ML13354B643

Issuance of Amendment for the Technical Specification Change Related to Snubber Surveillance Requirements

ML13354B643
Person / Time
Site:	Summer
Issue date:	02/06/2014
From:	Shawn Williams Plant Licensing Branch II
To:	Gatlin T South Carolina Electric & Gas Co
Williams, Shawn NRR/DORL 415-1009
References
TAC MF1383
Download: ML13354B643 (15)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 6, 2014 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville. SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 -ISSUANCE OF AMENDMENT FOR THE TECHNICAL SPECIFICATION CHANGE RELATED TO SNUBBER SURVEILLANCE REQUIREMENTS (TAC NO. MF1383)

Dear Mr. Gatlin:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 195 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit 1 (VCSNS), in response to your letter dated April 2, 2013Property "Letter" (as page type) with input value "RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., as supplemented by letters dated October 10 and December 5,2013. This amendment revises the Snubber Technical Specifications 3/4.7.7 to confirm planned revisions to the snubber inservice inspection and testing program.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's Biweekly Federal Register notice.

Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395

Enclosures:

1. Amendment No. 195 to NPF-12

2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTH CAROLINA ELECTRIC &GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 Renewed License No. NPF-12

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by South Carolina Electric &Gas Company (the licensee), dated April 2, 2013, as supplemented by letters dated October 10 and December 5, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance ofthis amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-12 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. South Carolina Electric &Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-12 and the Technical Specifications Date of Issuance: February 6, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 195 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the License and Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages I nsert Pages License License License No. NPF-12 License No. NPF-12 Page 3 Page 3 TS TS 3/47-16 3/47-16 3/47-17 3/47-17 3/47-18 3/47-19 3/47-20 3/4 7-21 6-12i

-3 (3)

SCE&G, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage amounts required for reactor operation, as described in the Final Safety Analysis Report, as amended through Amendment No. 33; (4)

SCE&G, pursuant to the Act and 10 CFR Part 30, 40 and 70 to receive, possess and use at any time byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

SCE&G, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus of components; and (6)

SCE&G, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as my be produced by the operation of the facility.

C.

This renewed license shall be deemed to contain, and is subject to, the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level SCE&G is authorized to perathe the facility at reactor core power levels not in excess of 2900 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to this renewed license.

The preoccupation tests, startup tests and other items identified in to this renewed license shall be completed as specified. is hereby incorporated into this renewed license.

(2)

Technical Specifications and Environmental Protection Plant The Technical Specifications contained in Appendix A, as revised through Amendment No. 195 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed Facility Operating License No. NPF-12 Amendment No. 195

PLANT SYSTEMS 3/4.7.7 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.7 All snubbers on systems required for safe shutdown/accident mitigation shall be OPERABLE. This includes safety and non-safety related snubbers on systems used to protect the code boundary and to ensure the structural integrity of these systems under dynamic loads.

APPLICABILITY:

MODES 1, 2, 3 and 4. MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation for Specification 4.7.7 on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.7 Each snubber shall be demonstrated OPERABLE by performance of the Snubber Testing Program in Section 6.8.4.n.

SUMMER - UNIT 1 3/47-16 Amendment No. 47,103,195

The following pages have been deleted.

3/47-17 3/47-18 3/47-19 3/47-20 3/47-21 SUMMER - UNIT 1 3/47-17 Amendment No. 195

ADMINISTRATIVE CONTROLS

n.

Snubber Testing Program This program conforms to the examination, testing and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a inservice inspection (lSI) requirements for supports. The program shall be in accordance with the following:

1)

This program shall meet 10 CFR 50.55a(g) lSI requirements for supports.

2)

The program shall meet the requirements for lSI of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b) subject to limitations and modifications listed in 10 CFR 50.55a(b) and subject to Commission approval.

3)

The program shall. as allowed by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements," and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in light-Water Reactor Nuclear Power Plants," or meet authorized alternatives pursuant to 10 CFR 50.55a(a)(3).

4)

The 120-month program updates shall be made in accordance with 10 CFR 50.55a(g)(4), 10 CFR 50.55a(g)(3)(v) and 10 CFR 50.55a(b)

(including 10 CFR 50.55a(b)(3)(v>> subject to the limitations and modifications listed therein.

SUMMER - UNIT 1 6-12i Amendment No.195

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• • • • . SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 195 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 DOCKET NO. 50-395

1.0 INTRODUCTION

By letter dated April 2, 2013Property "Letter" (as page type) with input value "RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13095A107), South Carolina Electric & Gas Company (SCE&G), the licensee, submitted a request for changes to the Virgil C. Summer Nuclear Station, Unit 1 (VCSNS) Technical Specifications (TSs). In response to a clarification, the licensee supplemented the original license amendment request (LAR) on October 3, 2013 (ADAMS Accession No. ML13281A190) and December 5,2013 (ADAMS Accession No. ML13343A152).

The supplements did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on 78 FR 31983.

The proposed amendment would revise the TS 3/4.7.7, specifically TS Surveillance Requirement (SR) 4.7.7 to reference the newly added Administrative Control, TS Section 6.8.4.n, "Snubbers Testing Program." This addition includes the planned revisions to the VCSNS snubber inservice inspection (lSI), testing, and service life monitoring programs and removes the specific snubber inservice examination and testing requirements from TSs. Additionally, the application included associated TS 3/4.7.7 Bases.

2.0 REGULATORY EVALUATION

A dynamic restraint (snubber) is a device designed to protect components from excess shock or sway caused by seismic disturbances or other transient forces. During normal operating conditions, the snubber allows for movement in tension and compression. When an impulse event occurs, the snubber becomes activated and acts as a restraint device. The device becomes rigid, absorbs the dynamic energy, and transfers it to the supporting structure.

The proposed change, in essence, relocates the specific snubber inservice examination and testing requirements located in TS 3/4.7.7 and replaces them with a new TS surveillance requirement 4.7.7 that requires "Each snubber shall be demonstrated OPERABLE by performance of the Snubber Testing Program in Section 6.8.4.n."

- 2 The revised Snubber Testing Program includes revisions to the VCSNS snubber lSI, testing, and service life monitoring programs. The purpose of the Snubber Testing Program as provided in the April 2, 2013, LAR, Attachment 5, "Snubber Examination, Testing, and Service Life Monitoring Program Plan" is to provide requirements for the performance and administration of assessing the operational readiness of those dynamic restraints whose specific functions are required to ensure the integrity of the reactor coolant pressure boundary.

Title 10 of the Code of Federal Regulations (10 CFR) 50.36, "Technical Specifications," provides the regulatory requirements for the contents in a licensee's TSs. Section 50.36(c) requires that the TSs include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCO); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plant's TSs. 10 CFR 50.36(c)(3) notes that SRs are requirements relating to test, calibration, or inspection to assure that necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.

The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to 10 CFR 50.34. The Commission may include such additional technical specifications as the Commission finds appropriate. In determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate.

In determining the acceptability of revising TS 3/4.7.7, the staff used the approved guidance in NUREG-1431, "Standard Technical Specifications, Westinghouse Plants, Revision 4.0," dated April 2012.

Requirements for inservice inspection of Class 1, Class 2, Class 3, Class MC, and Class CC components (including their supports) are located in 10 CFR 50.55a(g). 10 CFR 50.55a(g)(5)(ii) requires that, if a revised lSI program for a facility conflicts with the TS for that facility, the licensee shall apply to the Commission for amendment of the TS to conform the TS to the revised program.

The licensee shall submit this application at least six months before the start of the period during which the provisions become applicable.

10 CFR 50.55a(b)(3)(v) states that subsection ISTD. Article IWF-5000, "Inservice Inspection Requirements for Snubbers," of the ASME B& PV Code,Section XI, must be used when performing lSI examinations and tests of snubbers at nuclear power plants, with two exceptions.

Licensees may use Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Power Plants," ASME OM Code, 1995 Edition through the latest edition and addenda incorporated by reference in paragraph 50.55a(b)(2), in place of the requirements for snubbers in the editions and addenda up to the 2005 Addenda of the ASME B&PV Code,Section XI, IWF-5200(a) and (b) and IWF-5300(a) and (b), by making appropriate changes to their technical specifications or licensee-controlled documents. Preservice and in service examinations must be performed using the VT-3 visual examination method described in IWA-2213. However, licensees shall comply with the provisions for examining and testing snubbers in Subsection ISTD of the ASME OM Code and make appropriate changes to their technical specifications or licensee-controlled documents

- 3 when using the 2006 Addenda and later editions and addenda of Section XI of the ASME B&PV Code.

The ASME B&PV Code Section XI option no longer exists when using the 2006 addenda, later editions, and addenda of ASME B&PV Code Section XI because these editions and the addenda of Section XI do not provide inservice inspection provisions for snubbers. When using the 2006 addenda or later editions of ASME B&PV Code Section XI, snubber examination and testing must be in accordance with the ASME OM Code, Subsection ISTD.

VCSNS is currently in the third 1 O-year lSI interval. The third 10-year lSI interval at VCSNS is scheduled to end on December 31, 2013. The fourth 10-year lSI interval at VCSNS is scheduled to begin on January 1,2014 and end on December 31,2023. Currently, snubber examination and testing are performed in accordance with the specific requirements ofTS 3/4.7.7 instead of ASME Code Section XI requirements for snubber visual examination and testing, as authorized by NRC pursuant to 10 C.F.R. 50.55a(a)(3)(i) in a letter dated May 10, 2005 (ADAMS Accession No. ML051290198). For the fourth 1 O-year lSI interval at VCSNS, the snubber program will meet the requirements of the ASME OM Code, Subsection ISTD, Edition 2004 with 2005 and 2006 Addenda per 10 CFR 50.55a(b)(3)(B).

3.0 TECHNICAL EVALUATION

3.1 Licensee's Proposed TS Changes and Basis Information The proposed changes to the VCSNS TSs are summarized below:

• Reference to TS Specification 4.7.7.g in TS ACTION 3.7.7 will be replaced with reference to TS Specification 4.7.7.

• TS SR 4.7.7 will be revised to replace specific surveillance requirements for demonstrating snubber operability with reference to the newly added Administrative Control Section 6.8.4.n "Snubber Examination Program," as follows:

TS SR4.7.7 Each snubber shall be demonstrated OPERABLE by performance of the Snubber Testing Program in Section 6.8.4.n.

(Note: All other details about snubber visual inspection, functional testing and service life program requirements as described in TS SR 4.7.7 a, b, c, d, e, f, g, h, and i which are proposed to be deleted, are not being repeated here).

Section 6.8.4.n, "Snubber Testing Program," will be added to the TS Administrative Controls Section 6.8,4 "Procedures and Programs," to provide a description of the snubber testing program as follows:

6.8.4.n SNUBBER Testing Program This program conforms to the examination, testing, and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a lSI requirements for supports.

The program shall be in accordance with the following:

-4

a.

This program shall meet 10 CFR SO.SSa(g) lSI requirements for supports.

b.

The program shall meet the requirements for lSI of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR SO.SSa(b), subject to its limitations and modifications [conditions].

c.

The program shall, as allowed by 10 CFR SO.SSa(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants" in lieu of Section XI of the ASME BPV Code lSI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR SO.SSa(a)(3).

d.

The 120-month program updates shall be made in accordance with 10 CFR SO.SSa (including 10 CFR SO.SSa(b)(3)(v>> subject to the limitation and modifications [conditions] listed therein.

At VCSNS during third 10-year lSI interval, snubber visual inspection and functional testing are being performed in accordance with the specific requirements of TS 3/4.7.7. As requested by the licensee, in Relief Request PR-III-01, the NRC authorized use of TS 3/4.7.7 for the third 10-year lSI interval in lieu of the requirements contained in the 2000 Edition (no Addenda) of ASME B&PV Code Section XI.

For the fourth 10-year lSI interval, as required by 10 CFR SO.SSa(b)(3)(v)(B), VCSNS intends to adopt Subsection ISTD, of the ASME OM Code, 2004 Edition with 200S and 2006 addenda. The ASME B&PV Code Section XI option no longer exists when using the 2006 addenda and later editions and addenda of ASME B&PV Code Section XI because these editions and addenda of Section XI do not provide lSI provisions for snubbers. As such, the proposed changes to TS 3/4.7.7 are required to conform the TSs to this revised snubber program.

3.2 NRC Staff Evaluation of Proposed Changes The NRC Staff compared the proposed changes to the technical speCifications with the lSI requirements for snubbers contained in 10 CFR SO.SSa(b)(3)(v). Per 10 CFR SO.SSa(b)(3)(v)(B),

a licensee shall make appropriate changes to its technical specifications or licensee-controlled documents when using the 2006 Addenda and later editions of Section XI of the ASME B&PV Code. The staff considered whether the proposed changes were appropriate.

The licensee has developed a detailed "Snubber Testing Program," as a licensee-controlled document at VCSNS, which will be implemented in lieu of the deleted TS snubber examination, testing and service life program requirements. This "Snubber Testing Program," will contain a snubber examination, testing and service life monitoring program and will be based on the requirements referenced in the TS Administrative Control Section 6.8.4.n.

The NRC staff has reviewed the requirements for the "Snubber Testing Program," as described in the submittal and as proposed in the new TS 6.8.4.n. The staff finds that the program

- 5 requirements are consistent with the lSI and testing requirements for snubbers as required by 10 CFR 50.55a(g). The staff also notes that the snubber lSI and testing program at VCSNS will be performed per the requirements of the ASME OM Code 2004 Edition with 2005 and 2006 Addenda), Subsection ISTD because the licensee's code of record for the fourth 10-year lSI interval is ASME OM Code 2004 Edition with 2005 and 2006 Addenda. Therefore, the NRC staff concludes that the proposed new TS 6.8.4.n is acceptable.

The NRC staff further finds that the examination, testing and service life monitoring for snubbers in the "Snubber Testing Program," (SR 4.7.7) is sufficient to assure that the LCO for snubbers (i.e.

LCO 3.7.7) will be met. Therefore, the NRC staff concludes that the proposed SR 4.7.7 is consistent with the how surveillance requirements are defined in 10 CFR 50.36(c)(3) and, therefore, are acceptable.

The NRC staff finds that the proposed change to LCO 3.7.7 to revise its existing reference to Specification SR 4.7.7 is a necessary conforming change. Therefore, the staff concludes that this change is acceptable.

Based on the above, the NRC staff concludes that the proposed amendment to revise the Snubber TS 3/4.7.7 is acceptable. Specifically, the change replaces the TS SR 4.7.7 requirements for snubber examination, testing and service life monitoring with reference to the lSI program requirements for snubbers contained in TS Administrative Control Section 6.8.4.n and revises the Administrative Controls sections of the TSs to add a "Snubber Testing Program."

As specified in this submittal, the licensee will update the snubber inservice inspection and testing program at VCSNS for the fourth 10-year lSI interval to meet the requirements of the ASME OM Code, Edition 2004 with 2005 and 2006 Addenda, Subsection ISTD.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (78 FR 31983, May 28,2013). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

- 6

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

u.s. Code of Federal Regulations, Domestic Licensing of Production and Utilization Facilities, Part 50, Chapter I, Title 10, Section 50.55a, Codes and standards.

American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2007 Edition with 2008 addenda.

American Society of Mechanical Engineers (ASME)/American Nuclear Standards Institute (ANSI)

Operation and Maintenance of Nuclear Power Plants (OM), 2004 Edition with 2005 and 2006 Addenda.

Technical Specification, V. C. Summer Nuclear Station, Unit 1.

NUREG-1431, Revision 4, Standard Technical Specifications, Westinghouse Plants.

Letter, South Carolina Electric & Gas Company (SCE&G), to NRC, "Virgil C. summer Nuclear Station Unit 1 (VCSNS), Docket No. 50-395, Operating License No. NPF-12, License Amendment Request - LAR 12-06014, Changes to Snubber Surveillance Requirements, dated April 2, 2013 (ADAMS Accession No. ML13095A107).

Letter, South Carolina Electric & Gas Company (SCE&G), to NRC, "Virgil C. summer Nuclear Station Unit 1 (VCSNS), Docket No. 50-395, Operating License No. NPF-12, Revision to License Amendment Request - LAR 12-06014, Changes to Snubber Surveillance Requirements, dated October 3,2013 (ADAMS Accession No. ML13281A190).

Letter, South Carolina Electric & Gas Company (SCE&G), to NRC, "Virgil C. Summer Nuclear Station Unit 1 (VCSNS), Docket No. 50-395, Operating License No. NPF-12, Date Correction to License Amendment Request - LAR 12-06014, Changes to Snubber Surveillance Requirements, dated December 5, 2013 (ADAMS Accession No. ML13343A152).

Principal Contributors:

Gurjendra Bedi, NRR/DE/EPNB Date: February 6, 2014

February 6, 2014 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 -ISSUANCE OF AMENDMENT FOR THE TECHNICAL SPECIFICATION CHANGE RELATED TO SNUBBER SURVEILLANCE REQUIREMENTS (TAC NO. MF1383)

Dear Mr. Gatlin:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 195 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit 1 (VCSNS), in response to your letter dated April 2, 2013Property "Letter" (as page type) with input value "RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., as supplemented by letters dated October 10 and December 5,2013. This amendment revises the Snubber Technical Specifications 3/4.7.7 to confirm planned revisions to the snubber inservice inspection and testing program.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's Biweekly Federal Register notice.

Sincerely.

IRAJ Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-395

Enclosures:

1. Amendment No. 195 to NPF-12

2. Safety Evaluation cc w/encrs: Distribution via Listserv DISTRIBUTION:

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