Safety Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments), 16897-16898 [2019-08093]
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Federal Register / Vol. 84, No. 78 / Tuesday, April 23, 2019 / Notices
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Renewed Facility Operating License
No. NPF–86: The amendment revised
the Renewed Facility Operating License
and Technical Specifications.
Date of initial notice in Federal
Register: July 3, 2018 (83 FR 31186).
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated March 29, 2019.
No significant hazards consideration
comments received: No.
PSEG Nuclear LLC, Docket No. 50–
354, Hope Creek Generating Station,
Salem County, New Jersey
Date of amendment request: April 13,
2018, as supplemented by two letters
dated October 17, 2018.
Brief description of amendment: The
amendment revised Hope Creek
Generating Station Technical
Specification 3.8.3.1, ‘‘Distribution—
Operating,’’ to increase the alternating
current inverters allowed outage time
from 24 hours to 7 days. The change
was based on application of the Hope
Creek Generating Station probabilistic
risk assessment in support of a riskinformed extension and on additional
considerations and compensatory
actions.
Date of issuance: March 27, 2019.
Effective date: As of the date of
issuance and shall be implemented
within 60 days of the date of issuance.
Amendment No.: 215. A publiclyavailable version is in ADAMS under
Accession No. ML19065A156;
documents related to this amendment
are listed in the Safety Evaluation
enclosed with the amendment.
Renewed Facility Operating License
No. NPF–57: The amendment revised
the Renewed Facility Operating License
and Technical Specifications.
Date of initial notice in Federal
Register: June 19, 2018 (83 FR 28462).
Two supplemental letters dated October
17, 2018, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the NRC staff’s
original proposed no significant hazards
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated March 27, 2019.
No significant hazards consideration
comments received: No.
Tennessee Valley Authority, Docket
Nos. 50–259, 50–260, and 50–296,
Browns Ferry Nuclear Plant, Units 1, 2,
and 3, Limestone County, Alabama
Date of amendment request: October
18, 2018, as supplemented by letters
dated February 13, 2019, and March 8,
2019.
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17:49 Apr 22, 2019
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Brief description of amendments: The
amendments revised the Renewed
Facility Operating Licenses by changing
license conditions associated with the
fire protection program controlled by 10
CFR 50.48(c), ‘‘National Fire Protection
Association Standard NFPA 805.’’ The
amended license conditions incorporate
changes made to Table S–2, ‘‘Plant
Modifications Committed,’’ in
Tennessee Valley Authority letter dated
October 18, 2018, as supplemented by
letters dated February 13, 2019, and
March 8, 2019, which describes
modifications necessary to transition
into full compliance with 10 CFR
50.48(c).
Date of issuance: April 2, 2019.
Effective date: As of the date of
issuance and shall be implemented
immediately.
Amendment Nos.: 307 (Unit 1), 330,
(Unit 2), and 290 (Unit 3). A publiclyavailable version is in ADAMS under
Accession No. ML19037A137;
documents related to these amendments
are listed in the Safety Evaluation
enclosed with the amendments.
Renewed Facility Operating License
Nos. DPR–33, DPR–52, and DPR–68: The
amendments revised the Renewed
Facility Operating Licenses.
Date of initial notice in Federal
Register: December 18, 2018 (83 FR
64897). The supplemental letters dated
February 13, 2019, and March 8, 2019,
provided additional information that
clarified the application, did not expand
the scope of the application as originally
noticed, and did not change the NRC
staff’s original proposed no significant
hazards consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated April 2, 2019.
No significant hazards consideration
comments received: No.
Wolf Creek Nuclear Operating
Corporation, Docket No. 50–482, Wolf
Creek Generating Station, Unit 1, Coffey
County, Kansas
Date of amendment request: May 9,
2018, as supplemented by letter dated
November 19, 2018.
Brief description of amendment: The
amendment revised the Wolf Creek
Generating Station Radiological
Emergency Response Plan to (1) reduce
the number of required emergency
response organization positions, (2)
standardize activation times for the
technical support center to 75 minutes,
(3) replace the current full-time normal
work hours licensed medical
practitioner position with on-shift first
aid responders, and (4) remove
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16897
reference to performing dose assessment
using containment pressure indication.
Date of issuance: April 1, 2019.
Effective date: As of the date of
issuance and shall be implemented
within 180 days from the date of
issuance.
Amendment No.: 220. A publiclyavailable version is in ADAMS under
Accession No. ML19052A546;
documents related to this amendment
are listed in the Safety Evaluation
enclosed with the amendment.
Renewed Facility Operating License
No. NPF–42. The amendment revised
the Wolf Creek Generating Station
Radiological Emergency Response Plan.
Date of initial notice in Federal
Register: July 3, 2018 (83 FR 31187).
The supplemental letter dated
November 19, 2018, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the NRC staff’s
original proposed no significant hazards
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated April 1, 2019.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 16th day
of April, 2019
For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating
Reactor Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2019–07933 Filed 4–22–19; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2019–0100]
Safety Related Concrete Structures for
Nuclear Power Plants (Other Than
Reactor Vessels and Containments)
Nuclear Regulatory
Commission.
ACTION: Draft regulatory guide; request
for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment draft regulatory guide (DG),
DG–1283, ‘‘Safety Related Structures for
Nuclear Power Plants (Other than
Reactor Vessels and Containments).’’
This proposed guide, revision 3, of RG
1.142, of the same name, was revised to
endorse an updated version of American
Concrete Institute code (ACI) 349–2013,
‘‘Code Requirements for Nuclear Safety-
SUMMARY:
E:\FR\FM\23APN1.SGM
23APN1
16898
Federal Register / Vol. 84, No. 78 / Tuesday, April 23, 2019 / Notices
Related Concrete Structures and
Commentary.’’
Submit comments by June 24,
2019. Comments received after this date
will be considered if it is practical to do
so, but the NRC is able to ensure
consideration only for comments
received on or before this date.
Although a time limit is given,
comments and suggestions in
connection with items for inclusion in
guides currently being developed or
improvements in all published guides
are encouraged at any time.
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 Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2019–0100. Address
questions about NRC dockets IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
Jennifer.Borges@nrc.gov. For technical
questions, contact the individual(s)
listed in the FOR FURTHER INFORMATION
CONTACT section of this document.
• Mail comments to: Office of
Administration, Mail Stop: TWFN–7–
A60M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, ATTN: Program Management,
Announcements and Editing Staff.
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:
Madhumita Sircar, telephone: 301–415–
1804; email: Madhumita.Sircar@nrc.gov,
and Edward O’Donnell, telephone: 301–
415–3317; email: Edward.Odonnell@
nrc.gov. Both are staff members of the
Office of Nuclear Regulatory Research,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
DATES:
I. Obtaining Information and
Submitting Comments
jbell on DSK3GLQ082PROD with NOTICES
A. Obtaining Information
Please refer to Docket ID NRC–2019–
0100 when contacting the NRC about
the availability of information regarding
this action. You may obtain publicallyavailable information related to this
action, by any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2019–0100.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publicly
VerDate Sep<11>2014
17:49 Apr 22, 2019
Jkt 247001
available documents online in the
ADAMS Public Document collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘Begin Web-based ADAMS Search.’’ For
problems with ADAMS, 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 DG–1283 is available in
ADAMS under Accession No.
ML16172A240.
• 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–2019–
0100 in your comment submission, in
order to ensure that the NRC is able to
make your comment submission
available to the public in this docket.
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 enters
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. Additional Information
The NRC is issuing for public
comment a DG in the NRC’s ‘‘Regulatory
Guide’’ series. This series was
developed to describe and make
available to the public information
regarding methods that are acceptable to
the NRC staff for implementing specific
parts of the NRC’s regulations,
techniques that the staff uses in
evaluating specific issues or postulated
events, and data that the staff needs in
its review of applications for permits
and licenses.
The DG, entitled, ‘‘Safety Related
Concrete Structures for Nuclear Power
Plants (Other than Reactor Vessels and
Containments),’’ is temporarily
identified by its task number, DG–1283.
PO 00000
Frm 00063
Fmt 4703
Sfmt 4703
DG–1283 is proposed revision 3 of RG
1.142 of the same name. This revision
of the guide (Revision 3) was updated to
endorse, with certain exceptions, ACI
349–13, ‘‘Code Requirements for
Nuclear Safety-Related Concrete
Structures and Commentary,’’ except for
Appendix D, ‘‘Anchoring to Concrete.’’
Appendix D to ACI 349–13 is separately
endorsed by RG 1.199, ‘‘Anchoring
Components and Structural Supports in
Concrete’’.
III. Backfitting and Issue Finality
As discussed in the ‘‘Implementation’’
section of DG–1283, the NRC has no
current intention to impose this draft
regulatory guide on holders of current
operating licenses or combined licenses.
Accordingly, the issuance of this draft
regulatory guide, if finalized, would not
constitute ‘‘backfitting’’ as defined in
section 50.109(a)(1) of title 10 of the
Code of Federal Regulations (10 CFR) of
the Backfit Rule or be otherwise
inconsistent with the applicable issue
finality provisions in 10 CFR part 52.
This draft regulatory guide may be
applied to applications for operating
licenses and combined licenses
docketed by the NRC as of the date of
issuance of the final regulatory guide, as
well as future applications for operating
licenses and combined licenses
submitted after the issuance of the
regulatory guide. Such action would not
constitute backfitting as defined in 10
CFR 50.109(a)(1) or be otherwise
inconsistent with the applicable issue
finality provision in 10 CFR part 52,
inasmuch as such applicants or
potential applicants are not within the
scope of entities protected by the Backfit
Rule or the relevant issue finality
provisions in 10 CFR part 52.
Dated at Rockville, Maryland, this 16th day
of April, 2019.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic
Issues Branch, Division of Engineering, Office
of Nuclear Regulatory Research.
[FR Doc. 2019–08093 Filed 4–22–19; 8:45 am]
BILLING CODE 7590–01–P
RAILROAD RETIREMENT BOARD
Sunshine Act Meetings
TIME AND DATE:
10:00 a.m., April 30,
2019.
844 North Rush Street, Chicago,
Illinois 60611.
STATUS: Closed.
MATTERS TO BE CONSIDERED: (1) Internal
Personnel Matter.
PLACE:
E:\FR\FM\23APN1.SGM
23APN1
Agencies
[Federal Register Volume 84, Number 78 (Tuesday, April 23, 2019)]
[Notices]
[Pages 16897-16898]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-08093]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2019-0100]
Safety Related Concrete Structures for Nuclear Power Plants
(Other Than Reactor Vessels and Containments)
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft regulatory guide; request for comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for
public comment draft regulatory guide (DG), DG-1283, ``Safety Related
Structures for Nuclear Power Plants (Other than Reactor Vessels and
Containments).'' This proposed guide, revision 3, of RG 1.142, of the
same name, was revised to endorse an updated version of American
Concrete Institute code (ACI) 349-2013, ``Code Requirements for Nuclear
Safety-
[[Page 16898]]
Related Concrete Structures and Commentary.''
DATES: Submit comments by June 24, 2019. Comments received after this
date will be considered if it is practical to do so, but the NRC is
able to ensure consideration only for comments received on or before
this date. Although a time limit is given, comments and suggestions in
connection with items for inclusion in guides currently being developed
or improvements in all published guides are encouraged at any time.
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 Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0100. Address
questions about NRC dockets IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this document.
Mail comments to: Office of Administration, Mail Stop:
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
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: Madhumita Sircar, telephone: 301-415-
1804; email: [email protected], and Edward O'Donnell, telephone:
301-415-3317; email: [email protected]. Both are staff members of
the Office of Nuclear Regulatory Research, 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-2019-0100 when contacting the NRC
about the availability of information regarding this action. You may
obtain publically-available information related to this action, by any
of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0100.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the
ADAMS Public Document collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS
Search.'' For problems with ADAMS, contact the NRC's Public Document
Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email
to [email protected]. The DG-1283 is available in ADAMS under
Accession No. ML16172A240.
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-2019-0100 in your comment submission,
in order to ensure that the NRC is able to make your comment submission
available to the public in this docket.
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 enters 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. Additional Information
The NRC is issuing for public comment a DG in the NRC's
``Regulatory Guide'' series. This series was developed to describe and
make available to the public information regarding methods that are
acceptable to the NRC staff for implementing specific parts of the
NRC's regulations, techniques that the staff uses in evaluating
specific issues or postulated events, and data that the staff needs in
its review of applications for permits and licenses.
The DG, entitled, ``Safety Related Concrete Structures for Nuclear
Power Plants (Other than Reactor Vessels and Containments),'' is
temporarily identified by its task number, DG-1283. DG-1283 is proposed
revision 3 of RG 1.142 of the same name. This revision of the guide
(Revision 3) was updated to endorse, with certain exceptions, ACI 349-
13, ``Code Requirements for Nuclear Safety-Related Concrete Structures
and Commentary,'' except for Appendix D, ``Anchoring to Concrete.''
Appendix D to ACI 349-13 is separately endorsed by RG 1.199,
``Anchoring Components and Structural Supports in Concrete''.
III. Backfitting and Issue Finality
As discussed in the ``Implementation'' section of DG-1283, the NRC
has no current intention to impose this draft regulatory guide on
holders of current operating licenses or combined licenses.
Accordingly, the issuance of this draft regulatory guide, if finalized,
would not constitute ``backfitting'' as defined in section 50.109(a)(1)
of title 10 of the Code of Federal Regulations (10 CFR) of the Backfit
Rule or be otherwise inconsistent with the applicable issue finality
provisions in 10 CFR part 52.
This draft regulatory guide may be applied to applications for
operating licenses and combined licenses docketed by the NRC as of the
date of issuance of the final regulatory guide, as well as future
applications for operating licenses and combined licenses submitted
after the issuance of the regulatory guide. Such action would not
constitute backfitting as defined in 10 CFR 50.109(a)(1) or be
otherwise inconsistent with the applicable issue finality provision in
10 CFR part 52, inasmuch as such applicants or potential applicants are
not within the scope of entities protected by the Backfit Rule or the
relevant issue finality provisions in 10 CFR part 52.
Dated at Rockville, Maryland, this 16th day of April, 2019.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2019-08093 Filed 4-22-19; 8:45 am]
BILLING CODE 7590-01-P