[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]
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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 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 http://www.regulations.gov and search for Docket ID NRC-2012-0068. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. 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: [email protected].
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 http://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 http://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 [email protected]. 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 http://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 http://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]
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