83 FR 30464 - Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Changes to Containment Cooling and Spent Fuel Pool Makeup Strategies

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 83, Issue 125 (June 28, 2018)

Page Range		30464-30465
FR Document		2018-13860

The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment Nos. 126 and 125 to Combined Licenses (COLs), 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.

Federal Register, Volume 83 Issue 125 (Thursday, June 28, 2018)

[Federal Register Volume 83, Number 125 (Thursday, June 28, 2018)]
[Notices]
[Pages 30464-30465]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2018-13860]


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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; Changes to Containment Cooling and 
Spent Fuel Pool Makeup Strategies

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption and combined license amendment; issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is granting an 
exemption to allow a departure from the certification information of 
Tier 1 of the generic design control document (DCD) and is issuing 
License Amendment Nos. 126 and 125 to Combined Licenses (COLs), 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 June 7, 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 http://www.regulations.gov and search for Docket ID NRC-2008-0252. Address 
questions about NRC dockets to Jennifer Borges; 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 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]. 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 amendments and exemptions were submitted 
by letter dated July 14, 2017, and is available in ADAMS under 
Accession No. ML17198A596.
     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: Peter Hearn, Office of New Reactors, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; 
telephone: 301-415-1189; email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Introduction

    The NRC is granting an exemption from paragraph B of section III, 
``Scope and Contents,'' of appendix D, ``Design Certification Rule for 
the AP1000 Design,'' to part 52 of title 10 of the Code of Federal 
Regulations (10 CFR), and issuing License Amendment Nos. 126 and 125 to 
COLs, 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 that would revise Tier 1 information 
to change the inspected volume for the spent fuel pool and cask 
washdown pit with corresponding changes to the minimum volumes and 
reference measurement locations, and add an inspection for the minimum 
volume for the cask loading pit.
    Part of the justification for granting the exemption was provided 
by the review of the amendment. Because the exemption is necessary in 
order to issue the requested license amendment, the

[[Page 30465]]

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 10 CFR 50.12, 10 CFR 52.7, 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. ML18100A079.
    Identical exemption documents (except for referenced unit numbers 
and license numbers) were issued to the licensee for VEGP Units 3 and 4 
(COLs NPF-91 and NPF-92). The exemption documents for VEGP Units 3 and 
4 can be found in ADAMS under Accession Nos. ML18100A071 and 
ML18100A073, respectively. The exemption is reproduced (with the 
exception of abbreviated titles and additional citations) in Section II 
of this document. The amendment documents for COLs NPF-91 and NPF-92 
are available in ADAMS under Accession Nos. ML18100A074 and 
ML18100A077, 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 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 an application dated July 14, 2017, the licensee requested 
from the NRC or Commission an exemption to allow departures from Tier 1 
information in the certified Design Control Document (DCD) incorporated 
by reference in 10 CFR part 52, appendix D, ``Design Certification Rule 
for the AP1000 Design,'' as part of license amendment request (LAR) 17-
021, ``Changes to Containment Coolant and Spent Fuel Makeup 
Strategies.''
    For the reasons set forth in Section 3.1 of the NRC staff's Safety 
Evaluation, which can be found in ADAMS under Accession No. 
ML18100A079, 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 DCD Tier 1 information, as described in the licensee's 
request dated July 14, 2017. This exemption is related to, and 
necessary for, the granting of License Amendment Nos. 126 (Unit 3) and 
125 (Unit 4), which is being issued concurrently with this exemption.
    3. As explained in Section 5.0 of the NRC staff's Safety Evaluation 
(ADAMS Accession No. ML18100A079), 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.
    This exemption is effective as of the date of its issuance.

III. License Amendment Request

    By letter dated July 14, 2017 (ADAMS Accession No. ML17198A596), 
the licensee requested that the NRC amend the COLs for VEGP Units 3 and 
4, COLs NPF-91 and NPF-92. The proposed amendments are described in 
Section I of this document.
    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 
November 22, 2017 (82 FR 55654). 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.

IV. Conclusion

    Using the reasons set forth in the combined safety evaluation, the 
staff granted the exemption and issued the amendment that the licensee 
requested on July 14, 2017. The exemption and amendment were issued on 
June 7, 2018, as part of a combined package to the licensee (ADAMS 
Accession No. ML18100A069).

    Dated at Rockville, Maryland, this 22nd day of June, 2018.

    For the Nuclear Regulatory Commission.
Paul B. Kallan,
Acting Branch Chief, Licensing Branch 4, Division of Licensing, Siting, 
and Environmental Analysis, Office of New Reactors.
[FR Doc. 2018-13860 Filed 6-27-18; 8:45 am]
BILLING CODE 7590-01-P

Federal Register / Vol. 83, No. 125 / Thursday, June 28, 2018 / Notices 30465

NRC granted the exemption and issued E. the special circumstances outweigh IV. Conclusion
the amendment concurrently, rather any decrease in safety that may result
Using the reasons set forth in the
than in sequence. This included issuing from the reduction in standardization
combined safety evaluation, the staff
a combined safety evaluation containing caused by the exemption; and
granted the exemption and issued the
the NRC staff’s review of both the F. the exemption will not result in a amendment that the licensee requested
exemption request and the license significant decrease in the level of safety on July 14, 2017. The exemption and
amendment. The exemption met all otherwise provided by the design. amendment were issued on June 7,
applicable regulatory criteria set forth in 2. Accordingly, the licensee is granted 2018, as part of a combined package to
10 CFR 50.12, 10 CFR 52.7, and section an exemption from the certified DCD the licensee (ADAMS Accession No.
VIII.A.4 of appendix D to 10 CFR part Tier 1 information, as described in the ML18100A069).
52. The license amendment was found licensee’s request dated July 14, 2017.
to be acceptable as well. The combined Dated at Rockville, Maryland, this 22nd
This exemption is related to, and day of June, 2018.
safety evaluation is available in ADAMS necessary for, the granting of License
under Accession No. ML18100A079. For the Nuclear Regulatory Commission.
Amendment Nos. 126 (Unit 3) and 125
Identical exemption documents Paul B. Kallan,
(Unit 4), which is being issued
(except for referenced unit numbers and Acting Branch Chief, Licensing Branch 4,
concurrently with this exemption.
license numbers) were issued to the Division of Licensing, Siting, and
licensee for VEGP Units 3 and 4 (COLs 3. As explained in Section 5.0 of the Environmental Analysis, Office of New
NPF–91 and NPF–92). The exemption NRC staff’s Safety Evaluation (ADAMS Reactors.
documents for VEGP Units 3 and 4 can Accession No. ML18100A079), this [FR Doc. 2018–13860 Filed 6–27–18; 8:45 am]
be found in ADAMS under Accession exemption meets the eligibility criteria BILLING CODE 7590–01–P
Nos. ML18100A071 and ML18100A073, for categorical exclusion set forth in 10
respectively. The exemption is CFR 51.22(c)(9). Therefore, pursuant to
reproduced (with the exception of 10 CFR 51.22(b), no environmental NUCLEAR REGULATORY
abbreviated titles and additional impact statement or environmental COMMISSION
citations) in Section II of this document. assessment needs to be prepared in
The amendment documents for COLs connection with the issuance of the
[NRC–2018–0127; Docket Nos. 50–259, 50–
NPF–91 and NPF–92 are available in exemption. 260, 50–296, and 72–052; Docket Nos. 50–
ADAMS under Accession Nos. This exemption is effective as of the 327, 50–328, and 72–034; Docket Nos. 50–
ML18100A074 and ML18100A077, date of its issuance. 390, 50–391, and 72–1048]
respectively. A summary of the III. License Amendment Request
amendment documents is provided in Tennessee Valley Authority, Browns
Section III of this document. By letter dated July 14, 2017 (ADAMS Ferry Nuclear Plant, Units 1, 2, and 3,
Accession No. ML17198A596), the and Independent Spent Fuel Storage
II. Exemption licensee requested that the NRC amend Installation; Sequoyah Nuclear Plant,
Reproduced below is the exemption the COLs for VEGP Units 3 and 4, COLs Units 1 and 2, and Independent Spent
document issued to VEGP Units 3 and NPF–91 and NPF–92. The proposed Fuel Storage Installation; Watts Bar
4. It makes reference to the combined amendments are described in Section I Nuclear Plant, Units 1 and 2, and
safety evaluation that provides the of this document. Independent Spent Fuel Storage
reasoning for the findings made by the The Commission has determined for Installation
NRC (and listed under Item 1) in order these amendments that the application AGENCY: Nuclear Regulatory
to grant the exemption: complies with the standards and Commission.
1. In an application dated July 14, requirements of the Atomic Energy Act
2017, the licensee requested from the ACTION: License amendment request;
of 1954, as amended (the Act), and the
NRC or Commission an exemption to opportunity to comment, request a
Commission’s rules and regulations.
allow departures from Tier 1 hearing, and petition for leave to
The Commission has made appropriate
information in the certified Design intervene.
findings as required by the Act and the
Control Document (DCD) incorporated Commission’s rules and regulations in
by reference in 10 CFR part 52, SUMMARY: The U.S. Nuclear Regulatory
10 CFR chapter I, which are set forth in Commission (NRC) is considering
appendix D, ‘‘Design Certification Rule the license amendment.
for the AP1000 Design,’’ as part of issuance of amendments to Renewed
A notice of consideration of issuance Facility Operating License Nos. DPR–33,
license amendment request (LAR) 17– of amendment to facility operating
021, ‘‘Changes to Containment Coolant DPR–52, and DPR–68 for the Browns
license or COL, as applicable, proposed Ferry Nuclear Plant (Browns Ferry),
and Spent Fuel Makeup Strategies.’’ no significant hazards consideration
For the reasons set forth in Section 3.1 Units 1, 2, and 3, respectively; Renewed
determination, and opportunity for a Facility Operating License Nos. DPR–77
of the NRC staff’s Safety Evaluation,
hearing in connection with these and DPR–79 for the Sequoyah Nuclear
which can be found in ADAMS under
actions, was published in the Federal Plant (Sequoyah), Units 1 and 2,
Accession No. ML18100A079, the
Register on November 22, 2017 (82 FR respectively; and Facility Operating
Commission finds that:
A. The exemption is authorized by 55654). No comments were received License Nos. NPF–90 and NPF–96 for
law; during the 30-day comment period. the Watts Bar Nuclear Plant (Watts Bar),
B. the exemption presents no undue The Commission has determined that Units 1 and 2, respectively. The
amozie on DSK3GDR082PROD with NOTICES1

risk to public health and safety; these amendments satisfy the criteria for proposed amendments would revise the
C. the exemption is consistent with categorical exclusion in accordance implementation date for the NRC-
the common defense and security; with 10 CFR 51.22. Therefore, pursuant approved license amendments to
D. special circumstances are present to 10 CFR 51.22(b), no environmental upgrade the Emergency Action Level
in that the application of the rule in this impact statement or environmental (EAL) schemes for Browns Ferry, Units
circumstance is not necessary to serve assessment need be prepared for these 1, 2, and 3; Sequoyah, Units 1 and 2;
the underlying purpose of the rule; amendments. and Watts Bar, Units 1 and 2.

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Document Created: 2018-11-06 09:55:39
Document Modified: 2018-11-06 09:55:39

Category		Regulatory Information
Collection		Federal Register
sudoc Class		AE 2.7: GS 4.107: AE 2.106:
Publisher		Office of the Federal Register, National Archives and Records Administration
Section		Notices
Action		Exemption and combined license amendment; issuance.
Dates		The exemption and amendment were issued on June 7, 2018.
Contact		Peter Hearn, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1189; email: [email protected]
FR Citation		83 FR 30464