Proposed Revisions to Conduct of Operations, 21269-21270 [2017-09068]
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Federal Register / Vol. 82, No. 86 / Friday, May 5, 2017 / Notices
information related to this document
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0239. 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.
• 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
ADAMS accession number for each
document referenced in this document
(if that document is available in
ADAMS) is provided the first time that
a document is referenced.
• 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.
FOR FURTHER INFORMATION CONTACT:
April Pulvirenti, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
1390, email: April.Pulvirenti@nrc.gov.
SUPPLEMENTARY INFORMATION: The NRC
has granted the request of Entergy to
withdraw its September 1, 2016,
application (ADAMS accession no.
ML16245A359) for a proposed
amendment to Facility Operating
License No. NPF–38 for Waterford 3,
located in St. Charles Parish, Louisiana.
The amendment would have revised
the Waterford 3 TSs to relocate the
surveillance frequency requirements for
selected ESFAS Subgroup relays to a
licensee-controlled program.
Specifically, the license amendment
would have revised the Table Notation
for TS Table 4.3–2, ‘‘Engineered Safety
Features Actuation System
Instrumentation Surveillance
Requirements,’’ to relocate the
surveillance frequency of additional
relays to the Waterford 3 SFCP. The
Commission previously published a
proposed finding in the Federal
Register on November 22, 2016 (81 FR
83875), that the amendment involves no
significant hazards consideration. In
VerDate Sep<11>2014
17:43 May 04, 2017
Jkt 241001
addition, the licensee has supplemented
the application with a response to a
Request for Additional Information
dated January 26, 2017 (ADAMS
accession no. ML17039A909), and a
second supplement dated February 27,
2017 (ADAMS accession no.
ML17058A460). By letter dated March
22, 2017 (ADAMS accession no.
ML17082A459), the licensee requested
to withdraw the proposed amendment.
Dated at Rockville, Maryland, this 25th day
of April, 2017.
For the Nuclear Regulatory Commission.
April L Pulvirenti,
Project Manager, Plant Licensing Branch 4,
Division of Operator Reactor Licensing, Office
of Nuclear Reactor Regulation.
[FR Doc. 2017–09154 Filed 5–4–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2017–0111]
Proposed Revisions to Conduct of
Operations
Nuclear Regulatory
Commission.
ACTION: Standard Review Plan—draft
section revision; request for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is soliciting public
comment on draft NUREG–0800,
‘‘Standard Review Plan for the Review
of Safety Analysis Reports for Nuclear
Power Plants: LWR Edition,’’ Section
13.6.1, ‘‘Physical Security—Combined
License and Operating Reactors.’’ The
NRC seeks comments on the proposed
draft section revision of the Standard
Review Plan (SRP) concerning guidance
for the review of combined construction
and operating license (COL) and
operating license (OL) applications and
amendments for physical security.
DATES: Comments must be filed no later
than July 5, 2017. 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 on or before this date.
ADDRESSES: You may submit comments
by any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0111. 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.
SUMMARY:
PO 00000
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21269
• Mail comments to: Cindy Bladey,
Office of Administration, Mail Stop:
TWFN–08–D36, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
For additional direction on accessing
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
FOR FURTHER INFORMATION CONTACT:
Mark D. Notich, Office of New Reactors,
telephone: 301–415–3053; email
Mark.Notich@nrc.gov; U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2017–
0111 when contacting the NRC about
the availability of information regarding
this action. You may obtain publiclyavailable information related to this
document by any of the following
methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0111.
• 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 draft revision and current
revision to NUREG–0800, Section
13.6.1, ‘‘Physical Security—Combined
License and Operating Reactors,’’ are
available in ADAMS under Accession
Nos. ML17101A741 and ML102230082.
The redline strikeout comparing the
current version and draft revision is
available in ADAMS under Accession
No. ML 14295A061.
• 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–2017–
0111 in your comment submission.
The NRC cautions you not to include
identifying or contact information that
you do not want to be publicly
E:\FR\FM\05MYN1.SGM
05MYN1
21270
Federal Register / Vol. 82, No. 86 / Friday, May 5, 2017 / Notices
disclosed in your comment submission.
The NRC will post all comment
submissions at https://
www.regulations.gov as well as enter 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 into ADAMS.
SRADOVICH on DSK3GMQ082PROD with NOTICES
II. Further Information
The NRC seeks public comment on
the proposed draft section revision of
SRP Section 13.6.1. The changes to SRP
Chapter 13 reflect the current staff
reviews, methods and practices based
on lessons learned from the NRC’s
reviews of design certification and
combined license applications
completed since the last revision of this
chapter. The draft SRP section would
also provide guidance for reviewing an
application for a combined license
under part 52 of title 10 of the Code of
Federal Regulations (10 CFR).
Following NRC staff evaluation of
public comments, the NRC intends to
incorporate the approved revisions into
the next revision of NUREG–0800. The
SRP is guidance for the NRC staff. The
SRP is not a substitute for the NRC
regulations, and compliance with the
SRP is not required.
III. Backfitting and Issue Finality
Issuance of this draft SRP section, if
finalized, would not constitute
backfitting as defined in 10 CFR 50.109
of 10 CFR, (the Backfit Rule) or
otherwise be inconsistent with the issue
finality provisions in 10 CFR part 52.
The NRC’s position is based upon the
following considerations.
1. The draft SRP positions, if
finalized, would not constitute
backfitting, inasmuch as the SRP is
internal guidance to NRC staff directed
at the NRC staff with respect to their
regulatory responsibilities.
The SRP provides guidance to the
NRC staff on how to review an
application for NRC regulatory approval
in the form of licensing. Changes in
internal staff guidance are not matters
for which either nuclear power plant
applicants or licensees are protected
under either the Backfit Rule or the
VerDate Sep<11>2014
17:43 May 04, 2017
Jkt 241001
issue finality provisions of 10 CFR part
52.
2. The NRC staff has no intentions to
impose the SRP positions on current
licensees or already-issued regulatory
approvals either now or in the future.
The NRC staff does not intend to
impose or apply the positions described
in the draft SRP to existing (already
issued) licenses and regulatory
approvals. Hence, the issuance of a final
SRP—even if considered guidance
which is within the purview of the issue
finality provisions in 10 CFR part 52—
need not be evaluated as if it were a
backfit or as being inconsistent with
issue finality provisions. If, in the
future, the NRC staff seeks to impose a
position in the SRP on holders of
already issued licenses in a manner
which does not provide issue finality as
described in the applicable issue finality
provision, then the NRC staff must make
the showing as set forth in the Backfit
Rule or address the criteria for avoiding
issue finality as described in the
applicable issue finality provision.
3. Backfitting and issue finality do
not—with limited exceptions not
applicable here—protect current or
future applicants.
Applicants and potential applicants
are not, with certain exceptions,
protected by either the Backfit Rule or
any issue finality provisions under 10
CFR part 52. This is because neither the
Backfit Rule nor the issue finality
provisions under 10 CFR part 52—with
certain exclusions discussed below—
were intended to apply to every NRC
action which substantially changes the
expectations of current and future
applicants.
The exceptions to the general
principle are applicable whenever an
applicant references a 10 CFR part 52
license (e.g., an early site permit) and/
or NRC regulatory approval (e.g., a
design certification rule) with specified
issue finality provisions. The NRC staff
does not, at this time, intend to impose
the positions represented in the draft
SRP in a manner that is inconsistent
with any issue finality provisions. If, in
the future, the NRC staff seeks to impose
a position in the draft SRP in a manner
which does not provide issue finality as
described in the applicable issue finality
provisions, then the NRC staff must
address the criteria for avoiding issue
finality provisions.
Dated at Rockville, Maryland, this 1st day
of May, 2017.
PO 00000
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Fmt 4703
Sfmt 4703
For the Nuclear Regulatory Commission.
Joseph Colaccino,
Chief, New Reactor Rulemaking and
Guidance Branch, Division of Engineering
and Infrastructure, Office of New Reactors.
[FR Doc. 2017–09068 Filed 5–4–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–11; NRC–2017–0110]
Sacramento Municipal Utility District;
Rancho Seco Independent Spent Fuel
Storage Installation
Nuclear Regulatory
Commission.
ACTION: License amendment application;
opportunity to request a hearing and to
petition for leave to intervene.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) has received a
request from Sacramento Municipal
Utility District (SMUD) to amend the
license for the Rancho Seco
Independent Spent Fuel Storage
Installation (ISFSI) to allow the storage
of byproduct nuclear material. The
amendment would allow SMUD to use
the byproduct nuclear material to check
the functionality of radiation detection
instruments. The NRC is evaluating
whether approval of this request would
be categorically excluded from the
requirement to prepare an
environmental assessment.
DATES: A request for a hearing or
petition for leave to intervene must be
filed by July 5, 2017.
ADDRESSES: Please refer to Docket ID
NRC–2017–0110 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0110. 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.
• 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
SUMMARY:
E:\FR\FM\05MYN1.SGM
05MYN1
Agencies
[Federal Register Volume 82, Number 86 (Friday, May 5, 2017)]
[Notices]
[Pages 21269-21270]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-09068]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2017-0111]
Proposed Revisions to Conduct of Operations
AGENCY: Nuclear Regulatory Commission.
ACTION: Standard Review Plan--draft section revision; request for
comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting
public comment on draft NUREG-0800, ``Standard Review Plan for the
Review of Safety Analysis Reports for Nuclear Power Plants: LWR
Edition,'' Section 13.6.1, ``Physical Security--Combined License and
Operating Reactors.'' The NRC seeks comments on the proposed draft
section revision of the Standard Review Plan (SRP) concerning guidance
for the review of combined construction and operating license (COL) and
operating license (OL) applications and amendments for physical
security.
DATES: Comments must be filed no later than July 5, 2017. 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 on or before this date.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0111. 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: TWFN-08-D36, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
For additional direction on accessing information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Mark D. Notich, Office of New
Reactors, telephone: 301-415-3053; email Mark.Notich@nrc.gov; U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2017-0111 when contacting the NRC
about the availability of information regarding this action. You may
obtain publicly-available information related to this document by any
of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0111.
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
draft revision and current revision to NUREG-0800, Section 13.6.1,
``Physical Security--Combined License and Operating Reactors,'' are
available in ADAMS under Accession Nos. ML17101A741 and ML102230082.
The redline strikeout comparing the current version and draft revision
is available in ADAMS under Accession No. ML 14295A061.
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-2017-0111 in your comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly
[[Page 21270]]
disclosed in your comment submission. The NRC will post all comment
submissions at https://www.regulations.gov as well as enter 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 into ADAMS.
II. Further Information
The NRC seeks public comment on the proposed draft section revision
of SRP Section 13.6.1. The changes to SRP Chapter 13 reflect the
current staff reviews, methods and practices based on lessons learned
from the NRC's reviews of design certification and combined license
applications completed since the last revision of this chapter. The
draft SRP section would also provide guidance for reviewing an
application for a combined license under part 52 of title 10 of the
Code of Federal Regulations (10 CFR).
Following NRC staff evaluation of public comments, the NRC intends
to incorporate the approved revisions into the next revision of NUREG-
0800. The SRP is guidance for the NRC staff. The SRP is not a
substitute for the NRC regulations, and compliance with the SRP is not
required.
III. Backfitting and Issue Finality
Issuance of this draft SRP section, if finalized, would not
constitute backfitting as defined in 10 CFR 50.109 of 10 CFR, (the
Backfit Rule) or otherwise be inconsistent with the issue finality
provisions in 10 CFR part 52. The NRC's position is based upon the
following considerations.
1. The draft SRP positions, if finalized, would not constitute
backfitting, inasmuch as the SRP is internal guidance to NRC staff
directed at the NRC staff with respect to their regulatory
responsibilities.
The SRP provides guidance to the NRC staff on how to review an
application for NRC regulatory approval in the form of licensing.
Changes in internal staff guidance are not matters for which either
nuclear power plant applicants or licensees are protected under either
the Backfit Rule or the issue finality provisions of 10 CFR part 52.
2. The NRC staff has no intentions to impose the SRP positions on
current licensees or already-issued regulatory approvals either now or
in the future.
The NRC staff does not intend to impose or apply the positions
described in the draft SRP to existing (already issued) licenses and
regulatory approvals. Hence, the issuance of a final SRP--even if
considered guidance which is within the purview of the issue finality
provisions in 10 CFR part 52--need not be evaluated as if it were a
backfit or as being inconsistent with issue finality provisions. If, in
the future, the NRC staff seeks to impose a position in the SRP on
holders of already issued licenses in a manner which does not provide
issue finality as described in the applicable issue finality provision,
then the NRC staff must make the showing as set forth in the Backfit
Rule or address the criteria for avoiding issue finality as described
in the applicable issue finality provision.
3. Backfitting and issue finality do not--with limited exceptions
not applicable here--protect current or future applicants.
Applicants and potential applicants are not, with certain
exceptions, protected by either the Backfit Rule or any issue finality
provisions under 10 CFR part 52. This is because neither the Backfit
Rule nor the issue finality provisions under 10 CFR part 52--with
certain exclusions discussed below--were intended to apply to every NRC
action which substantially changes the expectations of current and
future applicants.
The exceptions to the general principle are applicable whenever an
applicant references a 10 CFR part 52 license (e.g., an early site
permit) and/or NRC regulatory approval (e.g., a design certification
rule) with specified issue finality provisions. The NRC staff does not,
at this time, intend to impose the positions represented in the draft
SRP in a manner that is inconsistent with any issue finality
provisions. If, in the future, the NRC staff seeks to impose a position
in the draft SRP in a manner which does not provide issue finality as
described in the applicable issue finality provisions, then the NRC
staff must address the criteria for avoiding issue finality provisions.
Dated at Rockville, Maryland, this 1st day of May, 2017.
For the Nuclear Regulatory Commission.
Joseph Colaccino,
Chief, New Reactor Rulemaking and Guidance Branch, Division of
Engineering and Infrastructure, Office of New Reactors.
[FR Doc. 2017-09068 Filed 5-4-17; 8:45 am]
BILLING CODE 7590-01-P