Mitigation Strategies for Beyond-Design-Basis External Events, 69702-69705 [2015-28593]
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69702
Federal Register / Vol. 80, No. 217 / Tuesday, November 10, 2015 / Notices
FY 2014–2018 Strategic Plan may be
found at: https://www.nsf.gov/pubs/
2014/nsf14043/nsf14043.pdf.
Since this collection will primarily be
used for accountability and evaluation
purposes, including responding to
queries from COVs and other scientific
experts, a census rather than sampling
design typically is necessary. At the
individual project level funding can be
adjusted based on individual project’s
responses to some of the surveys. Some
data collected under this collection will
serve as baseline data for separate
research and evaluation studies.
NSF-funded contract or grantee
researchers and internal or external
evaluators in part may identify control,
comparison, or treatment groups for
NSF’s E&T portfolio using some of the
descriptive data gathered through this
collection to conduct well-designed,
rigorous research and portfolio
evaluation studies.
Respondents: Individuals or
households, not-for-profit institutions,
business or other for profit, and Federal,
State, local or tribal government.
Number of Respondents: 8,184.
Burden on the Public: NSF estimates
that a total reporting and recordkeeping
burden of 58,449 hours will result from
activities to monitor EHR STEM
education programs. The calculation is
shown in table 1.
TABLE 1—ANTICIPATED PROGRAMS THAT WILL COLLECT DATA ON PROJECT PROGRESS AND OUTCOMES ALONG WITH
THE NUMBER OF RESPONDENTS AND BURDEN HOURS PER COLLECTION PER YEAR
Number of
respondents
Collection title
Advancing Informal STEM Learning (AISL) Monitoring System ...................................................
Centers of Research Excellence in Science and Technology (CREST) and Historically Black
Colleges and Universities Research Infrastructure for Science and Engineering (HBCU–
RISE) Monitoring System.
Graduate STEM Fellows in K–12 Education (GK–12) Monitoring System ...................................
Integrative Graduate Education and Research Traineeship Program (IGERT) Monitoring System.
Louis Stokes Alliances for Minority Participation (LSAMP) Monitoring System ............................
Louis Stokes Alliances for Minority Participation Bridge to the Doctorate (LSAMP–BD) Monitoring System.
Robert Noyce Teacher Scholarship Program (Noyce) Monitoring System ...................................
Research in Disabilities Education (RDE) Monitoring System ......................................................
Scholarships in Science, Technology, Engineering, and Mathematics (S–STEM) Monitoring
System.
Number of
responses
Annual hour
burden
155
40
155 ..............
40 ................
1,921
1,810
1,267
3,307
1,267 ...........
3,307 ...........
3,529
12,282
563
55
563 ..............
55 ................
12,949
2,090
422
12
500
5,908
1,368
6,000
277
422 ..............
12 ................
1,000 (500
respondents × 2
responses/
yr.).
277 ..............
6,648
Science, Technology, Engineering, and Mathematics Talent Expansion Program (STEP) Monitoring System.
Transforming Undergraduate Education in Science, Technology, Engineering, and Mathematics (TUES) Monitoring System.
Additional Collections not Specified ...............................................................................................
686
686 ..............
2,744
900
900 ..............
1,200
Total ........................................................................................................................................
8,184
8,684 ...........
58,449
The total estimate for this collection
is 58,449 annual burden hours. The
average annual reporting burden is
between 1.7 and 114 hours per
‘‘respondent,’’ depending on whether a
respondent is a direct participant who is
self-reporting or representing a project
and reporting on behalf of many project
participants.
NUCLEAR REGULATORY
COMMISSION
The U.S. Nuclear Regulatory
Commission (NRC) is soliciting public
comment on its draft Japan LessonsLearned Division Interim Staff Guidance
(JLD–ISG), JLD–ISG–2012–01, Draft
Revision 1, ‘‘Compliance with Order
EA–12–049, Order Modifying Licenses
with Regard to Requirements for
Mitigation Strategies for Beyond-DesignBasis External Events.’’ This draft JLD–
ISG revision provides guidance and
clarification to assist nuclear power
reactors applicants and licensees with
the identification of measures needed to
comply with requirements to mitigate
challenges to key safety functions.
[NRC–2012–0068]
DATES:
Dated: November 5, 2015.
Suzanne H. Plimpton,
Reports Clearance Officer, National Science
Foundation.
[FR Doc. 2015–28576 Filed 11–9–15; 8:45 am]
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Draft interim staff guidance;
request for comment.
ACTION:
Mitigation Strategies for BeyondDesign-Basis External Events
Nuclear Regulatory
Commission.
AGENCY:
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SUMMARY:
Submit comments by December
10, 2015. Comments received after this
date will be considered if it is practical
to do so, but the Commission is able to
ensure consideration only for comments
received before this date.
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You may submit comments
by any of the following methods (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0068. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: Cindy Bladey,
Office of Administration, Mail Stop:
OWFN–12–H08, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
For additional direction on obtaining
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
ADDRESSES:
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Federal Register / Vol. 80, No. 217 / Tuesday, November 10, 2015 / Notices
Eric
Bowman, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–2963; email:
Eric.Bowman@nrc.gov.
SUPPLEMENTARY INFORMATION:
FOR FURTHER INFORMATION CONTACT:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2012–
0068 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable information related to this
action by any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0068.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
69703
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.'' For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov.
• The documents identified in the
following table are available to
interested persons through one or more
of the following methods, as indicated.
ADAMS Accession No.
Document title
Abbreviated title
JLD–ISG–2012–01, ‘‘Compliance with Order EA–12–049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events,’’
Draft Revision 1.
See Previous Entry .....................................................................................................................
for JLD–ISG–2012–01 ................................................................................................................
Order EA–12–049, ‘‘Order Modifying Licenses with Regard to Requirements for Mitigation
Strategies for Beyond-Design-Basis External Events’’.
V.C. Summer Nuclear Station, Unit 2 License, License No. NPF–93 .......................................
V.C. Summer Nuclear Station, Unit 3 License, License No. NPF–94 .......................................
Enrico Fermi Nuclear Plant, Unit 3 License, License No. NPF—95 ..........................................
SECY–11–0093, ‘‘Near-Term Report and Recommendations for Agency Actions Following
the Events in Japan’’.
SECY–11–0124, ‘‘Recommended Actions to be Taken without Delay from the Near-Term
Task Force Report’’.
SECY–11–0137, ‘‘Prioritization of Recommended Actions to be Taken in Response to
Fukushima Lessons Learned’’.
Commission’s staff requirements memorandum (SRM) for SECY-11-0093 ..............................
SRM for SECY–11–0124 (see entry to SECY–11–0124 for full title) ........................................
SRM for SECY–11–0137 (see entry to SECY–11–0124 for full title) ........................................
Nuclear Energy Institute (NEI) Letter Titled, ‘‘An Integrated, Safety-Focused Approach to Expediting Implementation of Fukushima Daiichi Lessons Learned’’.
SECY–12–0025, ‘‘Proposed Orders and Requests for Information in Response to Lessons
Learned from Japan’s March 11, 2011, Great Tohoku Earthquake and Tsunami’’.
SRM for SECY–12–0025 (see entry for SECY–12–0025 for full title) .......................................
Request for Information Pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident.
NEI 12–06, ‘‘Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,’’ Revision B.
NEI 12–06, Revision B1 (See Previous Entry for NEI 12–06) ...................................................
‘‘NRC Response to Public Comments, JLD–ISG–2012–01 (Docket ID NRC–2012–0068)’’ .....
NEI 12–06, Revision C (See Previous Entry for NEI 12–06) .....................................................
NEI 12–06, Draft Revision 0 (See Previous Entry for NEI 12–06) ............................................
See Previous Entry for JLD–ISG–2012–01 ................................................................................
JLD–ISG–2012–01, Draft Revision 1.
ML15294A078
JLD–ISG–2012–01, Revision 0
ML12229A174
Order EA–12–049 ...................
ML12054A736
n/a ...........................................
n/a ...........................................
n/a ...........................................
SECY–11–0093 ......................
ML14100A092
ML14100A101
ML15084A170
ML11186A950
SECY–11–0124 ......................
ML11245A158
SECY–11–0137 ......................
ML11272A111
SRM–SECY–11–0093 ............
SRM–SECY–110124 ..............
SRM–SECY–11–0137 ............
n/a ...........................................
ML112310021
ML112911571
ML113490055
ML11353A008
SECY–12–0025 ......................
ML12039A103
SRM–SECY–12–0025 ............
50.54(f) Letter .........................
ML120690347
ML12053A340
NEI 12–06, Revision B ...........
ML12144A419
NEI 12–06, Revision B1 .........
n/a ...........................................
NEI 12–06, Revision C ...........
NEI 12–06, Draft Revision 0 ...
JLD–ISG–2012–01, Draft Revision 0.
n/a ...........................................
COMSECY–14–0037 ..............
ML12143A232
ML12229A253
ML121910390
ML12221A204
ML12146A014
SRM–COMSECY–14–0037 ....
NEI 12–06, Revision 1 ............
NEI 12–06, Revision 1A .........
NUREG–2161 .........................
ML15089A236
ML15244B006
ML15279A425
ML14255A365
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Vermont Yankee Nuclear Power Station’s Overall Integrate Plan .............................................
COMSECY–14–0037, ‘‘Integration of Mitigating Strategies for Beyond-Design-Basis External
Events and the Reevaluation (sic) of Flooding Hazards’’.
SRM–COMSECY–14–0037 ........................................................................................................
NEI 12–06, Revision 1 (See Previous Entry for NEI 12–06) .....................................................
NEI 12–06, Revision 1A (See Previous Entry for NEI 12–06) ...................................................
NUREG–2161, ‘‘Consequence Study of a Beyond-Design-Basis Earthquake Affecting the
Spent Fuel Pool for a U.S. Mark I Boiling Water Reactor’’.
• The NRC may post materials related
to this document, including public
comments, on the Federal rulemaking
Web site at https://www.regulations.gov
under Docket ID NRC–2012–0068. The
Federal rulemaking Web site allows you
to receive alerts when changes or
additions occur in a docket folder. To
subscribe: 1) Navigate to the docket
folder (NRC–2012–0068 ); 2) click the
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‘‘Sign up for Email Alerts’’ link; and 3)
enter your email address and select how
frequently you would like to receive
emails (daily, weekly, or monthly).
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
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B. Submitting Comments
Please include Docket ID NRC–2012–
0068 in your comment submission.
The NRC cautions you not to include
identifying or contact information that
you do not want to be publicly
disclosed in your comment submission.
The NRC posts all comment
submissions at https://
www.regulations.gov as well as entering
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the comment submissions into ADAMS.
The NRC does not routinely edit
comment submissions to remove
identifying or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information that
they do not want to be publicly
disclosed in their comment submission.
Your request should state that the NRC
does not routinely edit comment
submissions to remove such information
before making the comment
submissions available to the public or
entering the comment submissions into
ADAMS.
II. Background
The NRC staff issued JLD–ISG–2012–
01 Revision 0 on August 29, 2012. The
NRC staff developed JLD–ISG–2012–01
Draft Revision 1 to provide further
guidance and clarification to assist
nuclear power reactor applicants and
licensees with the identification of
measures needed to comply with
requirements to mitigate challenges to
key safety functions. These
requirements are contained in Order
EA–12–049. In addition, these
requirements are included in the
following license conditions: Virgil C.
Summer Nuclear Station, Unit 2 License
(V.C. Summer), License No. NPF–93,
Condition 2.D.(13), V.C. Summer
Nuclear Station, Unit 3 License, License
No. NPF–94, Condition 2.D.(13), and
Enrico Fermi Nuclear Plant, Unit 3
License, License No. NPF–95, Condition
2.D.(12)(g). The draft ISG is not a
substitute for the requirements in Order
EA–12–049, and compliance with the
ISG is not required. This ISG revision is
being issued in draft form for public
comment to involve the public in
development of the implementation
guidance.
Following the events at the
Fukushima Dai-ichi nuclear power plant
on March 11, 2011, the NRC established
a senior-level agency task force referred
to as the Near-Term Task Force (NTTF).
The NTTF was tasked with conducting
a systematic and methodical review of
the NRC regulations and processes, and
determining if the agency should make
additional improvements to these
programs in light of the events at
Fukushima Dai-ichi. As a result of this
review, the NTTF developed a
comprehensive set of recommendations,
documented in SECY–11–0093, dated
July 12, 2011. These recommendations
were enhanced by the NRC staff
following interactions with
stakeholders. Documentation of the
staff’s efforts is contained in SECY–11–
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0124, dated September 9, 2011, and
SECY–11–0137, dated October 3, 2011.
As directed by the Commission’s SRM
for SECY–11–0093, the NRC staff
reviewed the NTTF recommendations
within the context of the NRC’s existing
regulatory framework and considered
the various regulatory vehicles available
to the NRC to implement the
recommendations. SECY–11–0124 and
SECY–11–0137 established the staff’s
prioritization of the recommendations.
After receiving the Commission’s
direction in SRM–SECY–11–0124 and
SRM–SECY–11–0137, the NRC staff
conducted public meetings to discuss
enhanced mitigation strategies intended
to maintain or restore core cooling,
containment, and spent fuel pool (SFP)
cooling capabilities following beyonddesign-basis external events. At these
meetings, the industry described its
proposal for a Diverse and Flexible
Mitigation Capability (FLEX), as
documented in NEI’s letter, dated
December 16, 2011. FLEX is proposed as
a strategy to fulfill the key safety
functions of core cooling, containment
integrity, and spent fuel cooling.
Stakeholder input influenced the staff to
pursue a more performance-based
approach to improve the safety of
operating power reactors than was
originally envisioned in NTTF
Recommendation 4.2, SECY–11–0124,
and SECY–11–0137.
On February 17, 2012, the NRC staff
provided SECY–12–0025 to the
Commission, including the proposed
order to implement the enhanced
mitigation strategies. As directed by
SRM–SECY–12–0025, the NRC staff
issued Order EA–12–049 and, in
parallel, issued as a Request for
Information under 10 CFR 50.54(f) for a
reevaluation of licensees’ flooding and
seismic hazards.
Guidance and strategies required by
the order would be available if the loss
of power, motive force and normal
access to the ultimate heat sink to
prevent fuel damage in the reactor, and
SFP affected all units at a site
simultaneously. The order requires a
three-phase approach for mitigating
beyond-design-basis external events.
The initial phase requires the use of
installed equipment and resources to
maintain or restore core cooling,
containment, and SFP cooling. The
transition phase requires providing
sufficient, portable, onsite equipment
and consumables to maintain or restore
these functions until they can be
accomplished with resources brought
from off site. The final phase requires
obtaining sufficient offsite resources to
sustain those functions indefinitely.
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On May 4, 2012, NEI submitted
document 12–06, Revision B, and on
May 13, 2012, Revision B1, to provide
specifications for an industry-developed
methodology for the development,
implementation, and maintenance of
guidance and strategies in response to
the mitigating strategies order. The
strategies and guidance described in NEI
12–06 expand on the strategies the
industry developed and implemented to
address the limited set of beyonddesign-basis external events that involve
the loss of a large area of the plant due
to explosions and fire required pursuant
to paragraph (hh)(2) of 10 CFR 50.54(f),
‘‘Conditions of licenses.’’
On May 31, 2012, the NRC staff issued
a draft version of JLD–ISG–2012–01,
Revision 0, and published a notice of its
availability for public comment in the
Federal Register (FR) (77 FR 33779;
June 7, 2012), with the comment period
running through July 7, 2012, 30 days
from its publication. The staff received
seven comments during this time,
addressing the comments, as
documented in ‘‘NRC Response to
Public Comments, JLD–ISG–2012–01
(Docket ID NRC–2012–0068).’’
On July 3, 2012, NEI submitted
Revision C to NEI 12–06, incorporating
many of the exceptions and
clarifications included in the draft
version of this ISG. On August 3, 2012,
NEI submitted Draft Revision 0 to NEI
12–06, incorporating many of the
remaining exceptions and clarifications.
On August 21, 2012, NEI submitted
Revision 0 to NEI 12–06, making various
editorial corrections. The NRC reviewed
the August 21, 2012, submittal of
Revision 0 of NEI 12–06 and endorsed
it as a process the NRC considers
acceptable for meeting the regulatory
requirements with noted clarifications
in revision 0 of JLD–ISG–2012–01.
By February 2013, licensees of
operating power reactors submitted
their overall integrated plans (OIPs)
under the Mitigating Strategies order
describing the guidance and strategies to
be developed and implemented.
Because this development and
implementation was to be accomplished
in parallel with the reevaluation of the
seismic and flooding hazards under the
10 CFR 50.54(f) letter issued subsequent
to SECY–12–0025, these included in
their key assumptions a statement that
typically read, ‘‘[f]lood and seismic reevaluations pursuant to the 10 CFR
50.54(f) letter of March 12, 2012, are not
completed and therefore not assumed in
this submittal. As the reevaluations are
completed, appropriate issues will be
entered into the corrective action system
and addressed on a schedule
commensurate with other licensing
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bases changes.’’ (See, e.g., Vermont
Yankee Nuclear Power Station’s OIP)
In order to clarify the relationship
between the Mitigating Strategies order
and the hazard reevaluation, the NRC
staff provided COMSECY–14–0037 to
the Commission on November 21, 2014,
requesting that the Commission affirm
that ‘‘[l]icensees for operating nuclear
power plants need to address the
reevaluated flooding hazards within
their mitigating strategies for beyonddesign-basis external events (Order EA–
12–049 and related [Mitigation of
Beyond-Design-Basis Events] MBDBE
rulemaking).’’ COMSECY–14–0037
further requested affirmation that
‘‘[l]icensees for operating nuclear power
plants may need to address some
specific flooding scenarios that could
significantly damage the power plant
site by developing targeted or scenariospecific mitigating strategies, possibly
including unconventional measures, to
prevent fuel damage in reactor cores or
spent fuel pools.’’ In SRM–COMSECY–
14–0037, the Commission affirmed
these two items and noted that ‘‘it is
within the staff’s authority, and is the
staff’s responsibility, to determine, on a
plant-specific basis, whether targeted or
scenario-specific mitigating strategies,
possibly including unconventional
measures, are acceptable.’’
On August 25, 2015, NEI submitted
Revision 1 to NEI 12–06, incorporating
lessons learned in the implementation
of Order EA–12–049 and alternative
approaches taken by licensees for
compliance to that order. Following a
public webinar discussion of potential
exceptions and clarifications that took
place on September 21, 2015, NEI
submitted Revision 1A to NEI 12–06 on
October 5, 2015.
III. Specific Request for Comment
The NRC is seeking advice and
recommendations from the public on
the revision to this interim staff
guidance document. We are particularly
interested in comments and supporting
rationale from the public on the
following:
Spent Fuel Pool (SFP) Spray strategy:
Order EA–12–049 was issued in parallel
with the March 12, 2012, request for
information under 10 CFR 50.54(f) for
reevaluation of seismic and flooding
hazards. The order and the guidance
developed to support the development
and implementation of the mitigating
strategies were intended to address the
uncertainties associated with beyonddesign-basis external events. Since
March 12, 2012, the NRC has completed
NUREG–2161, ‘‘Consequence Study of a
Beyond-Design-Basis Earthquake
Affecting the Spent Fuel Pool for a U.S.
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Mark I Boiling Water Reactor,’’ which
predicted an SFP liner failure likelihood
of about two times in a million years
and a possibility of release of
radioactive materials only if that liner
failure occurs during 8 percent of the
operating cycle of the reference plant
considered in the study. The results of
the study showed that the risk of
individual latent cancer fatality within
10 miles of the reference plant due to
the effects of a beyond-design-basis
earthquake on the SFP is several orders
of magnitude below the quantitative
health objectives established in the
Commission’s safety goal policy, ‘‘Safety
Goals for the Operations of Nuclear
Power Plants,’’ 51 FR 28044, August 4,
1986, as corrected and republished at 51
FR 30028, August 21, 1986. These
results did not quantitatively credit the
existing SFP spray strategy under 10
CFR 50.54(hh)(2), which would be
necessary for conformance with the
guidance contained in this revision to
JLD–ISG–2012–01 through its
endorsement of NEI 12–06, Revision 1A,
at Tables C–3 and D–3 for boiling-water
reactors and pressurized-water reactors,
respectively. The NRC seeks comment
on whether continuing to require the
SFP spray strategy under Order EA–12–
049 is warranted in light of the analyses
performed for NUREG–2161, or whether
the need for this strategy should be
limited or removed.
Proposed Action
By this action, the NRC is requesting
public comments on JLD–ISG–2012–01
Draft Revision 1. This draft JLD–ISG
proposes guidance related to
requirements contained in Order EA–
12–049, Mitigation Strategies for
Beyond-Design-Basis External Events.
The NRC staff will make a final
determination regarding issuance of the
JLD–ISG after it considers any public
comments received in response to this
request.
Dated at Rockville, Maryland, this 4th day
of November, 2015.
For The Nuclear Regulatory Commission.
Stewart N. Bailey,
Acting Director, Japan Lessons-Learned
Division, Office of Nuclear Reactor
Regulation.
[FR Doc. 2015–28593 Filed 11–9–15; 8:45 am]
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69705
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–361, 50–362, and 72–41;
NRC–2015–0023]
Southern California Edison Company,
San Onofre Nuclear Generating
Station, Units 2 and 3
Nuclear Regulatory
Commission.
ACTION: Draft environmental assessment
and finding of no significant impact;
request for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment a draft environmental
assessment (EA) and finding of no
significant impact (FONSI) related to a
request to amend Facility Operating
License Nos. NPF–10 and NPF–15 and
Docket No. 72–41, issued to the
Southern California Edison Company
(SCE or ‘‘the licensee’’), for operation of
the San Onofre Nuclear Generating
Station, Units 2 and 3 (hereinafter
‘‘SONGS’’ or ‘‘the facility’’), including
the general-license Independent Spent
Fuel Storage Installation (ISFSI), located
in San Diego County, California. The
requested amendment would permit
licensee security personnel to use
certain firearms and ammunition
feeding devices not previously
permitted, notwithstanding State, local
and certain Federal firearms laws or
regulations that otherwise prohibit such
actions.
DATES: Submit comments by December
10, 2015. Comments received after this
date will be considered if it is practical
to do so, but the Commission is able to
ensure consideration only for comments
received before this date. Any potential
party as defined in § 2.4 of title 10 of the
Code of Federal Regulations (10 CFR),
who believes access to sensitive
unclassified non-safeguards information
(SUNSI) is necessary to respond to this
notice must request document access by
November 20, 2015.
ADDRESSES: You may submit comments
by any of the following methods (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2015–0023. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: Cindy Bladey,
Office of Administration, Mail Stop:
SUMMARY:
E:\FR\FM\10NON1.SGM
10NON1
Agencies
[Federal Register Volume 80, Number 217 (Tuesday, November 10, 2015)]
[Notices]
[Pages 69702-69705]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-28593]
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NUCLEAR REGULATORY COMMISSION
[NRC-2012-0068]
Mitigation Strategies for Beyond-Design-Basis External Events
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft interim staff guidance; request for comment.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting
public comment on its draft Japan Lessons-Learned Division Interim
Staff Guidance (JLD-ISG), JLD-ISG-2012-01, Draft Revision 1,
``Compliance with Order EA-12-049, Order Modifying Licenses with Regard
to Requirements for Mitigation Strategies for Beyond-Design-Basis
External Events.'' This draft JLD-ISG revision provides guidance and
clarification to assist nuclear power reactors applicants and licensees
with the identification of measures needed to comply with requirements
to mitigate challenges to key safety functions.
DATES: Submit comments by December 10, 2015. Comments received after
this date will be considered if it is practical to do so, but the
Commission is able to ensure consideration only for comments received
before this date.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0068. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: Cindy Bladey, Office of Administration,
Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
[[Page 69703]]
FOR FURTHER INFORMATION CONTACT: Eric Bowman, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-2963; email: Eric.Bowman@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2012-0068 when contacting the NRC
about the availability of information for this action. You may obtain
publicly-available information related to this action by any of the
following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0068.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov.
The documents identified in the following table are
available to interested persons through one or more of the following
methods, as indicated.
------------------------------------------------------------------------
Document title Abbreviated title ADAMS Accession No.
------------------------------------------------------------------------
JLD-ISG-2012-01, ``Compliance JLD-ISG-2012-01, ML15294A078
with Order EA-12-049, Order Draft Revision 1.
Modifying Licenses with
Regard to Requirements for
Mitigation Strategies for
Beyond-Design-Basis External
Events,'' Draft Revision 1.
See Previous Entry............ JLD-ISG-2012-01, ML12229A174
for JLD-ISG-2012-01........... Revision 0.
Order EA-12-049, ``Order Order EA-12-049.. ML12054A736
Modifying Licenses with
Regard to Requirements for
Mitigation Strategies for
Beyond-Design-Basis External
Events''.
V.C. Summer Nuclear Station, n/a.............. ML14100A092
Unit 2 License, License No.
NPF-93.
V.C. Summer Nuclear Station, n/a.............. ML14100A101
Unit 3 License, License No.
NPF-94.
Enrico Fermi Nuclear Plant, n/a.............. ML15084A170
Unit 3 License, License No.
NPF--95.
SECY-11-0093, ``Near-Term SECY-11-0093..... ML11186A950
Report and Recommendations
for Agency Actions Following
the Events in Japan''.
SECY-11-0124, ``Recommended SECY-11-0124..... ML11245A158
Actions to be Taken without
Delay from the Near-Term Task
Force Report''.
SECY-11-0137, ``Prioritization SECY-11-0137..... ML11272A111
of Recommended Actions to be
Taken in Response to
Fukushima Lessons Learned''.
Commission's staff SRM-SECY-11-0093. ML112310021
requirements memorandum (SRM)
for SECY[dash]11[dash]0093.
SRM for SECY-11-0124 (see SRM-SECY-110124.. ML112911571
entry to SECY-11-0124 for
full title).
SRM for SECY-11-0137 (see SRM-SECY-11-0137. ML113490055
entry to SECY-11-0124 for
full title).
Nuclear Energy Institute (NEI) n/a.............. ML11353A008
Letter Titled, ``An
Integrated, Safety-Focused
Approach to Expediting
Implementation of Fukushima
Daiichi Lessons Learned''.
SECY-12-0025, ``Proposed SECY-12-0025..... ML12039A103
Orders and Requests for
Information in Response to
Lessons Learned from Japan's
March 11, 2011, Great Tohoku
Earthquake and Tsunami''.
SRM for SECY-12-0025 (see SRM-SECY-12-0025. ML120690347
entry for SECY-12-0025 for
full title).
Request for Information 50.54(f) Letter.. ML12053A340
Pursuant to Title 10 of the
Code of Federal Regulations
(10 CFR) 50.54(f) Regarding
Recommendations 2.1, 2.3, and
9.3, of the Near-Term Task
Force Review of Insights from
the Fukushima Dai-ichi
Accident.
NEI 12-06, ``Diverse and NEI 12-06, ML12144A419
Flexible Coping Strategies Revision B.
(FLEX) Implementation
Guide,'' Revision B.
NEI 12-06, Revision B1 (See NEI 12-06, ML12143A232
Previous Entry for NEI 12-06). Revision B1.
``NRC Response to Public n/a.............. ML12229A253
Comments, JLD-ISG-2012-01
(Docket ID NRC-2012-0068)''.
NEI 12-06, Revision C (See NEI 12-06, ML121910390
Previous Entry for NEI 12-06). Revision C.
NEI 12-06, Draft Revision 0 NEI 12-06, Draft ML12221A204
(See Previous Entry for NEI Revision 0.
12-06).
See Previous Entry for JLD-ISG- JLD-ISG-2012-01, ML12146A014
2012-01. Draft Revision 0.
Vermont Yankee Nuclear Power n/a.............. ML13064A300
Station's Overall Integrate
Plan.
COMSECY-14-0037, ``Integration COMSECY-14-0037.. ML14238A616
of Mitigating Strategies for
Beyond-Design-Basis External
Events and the Reevaluation
(sic) of Flooding Hazards''.
SRM-COMSECY-14-0037........... SRM-COMSECY-14-00 ML15089A236
37.
NEI 12-06, Revision 1 (See NEI 12-06, ML15244B006
Previous Entry for NEI 12-06). Revision 1.
NEI 12-06, Revision 1A (See NEI 12-06, ML15279A425
Previous Entry for NEI 12-06). Revision 1A.
NUREG-2161, ``Consequence NUREG-2161....... ML14255A365
Study of a Beyond-Design-
Basis Earthquake Affecting
the Spent Fuel Pool for a
U.S. Mark I Boiling Water
Reactor''.
------------------------------------------------------------------------
The NRC may post materials related to this document,
including public comments, on the Federal rulemaking Web site at https://www.regulations.gov under Docket ID NRC-2012-0068. The Federal
rulemaking Web site allows you to receive alerts when changes or
additions occur in a docket folder. To subscribe: 1) Navigate to the
docket folder (NRC-2012-0068 ); 2) click the ``Sign up for Email
Alerts'' link; and 3) enter your email address and select how
frequently you would like to receive emails (daily, weekly, or
monthly).
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2012-0068 in your comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC posts all comment submissions at https://www.regulations.gov as well as entering
[[Page 69704]]
the comment submissions into ADAMS. The NRC does not routinely edit
comment submissions to remove identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment submissions into ADAMS.
II. Background
The NRC staff issued JLD-ISG-2012-01 Revision 0 on August 29, 2012.
The NRC staff developed JLD-ISG-2012-01 Draft Revision 1 to provide
further guidance and clarification to assist nuclear power reactor
applicants and licensees with the identification of measures needed to
comply with requirements to mitigate challenges to key safety
functions. These requirements are contained in Order EA-12-049. In
addition, these requirements are included in the following license
conditions: Virgil C. Summer Nuclear Station, Unit 2 License (V.C.
Summer), License No. NPF-93, Condition 2.D.(13), V.C. Summer Nuclear
Station, Unit 3 License, License No. NPF-94, Condition 2.D.(13), and
Enrico Fermi Nuclear Plant, Unit 3 License, License No. NPF-95,
Condition 2.D.(12)(g). The draft ISG is not a substitute for the
requirements in Order EA-12-049, and compliance with the ISG is not
required. This ISG revision is being issued in draft form for public
comment to involve the public in development of the implementation
guidance.
Following the events at the Fukushima Dai-ichi nuclear power plant
on March 11, 2011, the NRC established a senior-level agency task force
referred to as the Near-Term Task Force (NTTF). The NTTF was tasked
with conducting a systematic and methodical review of the NRC
regulations and processes, and determining if the agency should make
additional improvements to these programs in light of the events at
Fukushima Dai-ichi. As a result of this review, the NTTF developed a
comprehensive set of recommendations, documented in SECY-11-0093, dated
July 12, 2011. These recommendations were enhanced by the NRC staff
following interactions with stakeholders. Documentation of the staff's
efforts is contained in SECY-11-0124, dated September 9, 2011, and
SECY-11-0137, dated October 3, 2011.
As directed by the Commission's SRM for SECY-11-0093, the NRC staff
reviewed the NTTF recommendations within the context of the NRC's
existing regulatory framework and considered the various regulatory
vehicles available to the NRC to implement the recommendations. SECY-
11-0124 and SECY-11-0137 established the staff's prioritization of the
recommendations.
After receiving the Commission's direction in SRM-SECY-11-0124 and
SRM-SECY-11-0137, the NRC staff conducted public meetings to discuss
enhanced mitigation strategies intended to maintain or restore core
cooling, containment, and spent fuel pool (SFP) cooling capabilities
following beyond-design-basis external events. At these meetings, the
industry described its proposal for a Diverse and Flexible Mitigation
Capability (FLEX), as documented in NEI's letter, dated December 16,
2011. FLEX is proposed as a strategy to fulfill the key safety
functions of core cooling, containment integrity, and spent fuel
cooling. Stakeholder input influenced the staff to pursue a more
performance-based approach to improve the safety of operating power
reactors than was originally envisioned in NTTF Recommendation 4.2,
SECY-11-0124, and SECY-11-0137.
On February 17, 2012, the NRC staff provided SECY-12-0025 to the
Commission, including the proposed order to implement the enhanced
mitigation strategies. As directed by SRM-SECY-12-0025, the NRC staff
issued Order EA-12-049 and, in parallel, issued as a Request for
Information under 10 CFR 50.54(f) for a reevaluation of licensees'
flooding and seismic hazards.
Guidance and strategies required by the order would be available if
the loss of power, motive force and normal access to the ultimate heat
sink to prevent fuel damage in the reactor, and SFP affected all units
at a site simultaneously. The order requires a three-phase approach for
mitigating beyond-design-basis external events. The initial phase
requires the use of installed equipment and resources to maintain or
restore core cooling, containment, and SFP cooling. The transition
phase requires providing sufficient, portable, onsite equipment and
consumables to maintain or restore these functions until they can be
accomplished with resources brought from off site. The final phase
requires obtaining sufficient offsite resources to sustain those
functions indefinitely.
On May 4, 2012, NEI submitted document 12-06, Revision B, and on
May 13, 2012, Revision B1, to provide specifications for an industry-
developed methodology for the development, implementation, and
maintenance of guidance and strategies in response to the mitigating
strategies order. The strategies and guidance described in NEI 12-06
expand on the strategies the industry developed and implemented to
address the limited set of beyond-design-basis external events that
involve the loss of a large area of the plant due to explosions and
fire required pursuant to paragraph (hh)(2) of 10 CFR 50.54(f),
``Conditions of licenses.''
On May 31, 2012, the NRC staff issued a draft version of JLD-ISG-
2012-01, Revision 0, and published a notice of its availability for
public comment in the Federal Register (FR) (77 FR 33779; June 7,
2012), with the comment period running through July 7, 2012, 30 days
from its publication. The staff received seven comments during this
time, addressing the comments, as documented in ``NRC Response to
Public Comments, JLD-ISG-2012-01 (Docket ID NRC-2012-0068).''
On July 3, 2012, NEI submitted Revision C to NEI 12-06,
incorporating many of the exceptions and clarifications included in the
draft version of this ISG. On August 3, 2012, NEI submitted Draft
Revision 0 to NEI 12-06, incorporating many of the remaining exceptions
and clarifications. On August 21, 2012, NEI submitted Revision 0 to NEI
12-06, making various editorial corrections. The NRC reviewed the
August 21, 2012, submittal of Revision 0 of NEI 12-06 and endorsed it
as a process the NRC considers acceptable for meeting the regulatory
requirements with noted clarifications in revision 0 of JLD-ISG-2012-
01.
By February 2013, licensees of operating power reactors submitted
their overall integrated plans (OIPs) under the Mitigating Strategies
order describing the guidance and strategies to be developed and
implemented. Because this development and implementation was to be
accomplished in parallel with the reevaluation of the seismic and
flooding hazards under the 10 CFR 50.54(f) letter issued subsequent to
SECY-12-0025, these included in their key assumptions a statement that
typically read, ``[f]lood and seismic re-evaluations pursuant to the 10
CFR 50.54(f) letter of March 12, 2012, are not completed and therefore
not assumed in this submittal. As the reevaluations are completed,
appropriate issues will be entered into the corrective action system
and addressed on a schedule commensurate with other licensing
[[Page 69705]]
bases changes.'' (See, e.g., Vermont Yankee Nuclear Power Station's
OIP)
In order to clarify the relationship between the Mitigating
Strategies order and the hazard reevaluation, the NRC staff provided
COMSECY-14-0037 to the Commission on November 21, 2014, requesting that
the Commission affirm that ``[l]icensees for operating nuclear power
plants need to address the reevaluated flooding hazards within their
mitigating strategies for beyond-design-basis external events (Order
EA-12-049 and related [Mitigation of Beyond-Design-Basis Events] MBDBE
rulemaking).'' COMSECY-14-0037 further requested affirmation that
``[l]icensees for operating nuclear power plants may need to address
some specific flooding scenarios that could significantly damage the
power plant site by developing targeted or scenario-specific mitigating
strategies, possibly including unconventional measures, to prevent fuel
damage in reactor cores or spent fuel pools.'' In SRM-COMSECY-14-0037,
the Commission affirmed these two items and noted that ``it is within
the staff's authority, and is the staff's responsibility, to determine,
on a plant-specific basis, whether targeted or scenario-specific
mitigating strategies, possibly including unconventional measures, are
acceptable.''
On August 25, 2015, NEI submitted Revision 1 to NEI 12-06,
incorporating lessons learned in the implementation of Order EA-12-049
and alternative approaches taken by licensees for compliance to that
order. Following a public webinar discussion of potential exceptions
and clarifications that took place on September 21, 2015, NEI submitted
Revision 1A to NEI 12-06 on October 5, 2015.
III. Specific Request for Comment
The NRC is seeking advice and recommendations from the public on
the revision to this interim staff guidance document. We are
particularly interested in comments and supporting rationale from the
public on the following:
Spent Fuel Pool (SFP) Spray strategy: Order EA-12-049 was issued in
parallel with the March 12, 2012, request for information under 10 CFR
50.54(f) for reevaluation of seismic and flooding hazards. The order
and the guidance developed to support the development and
implementation of the mitigating strategies were intended to address
the uncertainties associated with beyond-design-basis external events.
Since March 12, 2012, the NRC has completed NUREG-2161, ``Consequence
Study of a Beyond-Design-Basis Earthquake Affecting the Spent Fuel Pool
for a U.S. Mark I Boiling Water Reactor,'' which predicted an SFP liner
failure likelihood of about two times in a million years and a
possibility of release of radioactive materials only if that liner
failure occurs during 8 percent of the operating cycle of the reference
plant considered in the study. The results of the study showed that the
risk of individual latent cancer fatality within 10 miles of the
reference plant due to the effects of a beyond-design-basis earthquake
on the SFP is several orders of magnitude below the quantitative health
objectives established in the Commission's safety goal policy, ``Safety
Goals for the Operations of Nuclear Power Plants,'' 51 FR 28044, August
4, 1986, as corrected and republished at 51 FR 30028, August 21, 1986.
These results did not quantitatively credit the existing SFP spray
strategy under 10 CFR 50.54(hh)(2), which would be necessary for
conformance with the guidance contained in this revision to JLD-ISG-
2012-01 through its endorsement of NEI 12-06, Revision 1A, at Tables C-
3 and D-3 for boiling-water reactors and pressurized-water reactors,
respectively. The NRC seeks comment on whether continuing to require
the SFP spray strategy under Order EA-12-049 is warranted in light of
the analyses performed for NUREG-2161, or whether the need for this
strategy should be limited or removed.
Proposed Action
By this action, the NRC is requesting public comments on JLD-ISG-
2012-01 Draft Revision 1. This draft JLD-ISG proposes guidance related
to requirements contained in Order EA-12-049, Mitigation Strategies for
Beyond-Design-Basis External Events. The NRC staff will make a final
determination regarding issuance of the JLD-ISG after it considers any
public comments received in response to this request.
Dated at Rockville, Maryland, this 4th day of November, 2015.
For The Nuclear Regulatory Commission.
Stewart N. Bailey,
Acting Director, Japan Lessons-Learned Division, Office of Nuclear
Reactor Regulation.
[FR Doc. 2015-28593 Filed 11-9-15; 8:45 am]
BILLING CODE 7590-01-P