
measures can and will be taken in the
event of a radiological emergency.
Consequently, special circumstances are
present because requiring MYAPC to
comply with the regulations that the
staff describes in its SE is not necessary
to achieve the underlying purpose of the
EP regulations.
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42558
5.0
Federal Register / Vol. 78, No. 136 / Tuesday, July 16, 2013 / Notices
Environmental Assessment (EA)
Identification of Proposed Action
By letter dated June 8, 2012, MYAPC
submitted an exemption request in
accordance with 10 CFR 50.12 from
specific EP requirements of 10 CFR
50.47 and Appendix E to 10 CFR part
50 for MY. Specifically, the exemption
would eliminate unnecessary
requirements associated with offsite
consequences, protective actions,
hostile action and emergency facilities
due to the current status of MY.
emcdonald on DSK67QTVN1PROD with NOTICES
Need for the Proposed Action
In accordance with 10 CFR 50.82, the
10 CFR part 50 licensed area for MY has
been reduced to a small area
surrounding the ISFSI. In this condition,
MY poses a significantly reduced risk to
public health and safety from design
basis accidents or credible beyond
design basis accidents since these
cannot result in radioactive releases
which exceed EPA PAGS at the site
boundary. Because of this reduced risk,
compliance with all the requirements in
10 CFR 50.47 and 10 CFR part 50,
Appendix E is not appropriate. The
requested exemption from portions of
10 CFR 50.47 and 10 CFR part 50,
Appendix E is needed to continue
implementation of the MY ISFSI
emergency plan that is appropriate for a
stand-alone ISFSI and is commensurate
with the reduced risk posed by the
facility. The requested exemption will
allow spent fuel to continue to be stored
safely without imposing burdensome
and costly new requirements that
provide no increased safety benefit.
Environmental Impacts of the Proposed
Action
The NRC has determined that, given
the continued implementation of the
MY ISFSI emergency plan, with the
exemptions noted in its SE, no credible
events would result in doses to the
public beyond the owner controlled area
boundary that would exceed the EPA
PAGs. Additionally, the staff has
concluded that the MY ISFSI emergency
plan, with the exemptions described in
its SE, provides for an acceptable level
of emergency preparedness at the
MYAPC facility in its shutdown and
defueled condition, and also provides
reasonable assurance that adequate
protective measures can and will be
taken in the event of a radiological
emergency at the MYAPC facility. Based
on these findings, the NRC concludes
that there are no radiological
environmental impacts due to granting
the approval of the exemptions, the
proposed action will not increase the
probability or consequences of
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18:49 Jul 15, 2013
Jkt 229001
accidents, no changes are being made in
the types or quantities of effluents that
may be released offsite, and there is no
significant increase in occupational or
public radiation exposure. Therefore,
there are no significant radiological
environmental impacts associated with
the proposed action. The proposed
action does not affect non-radiological
plant effluents and has no other
environmental impact. Therefore, there
are no significant non-radiological
impacts associated with the proposed
action. Based on the assessment above,
the proposed action will not have a
significant effect on the quality of the
human environment.
Alternative to the Proposed Action
Since there is no significant
environmental impact associated with
the proposed action, any alternatives
with equal or greater environmental
impact are not evaluated. The
alternative to the proposed action would
be to deny approval of the exemption.
This alternative would have the same
environmental impact.
Finding of No Significant Impact
The environmental impacts of the
proposed action have been reviewed in
accordance with the requirements set
forth in 10 CFR part 51. Based upon the
EA, the Commission finds that the
proposed action of granting an
exemption will not significantly impact
the quality of the human environment.
Accordingly, the Commission has
determined not to prepare an
environmental impact statement for the
proposed exemption.
6.0 Conclusion
The NRC concludes that the licensee’s
request for an exemption from certain
requirements of 10 CFR 50.47(b) and 10
CFR part 50, Appendix E, Section IV as
specified in the SE are acceptable in
view of the greatly reduced offsite
radiological consequences associated
with the ISFSI.
The exemption request has been
reviewed against the acceptance criteria
included in 10 CFR 50.47, Appendix E
to 10 CFR part 50, 10 CFR 72.32 and
Interim Staff Guidance—16. The review
considered the ISFSI and the low
likelihood of any credible accident
resulting in radiological releases
requiring offsite protective measures.
These evaluations were supported by
the previously documented licensee and
staff accident analyses. The staff
concludes that: the MY ISFSI
Emergency Plan provides: (1) An
adequate basis for an acceptable state of
emergency preparedness; and (2) the
emergency plan, in conjunction with
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Frm 00073
Fmt 4703
Sfmt 4703
arrangements made with offsite
response agencies, provides reasonable
assurance that adequate protective
measures can and will be taken in the
event of a radiological emergency at the
MYAPC facility.
The NRC has determined that
pursuant to 10 CFR 50.12, the
exemptions described in the SE are
authorized by law, will not endanger
life or property or the common defense
and security, and are otherwise in the
public interest, and special
circumstances are present.
7.0 Further Information
Documents related to this action,
including the application for renewal
and supporting documentation, are
available online in the NRC library at
https://www.nrc.gov/reading-rm/
adams.html. From this site, you can
access the NRC’s ADAMS, which
provides text and image files of NRC’s
public documents. If you do not have
access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC
Public Document Room (PDR) Reference
staff at 1–800–397–4209, 301–415–4737
or by email to pdr.resource@nrc.gov.
These documents may also be viewed
electronically on the public computers
located at the NRC’s PDR, O 1 F21, One
White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR
reproduction contractor will copy
documents for a fee.
Dated at Rockville, Maryland, this 28th day
of June, 2013.
For the Nuclear Regulatory Commission.
Michele M. Sampson,
Acting Chief, Licensing Branch, Division of
Spent Fuel Storage and Transportation, Office
of Nuclear Material Safety and Safeguards.
[FR Doc. 2013–16988 Filed 7–15–13; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0149]
Proposed Revision 0 to Fitness-forDuty Standard Review Plan
Nuclear Regulatory
Commission.
ACTION: Notice of availability and
request for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is soliciting public
comment on draft NUREG–0800,
‘‘Standard Review Plan for the Review
of Safety Analysis Reports for Nuclear
Power Plants,’’ LWR Edition: Section
13.7 ‘‘Fitness-for-Duty,’’ and Section
13.7.1 ‘‘Fitness-for-Duty—Operational
SUMMARY:
E:\FR\FM\16JYN1.SGM
16JYN1
Agencies
[Federal Register Volume 78, Number 136 (Tuesday, July 16, 2013)]
[Notices]
[Pages 42556-42558]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-16988]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-309 and 72-30; NRC-2013-0156]
Maine Yankee Atomic Power Company; Maine Yankee Atomic Power
Plant Issuance of Environmental Assessment and Finding of No
Significant Impact Regarding an Exemption Request
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of environmental assessment and finding of no
significant impact.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: John Goshen, Project Manager, Division
of Spent Fuel Storage and Transportation, Office of Nuclear Material
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington,
DC 20555. Telephone: 301-287-9250, Fax number: 301-287-9341; Email:
John.Goshen@nrc.gov.
1.0 Introduction
On November 23, 2011, the U.S. Nuclear Regulatory Commission (NRC)
issued a final rule amending certain emergency planning (EP)
requirements in the regulations that govern domestic licensing of
production and utilization facilities (76 FR 72560; November 23, 2011)
(EP Final Rule). The EP Final Rule was effective on December 23, 2011,
with various implementation dates for each of the rule changes.
Maine Yankee Atomic Power Company (MYAPC) is holder of Facility
Operating License DPR-36 for the Maine Yankee Atomic Power Plant (MY).
The license, issued pursuant to the Atomic Energy Act of 1954, as
amended, and part 50 of Title 10 of the Code of Federal Regulations (10
CFR), allows MY to possess and store spent nuclear fuel at the
permanently shut down and decommissioned facility under the provision
of 10 CFR part 72, subpart K, ``General License for Storage of Spent
Fuel at Power Reactor Sites.'' In a letter dated August 7, 1997
(Agencywide Document Access and Management System (ADAMS) Legacy
Accession No. 9708140225), MYAPC informed the NRC that the MY facility
had permanently ceased power operations and fuel had been removed from
the reactor and placed in the fuel pool.
After ceasing operations at the reactor, MYAPC began transferring
spent nuclear fuel from the spent fuel pool to the MY independent spent
fuel storage installation (ISFSI) for long- term dry storage. These
activities were completed in 2004, and final decommissioning of the
reactor site was completed in 2005. The MY ISFSI is a vertical dry cask
storage facility for spent nuclear fuel. The ISFSI is located on
approximately three acres of land that was not released for
unrestricted use after completion of decommissioning of the reactor
(ADAMS Accession No. ML052380223).
On June 8, 2012, MYAPC submitted a letter, ``Request for Exemption
to Revised Emergency Planning Regulations'' (ADAMS Accession No.
ML12172A298 *), requesting exemption from specific EP requirements of
10 CFR 50.47 and Appendix E to 10 CFR part 50 for the MY ISFSI.
---------------------------------------------------------------------------
* Document contains sensitive security related information and
is not publically available.
---------------------------------------------------------------------------
MYAPC states that this exemption request and its impact on the
corresponding emergency plan: (1) Is authorized by law; (2) will not
present an undue risk to the public health and safety; and (3) is
consistent with the common defense and security in accordance with 10
CFR 50.12. MYAPC states that its intent in submitting this exemption
request is to maintain the regulatory structure in place prior to
issuance of the EP Final Rule and, therefore, does not propose any
changes to the emergency plan or implementing procedures other than
simple regulatory reference changes that can be implemented under 10
CFR 50.54(q).
2.0 Discussion
On August 7, 1997, MYAPC notified the NRC that it had decided to
cease operating MY. On November 6, 1997 (ADAMS Legacy Accession No.
9711130334), MYAPC requested an exemption from the provisions of 10 CFR
50.54(q) that required emergency plans to meet all of the standards of
10 CFR 50.47(b) and all of the requirements of Appendix E to 10 CFR
part 50 so that the licensee would have to meet only certain EP
standards and requirements. Additionally, MYAPC requested approval of a
proposed MY Defueled Emergency Plan (DEP) that proposed to meet those
limited standards and requirements.
The NRC approved the requested exemption and the DEP on September
3, 1998 (ADAMS Legacy Accession No. 9809140214). The safety evaluation
report (SER) established EP requirements for MY as documented in the
DEP. The NRC staff concluded that the licensee's emergency plan was
acceptable in view of the greatly reduced offsite radiological
consequences associated with the decommissioning plant status. The
staff found that the postulated dose to the general public from any
reasonably conceivable accident would not exceed the U.S. Environmental
Protection Agency (EPA) Protective Action Guides (PAGs), and for the
bounding accident, the length of time available to respond to a loss of
spent fuel cooling or reduction in water level gave confidence that
offsite measures for the public could be taken without preparation.
On August 28, 2002 (ADAMS Accession No. ML022550037 *), the DEP was
revised under 10 CFR 50.54(q) to include an emergency plan specific to
the onsite ISFSI as the licensee commenced moving spent nuclear fuel to
the ISFSI. This ISFSI Emergency Plan was included as an Attachment III
to the DEP.
According to MYAPC, the power plant buildings have been dismantled
and the materials to be removed have been shipped offsite. As part of
completing decommissioning, all spent nuclear fuel and greater than
class C waste was ultimately transferred to the ISFSI in February 2004.
On September 27, 2004 (ADAMS Accession No. ML042790408 *), the DEP
was revised under 10 CFR 50.54(q) to reflect that all spent nuclear
fuel had been transferred into the ISFSI, the Spent Fuel Pool was
drained, and all evolutions that could produce a radiological event
serious enough to trigger the declaration of an emergency at the plant
have been completed.
[[Page 42557]]
Therefore, the licensee terminated the DEP but retained the MY ISFSI
Emergency Plan. This action eliminated all facets of the emergency plan
not related to the ISFSI. The standalone MY ISFSI Emergency Plan
reflected the emergency preparedness and response requirements
applicable to MYAPC in light of the exemption granted in 1998. The
ISFSI Emergency Plan provides reasonable assurance that adequate
protective measures can and will be taken in the event of a
radiological emergency at the MY ISFSI for the same reasons that the
NRC found that the DEP met the applicable EP requirements. Since the
approval and SER for the original MY DEP, MYAPC has not requested nor
received substantive exemptions from emergency planning requirements.
Revision 1 of the MY ISFSI Emergency Plan, February 17, 2011 (ADAMS
Accession No. ML110601310 *), reflects the current conditions, where
the only thing remaining onsite is the ISFSI and its related support
systems, structures, and components.
With the Final EP Rule, several requirements in 10 CFR part 50 were
modified or added, including changes in Sec. 50.47, Sec. 50.54, and
Appendix E. Specific implementation dates were provided for each EP
rule change. The Final EP Rule codified certain voluntary protective
measures contained in NRC Bulletin 2005-02, ``Emergency Preparedness
and Response Actions for Security-Based Events,'' and generically
applicable requirements similar to those previously imposed by NRC
Order EA-02-026, ``Order for Interim Safeguards and Security
Compensatory Measures,'' dated February 25, 2002.
In addition, the EP Final Rule amended other licensee emergency
plan requirements to: (1) Enhance the ability of licensees in preparing
for and in taking certain protective actions in the event of a
radiological emergency; (2) address, in part, security issues
identified after the terrorist events of September 11, 2001; (3)
clarify regulations to effect consistent emergency plan implementation
among licensees; and (4) modify certain EP requirements to be more
effective and efficient. However, the EP Final Rule was only an
enhancement to the NRC's regulations and was not necessary for adequate
protection. On page 72563 of the Federal Register notice for the EP
Final Rule, the Commission ``determined that the existing regulatory
structure ensures adequate protection of public health and safety and
common defense and security.''
3.0 Regulatory Evaluation
In the Final Rule for Storage of Spent Fuel in NRC-Approved Storage
Casks at Power Reactor Sites (55 FR 29181; July 18, 1990), the NRC
amended its regulations to provide for the storage of spent nuclear
fuel under a general license on the site of any nuclear power reactor.
In its Statement of Considerations (SOC) for the Final Rule (55 FR
29185), the Commission responded to comments related to emergency
preparedness for spent fuel dry storage, stating, ``The new 10 CFR
72.32(c) . . . states that, `For an ISFSI that is located on the site
of a nuclear power reactor licensed for operation by the Commission,
the emergency plan required by 10 CFR 50.47 shall be deemed to satisfy
the requirements of this section.' One condition of the general license
is that the reactor licensee must review the reactor emergency plan and
modify it as necessary to cover dry cask storage and related
activities. If the emergency plan is in compliance with 10 CFR 50.47,
then it is in compliance with the Commission's regulations with respect
to dry cask storage.''
In the SOC for the Final Rule for EP requirements for ISFSIs and
Monitored Retrievable Storage Installation (MRS) (60 FR 32430; June 22,
1995), the Commission stated, in part, that ``current reactor emergency
plans cover all at- or near-reactor ISFSI's. An ISFSI that is to be
licensed for a stand-alone operation will need an emergency plan
established in accordance with the requirements in this rulemaking''
(60 FR 32431). The Commission responded to comments (60 FR 32435)
concerning offsite emergency planning for ISFSIs or an MRS and
concluded that ``the offsite consequences of potential accidents at an
ISFSI or a MRS would not warrant establishing Emergency Planning
Zones.''
As part of the review for MYAPC's current exemption request, the
staff also used the EP regulations in 10 CFR 72.32 and Spent Fuel
Project Office Interim Staff Guidance (ISG)--16, ``Emergency
Planning,'' (ADAMS Accession No. ML003724570) as references to ensure
consistency between specific-licensed and general-licensed ISFSIs.
4.0 Technical Evaluation
Pursuant to 10 CFR 50.12, the Commission may, upon application by
any interested person or upon its own initiative, grant exemptions from
the requirements of 10 CFR part 50 when: (1) The exemptions are
authorized by law, will not present an undue risk to public health or
safety, and are consistent with the common defense and security; and
(2) when special circumstances are present. The staff reviewed this
request to determine whether the specific exemptions should be granted,
and the safety evaluation (SE) is provided in its letter to MYAPC,
dated May 2, 2013 (ADAMS Accession No. ML13112A842). After evaluating
the exemption requests, the staff determined MYAPC should be granted
the exemptions detailed in the SE.
The NRC has found that MYAPC meets the criteria for an exemption in
Sec. 50.12. The Atomic Energy Act of 1954, as amended, and the
Commission's regulations permit the Commission to grant exemptions from
the regulations in 10 CFR part 50. Granting exemptions is consistent
with the authority provided to the Commission in the Atomic Energy Act
of 1954, as amended. Therefore, the exemption is authorized by law.
As noted in Section 2.0, ``Discussion'' above, MYAPC's compliance
with the EP requirements in effect before the effective date of the EP
Final Rule demonstrated reasonable assurance of adequate protection of
the public health and safety and common defense and security. In its
SE, the NRC staff explains that MYAPC's implementation of its ISFSI
emergency plan, with the exemptions, will continue to provide this
reasonable assurance of adequate protection. Thus, granting the
exemptions will not present an undue risk to public health or safety
and is not inconsistent with the common defense and security.
For the Commission to grant an exemption, special circumstances
must exist. Under Sec. 50.12(a)(2)(ii), special circumstances are
present when ``[a]pplication of the regulation in the particular
circumstances would not serve the underlying purpose of the rule or is
not necessary to achieve the underlying purpose of the rule.'' These
special circumstances exist here. The NRC has determined that MYAPC's
compliance with the regulations described in its SE is not necessary
for the licensee to demonstrate that, under its emergency plan, there
is reasonable assurance that adequate protective measures can and will
be taken in the event of a radiological emergency. Consequently,
special circumstances are present because requiring MYAPC to comply
with the regulations that the staff describes in its SE is not
necessary to achieve the underlying purpose of the EP regulations.
[[Page 42558]]
5.0 Environmental Assessment (EA)
Identification of Proposed Action
By letter dated June 8, 2012, MYAPC submitted an exemption request
in accordance with 10 CFR 50.12 from specific EP requirements of 10 CFR
50.47 and Appendix E to 10 CFR part 50 for MY. Specifically, the
exemption would eliminate unnecessary requirements associated with
offsite consequences, protective actions, hostile action and emergency
facilities due to the current status of MY.
Need for the Proposed Action
In accordance with 10 CFR 50.82, the 10 CFR part 50 licensed area
for MY has been reduced to a small area surrounding the ISFSI. In this
condition, MY poses a significantly reduced risk to public health and
safety from design basis accidents or credible beyond design basis
accidents since these cannot result in radioactive releases which
exceed EPA PAGS at the site boundary. Because of this reduced risk,
compliance with all the requirements in 10 CFR 50.47 and 10 CFR part
50, Appendix E is not appropriate. The requested exemption from
portions of 10 CFR 50.47 and 10 CFR part 50, Appendix E is needed to
continue implementation of the MY ISFSI emergency plan that is
appropriate for a stand-alone ISFSI and is commensurate with the
reduced risk posed by the facility. The requested exemption will allow
spent fuel to continue to be stored safely without imposing burdensome
and costly new requirements that provide no increased safety benefit.
Environmental Impacts of the Proposed Action
The NRC has determined that, given the continued implementation of
the MY ISFSI emergency plan, with the exemptions noted in its SE, no
credible events would result in doses to the public beyond the owner
controlled area boundary that would exceed the EPA PAGs. Additionally,
the staff has concluded that the MY ISFSI emergency plan, with the
exemptions described in its SE, provides for an acceptable level of
emergency preparedness at the MYAPC facility in its shutdown and
defueled condition, and also provides reasonable assurance that
adequate protective measures can and will be taken in the event of a
radiological emergency at the MYAPC facility. Based on these findings,
the NRC concludes that there are no radiological environmental impacts
due to granting the approval of the exemptions, the proposed action
will not increase the probability or consequences of accidents, no
changes are being made in the types or quantities of effluents that may
be released offsite, and there is no significant increase in
occupational or public radiation exposure. Therefore, there are no
significant radiological environmental impacts associated with the
proposed action. The proposed action does not affect non-radiological
plant effluents and has no other environmental impact. Therefore, there
are no significant non-radiological impacts associated with the
proposed action. Based on the assessment above, the proposed action
will not have a significant effect on the quality of the human
environment.
Alternative to the Proposed Action
Since there is no significant environmental impact associated with
the proposed action, any alternatives with equal or greater
environmental impact are not evaluated. The alternative to the proposed
action would be to deny approval of the exemption. This alternative
would have the same environmental impact.
Finding of No Significant Impact
The environmental impacts of the proposed action have been reviewed
in accordance with the requirements set forth in 10 CFR part 51. Based
upon the EA, the Commission finds that the proposed action of granting
an exemption will not significantly impact the quality of the human
environment. Accordingly, the Commission has determined not to prepare
an environmental impact statement for the proposed exemption.
6.0 Conclusion
The NRC concludes that the licensee's request for an exemption from
certain requirements of 10 CFR 50.47(b) and 10 CFR part 50, Appendix E,
Section IV as specified in the SE are acceptable in view of the greatly
reduced offsite radiological consequences associated with the ISFSI.
The exemption request has been reviewed against the acceptance
criteria included in 10 CFR 50.47, Appendix E to 10 CFR part 50, 10 CFR
72.32 and Interim Staff Guidance--16. The review considered the ISFSI
and the low likelihood of any credible accident resulting in
radiological releases requiring offsite protective measures. These
evaluations were supported by the previously documented licensee and
staff accident analyses. The staff concludes that: the MY ISFSI
Emergency Plan provides: (1) An adequate basis for an acceptable state
of emergency preparedness; and (2) the emergency plan, in conjunction
with arrangements made with offsite response agencies, provides
reasonable assurance that adequate protective measures can and will be
taken in the event of a radiological emergency at the MYAPC facility.
The NRC has determined that pursuant to 10 CFR 50.12, the
exemptions described in the SE are authorized by law, will not endanger
life or property or the common defense and security, and are otherwise
in the public interest, and special circumstances are present.
7.0 Further Information
Documents related to this action, including the application for
renewal and supporting documentation, are available online in the NRC
library at https://www.nrc.gov/reading-rm/adams.html. From this site,
you can access the NRC's ADAMS, which provides text and image files of
NRC's public documents. If you do not have access to ADAMS or if there
are problems in accessing the documents located in ADAMS, contact the
NRC Public Document Room (PDR) Reference staff at 1-800-397-4209, 301-
415-4737 or by email to pdr.resource@nrc.gov. These documents may also
be viewed electronically on the public computers located at the NRC's
PDR, O 1 F21, One White Flint North, 11555 Rockville Pike, Rockville,
MD 20852. The PDR reproduction contractor will copy documents for a
fee.
Dated at Rockville, Maryland, this 28th day of June, 2013.
For the Nuclear Regulatory Commission.
Michele M. Sampson,
Acting Chief, Licensing Branch, Division of Spent Fuel Storage and
Transportation, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2013-16988 Filed 7-15-13; 8:45 am]
BILLING CODE 7590-01-P