Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Changes to Chemical and Volume Control System, 25159-25161 [2014-10113]

Download as PDF mstockstill on DSK4VPTVN1PROD with NOTICES Federal Register / Vol. 79, No. 85 / Friday, May 2, 2014 / Notices responding to emergencies, monitoring ongoing events, confirming licensing bases, studying potentially generic safety problems, assessing trends and patterns of operational experience, monitoring performance, identifying precursors of more significant events, and providing operational experience to the industry. Sections 1 and 2 of NUREG–1022, Revision 3 contain general guidance applicable to all event reports. Section 3 of NUREG–1022, Revision 3 contains guidance for each of the specific reporting criterion found within the rule. Section 4 of NUREG– 1022 Revision 3 contains additional general guidance applicable to reports submitted under 10 CFR 50.72. Section 5 of NUREG–1022, Revision 3 contains additional general guidance applicable to reports submitted under 10 CFR 50.73. Section 3.2.13 of NUREG–1022, Revision 3 provides guidance for reporting to the NRC the events listed under 10 CFR 50.72(b)(3)(xiii): any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. Although some of the guidance is specific, much of the guidance is general in nature. In many areas, the decision to report under 10 CFR 50.72(b)(3)(xiii) involves a licensee’s use of engineering judgment. A licensee’s use of engineering judgment can result in inconsistent application. During public meetings conducted on April 3, 2013 (ADAMS Accession No. ML13100A390), and on May 7, 2013 (ADAMS Accession No. ML13109A228), the NRC discussed with external stakeholders, including the NEI, what specific considerations might be evaluated against when the NRC determines if acceptable engineering judgment was applied by a licensee. NEI 13–01, ‘‘Reportable Action Levels for Loss of Emergency Preparedness Capabilities,’’ (ADAMS Accession No. ML13281A794) was then drafted with the purpose of providing a detailed uniform approach to reporting under 10 CFR 50.72(b)(3)(xiii). NEI 13–01 provides specific guidance for reporting under 10 CFR 50.72(b)(3)(xiii). By letter dated October 8, 2013 (ADAMS Accession No. ML13281A780), NEI requested NRC endorsement of NEI 13– 01. It should also be noted that some of the specific guidance found in NEI 13– 01, differs from certain specific positions found in Section 3.2.13 of NUREG–1022, Revision 3. In draft NUREG–1022, Revision 3, Supplement 1, ‘‘Event Reporting Guidelines: 10 CFR 50.72(b)(3)(xiii)’’ (ADAMS Accession No. ML14114A384), the NRC proposes to endorse NEI 13–01, VerDate Mar<15>2010 00:23 May 02, 2014 Jkt 232001 ‘‘Reportable Action Levels for Loss of Emergency Preparedness Capabilities,’’ dated October 2013, as an acceptable alternative to guidance found in Section 3.2.13 of NUREG–1022, Revision 3, for reporting considerations associated with 10 CFR 50.72(b)(3)(xiii). Since Sections 1, 2, and 4 of NUREG– 1022, Revision 3 contain general guidance for event reporting that would still be applicable to reports submitted under 10 CFR 50.72(b)(3)(xiii), these sections are not considered superseded by licensee adoption of NEI 13–01. III. Backfitting and Issue Finality Draft NUREG–1022, Revision 3, Supplement 1, if finalized, would provide guidance on the method that the NRC staff finds acceptable for a licensee to meet the information and collection requirements of 10 CFR 50.72(b)(3)(xiii). The issuance of this guidance would not be backfitting, as the term is defined in 10 CFR 50.109, or inconsistent with the issue finality provisions on 10 CFR part 52, because information collection and reporting requirements are not included within the scope of the NRC’s backfitting protections or part 52 finality provisions. Dated at Rockville, Maryland, this 25th day of April 2014. For the Nuclear Regulatory Commission. Christopher Regan, Branch Chief, Reactor Inspection Branch, Division of Inspections and Regional Support, Office of Nuclear Reactor Regulation. [FR Doc. 2014–10141 Filed 5–1–14; 8:45 am] BILLING CODE 7590–01–P 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 and Gas; Changes to Chemical and Volume Control System Nuclear Regulatory Commission. ACTION: Exemption and combined license amendment; issuance. AGENCY: 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 issuing License Amendment No. 11 to Combined Licenses (COL) NPF–93 and NPF–94. The COLs were issued to South Carolina Electric and Gas (SCE&G) and South Carolina Public Service Authority (Santee Cooper) (the SUMMARY: PO 00000 Frm 00067 Fmt 4703 Sfmt 4703 25159 licensee), for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3 located in Fairfield County, South Carolina. The amendment requests changes that modify the Chemical and Volume Control System (CVS), including changes to information located in Tier 1 Tables 2.3.2–1 and 2.3.2–2, and Tier 1 Figures 2.2.1–1 and 2.3.2–1. The granting of the exemption allows the changes to Tier 1 information as specified in the license amendment request (LAR). Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently. Please refer to Docket ID NRC–2008–0441 when contacting the NRC about the availability of information regarding this document. You may access 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–2008–0441. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; 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 access 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: Denise McGovern, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–0681; email: Denise.McGovern@nrc.gov. ADDRESSES: SUPPLEMENTARY INFORMATION: E:\FR\FM\02MYN1.SGM 02MYN1 mstockstill on DSK4VPTVN1PROD with NOTICES 25160 Federal Register / Vol. 79, No. 85 / Friday, May 2, 2014 / Notices 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 No. 11 to COLs, NPF–93 and NPF–94, to the licensee. The request for the amendment and exemption were submitted by letter dated March 13, 2013 (ADAMS Accession No. ML13074A698). The licensee supplemented this request on July 11, 2013 (ADAMS Accession No. ML13197A430) October 28, 2013 (ADAMS Accession No. ML13305A224), and November 26, 2013 (ADAMS Accession No. ML13338A272). 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 to modify the design of the CVS. As part of this request, the licensee needed to change information located in Tier 1 Tables 2.3.2–1 and 2.3.2–2, and Tier 1 Figures 2.2.1–1 and 2.3.2–1. These changes were necessary as part of a design modification which provides a spring-assisted check valve to the Reactor Coolant System Purification Return Line in order to maintain overpressure protection, replaces an isolation check valve in the CVS with an air operated globe valve, and separates the zinc and hydrogen injection lines. 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. ML13357A658. 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). These documents can be found in ADAMS under Accession Nos. ML13357A569 and ML13357A598. The exemption is reproduced (with the exception of abbreviated titles and additional VerDate Mar<15>2010 00:23 May 02, 2014 Jkt 232001 citations) in Section II of this document. The amendment documents for COLs NPF–93 and NPF–94 are available in ADAMS under Accession Nos. ML13357A498 and ML13357A539. A summary of the amendment documents is provided in Section III of this document. II. Exemption Reproduced below is the exemption document issued to VCSNS 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 a letter dated March 13, 2013, and as supplemented by the letters dated July 11, October 28, and November 26, 2013, South Carolina Electric & Gas Company (licensee) requested from the U. S. Nuclear Regulatory Commission (Commission) an exemption from the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Appendix D, ‘‘Design Certification Rule for the AP1000 Design, Scope, and Contents,’’ Section III.B, as part of license amendment request, (LAR 13–07) ‘‘Changes to the Chemical and Volume Control System.’’ 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. ML13357A658, 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 to the provisions of 10 CFR part 52, Appendix D, Section III.B, to allow deviations from the certified Design Control Document (DCD) Tier 1 Figures 2.2.1–1 and 2.3.2–1 and Tables 2.3.2–1 and 2.3.2–2, as described in the licensee’s request dated March 13, 2013, and supplemented by the letters dated July 11, October 28, and November 26, 2013. This exemption is related to, and necessary for the granting of License Amendment No. 11, which is being PO 00000 Frm 00068 Fmt 4703 Sfmt 4703 issued concurrently with this exemption. 3. As explained in Section 5.0 of the NRC staff’s Safety Evaluation (ADAMS Accession No. ML13357A658), 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 February 24, 2013. III. License Amendment Request By letter dated March 13, 2013, the licensee requested that the NRC amend the COLs for VCSNS Units 2 and 3, COLs NPF–93 and NPF–94. The licensee supplemented this application on July 11, October 28, and November 26, 2013. The proposed amendment would depart from Tier 2 Material previously incorporated into the UFSAR. Additionally, these Tier 2 changes involve changes to Tier 1 Information in the UFSAR, and the proposed amendment would also revise the associated material that has been included in Appendix C of each of the VCSNS, Units 2 and 3 COLs. The requested amendment will revise the Tier 2 UFSAR information pertaining to the CVS, found throughout the UFSAR. These Tier 2 changes require modifications to particular information located in Tier 1 Tables 2.3.2–1 and 2.3.2–2, and Tier 1 Figures 2.2.1–1 and 2.3.2–1. These changes were necessary as part of a design modification which provides a spring-assisted check valve to the Reactor Coolant System Purification Return Line in order to maintain overpressure protection, replaces an isolation check valve in the CVS with an air operated globe valve, and separates the zinc and hydrogen injection lines. 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 E:\FR\FM\02MYN1.SGM 02MYN1 Federal Register / Vol. 79, No. 85 / Friday, May 2, 2014 / Notices April 2, 2013 (78 FR 19746). No comments were received during the 60day 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 March 13, 2013 and revised by letter dated July 11, October 28, and November 26, 2013. The exemption and amendment were issued on February 24, 2014 as part of a combined package to the licensee (ADAMS Accession No. ML13357A436). Dated at Rockville, Maryland, this 28th day of April 2014. For the Nuclear Regulatory Commission. Lawrence J. Burkhart, Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. 2014–10113 Filed 5–1–14; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–250 and 50–251; NRC– 2014–0100] Florida Power & Light Company; Turkey Point Nuclear Generating Unit Nos. 3 and 4 Nuclear Regulatory Commission. ACTION: License amendment application; withdrawal by applicant. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) received a request from Florida Power & Light Company (the licensee) to withdraw its application dated October 30, 2012, for proposed amendments to Renewed Facility Operating License Nos. DPR–31 and DPR–41. The proposed amendments would have revised Technical Specification (TS) 3/4.5.2, ‘‘ECCS [Emergency core cooling system] Subsystems—Tavg Greater Than or Equal To 350 °F [degrees Fahrenheit],’’ and TS 3/4.8.1, ‘‘A.C. [Alternating Current] Sources.’’ The NRC permitted the licensee to withdraw the application. ADDRESSES: Please refer to Docket ID NRC–2014–0100 when contacting the NRC about the availability of information regarding this document. You may access publicly available mstockstill on DSK4VPTVN1PROD with NOTICES SUMMARY: VerDate Mar<15>2010 00:23 May 02, 2014 Jkt 232001 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–2014–0100. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; 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: Audrey L. Klett, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415– 0489; email: Audrey.Klett@nrc.gov. SUPPLEMENTARY INFORMATION: The NRC permitted Florida Power & Light Company to withdraw its application dated October 30, 2012 (ADAMS Accession No. ML12307A019), for proposed amendments to Renewed Facility Operating License Nos. DPR–31 and DPR–41 for the Turkey Point Nuclear Generating Unit Nos. 3 and 4, respectively, located in Miami-Dade County, Florida. The proposed amendments would have revised TS 3/ 4.5.2, ‘‘ECCS Subsystems—Tavg Greater Than or Equal To 350 °F,’’ and TS 3/ 4.8.1, ‘‘A.C. Sources.’’ The NRC issued a Notice of Consideration of Issuance of Amendments to Facility Operating Licenses published in the Federal Register (FR) on February 19, 2013 (78 FR 11692). However, by letter dated March 26, 2014 (ADAMS Accession No. ML14104B433), the licensee requested to withdraw the proposed amendments. Dated at Rockville, Maryland, this 21st day of April 2014. PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 25161 For the Nuclear Regulatory Commission. Audrey L. Klett, Project Manager, Plant Licensing Branch II– 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2014–10148 Filed 5–1–14; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 40–09091; NRC–2011–0148] Issuance of Materials License and Staff’s Record of Decision for Strata Energy, Inc. Ross ISR Project Nuclear Regulatory Commission. ACTION: License and staff’s record of decision; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) has issued a license to Strata Energy, Inc. (Strata) for its Ross Uranium In-Situ Recovery (ISR) Facility in Crook County, Wyoming. Under conditions listed in the license, the Source and Byproduct Materials License SUA–1601 authorizes Strata to operate its facilities as proposed in its license application, as amended, and to possess uranium source and byproduct material at the Ross ISR Facility. In addition, the NRC staff has published a record of decision (ROD) that supports the NRC’s decision to approve Strata’s license application for the Ross ISR Facility and to issue the license. ADDRESSES: Please refer to Docket ID NRC–2011–0148 when contacting the NRC about the availability of information regarding this document. You may access 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–2011–0148. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; 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 access publicly available documents online in the NRC Library at https://www.nrc.gov/readingrm/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 SUMMARY: E:\FR\FM\02MYN1.SGM 02MYN1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 79, Number 85 (Friday, May 2, 2014)]
[Notices]
[Pages 25159-25161]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-10113]

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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 and Gas; Changes to Chemical and Volume Control System

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption and combined license amendment; issuance.

-----------------------------------------------------------------------

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 issuing License
Amendment No. 11 to Combined Licenses (COL) NPF-93 and NPF-94. The COLs
were issued to South Carolina Electric and Gas (SCE&G) and South
Carolina Public Service Authority (Santee Cooper) (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
amendment requests changes that modify the Chemical and Volume Control
System (CVS), including changes to information located in Tier 1 Tables
2.3.2-1 and 2.3.2-2, and Tier 1 Figures 2.2.1-1 and 2.3.2-1. The
granting of the exemption allows the changes to Tier 1 information as
specified in the license amendment request (LAR). Because the
acceptability of the exemption was determined in part by the
acceptability of the amendment, the exemption and amendment are being
issued concurrently.

ADDRESSES: Please refer to Docket ID NRC-2008-0441 when contacting the
NRC about the availability of information regarding this document. You
may access 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-2008-0441. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; 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 access 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: Denise McGovern, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-0681; email: Denise.McGovern@nrc.gov.

SUPPLEMENTARY INFORMATION:

[[Page 25160]]

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 No. 11 to COLs, NPF-
93 and NPF-94, to the licensee. The request for the amendment and
exemption were submitted by letter dated March 13, 2013 (ADAMS
Accession No. ML13074A698). The licensee supplemented this request on
July 11, 2013 (ADAMS Accession No. ML13197A430) October 28, 2013 (ADAMS
Accession No. ML13305A224), and November 26, 2013 (ADAMS Accession No.
ML13338A272). 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 to modify the design of
the CVS. As part of this request, the licensee needed to change
information located in Tier 1 Tables 2.3.2-1 and 2.3.2-2, and Tier 1
Figures 2.2.1-1 and 2.3.2-1. These changes were necessary as part of a
design modification which provides a spring-assisted check valve to the
Reactor Coolant System Purification Return Line in order to maintain
overpressure protection, replaces an isolation check valve in the CVS
with an air operated globe valve, and separates the zinc and hydrogen
injection lines.
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. ML13357A658.
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). These documents can be found in ADAMS under
Accession Nos. ML13357A569 and ML13357A598. 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. ML13357A498 and
ML13357A539. A summary of the amendment documents is provided in
Section III of this document.

II. Exemption

Reproduced below is the exemption document issued to VCSNS 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 a letter dated March 13, 2013, and as supplemented by the
letters dated July 11, October 28, and November 26, 2013, South
Carolina Electric & Gas Company (licensee) requested from the U. S.
Nuclear Regulatory Commission (Commission) an exemption from the
provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part
52, Appendix D, ``Design Certification Rule for the AP1000 Design,
Scope, and Contents,'' Section III.B, as part of license amendment
request, (LAR 13-07) ``Changes to the Chemical and Volume Control
System.''
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.
ML13357A658, 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 to the
provisions of 10 CFR part 52, Appendix D, Section III.B, to allow
deviations from the certified Design Control Document (DCD) Tier 1
Figures 2.2.1-1 and 2.3.2-1 and Tables 2.3.2-1 and 2.3.2-2, as
described in the licensee's request dated March 13, 2013, and
supplemented by the letters dated July 11, October 28, and November 26,
2013. This exemption is related to, and necessary for the granting of
License Amendment No. 11, 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. ML13357A658), 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 February 24, 2013.

III. License Amendment Request

By letter dated March 13, 2013, the licensee requested that the NRC
amend the COLs for VCSNS Units 2 and 3, COLs NPF-93 and NPF-94. The
licensee supplemented this application on July 11, October 28, and
November 26, 2013. The proposed amendment would depart from Tier 2
Material previously incorporated into the UFSAR. Additionally, these
Tier 2 changes involve changes to Tier 1 Information in the UFSAR, and
the proposed amendment would also revise the associated material that
has been included in Appendix C of each of the VCSNS, Units 2 and 3
COLs. The requested amendment will revise the Tier 2 UFSAR information
pertaining to the CVS, found throughout the UFSAR. These Tier 2 changes
require modifications to particular information located in Tier 1
Tables 2.3.2-1 and 2.3.2-2, and Tier 1 Figures 2.2.1-1 and 2.3.2-1.
These changes were necessary as part of a design modification which
provides a spring-assisted check valve to the Reactor Coolant System
Purification Return Line in order to maintain overpressure protection,
replaces an isolation check valve in the CVS with an air operated globe
valve, and separates the zinc and hydrogen injection lines.
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

[[Page 25161]]

April 2, 2013 (78 FR 19746). No comments were received during the 60-
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 March 13, 2013 and revised by letter dated July 11,
October 28, and November 26, 2013. The exemption and amendment were
issued on February 24, 2014 as part of a combined package to the
licensee (ADAMS Accession No. ML13357A436).

Dated at Rockville, Maryland, this 28th day of April 2014.
For the Nuclear Regulatory Commission.
Lawrence J. Burkhart,
Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2014-10113 Filed 5-1-14; 8:45 am]
BILLING CODE 7590-01-P

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