82 FR 19755 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric & Gas Company; South Carolina Public Service Authority Debris Screen Related Dimensions

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 82, Issue 81 (April 28, 2017)

Page Range		19755-19756
FR Document		2017-08615

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 No. 66 to Combined Licenses (COL), NPF-93 and NPF-94. The COLs were issued to South Carolina Electric & Gas Company and the South Carolina Public Service Authority, (both collectively referred to as the licensee) for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County, South Carolina. 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 82 Issue 81 (Friday, April 28, 2017)

[Federal Register Volume 82, Number 81 (Friday, April 28, 2017)]
[Notices]
[Pages 19755-19756]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2017-08615]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 52-027 and 52-028; NRC-2008-0441]


Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina 
Electric & Gas Company; South Carolina Public Service Authority Debris 
Screen Related Dimensions

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 No. 66 to Combined Licenses (COL), NPF-93 and NPF-94. 
The COLs were issued to South Carolina Electric & Gas Company and the 
South Carolina Public Service Authority, (both collectively referred to 
as the licensee) for construction and operation of the Virgil C. Summer 
Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County, 
South Carolina.
    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 March 27, 2017.

ADDRESSES: Please refer to Docket ID NRC-2008-0441 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 http://www.regulations.gov and search for Docket ID NRC-2008-0252. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     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 amendment and exemption was submitted by 
letter dated August 12, 2016 (ADAMS Accession No. ML16225A437).
     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: Ruth Reyes, Office of New Reactors, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; 
telephone: 301-415-3249; email: [email protected].

SUPPLEMENTARY INFORMATION: 

[[Page 19756]]

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,'' to part 52 of title 10 of the Code of Federal Regulations 
(10 CFR), and issuing License Amendment No. 66 to COLs, NP-93 and NPF-
94, 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 the Updated Final Safety Analysis Report in the form of 
departures from the incorporated plant-specific DCD Tier 2 information. 
The proposed amendment also involves related changes to plant-specific 
Tier 1 information, with corresponding changes to the associated COL 
Appendix C information. The proposed changes are to information 
identifying the frontal face area and screen surface area for the In-
Containment Refueling Water Storage Tank (IRWST) screens, the location 
and dimensions of the protective plate located above the containment 
recirculation (CR) screens, and increasing the maximum Normal Residual 
Heat Removal System flowrate through the IRWST and CR screens.
    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 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. ML17040A590.
    Identical exemption documents (except for referenced unit numbers 
and license numbers) were issued to the licensee for VCSNS Units 2 and 
3 (COLs NPF-93 and NPF-94). The exemption documents for VCSNS Units 2 
and 3 can be found in ADAMS under Accession Nos. ML17040A547 and 
ML17040A553, 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-93 and NPF-94 
are available in ADAMS under Accession Nos. ML17040A543 and 
ML17040A545, 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 V. C. Summer 
Units 2 and 3. 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 August 12, 2016, the licensee requested 
from the Commission an exemption to allow departures from Tier 1 
information in the certified DCD incorporated by reference in 10 CFR 
part 52, appendix D, as part of License Amendment Request 14-11, 
``Debris Screen Related Dimensions.''
    For the reasons set forth in Section 3.1 of the NRC staff's Safety 
Evaluation, which can be found at ADAMS Accession No. ML17040A590, 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, with corresponding changes to 
Appendix C of the Facility COLs as described in the licensee's request 
dated August 12, 2016. This exemption is related to, and necessary for, 
the granting of License Amendment No. 66, 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 August 12, 2016, the licensee requested that the 
NRC amend the COLs for VCSNS, Units 2 and 3, COLs NPF-93 and NPF-94. 
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 combined license, 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 October 11, 2016 (81 FR 70182). 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 August 12, 2016.
    The exemption and amendment were issued on March 27, 2017, as part 
of a combined package to the licensee (ADAMS Accession No. 
ML17040A530).

    Dated at Rockville, Maryland, this 17th day of April 2017.

    For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
 Chief, Licensing Branch 4, Division of New Reactor Licensing, Office 
of New Reactors.
[FR Doc. 2017-08615 Filed 4-27-17; 8:45 am]
 BILLING CODE 7590-01-P

19756 Federal Register / Vol. 82, No. 81 / Friday, April 28, 2017 / Notices

I. Introduction ADAMS under Accession Nos. III. License Amendment Request
The NRC is granting an exemption ML17040A543 and ML17040A545,
respectively. A summary of the By letter dated August 12, 2016, the
from Paragraph B of Section III, ‘‘Scope licensee requested that the NRC amend
and Contents,’’ of appendix D, ‘‘Design amendment documents is provided in
Section III of this document. the COLs for VCSNS, Units 2 and 3,
Certification Rule for the AP1000,’’ to
COLs NPF–93 and NPF–94. The
part 52 of title 10 of the Code of Federal II. Exemption proposed amendment is described in
Regulations (10 CFR), and issuing
License Amendment No. 66 to COLs, Reproduced below is the exemption Section I of this Federal Register notice.
NP–93 and NPF–94, to the licensee. The document issued to V. C. Summer Units The Commission has determined for
exemption is required by Paragraph A.4 2 and 3. It makes reference to the these amendments that the application
of Section VIII, ‘‘Processes for Changes combined safety evaluation that complies with the standards and
and Departures,’’ appendix D, to 10 CFR provides the reasoning for the findings requirements of the Atomic Energy Act
part 52 to allow the licensee to depart made by the NRC (and listed under Item of 1954, as amended (the Act), and the
from Tier 1 information. With the 1) in order to grant the exemption: Commission’s rules and regulations.
requested amendment, the licensee 1. In an application dated August 12, The Commission has made appropriate
sought proposed changes that would 2016, the licensee requested from the findings as required by the Act and the
revise the Updated Final Safety Commission an exemption to allow Commission’s rules and regulations in
Analysis Report in the form of departures from Tier 1 information in
10 CFR chapter I, which are set forth in
departures from the incorporated plant- the certified DCD incorporated by
the license amendment.
specific DCD Tier 2 information. The reference in 10 CFR part 52, appendix
proposed amendment also involves D, as part of License Amendment A notice of consideration of issuance
related changes to plant-specific Tier 1 Request 14–11, ‘‘Debris Screen Related of amendment to facility operating
information, with corresponding Dimensions.’’ license or combined license, as
changes to the associated COL For the reasons set forth in Section 3.1 applicable, proposed no significant
Appendix C information. The proposed of the NRC staff’s Safety Evaluation, hazards consideration determination,
changes are to information identifying which can be found at ADAMS and opportunity for a hearing in
the frontal face area and screen surface Accession No. ML17040A590, the connection with these actions, was
area for the In-Containment Refueling Commission finds that: published in the Federal Register on
Water Storage Tank (IRWST) screens, A. The exemption is authorized by October 11, 2016 (81 FR 70182). No
the location and dimensions of the law; comments were received during the 30-
protective plate located above the B. the exemption presents no undue day comment period.
containment recirculation (CR) screens, risk to public health and safety; The Commission has determined that
and increasing the maximum Normal C. the exemption is consistent with these amendments satisfy the criteria for
Residual Heat Removal System flowrate the common defense and security; categorical exclusion in accordance
through the IRWST and CR screens. D. special circumstances are present with 10 CFR 51.22. Therefore, pursuant
Part of the justification for granting in that the application of the rule in this
the exemption was provided by the to 10 CFR 51.22(b), no environmental
circumstance is not necessary to serve impact statement or environmental
review of the amendment. Because the the underlying purpose of the rule;
exemption is necessary in order to issue assessment need be prepared for these
E. the special circumstances outweigh amendments.
the requested license amendment, the
any decrease in safety that may result
NRC granted the exemption and issued IV. Conclusion
from the reduction in standardization
the amendment concurrently, rather
caused by the exemption; and
than in sequence. This included issuing Using the reasons set forth in the
a combined safety evaluation containing F. the exemption will not result in a combined safety evaluation, the staff
the NRC staff’s review of both the significant decrease in the level of safety
granted the exemption and issued the
exemption request and the license otherwise provided by the design.
amendment that the licensee requested
amendment. The exemption met all 2. Accordingly, the licensee is granted on August 12, 2016.
applicable regulatory criteria set forth in an exemption from the certified DCD
Tier 1 information, with corresponding The exemption and amendment were
10 CFR 50.12, 10 CFR 52.7, and Section
changes to Appendix C of the Facility issued on March 27, 2017, as part of a
VIII.A.4 of appendix D to 10 CFR part
52. The license amendment was found COLs as described in the licensee’s combined package to the licensee
to be acceptable as well. The combined request dated August 12, 2016. This (ADAMS Accession No. ML17040A530).
safety evaluation is available in ADAMS exemption is related to, and necessary Dated at Rockville, Maryland, this 17th day
under Accession No. ML17040A590. for, the granting of License Amendment of April 2017.
Identical exemption documents No. 66, which is being issued For the Nuclear Regulatory Commission.
(except for referenced unit numbers and concurrently with this exemption.
Jennifer Dixon-Herrity,
license numbers) were issued to the 3. As explained in Section 5.0 of the
NRC staff’s Safety Evaluation this Chief, Licensing Branch 4, Division of New
licensee for VCSNS Units 2 and 3 (COLs
exemption meets the eligibility criteria Reactor Licensing, Office of New Reactors.
NPF–93 and NPF–94). The exemption
for categorical exclusion set forth in 10 [FR Doc. 2017–08615 Filed 4–27–17; 8:45 am]
documents for VCSNS Units 2 and 3 can
asabaliauskas on DSK3SPTVN1PROD with NOTICES

be found in ADAMS under Accession CFR 51.22(c)(9). Therefore, pursuant to BILLING CODE 7590–01–P

Nos. ML17040A547 and ML17040A553, 10 CFR 51.22(b), no environmental
respectively. The exemption is impact statement or environmental
reproduced (with the exception of assessment needs to be prepared in
abbreviated titles and additional connection with the issuance of the
citations) in Section II of this document. exemption.
The amendment documents for COLs 4. This exemption is effective as of the
NPF–93 and NPF–94 are available in date of its issuance.

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Document Created: 2017-04-28 03:02:57
Document Modified: 2017-04-28 03:02:57

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 March 27, 2017.
Contact		Ruth Reyes, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-3249; email: [email protected]
FR Citation		82 FR 19755