Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4 Main Control Room Emergency Habitability System Changes, 24511-24513 [2018-11459]
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Federal Register / Vol. 83, No. 103 / Tuesday, May 29, 2018 / Notices
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 website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2018–0092. Address
questions about NRC dockets to Jennifer
Borges; telephone: 301–287–9127;
email: Jennifer.Borges@nrc.gov. For
technical questions, contact the
individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: May Ma, Office
of Administration, Mail Stop: TWFN 7–
A60M, 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:
Dennis Gordon, Office of Nuclear
Security and Incident Response,
telephone: 301–287–3633, email:
Dennis.Gordon@nrc.gov and Mekonen
Bayssie, Office of Nuclear Regulatory
Research; telephone: 301–415–1699,
email: Mekonen.Bayssie@nrc.gov. Both
are staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
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I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2018–
0092 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–2018–0092.
• 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. DG–5048
is available in ADAMS under Accession
No. ML17124A490.
• NRC’s PDR: You may examine and
purchase copies of public documents at
VerDate Sep<11>2014
16:39 May 25, 2018
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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–2018–
0092 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 will post 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. Background
On May 14, 2018 (83 FR 22297), the
NRC solicited comments on DG–5048,
‘‘Standard Format and Content of
Physical Security Plans, Training and
Qualifications Plans, and Safeguards
Contingency Plans for Nuclear Power
Plants’’ (ADAMS Accession No.
ML17124A490). The public comment
period was originally scheduled to end
on July 13, 2018. On May 14, 2018, the
Nuclear Energy Institute (NEI) requested
that the comment period be extended,
stating that ‘‘the change would allow
NEI and its members’ sufficient time to
perform a thorough review of the
document consistent with other work
priorities’’ (ADAMS Accesion No.
ML18136A546). The NRC agreed to the
request because of the length and
comprehensiveness of this DG.
Accordingly, the NRC is extending the
public comment period on this
document until August 13, 2018, to
allow more time for members of the
public to submit their comments.
Dated at Rockville, Maryland, this 23rd day
of May, 2018.
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. 2018–11460 Filed 5–25–18; 8:45 am]
BILLING CODE 7590–01–P
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24511
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–025 and 52–026; NRC–
2008–0252]
Southern Nuclear Operating Company,
Inc.; Vogtle Electric Generating Plant,
Units 3 and 4 Main Control Room
Emergency Habitability System
Changes
Nuclear Regulatory
Commission.
ACTION: Exemption and combined
license amendment; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) has issued an
exemption to allow a departure from the
certification information of Tier 1 of the
generic design control document and
issued License Amendment Nos. 108
and 107 to Combined License (COL)
Nos. NPF–91 and NPF–92, respectively.
The COLs were issued to Southern
Nuclear Operating Company, Inc., and
Georgia Power Company; Oglethorpe
Power Corporation; MEAG Power
SPVM, LLC; MEAG Power SPVJ, LLC;
MEAG Power SPVP, LLC; and the City
of Dalton, Georgia (the licensee), for
construction and operation of the Vogtle
Electric Generating Plant (VEGP), Units
3 and 4, located in Burke County,
Georgia.
The granting of the exemption allows
the changes to Tier 1 information asked
for in the amendment. Because the
acceptability of the exemption was
determined in part by the acceptability
of the amendment, the exemption and
amendment are being issued
concurrently.
SUMMARY:
The exemption and amendment
were issued on February 1, 2018.
ADDRESSES: Please refer to Docket ID
NRC–2008–0252 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 website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2008–0252. Address
questions about NRC dockets to Jennifer
Borges telephone: 301–287–9127; email:
Jennifer.Borges@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
DATES:
E:\FR\FM\29MYN1.SGM
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24512
Federal Register / Vol. 83, No. 103 / Tuesday, May 29, 2018 / Notices
daltland on DSKBBV9HB2PROD with NOTICES
‘‘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 (if it is available in
ADAMS) is provided the first time that
it is mentioned in this document. The
request for the amendment and
exemption was submitted by letter
dated May 9, 2017 (ADAMS Accession
No. ML17129A608), as supplemented
by letter dated September 15, 2017
(ADAMS Accession No. ML17258B211).
• 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:
Chandu Patel, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–3025; email: Chandu.Patel@
nrc.gov.
SUPPLEMENTARY INFORMATION:
license amendment. The exemption met
all applicable regulatory criteria set
forth in sections 50.12 and 52.7 of 10
CFR, and section VIII.A.4 of appendix D
to 10 CFR part 52. The license
amendment was found to be acceptable
as well. The combined safety evaluation
is available in ADAMS under Accession
No. ML18011A894.
Identical exemption documents
(except for referenced unit numbers and
license numbers) were issued to the
licensee for VEGP, Units 3 and 4 (COL
Nos. NPF–91 and NPF–92). The
exemption documents for VEGP, Units 3
and 4, can be found in ADAMS under
Accession Nos. ML18011A888 and
ML18011A889, respectively. The
exemption is reproduced (with the
exception of abbreviated titles and
additional citations) in Section II of this
document. The amendment documents
for COL Nos. NPF–91 and NPF–92 are
available in ADAMS under Accession
Nos. ML18011A890 and ML18011A891,
respectively. A summary of the
amendment documents is provided in
Section III of this document.
I. Background
The NRC is granting an exemption
from paragraph B of section III, ‘‘Scope
and Contents,’’ of appendix D, ‘‘Design
Certification Rule for the AP1000,’’ to
part 52 of title 10 of the Code of Federal
Regulations (10 CFR), and issuing
License Amendment Nos. 108 and 107
to COL Nos. NPF–91 and NPF–92,
respectively, to the licensee. The
exemption is required by paragraph A.4
of section VIII, ‘‘Processes for Changes
and Departures,’’ appendix D, to 10 CFR
part 52, to allow the licensee to depart
from Tier 1 information. With the
requested amendment, the licensee
sought proposed changes to Updated
Final Safety Analysis Report Tier 2
information and plant-specific Tier 1
information, with corresponding
changes to COL Appendix C.
Specifically, the changes revise the
licensing basis information to reflect
design changes to the main control room
emergency habitability system to
address the main control room envelope
temperature response.
Part of the justification for granting
the exemption was provided by the
review of the amendment. Because the
exemption was necessary in order to
issue the requested license amendment,
the NRC granted the exemption and
issued the amendment concurrently,
rather than in sequence. This included
issuing a combined safety evaluation
containing the NRC staff’s review of
both the exemption request and the
Reproduced below is the exemption
document issued to VEGP, Units 3 and
Unit 4. It makes reference to the
combined safety evaluation that
provides the reasoning for the findings
made by the NRC (and listed under Item
1) in order to grant the exemption:
1. In a letter dated May 9, 2017, as
supplemented by letter dated September
15, 2017, Southern Nuclear Operating
Company requested from the
Commission an exemption to allow
departures from Tier 1 information in
the certified design control document
incorporated by reference in 10 CFR
part 52, appendix D, as part of license
amendment request 17–001, ‘‘Main
Control Room Emergency Habitability
System Changes to Satisfy PostActuation Performance Requirements.’’
For the reasons set forth in Section 3.1
of the NRC staff’s safety evaluation, the
Commission finds that:
A. The exemption is authorized by
law;
B. The exemption presents no undue
risk to public health and safety;
C. The exemption is consistent with
the common defense and security;
D. Special circumstances are present
in that the application of the rule in this
circumstance is not necessary to serve
the underlying purpose of the rule;
E. The special circumstances
outweigh any decrease in safety that
may result from the reduction in
standardization caused by the
exemption; and
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II. Exemption
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F. The exemption will not result in a
significant decrease in the level of safety
otherwise provided by the design.
2. Accordingly, the licensee is granted
an exemption from the certified design
control document Tier 1 information,
with corresponding changes to
Appendix C of the Facility Combined
License, as described in the request
dated May 9, 2017, as supplemented by
letter dated September 15, 2017. This
exemption is related to, and necessary
for the granting of License Amendment
No. 108 [for Unit 3 and No. 107 for Unit
4], which is being issued concurrently
with this exemption.
3. As explained in Section 5.0 of the
NRC staff’s safety evaluation, this
exemption meets the eligibility criteria
for categorical exclusion set forth in 10
CFR 51.22(c)(9). Therefore, pursuant to
10 CFR 51.22(b), no environmental
impact statement or environmental
assessment needs to be prepared in
connection with the issuance of the
exemption.
4. This exemption is effective as of the
date of its issuance.
III. License Amendment Request
Sfmt 4703
By letter dated May 9, 2017, as
supplemented by letter dated September
15, 2017, the licensee requested that the
NRC amend the COLs for VEGP, Units
3 and 4, COL Nos. NPF–91 and NPF–92.
The proposed amendment is described
in Section I of this Federal Register
notice.
The Commission has determined for
these amendments that the application
complies with the standards and
requirements of the Atomic Energy Act
of 1954, as amended (the Act), and the
Commission’s rules and regulations.
The Commission has made appropriate
findings as required by the Act and the
Commission’s rules and regulations in
10 CFR chapter I, which are set forth in
the license amendment.
A notice of consideration of issuance
of amendment to facility operating
license or COL, as applicable, proposed
no significant hazards consideration
determination, and opportunity for a
hearing in connection with these
actions, was published in the Federal
Register on July 18, 2017 (82 FR 32884).
No comments were received during the
30-day comment period.
The Commission has determined that
these amendments satisfy the criteria for
categorical exclusion in accordance
with 10 CFR 51.22. Therefore, pursuant
to 10 CFR 51.22(b), no environmental
impact statement or environmental
assessment need be prepared for these
amendments.
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Federal Register / Vol. 83, No. 103 / Tuesday, May 29, 2018 / Notices
IV. Conclusion
Using the reasons set forth in the
combined safety evaluation, the staff
granted the exemptions and issued the
amendments that the licensee requested
on May 9, 2017, as supplemented by
letter dated September 15, 2017.
The exemptions and amendments
were issued on February 1, 2018, as part
of a combined package to the licensee
(ADAMS Accession No. ML18011A885).
Dated at Rockville, Maryland, this 23rd day
of May, 2018.
For the Nuclear Regulatory Commission.
Paul B. Kallan,
Acting Branch Chief, Licensing Branch 4,
Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2018–11459 Filed 5–25–18; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2017–0205]
Instructions for Recording and
Reporting Occupational Radiation
Dose Data
Nuclear Regulatory
Commission.
ACTION: Regulatory guide; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing Revision 4
to Regulatory Guide (RG) 8.7,
‘‘Instructions for Recording and
Reporting Occupational Radiation Dose
Data.’’ Revision 4 addresses issues that
were identified after Revision 3 was
issued in December 2016. Revision 4
reinstates the long-standing staff
position concerning a licensee’s
consideration of prior occupational dose
when making prospective occupational
dose monitoring determinations.
Revision 4 retains the guidance from
Revision 3 on completing NRC Form 4,
‘‘Cumulative Occupational Dose
History,’’ and NRC Form 5,
‘‘Occupational Dose Record for a
Monitoring Period.’’
DATES: Revision 4 to RG 8.7 is available
on May 29, 2018.
ADDRESSES: Please refer to Docket ID
NRC–2017–0205 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 website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0205. Address
questions about NRC dockets to Jennifer
Borges; telephone: 301–287–9127;
email: Jennifer.Borges@nrc.gov. For
daltland on DSKBBV9HB2PROD with NOTICES
SUMMARY:
VerDate Sep<11>2014
16:39 May 25, 2018
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technical questions, contact the
individuals 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 Document 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 notice (if it
is available in ADAMS) is provided the
first time that it is mentioned in this
document. Revision 4 to RG 8.7 and the
regulatory analysis may be found in
ADAMS under Accession Nos.
ML17221A245 and ML17152A299,
respectively.
• 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.
RGs are not copyrighted, and NRC
approval is not required to reproduce
them.
FOR FURTHER INFORMATION CONTACT:
Harriet Karagiannis, telephone: 301–
415–2493, email: Harriet.Karagiannis@
nrc.gov or Minh-Thuy Nguyen,
telephone: 301–415–5163; email: MinhThuy.Nguyen@nrc.gov. Both are staff of
the Office of Nuclear Regulatory
Research, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an
existing guide 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 NRC staff uses in
evaluating specific issues or postulated
events, and data that the NRC staff
needs in its review of applications for
permits and licenses.
Revision 4 of RG 8.7 was issued with
a temporary identification of Draft
Regulatory Guide, DG–8056, to address
issues identified by the NRC staff and
other stakeholders subsequent to the
issuance of RG 8.7, Revision 3, on
December 8, 2016 (81 FR 88710).
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24513
Revision 3 modified a staff position
regarding the consideration of prior
occupational dose and whether that
should be a factor in licensee
occupational monitoring determinations
in accordance with section 20.1502 of
title 10 of the Code of Federal
Regulations (10 CFR).
After issuing Revision 3, the Nuclear
Energy Institute submitted a letter to the
NRC under ADAMS Package Accession
No. ML18138A166 stating that Revision
3 requires licensees to consider
exposures received by employees during
prior employment at a different facility
when determining whether monitoring
is required pursuant to 10 CFR 20.1502,
which was a change in agency position
from: (1) The staff position that was in
both Revisions 1 and 2 of RG 8.7, (2) the
staff position that is in RG 8.34,
‘‘Monitoring Criteria and Methods to
Calculate Occupational Radiation
Doses,’’ and (3) over two decades of
industry practice developed in
accordance with these staff positions.
The NRC staff decided to issue
Revision 4 to RG 8.7 to address the
monitoring issues that were identified
after Revision 3 was issued. The staff,
however, is not rescinding Revision 3
because it allows a more conservative
option for those licensees who want to
consider prior occupational dose when
making 10 CFR 20.1502 determinations.
Revision 4 also retains the guidance
from Revision 3 on completing NRC
Form 4 and NRC Form 5.
II. Additional Information
DG–8056 was published in the
Federal Register on October 16, 2017
(82 FR 48125) for a 60-day public
comment period. The public comment
period closed on December 15, 2017.
Responses to comments received on
DG–8056 are available under ADAMS
Accession No. ML17221A246.
III. Congressional Review Act
This RG is a rule as defined in the
Congressional Review Act (5 U.S.C.
801–808). However, the Office of
Management and Budget has not found
it to be a major rule as defined in the
Congressional Review Act.
IV. Backfitting
This RG addresses compliance with
the NRC’s requirements in 10 CFR part
20 to record and report an individual’s
cumulative occupational dose history
and the occupational dose received by
an individual for a specific monitoring
period. The NRC regards these
requirements as constituting
information collection and reporting
requirements. The NRC has long taken
the position that information collection
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Agencies
[Federal Register Volume 83, Number 103 (Tuesday, May 29, 2018)]
[Notices]
[Pages 24511-24513]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-11459]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-025 and 52-026; NRC-2008-0252]
Southern Nuclear Operating Company, Inc.; Vogtle Electric
Generating Plant, Units 3 and 4 Main Control Room Emergency
Habitability System Changes
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption and combined license amendment; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued an
exemption to allow a departure from the certification information of
Tier 1 of the generic design control document and issued License
Amendment Nos. 108 and 107 to Combined License (COL) Nos. NPF-91 and
NPF-92, respectively. The COLs were issued to Southern Nuclear
Operating Company, Inc., and Georgia Power Company; Oglethorpe Power
Corporation; MEAG Power SPVM, LLC; MEAG Power SPVJ, LLC; MEAG Power
SPVP, LLC; and the City of Dalton, Georgia (the licensee), for
construction and operation of the Vogtle Electric Generating Plant
(VEGP), Units 3 and 4, located in Burke County, Georgia.
The granting of the exemption allows the changes to Tier 1
information asked for in the amendment. Because the acceptability of
the exemption was determined in part by the acceptability of the
amendment, the exemption and amendment are being issued concurrently.
DATES: The exemption and amendment were issued on February 1, 2018.
ADDRESSES: Please refer to Docket ID NRC-2008-0252 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 website: Go to https://www.regulations.gov and search for Docket ID NRC-2008-0252. Address
questions about NRC dockets to Jennifer Borges telephone: 301-287-9127;
email: [email protected]. 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
[[Page 24512]]
``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]. The ADAMS accession number for each
document referenced (if it is available in ADAMS) is provided the first
time that it is mentioned in this document. The request for the
amendment and exemption was submitted by letter dated May 9, 2017
(ADAMS Accession No. ML17129A608), as supplemented by letter dated
September 15, 2017 (ADAMS Accession No. ML17258B211).
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: Chandu Patel, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-3025; email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Background
The NRC is granting an exemption from paragraph B of section III,
``Scope and Contents,'' of appendix D, ``Design Certification Rule for
the AP1000,'' to part 52 of title 10 of the Code of Federal Regulations
(10 CFR), and issuing License Amendment Nos. 108 and 107 to COL Nos.
NPF-91 and NPF-92, respectively, to the licensee. The exemption is
required by paragraph A.4 of section VIII, ``Processes for Changes and
Departures,'' appendix D, to 10 CFR part 52, to allow the licensee to
depart from Tier 1 information. With the requested amendment, the
licensee sought proposed changes to Updated Final Safety Analysis
Report Tier 2 information and plant-specific Tier 1 information, with
corresponding changes to COL Appendix C. Specifically, the changes
revise the licensing basis information to reflect design changes to the
main control room emergency habitability system to address the main
control room envelope temperature response.
Part of the justification for granting the exemption was provided
by the review of the amendment. Because the exemption was necessary in
order to issue the requested license amendment, the NRC granted the
exemption and issued the amendment concurrently, rather than in
sequence. This included issuing a combined safety evaluation containing
the NRC staff's review of both the exemption request and the license
amendment. The exemption met all applicable regulatory criteria set
forth in sections 50.12 and 52.7 of 10 CFR, and section VIII.A.4 of
appendix D to 10 CFR part 52. The license amendment was found to be
acceptable as well. The combined safety evaluation is available in
ADAMS under Accession No. ML18011A894.
Identical exemption documents (except for referenced unit numbers
and license numbers) were issued to the licensee for VEGP, Units 3 and
4 (COL Nos. NPF-91 and NPF-92). The exemption documents for VEGP, Units
3 and 4, can be found in ADAMS under Accession Nos. ML18011A888 and
ML18011A889, respectively. The exemption is reproduced (with the
exception of abbreviated titles and additional citations) in Section II
of this document. The amendment documents for COL Nos. NPF-91 and NPF-
92 are available in ADAMS under Accession Nos. ML18011A890 and
ML18011A891, respectively. A summary of the amendment documents is
provided in Section III of this document.
II. Exemption
Reproduced below is the exemption document issued to VEGP, Units 3
and Unit 4. It makes reference to the combined safety evaluation that
provides the reasoning for the findings made by the NRC (and listed
under Item 1) in order to grant the exemption:
1. In a letter dated May 9, 2017, as supplemented by letter dated
September 15, 2017, Southern Nuclear Operating Company requested from
the Commission an exemption to allow departures from Tier 1 information
in the certified design control document incorporated by reference in
10 CFR part 52, appendix D, as part of license amendment request 17-
001, ``Main Control Room Emergency Habitability System Changes to
Satisfy Post-Actuation Performance Requirements.''
For the reasons set forth in Section 3.1 of the NRC staff's safety
evaluation, the Commission finds that:
A. The exemption is authorized by law;
B. The exemption presents no undue risk to public health and
safety;
C. The exemption is consistent with the common defense and
security;
D. Special circumstances are present in that the application of the
rule in this circumstance is not necessary to serve the underlying
purpose of the rule;
E. The special circumstances outweigh any decrease in safety that
may result from the reduction in standardization caused by the
exemption; and
F. The exemption will not result in a significant decrease in the
level of safety otherwise provided by the design.
2. Accordingly, the licensee is granted an exemption from the
certified design control document Tier 1 information, with
corresponding changes to Appendix C of the Facility Combined License,
as described in the request dated May 9, 2017, as supplemented by
letter dated September 15, 2017. This exemption is related to, and
necessary for the granting of License Amendment No. 108 [for Unit 3 and
No. 107 for Unit 4], which is being issued concurrently with this
exemption.
3. As explained in Section 5.0 of the NRC staff's safety
evaluation, this exemption meets the eligibility criteria for
categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore,
pursuant to 10 CFR 51.22(b), no environmental impact statement or
environmental assessment needs to be prepared in connection with the
issuance of the exemption.
4. This exemption is effective as of the date of its issuance.
III. License Amendment Request
By letter dated May 9, 2017, as supplemented by letter dated
September 15, 2017, the licensee requested that the NRC amend the COLs
for VEGP, Units 3 and 4, COL Nos. NPF-91 and NPF-92. The proposed
amendment is described in Section I of this Federal Register notice.
The Commission has determined for these amendments that the
application complies with the standards and requirements of the Atomic
Energy Act of 1954, as amended (the Act), and the Commission's rules
and regulations. The Commission has made appropriate findings as
required by the Act and the Commission's rules and regulations in 10
CFR chapter I, which are set forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or COL, as applicable, proposed no significant
hazards consideration determination, and opportunity for a hearing in
connection with these actions, was published in the Federal Register on
July 18, 2017 (82 FR 32884). No comments were received during the 30-
day comment period.
The Commission has determined that these amendments satisfy the
criteria for categorical exclusion in accordance with 10 CFR 51.22.
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact
statement or environmental assessment need be prepared for these
amendments.
[[Page 24513]]
IV. Conclusion
Using the reasons set forth in the combined safety evaluation, the
staff granted the exemptions and issued the amendments that the
licensee requested on May 9, 2017, as supplemented by letter dated
September 15, 2017.
The exemptions and amendments were issued on February 1, 2018, as
part of a combined package to the licensee (ADAMS Accession No.
ML18011A885).
Dated at Rockville, Maryland, this 23rd day of May, 2018.
For the Nuclear Regulatory Commission.
Paul B. Kallan,
Acting Branch Chief, Licensing Branch 4, Division of New Reactor
Licensing, Office of New Reactors.
[FR Doc. 2018-11459 Filed 5-25-18; 8:45 am]
BILLING CODE 7590-01-P