Mitigation Strategies for Beyond-Design-Basis External Events, 79056-79060 [2016-27169]
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Federal Register / Vol. 81, No. 218 / Thursday, November 10, 2016 / Notices
10202, Office of Management and
Budget, Washington, DC 20503;
telephone: 202–395–7315, email: oira_
submission@omb.eop.gov.
FOR FURTHER INFORMATION CONTACT:
David Cullison, NRC Clearance Officer,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–2084; email:
INFOCOLLECTS.Resource@nrc.gov.
SUPPLEMENTARY INFORMATION:
asabaliauskas on DSK3SPTVN1PROD with NOTICES
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2015–
0283 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–2015–0283. A copy
of the collection of information and
related instructions may be obtained
without charge by accessing Docket ID
NRC–2015–0283 on this Web site.
• 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/
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. A copy
of the collection of information and
related instructions may be obtained
without charge by accessing ADAMS
Accession No. ML16245A845. The
supporting statement is available in
ADAMS under Accession No.
ML16245A863.
• 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.
• NRC’s Clearance Officer: A copy of
the collection of information and related
instructions may be obtained without
charge by contacting the NRC’s
Clearance Officer, David Cullison,
Office of the Chief Information Officer,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–2084; email:
INFOCOLLECTS.Resource@nrc.gov.
B. Submitting Comments
The NRC cautions you not to include
identifying or contact information in
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comment submissions that you do not
want to be publicly disclosed in your
comment submission. All comment
submissions are posted at https://
www.regulations.gov and entered into
ADAMS. Comment submissions are not
routinely edited to remove identifying
or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the OMB, 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 comment submissions are not
routinely edited to remove such
information before making the comment
submissions available to the public or
entering the comment into ADAMS.
II. Background
Under the provisions of the
Paperwork Reduction Act of 1995 (44
U.S.C. Chapter 35), the NRC recently
submitted a request for renewal of an
existing collection of information to
OMB for review entitled: ‘‘NRC Forms
541 and 541A, ‘Uniform Low-Level
Radioactive Waste Manifest, Container
and Waste Description, and
Continuation Page.’ ’’ The NRC hereby
informs potential respondents that an
agency may not conduct or sponsor, and
that a person is not required to respond
to, a collection of information unless it
displays a currently valid OMB control
number.
The NRC published a Federal
Register notice with a 60-day comment
period on this information collection on
June 22, 2016 (81 FR 40727).
1. The title of the information
collection: ‘‘NRC Forms 541 and 541A,
‘Uniform Low-Level Radioactive Waste
Manifest, Container and Waste
Description, and Continuation Page.’ ’’
2. OMB approval number: 3150–0166.
3. Type of submission: Extension.
4. The form number, if applicable:
NRC Forms 541 and 541A.
5. How often the collection is required
or requested: Forms are used by
shippers whenever radioactive waste is
shipped. Quarterly or less frequent
reporting is made to Agreement States
depending on specific license
conditions. No reporting is made to the
NRC.
6. Who will be required or asked to
respond: All NRC or Agreement State
low-level waste facilities licensed
pursuant to part 61 of title 10 of the
Code of Federal Regulations (10 CFR) or
equivalent Agreement State regulations.
All generators, collectors, and
processors of low-level waste intended
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for disposal at a low-level waste facility
must complete the appropriate forms.
7. The estimated number of annual
responses: 5,600.
8. The estimated number of annual
respondents: 220.
9. The estimated number of hours
needed annually to comply with the
information collection requirement or
request: 18,480.
10. Abstract: NRC Forms 541 and
541A provide a set of standardized
forms to meet U.S. Department of
Transportation (DOT), NRC, and State
requirements. The forms were
developed by NRC at the request of lowlevel waste industry groups. The forms
provide uniformity and efficiency in the
collection of information contained in
manifests which are required to control
transfers of low-level radioactive waste
intended for disposal at a land disposal
facility. The NRC Form 541 contains
information needed by disposal site
facilities to safely dispose of low-level
waste and information to meet NRC and
State requirements regulating these
activities.
Dated at Rockville, Maryland, this 2nd day
of November, 2016.
For the Nuclear Regulatory Commission.
David Cullison,
NRC Clearance Officer, Office of the Chief
Information Officer.
[FR Doc. 2016–27124 Filed 11–9–16; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2012–0068]
Mitigation Strategies for BeyondDesign-Basis External Events
Nuclear Regulatory
Commission.
ACTION: Draft interim staff guidance;
request for comment.
AGENCY:
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 2, ‘‘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 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.
DATES: Submit comments by December
12, 2016. Comments received after this
SUMMARY:
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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.
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
asabaliauskas on DSK3SPTVN1PROD with NOTICES
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/
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. In
addition, for the convenience of the
reader, the ADAMS accession numbers
are provided in a table in Section IV of
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this notice entitled, Availability of
Documents.
• 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
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 and
JLD–ISG–2012–01 Revision 1 on January
22, 2016. The NRC staff developed JLD–
ISG–2012–01 Draft Revision 2 to
provide further guidance and
clarification primarily to assist nuclear
power reactor applicants and licensees
when assessing the results of seismic
hazard reevaluations with respect to the
guidance and strategies required by
Order EA–12–049. JLD–ISG–2012–01
provides 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 No. NPF–93, Condition 2.D.(13),
V.C. Summer Nuclear Station, Unit 3,
License No. NPF–94, Condition 2.D.(13),
and Enrico Fermi Nuclear Plant, Unit 3,
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
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79057
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 March 11, 2011,
accident at the Fukushima Dai-ichi
nuclear power plant, the NRC
established a senior-level agency task
force referred to as the Near-Term Task
Force (NTTF). The NTTF conducted a
systematic and methodical review of the
NRC regulations and processes to
determine whether the agency should
make additional improvements in NRC
regulations or processes 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 staff
requirements memorandum (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 the Nuclear Energy
Institute’s (NEI) letter, dated December
16, 2011. The FLEX is proposed as a
strategy to fulfill the key safety
functions of core cooling, containment
integrity, and spent fuel cooling.
Stakeholder input led 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
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parallel, issued as a Request for
Information under Title 10 of the Code
of Federal Regulations (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 NEI 12–06, Revision B, and
on May 13, 2012, Revision B1, to
provide specifications for an industrydeveloped methodology for the
development, implementation, and
maintenance of guidance and strategies
in response to Order EA–12–049. 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) on June 7, 2012
(77 FR 33779), with the comment period
running through July 7, 2012, 30 days
after 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 JLD–ISG–2012–01, Revision
0. On August 3, 2012, NEI submitted
NEI 12–06, Draft Revision 0,
incorporating many of the remaining
exceptions and clarifications. On
August 21, 2012, NEI submitted NEI 12–
06, Revision 0, making various editorial
corrections. The NRC reviewed the
August 21, 2012, submittal of Revision
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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 Order EA–12–049 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 bases changes.’’
(See, e.g., Vermont Yankee Nuclear
Power Station’s OIP)
In order to clarify the relationship
between Order EA–12–049 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
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place on September 21, 2015, NEI
submitted Revision 1A to NEI 12–06 on
October 5, 2015.
On October 30, 2015, the NRC staff
issued a draft version of JLD–ISG–2012–
01, Revision 1, and published a notice
of its availability for public comment in
the FR on November 10, 2015 (80 FR
69702), with the comment period
running through December 10, 2015, 30
days from its publication. The staff
received four 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 December 10, 2015, NEI submitted
Revision 2 to NEI 12–06, incorporating
many of the exceptions and
clarifications included in the draft
version of JLD–ISG–2012–01, Revision
1. The NRC reviewed Revision 2 to NEI
12–06 and endorsed it as a process the
NRC considers acceptable for meeting
the regulatory requirements with noted
clarifications in JLD–ISG–2012–01,
Revision 1.
On September 7, 2016, NEI submitted
a draft revision of Appendix H to NEI
12–06 to support a public meeting held
on September 8, 2016, incorporating
additional guidance for licensees when
addressing the reevaluated seismic
hazards for compliance with Order EA–
12–049. Specifically, Section H.4.5
(‘‘Path 5’’) is intended to address
Mitigation Strategies Assessments for
plants with reevaluated seismic hazard
information that includes a ground
motion response spectrum that has
spectral ordinates more than 2 times the
Safe Shutdown Earthquake anywhere in
the 1 to 10 hertz frequency range. Such
guidance includes deterministic and
risk-informed approaches that can be
used to assess the impact of the
reevaluated hazard information on
mitigation strategies. Following the
public meeting held on September 8,
2016, NEI submitted Revision 3 to NEI
12–06 on September 22, 2016. NEI 12–
06, Revision 3 also addresses certain
lessons learned in the implementation
of Order EA–12–049.
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:
1. In NEI 12–06, Revision 3, Section
11.5.4.f, NEI proposes to modify the
time limits for initiation of actions to
restore a site’s capability to mitigate a
beyond-design-basis external event and
implementation of compensatory
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measures. Section 11.5.4.f of NEI 12–06,
Revision 0 and Revision 2, states these
time limits as 24 hours to initiate
actions and 72 hours to implement
compensatory measures. In NEI 12–06,
Revision 3, Section 11.5.4.f, these time
limits are extended to 72 hours for
initiation of actions and 7 days for
implementation of compensatory
measures. The former time limits were
previously endorsed as an element of an
acceptable method of meeting the Order
EA–12–049 requirements for
maintaining the strategies and
guidelines to mitigate a beyond-designbasis external event in JLD–ISG–2012–
01, Revision 0 and Revision 1. The NRC
staff seeks input on potential
justifications for this extension of the
allowable outage times for a licensee’s
capability to mitigate a beyond-designbasis external event. Input is
specifically requested on the potential
benefits of extending these time limits,
operating experience on time frames
actually necessary to implement
compensatory measures for the
unavailability of similar equipment, and
any potential unintended consequences
of extending these time limits.
2. In JLD–ISG–2012–01, Revision 1,
the NRC staff endorsed the NEI 12–06,
Revision 2, Section 11.5.4.b 45-day time
limit for having an available but
unprotected set of equipment as part of
the site’s capability to mitigate a
beyond-design-basis external event. The
45-day time limit aligned with the
standard 6-week short work cycle
period and allowed sufficient time for
the pre-staging of one set of equipment
in a location that is not entirely
protected from all external hazards for
the purpose of shutdown risk
management during outages, which
typically have durations less than 45
days. In NEI 12–06, Revision 3, Section
11.5.4.g, this time period is reduced to
14 days, which could conflict with the
pre-staging of equipment for risk
management during outages. The NRC
staff seeks input on appropriate
methods of control of pre-staging of
equipment for shutdown risk
management.
3. In NEI 12–06, Revision 3, Sections
H.4.5.3, H.4.5.4, and H.4.5.5, NEI
proposes to allow the use of risk
insights from the seismic probabilistic
risk assessments (SPRAs), being
completed by some licensees in
response to the NRC’s March 12, 2012,
10 CFR 50.54(f) letter, to assess the
mitigating strategies developed in
response to Order EA–12–049 against
the reevaluated seismic hazard
information. The purpose of these
mitigating strategies assessments is to
determine if changes to the mitigating
strategies are needed to account for the
reevaluated seismic hazard. The NRC
staff seeks input on specific aspects of
NEI’s proposals in light of issues
discussed in NCP–2016–014, a nonconcurrence submitted by two NRC staff
members regarding certain aspects of
NEI 12–06, Revision 3. First, NCP–
2016–014 raised concerns associated
with NEI’s proposed use of risk
screening criteria. For example, in
Section H.4.5.3, NEI proposes to
establish screening criteria based on the
overall seismic core damage frequency
and seismic large early release
frequency identified through the SPRA.
If these screening criteria are met,
licensees’ FLEX mitigating strategies or
alternate mitigating strategies would be
considered sufficient to address the
effects of the reevaluated seismic hazard
information without the need for
modification. The NRC staff seeks input
on the appropriateness of the approach
proposed by NEI in light of the concerns
raised by NCP–2016–014. Second, in
Sections H.4.5.4 and H.4.5.5, NEI
describes proposed iterative processes
that evaluate the benefit of enhancing
the seismic capacity of certain
mitigating strategies structures, systems,
and components (SSCs). As part of these
processes, licensees would enhance
such SSCs until the risk benefit of
further enhancements is sufficiently
small based on criteria established in
each section. In Section H.4.5.4 the
approach focuses on the benefit in terms
of reduction in overall seismic core
damage frequency and seismic large
early release frequency. The approach
described in Section H.4.5.5 focuses on
the benefit in terms of reduction in risk
from sequences in the SPRAs involving
mitigating strategies SSCs. The NRC
staff seeks input on these approaches in
light of the concerns raised by NCP–
2016–014 regarding the use of riskbased screening values and risk
partitioning. Finally, NCP–2016–014
identified two alternate approaches that
could be used to conduct seismic
mitigating strategies assessments. The
NRC staff seeks input on these
approaches and whether they represent
more appropriate alternatives to the
approaches described in NEI 12–06,
Revision 3.
IV. Backfitting and Issue Finality
This draft ISG would provide
guidance on an acceptable method for
implementing the requirements
contained in Order EA–12–049.
Licensees would be able to voluntarily
use the guidance in JLD–ISG–2012–01,
Draft Revision 2 to demonstrate
compliance with Order EA–12–049. If
this draft ISG is issued, methods or
solutions that differ from those
described in this draft ISG may be
deemed acceptable if they provide
sufficient basis and information for the
NRC to verify that the proposed
alternative demonstrates compliance
with Order EA–12–049. Issuance of this
ISG would not constitute backfitting as
defined in 10 CFR 50.109, ‘‘Backfitting’’
(the Backfit Rule), and would not
otherwise be inconsistent with the issue
finality provisions in 10 CFR part 52,
‘‘Licenses, Certifications, and Approvals
for Nuclear Power Plants.’’
V. Availability of Documents
The documents identified in the
following table are available to
interested persons through one or more
of the following methods, as indicated.
asabaliauskas on DSK3SPTVN1PROD with NOTICES
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 2.
JLD–ISG–2012–01, Revision 1 (See Previous Entry for JLD–
ISG–2012–01).
JLD–ISG–2012–01, Revision 0 (See Previous Entry for JLD–
ISG–2012–01).
Order EA–12–049, ‘‘Order Modifying Licenses with Regard to
Requirements for Mitigation Strategies for Beyond-DesignBasis External Events’’.
V.C. Summer Nuclear Station, Unit 2 License, License No. NPF–
93.
JLD–ISG–2012–01, Draft Revision 2 ..................
ML16277A617
JLD–ISG–2012–01, Revision 1 ...........................
ML15357A163
JLD–ISG–2012–01, Revision 0 ...........................
ML12229A174
Order EA–12–049 ................................................
ML12054A736
n/a ........................................................................
ML14100A092
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Adams Accession No.
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Federal Register / Vol. 81, No. 218 / Thursday, November 10, 2016 / Notices
Abbreviated title
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).
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) .......
JLD–ISG–2012–01, Draft Revision 0 (See Previous Entry for
JLD–ISG–2012–01).
‘‘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)
NEI 12–06, Revision 0 (See Previous Entry for NEI 12–06) .........
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) .......
JLD–ISG–2012–01, Draft Revision 1 (See Previous Entry for
JLD–ISG–2012–01).
NRC Responses to Public Comments: Revision to Japan Lessons-Learned Division Interim Staff Guidance JLD–ISG–2012–
01.
NEI 12–06, Revision 2 (See Previous Entry for NEI 12–06) .........
Appendix H to NEI 12–06, Draft to Support Public Meeting on
September 8, 2016.
NEI 12–06, Revision 3 (See Previous Entry for NEI 12–06) .........
NRC Non-Concurrence Process document NCP–2016–014 .........
asabaliauskas on DSK3SPTVN1PROD with NOTICES
Document title
n/a ........................................................................
ML14100A101
n/a ........................................................................
SECY–11–0093 ...................................................
ML15084A170
ML11186A950
SECY–11–0124 ...................................................
ML11245A158
SECY–11–0137 ...................................................
ML11272A111
SRM–SECY–11–0093 .........................................
ML112310021
SRM–SECY–11–0124 .........................................
ML112911571
SRM–SECY–11–0137 .........................................
ML113490055
n/a ........................................................................
ML11353A008
SECY–12–0025 ...................................................
ML12039A103
SRM–SECY–12–0025 .........................................
ML120690347
50.54(f) Letter ......................................................
ML12053A340
NEI 12–06, Revision B ........................................
ML12144A419
NEI 12–06, Revision B1 ......................................
JLD–ISG–2012–01, Draft Revision 0 ..................
ML12143A232
ML12146A014
n/a ........................................................................
ML12229A253
NEI 12–06, Revision C ........................................
NEI 12–06, Draft Revision 0 ...............................
NEI 12–06, Revision 0 ........................................
n/a ........................................................................
COMSECY–14–0037 ...........................................
ML121910390
ML12221A204
ML12242A378
ML13064A300
ML14238A616
SRM–COMSECY–14–0037 .................................
NEI 12–06, Revision 1 ........................................
NEI 12–06, Revision 1A ......................................
JLD–ISG–2012–01, Draft Revision 1 ..................
ML15089A236
ML15244B006
ML15279A426
ML15294A078
n/a ........................................................................
ML15357A147
NEI 12–06, Revision 2 ........................................
n/a ........................................................................
ML16005A625
ML16251A251
NEI 12–06, Revision 3 ........................................
NCP–2016–014 ...................................................
ML16267A274
ML16295A104
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).
VerDate Sep<11>2014
17:46 Nov 09, 2016
Jkt 241001
Dated at Rockville, Maryland, this 4th day
of November, 2016.
For the Nuclear Regulatory Commission.
Michael X. Franovich,
Acting Director, Japan Lessons-Learned
Division, Office of Nuclear Reactor
Regulation.
[FR Doc. 2016–27169 Filed 11–9–16; 8:45 am]
Adams Accession No.
NUCLEAR REGULATORY
COMMISSION
[NRC–2015–0281]
Information Collection: NRC Forms 540
and 540A, Uniform Low-Level
Radioactive Waste Manifest (Shipping
Paper) and Continuation Page
BILLING CODE 7590–01–P
PO 00000
Nuclear Regulatory
Commission.
ACTION: Notice of submission to the
Office of Management and Budget;
request for comment.
AGENCY:
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]]>Agencies
[Federal Register Volume 81, Number 218 (Thursday, November 10, 2016)]
[Notices]
[Pages 79056-79060]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-27169]
-----------------------------------------------------------------------
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.
-----------------------------------------------------------------------
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 2,
``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 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.
DATES: Submit comments by December 12, 2016. Comments received after
this
[[Page 79057]]
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.
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. In
addition, for the convenience of the reader, the ADAMS accession
numbers are provided in a table in Section IV of this notice entitled,
Availability of Documents.
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 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
and JLD-ISG-2012-01 Revision 1 on January 22, 2016. The NRC staff
developed JLD-ISG-2012-01 Draft Revision 2 to provide further guidance
and clarification primarily to assist nuclear power reactor applicants
and licensees when assessing the results of seismic hazard
reevaluations with respect to the guidance and strategies required by
Order EA-12-049. JLD-ISG-2012-01 provides 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 No. NPF-93, Condition 2.D.(13), V.C. Summer
Nuclear Station, Unit 3, License No. NPF-94, Condition 2.D.(13), and
Enrico Fermi Nuclear Plant, Unit 3, 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 March 11, 2011, accident at the Fukushima Dai-ichi
nuclear power plant, the NRC established a senior-level agency task
force referred to as the Near-Term Task Force (NTTF). The NTTF
conducted a systematic and methodical review of the NRC regulations and
processes to determine whether the agency should make additional
improvements in NRC regulations or processes 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 staff requirements memorandum (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 the Nuclear Energy Institute's
(NEI) letter, dated December 16, 2011. The FLEX is proposed as a
strategy to fulfill the key safety functions of core cooling,
containment integrity, and spent fuel cooling. Stakeholder input led
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
[[Page 79058]]
parallel, issued as a Request for Information under Title 10 of the
Code of Federal Regulations (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 NEI 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 Order EA-12-049.
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) on June 7, 2012 (77 FR
33779), with the comment period running through July 7, 2012, 30 days
after 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 JLD-ISG-2012-01, Revision 0. On August 3, 2012, NEI
submitted NEI 12-06, Draft Revision 0, incorporating many of the
remaining exceptions and clarifications. On August 21, 2012, NEI
submitted NEI 12-06, Revision 0, 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 Order EA-12-049 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 bases changes.'' (See, e.g.,
Vermont Yankee Nuclear Power Station's OIP)
In order to clarify the relationship between Order EA-12-049 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.
On October 30, 2015, the NRC staff issued a draft version of JLD-
ISG-2012-01, Revision 1, and published a notice of its availability for
public comment in the FR on November 10, 2015 (80 FR 69702), with the
comment period running through December 10, 2015, 30 days from its
publication. The staff received four 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 December 10, 2015, NEI submitted Revision 2 to NEI 12-06,
incorporating many of the exceptions and clarifications included in the
draft version of JLD-ISG-2012-01, Revision 1. The NRC reviewed Revision
2 to NEI 12-06 and endorsed it as a process the NRC considers
acceptable for meeting the regulatory requirements with noted
clarifications in JLD-ISG-2012-01, Revision 1.
On September 7, 2016, NEI submitted a draft revision of Appendix H
to NEI 12-06 to support a public meeting held on September 8, 2016,
incorporating additional guidance for licensees when addressing the
reevaluated seismic hazards for compliance with Order EA-12-049.
Specifically, Section H.4.5 (``Path 5'') is intended to address
Mitigation Strategies Assessments for plants with reevaluated seismic
hazard information that includes a ground motion response spectrum that
has spectral ordinates more than 2 times the Safe Shutdown Earthquake
anywhere in the 1 to 10 hertz frequency range. Such guidance includes
deterministic and risk-informed approaches that can be used to assess
the impact of the reevaluated hazard information on mitigation
strategies. Following the public meeting held on September 8, 2016, NEI
submitted Revision 3 to NEI 12-06 on September 22, 2016. NEI 12-06,
Revision 3 also addresses certain lessons learned in the implementation
of Order EA-12-049.
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:
1. In NEI 12-06, Revision 3, Section 11.5.4.f, NEI proposes to
modify the time limits for initiation of actions to restore a site's
capability to mitigate a beyond-design-basis external event and
implementation of compensatory
[[Page 79059]]
measures. Section 11.5.4.f of NEI 12-06, Revision 0 and Revision 2,
states these time limits as 24 hours to initiate actions and 72 hours
to implement compensatory measures. In NEI 12-06, Revision 3, Section
11.5.4.f, these time limits are extended to 72 hours for initiation of
actions and 7 days for implementation of compensatory measures. The
former time limits were previously endorsed as an element of an
acceptable method of meeting the Order EA-12-049 requirements for
maintaining the strategies and guidelines to mitigate a beyond-design-
basis external event in JLD-ISG-2012-01, Revision 0 and Revision 1. The
NRC staff seeks input on potential justifications for this extension of
the allowable outage times for a licensee's capability to mitigate a
beyond-design-basis external event. Input is specifically requested on
the potential benefits of extending these time limits, operating
experience on time frames actually necessary to implement compensatory
measures for the unavailability of similar equipment, and any potential
unintended consequences of extending these time limits.
2. In JLD-ISG-2012-01, Revision 1, the NRC staff endorsed the NEI
12-06, Revision 2, Section 11.5.4.b 45-day time limit for having an
available but unprotected set of equipment as part of the site's
capability to mitigate a beyond-design-basis external event. The 45-day
time limit aligned with the standard 6-week short work cycle period and
allowed sufficient time for the pre-staging of one set of equipment in
a location that is not entirely protected from all external hazards for
the purpose of shutdown risk management during outages, which typically
have durations less than 45 days. In NEI 12-06, Revision 3, Section
11.5.4.g, this time period is reduced to 14 days, which could conflict
with the pre-staging of equipment for risk management during outages.
The NRC staff seeks input on appropriate methods of control of pre-
staging of equipment for shutdown risk management.
3. In NEI 12-06, Revision 3, Sections H.4.5.3, H.4.5.4, and
H.4.5.5, NEI proposes to allow the use of risk insights from the
seismic probabilistic risk assessments (SPRAs), being completed by some
licensees in response to the NRC's March 12, 2012, 10 CFR 50.54(f)
letter, to assess the mitigating strategies developed in response to
Order EA-12-049 against the reevaluated seismic hazard information. The
purpose of these mitigating strategies assessments is to determine if
changes to the mitigating strategies are needed to account for the
reevaluated seismic hazard. The NRC staff seeks input on specific
aspects of NEI's proposals in light of issues discussed in NCP-2016-
014, a non-concurrence submitted by two NRC staff members regarding
certain aspects of NEI 12-06, Revision 3. First, NCP-2016-014 raised
concerns associated with NEI's proposed use of risk screening criteria.
For example, in Section H.4.5.3, NEI proposes to establish screening
criteria based on the overall seismic core damage frequency and seismic
large early release frequency identified through the SPRA. If these
screening criteria are met, licensees' FLEX mitigating strategies or
alternate mitigating strategies would be considered sufficient to
address the effects of the reevaluated seismic hazard information
without the need for modification. The NRC staff seeks input on the
appropriateness of the approach proposed by NEI in light of the
concerns raised by NCP-2016-014. Second, in Sections H.4.5.4 and
H.4.5.5, NEI describes proposed iterative processes that evaluate the
benefit of enhancing the seismic capacity of certain mitigating
strategies structures, systems, and components (SSCs). As part of these
processes, licensees would enhance such SSCs until the risk benefit of
further enhancements is sufficiently small based on criteria
established in each section. In Section H.4.5.4 the approach focuses on
the benefit in terms of reduction in overall seismic core damage
frequency and seismic large early release frequency. The approach
described in Section H.4.5.5 focuses on the benefit in terms of
reduction in risk from sequences in the SPRAs involving mitigating
strategies SSCs. The NRC staff seeks input on these approaches in light
of the concerns raised by NCP-2016-014 regarding the use of risk-based
screening values and risk partitioning. Finally, NCP-2016-014
identified two alternate approaches that could be used to conduct
seismic mitigating strategies assessments. The NRC staff seeks input on
these approaches and whether they represent more appropriate
alternatives to the approaches described in NEI 12-06, Revision 3.
IV. Backfitting and Issue Finality
This draft ISG would provide guidance on an acceptable method for
implementing the requirements contained in Order EA-12-049. Licensees
would be able to voluntarily use the guidance in JLD-ISG-2012-01, Draft
Revision 2 to demonstrate compliance with Order EA-12-049. If this
draft ISG is issued, methods or solutions that differ from those
described in this draft ISG may be deemed acceptable if they provide
sufficient basis and information for the NRC to verify that the
proposed alternative demonstrates compliance with Order EA-12-049.
Issuance of this ISG would not constitute backfitting as defined in 10
CFR 50.109, ``Backfitting'' (the Backfit Rule), and would not otherwise
be inconsistent with the issue finality provisions in 10 CFR part 52,
``Licenses, Certifications, and Approvals for Nuclear Power Plants.''
V. Availability of Documents
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 with Order JLD-ISG-2012-01, Draft ML16277A617
EA-12-049, Order Modifying Licenses Revision 2.
with Regard to Requirements for
Mitigation Strategies for Beyond-Design-
Basis External Events,'' Draft Revision
2.
JLD-ISG-2012-01, Revision 1 (See JLD-ISG-2012-01, Revision ML15357A163
Previous Entry for JLD-ISG-2012-01). 1.
JLD-ISG-2012-01, Revision 0 (See JLD-ISG-2012-01, Revision ML12229A174
Previous Entry for JLD-ISG-2012-01). 0.
Order EA-12-049, ``Order Modifying Order EA-12-049........... ML12054A736
Licenses with Regard to Requirements
for Mitigation Strategies for Beyond-
Design-Basis External Events''.
V.C. Summer Nuclear Station, Unit 2 n/a....................... ML14100A092
License, License No. NPF-93.
[[Page 79060]]
V.C. Summer Nuclear Station, Unit 3 n/a....................... ML14100A101
License, License No. NPF-94.
Enrico Fermi Nuclear Plant, Unit 3 n/a....................... ML15084A170
License, License No. NPF-95.
SECY-11-0093, ``Near-Term Report and SECY-11-0093.............. ML11186A950
Recommendations for Agency Actions
Following the Events in Japan''.
SECY-11-0124, ``Recommended Actions to SECY-11-0124.............. ML11245A158
be Taken without Delay from the Near-
Term Task Force Report''.
SECY-11-0137, ``Prioritization of SECY-11-0137.............. ML11272A111
Recommended Actions to be Taken in
Response to Fukushima Lessons Learned''.
Commission's staff requirements SRM-SECY-11-0093.......... ML112310021
memorandum (SRM) for
SECY[dash]11[dash]0093.
SRM for SECY-11-0124 (see entry to SECY- SRM-SECY-11-0124.......... ML112911571
11-0124 for full title).
SRM for SECY-11-0137 (see entry to SECY- SRM-SECY-11-0137.......... ML113490055
11-0124 for full title).
NEI Letter Titled, ``An Integrated, n/a....................... ML11353A008
Safety-Focused Approach to Expediting
Implementation of Fukushima Daiichi
Lessons Learned''.
SECY-12-0025, ``Proposed Orders and SECY-12-0025.............. ML12039A103
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- SRM-SECY-12-0025.......... ML120690347
12-0025 for full title).
Request for Information Pursuant to 50.54(f) Letter........... ML12053A340
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 NEI 12-06, Revision B..... ML12144A419
Strategies (FLEX) Implementation
Guide,'' Revision B.
NEI 12-06, Revision B1 (See Previous NEI 12-06, Revision B1.... ML12143A232
Entry for NEI 12-06).
JLD-ISG-2012-01, Draft Revision 0 (See JLD-ISG-2012-01, Draft ML12146A014
Previous Entry for JLD-ISG-2012-01). Revision 0.
``NRC Response to Public Comments, JLD- n/a....................... ML12229A253
ISG-2012-01 (Docket ID NRC-2012-0068)''.
NEI 12-06, Revision C (See Previous NEI 12-06, Revision C..... ML121910390
Entry for NEI 12-06).
NEI 12-06, Draft Revision 0 (See NEI 12-06, Draft Revision ML12221A204
Previous Entry for NEI 12-06). 0.
NEI 12-06, Revision 0 (See Previous NEI 12-06, Revision 0..... ML12242A378
Entry for NEI 12-06).
Vermont Yankee Nuclear Power Station's n/a....................... ML13064A300
Overall Integrate Plan.
COMSECY-14-0037, ``Integration of COMSECY-14-0037........... ML14238A616
Mitigating Strategies for Beyond-Design-
Basis External Events and the
Reevaluation (sic) of Flooding
Hazards''.
SRM-COMSECY-14-0037..................... SRM-COMSECY-14-0037....... ML15089A236
NEI 12-06, Revision 1 (See Previous NEI 12-06, Revision 1..... ML15244B006
Entry for NEI 12-06).
NEI 12-06, Revision 1A (See Previous NEI 12-06, Revision 1A.... ML15279A426
Entry for NEI 12-06).
JLD-ISG-2012-01, Draft Revision 1 (See JLD-ISG-2012-01, Draft ML15294A078
Previous Entry for JLD-ISG-2012-01). Revision 1.
NRC Responses to Public Comments: n/a....................... ML15357A147
Revision to Japan Lessons-Learned
Division Interim Staff Guidance JLD-ISG-
2012-01.
NEI 12-06, Revision 2 (See Previous NEI 12-06, Revision 2..... ML16005A625
Entry for NEI 12-06).
Appendix H to NEI 12-06, Draft to n/a....................... ML16251A251
Support Public Meeting on September 8,
2016.
NEI 12-06, Revision 3 (See Previous NEI 12-06, Revision 3..... ML16267A274
Entry for NEI 12-06).
NRC Non-Concurrence Process document NCP- NCP-2016-014.............. ML16295A104
2016-014.
----------------------------------------------------------------------------------------------------------------
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).
Dated at Rockville, Maryland, this 4th day of November, 2016.
For the Nuclear Regulatory Commission.
Michael X. Franovich,
Acting Director, Japan Lessons-Learned Division, Office of Nuclear
Reactor Regulation.
[FR Doc. 2016-27169 Filed 11-9-16; 8:45 am]
BILLING CODE 7590-01-P
