ML14073A405

Issuance of Amendment for the Technical Specifications Changes Related to Snubber Surveillance Requirements

ML14073A405
Person / Time
Site:	Surry
Issue date:	04/24/2014
From:	Martha Barillas Plant Licensing Branch II
To:	Heacock D Virginia Electric & Power Co (VEPCO)
Barillas M
References
TAC MF1872, TAC MF1873
Download: ML14073A405 (21)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 24, 2014 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company lnnsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

SURRY POWER STATION, UNITS 1 AND 2 -ISSUANCE OF AMENDMENT FOR THE TECHNICAL SPECIFICATIONS CHANGES RELATED TO SNUBBER SURVEILLANCE REQUIREMENTS (TAC NOS. MF1872 AND MF1873).

Dear Mr. Heacock:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 281 to Renewed Facility Operating License DPR-32 and Amendment No. 281 to Renewed Facility Operating.License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2 respectively, in response to your letter dated May 13, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML13137A313), as supplemented by letters dated September 9, 2013 (ADAMS ML13260A250} and March 13,* 2014 (ADAMS ML14019A083).

The amendment revises Technical Specifications (TS} 4.17, "Shock Suppressors (Snubbers)," to delete detailed surveillance requirements and reference the newly added Section, TS 6.4".T,

lnservice Examination, Testing, and Service Life Monitoring Program for Snubbers," which requires that the Surry, Units 1 and 2, snubber inservice examination, testing, and service life monitoring program be in accordance with the American Society of Mechanical Engineers (ASME)

Operation and Maintenance of Nuclear Power Plants (OM) Code, Subsection ISTD, as required by Title. 10 of the Code of Federal Regulations (CFR) 50.55a(b.)(3). *The amendment also relocates the detailed snubber program plan surveillance requirements to the Surry Units 1 and 2 lnservice Examination, Testing, and Service Life Monitoring Program Plans for Snubbers.

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

If you have any questions, please call me on 301-415-2760.

Docket Nos. 50-280 and 50-281

Enclosures:

1. Amendment No. 281 to DPR-32

2. Amendment No. 281 to DPR-37

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

Sincerely,

---4t/?-

Martha Barillas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation n

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 281

• Renewed License No. DPR-32

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated May 13, 2013, as supplemented by letters dated September 9, 2013, and March 13, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's r'ules 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 of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

\\

( 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-32 is hereby amended to read as follows:

(B)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 281, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

Attachment:

Changes to License No. DPR-32 and the Technical Specifications

.FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: April 2 4, 2 014

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2587 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No281 (are hereby incorporated in the renewed license. The licensee shall operate the -facility in accordance with the Technical Specifications.

C. Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.

D. Records E.

F.

G.

H.

I.

The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.

Deleted by Amendment 65 _

Deleted by Amendment 71 Deleted by Amendment 227 Deleted by Amendment 227 Fire Protection The licensee shall implement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19, 1979, (and Supplements dated May 29, 1980, October9, 1980, December 18, 1980, February 13,1981, December4, 1981, April27, 1982, November 18,1982, January 17,1984, February 25, 1988, and Surry-Unit 1 Renewed License No. DPR-32 Amendment No 281

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 2 81 Renewed License No. DPR-37

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated May 13, 2013, as supplemented by letters dated September 9, 2013, and March 13, 2014, 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 of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

c

2.

. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-37 is hereby amended to read as follows:

(B)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 281, are hereby incorporated in the renewed license. The licensee shall operate the facility iri accordance with the Technical Specifications.

3.

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

Attachment:

Changes License No. DPR-37 and the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: April 24, 2014 E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and the rules. regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A. Maximum Power Level

• The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2587 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No281. are hereby incorporated in this renewed license. The licensee l.. J shall operate the facility in accordance with the Technical Specifications.

C. Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.

D. Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.

E. Deleted by Amendment 54 F Deleted by Amendment 59 and Amendment 65 G. Deleted by Amendment 227 H. Deleted by Amendment 227 Surry-Unit 2 Renewed License No. DPR-37 Amendment No 281

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ATTACHMENT TO LICENSE AMENDMENT NO. 281 RENEWED FACILITY OPERATING LICENSE NO. DPR-32 DOCKET NO. 50-280 AND LICENSE AMENDMENT NO. 281 RENEWED FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NO. 50-281 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages License License No. DPR-32, page 3 License No. DPR-37, page 3 TSs 4.17-1 4.17-2 4.17-3 4.17-4 4.17-5 4.17-6 4.17-7 4.17-8 4.17-9 4.17-10 6.4-15 Insert Pages License License No. DPR-32, page 3 License No. DPR-37, page 3 TSs 4.17-1 4.17-2 4.17-3 6.4-15 6.4-16

TS 4.17-1 4.17 SHOCK SUPPRESSORS (SNUBBERS)

Applicability Applies to all hydraulic and J?echanical shock suppressors (snubbers) which are required to protect the Reactor Coolant System and other safety-related systems. Snubbers excluded from this inspection are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

Objective To specify the minimum frequency and type of surveillance to be applied to the hydraulic and mechanical snubbers required to protect the Reactor Coolant System and other safety-related systems.

Specification Each snubber shall be demonstrated OPERABLE by performance of the Units 1 and 2 Inservice Examination, Testing, and Service Life Monitoring Program Plans for Snubbers.

The Program is defined in TS 6.4.T..

A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the action requirements of Specification 3.20 shall be met.

)

Amendment Nos. 281, 281

TS4.17-2 Bases All snubbers are required operable to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

Amendment Nos. 281, 281

TS4.17-3 Pages 4.17-3 through 4.17-52 have been deleted.

Amendment Nos. 281, 281

TS 6.4-15

4. Measurement, at designated locations, of the MCRJESGR envelope pressure relative to all external areas adjacent to the MCRJESGR envelope boundary during the pressurization mode of operation by one train of the MCR/ESGR EVS, operating at the flow rate required by TS 4.20, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the MCRJESGR envelope boundary.

5. The quantitative limits on unfiltered air inleakage into the MCRIESGR envelope.

These limits shall be stated in a manner to allow direct comparison to the t,Infiltered air inleakage measured by the testing described in paragraph 3. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of MCR/ESGR envelope occupants to these hazards will be within the assumptions in the licensing basis.

6. The provisions of SR 4.0.2 are applicable to the Frequencies for assessing

• MCRIESGR envelope habitability, determining MCRIESGR envelope unfiltered inleakage, and measuring MCR/ESGR envelope pressure and assessing the MCRJESGR envelope boundary as required by paragraphs 3 and 4, respectively.

S. Surveillance Frequency Control Program (SFCP)

This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specification are performed at interval sufficient to assure the associated Limiting Conditions for Operation are met.

a.

The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b.

Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c.

The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

T. Inservice Examination, Testing, and Service Life Monitoring Program for Snubbers 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:

Amendment Nos. 281, 281

TS 6.4-16

a.

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

b.

The 'program shall meet the requirements of 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 its limitations and modifications, and subject to Commission approval.

c.

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," in lieu of Section XI of the ASME BPV Code lSI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR 50.55a(a)(3).

d.

The 120-month program updates shall be made in accordance with 10 CFR 50.55a (including 10 CFR 50.55a(b)(3)(v)) subject to the limitations and modifications listed therein.

Amendment Nos. 281, 281

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 281 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 281 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281

1.0 INTRODUCTION

Sy license amendment request (LAR) dated May 13, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13137A313), as supplemented by letters dated September 9, 2013, (ADAMS Accession No. ML13260A250), and March 13, 2014 (ADAMS Accession No. ML14079A083) the Virginia Electric and Power Company (licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) a request to revise Technical Specifications (TS) 4.17, "Shock Suppressors (Snubbers)," to delete detailed surveillance requirements and reference the newly added Section, TS 6.4.T, "lnservice Examination, Testing, and Service Life Monitoring Program for Snubbers," which requires that the Surry, Units 1 and 2, proposed

• snubber inservice examination, testing, and service life monitoring program be in accordance with the American Society of Mechanicai.Engineers (ASME) Operation and Maintenance of Nuclear Power Plants (OM) Code, Subsection ISTD, as required by Title 10 of the Code of Federal Regulations (CFR) 50.55a(b)(3). The amendment also relocates the detailed snubber program plan surveillance requirements to the Surry Units 1 and 2 lnservice Examination, Testing, and Service Life Monitoring Program Plans for Snubbers.

The supplements, dated September 9, 2013, and March 13, 2014, provided additional information that clarified the application, 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 July 9, 2013.

2.0 REGULATORY EVALUATION

The Surry, Units 1 and 2, snubber monitoring program provides requirements for the performance and administration of assessing the operational readiness of those dynamic restraints (Snubbers) whose specific functions are required to shutdown the reactor to the safe shutdown condition, maintain the reactor in the safe shutdown condition, mitigate the consequences of an accident, or to ensure the integrity of the reactor coolant pressure boundary.

The proposed change would relocate the specific snubber inservice examination, and testing, and service life monitoring program requirements located in TS 4.17 to a newly added section, TS 6.4.T.

Title 10 of the Code of Federal Regulations (1 0 CFR) 50.36, "Technical Specifications," provides the regulatory requirements for the contents in a licensee's TSs. This regulation requires that the TSs include items in the following five specific categories related to station operation. These categories include (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 surveillance requirements to be included in a plant's TSs. Section 50.36(c)(3) states that SRs are requirements relating to test, calibration, or inspection to assure that necessary quality of systems and components is maintained.

In general, there are two classes of changes toTS: (1) changes needed to reflect modifications to the design bases (TS are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required contents and preferred format of TS. This amendment deals with the second class of changes. In determining the acceptability of revising TS 4.17, the staff used guidance in NUREG-1431, "Standard Technical Specifications, Westinghouse Plants, Revision 4.0," dated April20~2.

The provisions of 10 CFR 50.55a(g)(5)(ii) require that, if a revised lSI program for a facility conflicts with the TS for that facility, th_e licensee shall apply to the Commission for amendment of.

the TS to conform the TS to the revised program.

The provisions of 1 0 CFR 50.55a(b)(3)(v) allow licensees the option of using the inservice examination and testing provisions for snubbers in the American Society of Mechanical

. Engineers Boiler and Pressure Vessel (ASME B&PV) Code Section XI, or the ASME Operation and Maintenance of Nuclear Power Plants (OM) Code. However, the 2006 addenda and later editions, and addenda of ASME B&PV Code Section XI, do not have inservice inspection provisions for snubbers. When using the 2006 addenda or later editions and addenda of ASME B&PV Code Section XI, 10 CFR 50.55a(b)(3)(v)(B) provides that snubber examination and testing must be in accordance with the ASME OM Code, Subsection ISTD.

Surry Unit 1 is currently in the fifth 1 0-year lSI interval for snubber inservice examination and testing. The Surry Unit 1 fourth 1 0-year lSI interval for snubber inservice examination and testing ended on December 13, 2013. Surry Unit 2 is currently in the fourth 1 0-year lSI interval for snubber inservice examination and testing, which is scheduled to end on May 9, 2014. The fifth 1 0-year lSI interval at Surry Unit 1 began on December 14, 2013 and.is scheduled to end on October 13, 2023. The fifth 1 0-year lSI interval at Surry, Unit 2, is scheduled to begin on May 10, 2014, and to end on May 09, 2024. Surry Unit 1 fifth 10 year lSI interval, snubber examination and testing is being performed in accordance with the requirements of the ASME OM Code, Subsection ISTD, 2004 Edition per 10 CFR 50.55a(b)(3)(v)(A). Surry Unit 2 fourth 1 0-year lSI interval for snubber examination and testing is being performed in accordance with the specific requirements of TS 4.17 and Relief Request CS-001 as authorized in 2004 by NRC in ADAMS Accession No. ML041460381. The licensee proposes to revise the TS to require that the 1 0-year lSI interval snubber inservice examination and testing program at Surry, Units 1 and 2, meet the requirements of the ASME OM Code, Subsection ISTD, 2004 Edition per 10 CFR 50.55a(b)(3)(v)(A).

3.0 TECHNICAL EVALUATION

3.1 Licensee's Proposed TS Changes and Basis Information The proposed changes to the Surry, Units 1 and 2, TSs are summarized below:

TS 4.17, "Shock Suppressors (Snubbers)," specification will be revised to replace specific surveillance requirements for demonstrating snubber operability with a reference to the newly added Administrative Control Section, 6.4.T "lnservice Examination, Testing, and Service Life Monitoring Program for Snubbers," as follows:

TS 4.17 Specification Each snubber shall be demonstrated OPERABLE by performance of the Units 1 and 2 lnservice Examination, Testing, and Service Life Monitoring Program Plans for Snubbers.

The program is defined in TS 6.4.T.

A review and evaluation shall be performed and documented to justify operation with an unacceptable snubber. If continued operation cannot be justified the snubber shall be declared inoperable and action requirements of Specification 3.20 shall be met.

The previous details about snubber visual inspection, functional testing and service life program requirements that are described in TS 4.17 Specification sections A, B, C, D, E and Fare to be deleted.

Section 6.4.T, "lnservice Examination, Testing, and Service Life Monitoring Program for Snubbers," will be added to the TS Administrative Controls Section 6.4 "Procedures and Programs," to provide a description of the snubber testing program as follows:

. 6.4.T lnservice Examination, Testing and Service Life Monitoring Program for Snubbers 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:

a. The program shall meet 1 0 CFR 50.55a(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 ASME BPV Code and the ASME OM Code that are incorporated by reference in 10 CFR 50.55a(b), subject to its limitations and modifications, and subject to Commission approval.

c. The program shall, as allowed by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Preservice and lnservice 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 50.55a(a)(3).

d. The 120-month program updates shall be made in accordance with 10 CFR 50.55a (including 10 CFR 50.55a(b)(3)(v)) subject to the limitations and modifications [conditions]

listed therein.

At Surry, Unit 1, during the fourth 1 0-year lSI interval, snubber visual inspection and functional testing were performed in accordance with the specific requirements of TS 4.17 as approved by NRC in Relief Request CS-001 (ADAMS Accession No. ML040960543). Similarly, at Surry Unit 2, the fourth 1 0-year lSI interval for the snubber visual examination and testing is being performed in accordance with TS 4.17 and Relief Request CS-001 in lieu of certain requirements contained in the 1998 Edition with addenda up to and including the 2000 Addenda of ASME BP&V Code Section XI (ADAMS Accession No. ML041460381 ).

For the fifth 1 0-year lSI interval, as allowed by 10 CFR 50.55a(b)(3)(v)(A), Surry, Unit 1 has adopted Subsection ISTD, of the ASME OM Code, 2004 Edition, and Unit 2 will adopt Subsection ISTD, of the ASME OM Code, 2004 Edition. As requested by the licensee, in Relief Requests S1-15-ISI-01 and S2-15-ISI-01 (ADAMS Accession No. ML 131 OOA049), the NRC authorized that the fifth 1 0-year lSI interval be conducted to the requirements of the 2004 Edition of ASME B&PV Code Section XI, instead of the 2007 Edition with 2008 Addenda, which are the latest edition and addenda endorsed by 10 CFR 50.55a(b). As such, the proposed changes toTS 4.17 are required to conform the TS to reflect this revised snubber program.

3.2 NRC Staff Evaluation of Proposed Changes The licensee has developed a detailed "lnservice Examination, Testing and Service Life Monitoring Program Plan for Snubbers (Snubber Testing Program)," as a licensee-controlled document at Surry, Units 1 and 2, which will be implemented in lieu of the deleted TS snubber inservice examination, testing and service life program requirements in TS 4.17. This Snubber Testing Program will contain a snubber inservice examination, testing and service life monitoring program based on the requirements referenced in the TS Administrative Control Section 6.4.T.

The NRC staff has reviewed the requirements for the Snubber Testing Program, as described in its submittal and as proposed in the newTS 6.4.T. In NUREG-1431, Rev.4, Standard Technical Specifications, Westinghouse Plants, Nf3C allowed licensees to relocate their snubber program from TS to a licensee-controlled document. The snubber program must be maintained in a licensee-controlled document and must meet the 1 0 CFR 50.55a requirements. The licensee proposes to relocate the snubber program requirements to the Administrative Controls section of Surry TS. The NRC staff finds that the program requirements are consistent with the inservice examination and testing requirements for snubbers as required by 10 CFR 50.55a. TS 6.4.T requires that the snubber inservice examination and testing program at Surry, Units 1 and 2, meet 10 CFR requirements and be performed per the requirements of the ASME OM Code, Subsection ISTD, 2004 Edition, as required by 10 CFR 50.55a(b)(3)(v)(A) or meet authorized alternatives.

Therefore, the NRC staff concludes. that the proposed deletion of the detailed snubber surveillance requirements in TS 4.17 and the newly proposed TS 6.4.T are acceptable.

Based on the above finding that the Snubber Testing Program is consistent with 10 CFR 50.55a, the NRC staff further finds that the examination, testing and service life monitoring for snubbers in accordance with the Snubber Testing Program, as required by TS 4.17, is sufficient to demonstrate that snubbers are OPERABLE in accordance with TS 3.20, '"'Shock Suppressors (Snubbers)," specifications under TS 3.0 "Limiting Conditions for Operation." Therefore, the NRC staff concludes that the proposed changes to TS 4.17 are consistent with the requirements in 10 CFR 50.36(c)(3) and, therefore, are acceptable.

The fifth 1 0-year lSI interval at Surry, Unit 1, began on December 14, 2013, and scheduled to end on October 13, 2023. Whereas, the fifth 1 0-year lSI interval at Surry, Unit 2, is scheduled to begin on May 10, 2014, and end on May 09, 2024. In its submittal, the licensee included the updated snubber in service inspection and testing program.at Surry, Units 1 and 2, for the fifth 1 0-year lSI interval, to meet the requirements of the ASME OM Code, Subsection ISTD, 2004 Edition.

As set forth above, the NRC staff concludes that the proposed TS amendments are acceptable.

Specifically, the change replaces the TS 4.17 specification requirements for snubber inservice examination, testing and service life monitoring with a reference to the lSI program requirements for snubbers contained in TS Administrative Control Section 6.4.T and revises the Administrative Controls sections of the TSs to add TS 6.4.T, "lnservice, Examination, Testing; and Service Life Monitoring Program for Snubbers." TS 6.4.T requires the program to meet 10 CFR 50.55a or authorized alternatives.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 1 0 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve 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 haspreviously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (78 FR 41122, dated July 9, 2013}. Accordingly, the amendments meet 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 amendments.

6.0 CONCLUSION

The Commission has concluded, based on the consiqerations 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 lnservice 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, Surry Power Station, Units 1 and 2 (ML05291 03,58).

NUREG-1431, Rev. 4, Standard Technical Specifications, Westinghouse Plants (ML 121 OOA222).

Letter, Virginia Electric and Power Company (Dominion), to NRC, "Surry Power Station Units 1 and 2, Docket Nos. 50-280 and 50-281, Operati~g License Nos. DPR-32 and DPR-37, Proposed License Amendment Request Regarding Relocation of Snubber Surveillance Requirements from Technical Specification 4.17 to Snubber Program, dated May 13, 2013 (ML13137A313).

Principal Contributors: Gurjendra Bedi, NRR Robert Wolfgang, NRR Date: April 24, 2014

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

If you have any questions, please call me on 301-415-2760.

Sincerely,

/RA/

Martha Barillas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281

Enclosures:

1. Amendment No. 281 to DPR-32

2. Amendment No. 281 to DPR-37

3. Safety Evaluation

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