ML13302B893

Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D

ML13302B893
Person / Time
Site:	North Anna
Issue date:	10/02/2013
From:	Blakeney D Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML13302B894	List: ML13302B891 ML13302B892 ML13302B893
References
13-518
Download: ML13302B893 (6)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 2, 2013 U.S. Nuclear Regulatory Commission Serial No.13-518 Attention: Document Control Desk NAPS/JHL RO Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNITS I AND 2 ANNUAL SUBMITTAL OF TECHNICAL SPECIFICATION BASES CHANGES PURSUANT TO TECHNICAL SPECIFICATION 5.5.13.d Pursuant to Technical Specifications 5.5.13.d, "Technical Specifications (TS) Bases Control Program," Dominion hereby submits the changes to the Bases of the Technical Specifications implemented during the period of October 1, 2012 through September 30, 2013. A summary of these changes is provided in Attachment 1. Enclosed is an electronic copy (CD) of the entire TS Bases through Revision 51 for your information.

Bases changes to the Technical Specifications that were not previously submitted to the NRC as part of a License Amendment Request were reviewed and approved by the Facility Safety Review Committee. It was determined that these changes did not require a change to the Technical Specifications or license, or involve a change to the UFSAR or Bases that required NRC prior approval pursuant to 10CFR50.59. These changes have been incorporated into the TS Bases. A summary of these Bases changes is provided in Attachment 1.

TS Bases changes that were submitted to the NRC for information along with the associated License Amendment Request transmittals, submitted pursuant to 10CFR50.90, were also reviewed and approved by the Facility Safety Review Committee. These changes have been implemented with the respective License Amendments. A summary of these changes is provided in Attachment 2.

If you have any questions regarding this submittal, please contact Mr. Page Kemp at (540) 894-2295.

Sincerely, David B. Blakeney Director, Nuclear Safety and Licensing A40D

Attachments

1. Summary of TS Bases Changes Not Previously Submitted to the NRC

2. Summary of TS Bases Changes Associated with License Amendments Enclosure - CD of Current TS Bases (Revision 51)

Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I!

Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. J. E. Reasor, Jr. (without Enclosure)

Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.

Suite 300 Glen Allen, Virginia 23060 State Health Commissioner (without Enclosure)

Virginia Department of Health James Madison Building - 7 th Floor 109 Governor Street Room 730 Richmond, Virginia 23219 Dr, V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 G-9A Rockville, Maryland 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 G-9A Rockville, Maryland 20852-2738 NRC Senior Resident Inspector (without Enclosure)

North Anna Power Station

ATTACHMENT I

SUMMARY

OF TS BASES CHANGES NOT PREVIOUSLY SUBMITTED TO THE NRC Virginia Electric and Power Company (Dominion)

North Anna Power Station Units I and 2

Summary of TS Bases Changes Not Previously Submitted to the NRC Implementation of ETE-NAF-2013-0047, Revised Steam Generator Tube Rupture (SGTR) Event Analysis Technical Specification (TS) Bases 3.7.10 Main Control Room/Emergency Switchgear Room Emergency Ventilation System (MCRIESGR EVS) is revised to maintain consistency with the UFSAR. ETE-NAF-2013-0047 Revision 0, Implementation of the revised NAPS Steam Generator Tube Rupture (SGTR) event analysis (RA-0031-1-0 and SM-1637-1-0), including 50.59 Evaluation No.

13-SE-OT-03, and proposed UFSAR Change Request No. UCR-2012-028, were previously approved by the Facility Safety Review Committee.

The Applicable Safety Analysis discussion in the bases of TS 3.7.10 describes that the MCR/ESGR EVS is credited in the Loss of Coolant Accident (LOCA).

The bases was revised as follows:

"The SGTR analysis assumes MCR/ESGR envelope isolation occurs. An unfiltered MCRPESGR inleakage of 250 cfm is assumed, with filtered makeup air of 900 cfm commencing at 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />."

The discussion also indicates that the Fuel Handling Accident credits isolation of the control room, but that the other design basis accidents do not.

Engineering Technical Evaluation ETE-NAF-2013-0047 implements the new Steam Generator Tube Rupture (SGTR) event analysis documented in calculation RA-0031-1-0. RA-0031-1-0 documents the doses in the NAPS control room, at the exclusion area boundary (EAB), and at the low population zone (LPZ) as a result of a SGTR accident using the RADTRAD-NAI computer code. RA-0031-1-0 bases its calculations on the alternative source term (AST) methodologies that have been previously approved in accordance with Regulatory Guide 1.183, and incorporates a revised SG Power Operated Relief Valve (PORV) flow capacity. The previous design and licensing basis analyses conservatively did not credit control room isolation, although isolation will occur following a Safety Injection (SI) signal generated from this event. Under the provisions of 10 CFR 50.59, the control room isolation that occurs automatically may be credited in the SGTR analysis.

ATTACHMENT 2

SUMMARY

OF TS BASES CHANGES ASSOCIATED WITH LICENSE AMENDMENTS Virginia Electric and Power Company (Dominion)

North Anna Power Station Units I and 2

Summary of TS Bases Changes Associated with License Amendments Elimination of Steam Generator Water Level Low Coincident with Steam Flow/Feedwater Flow Mismatch Reactor Trip Function The amendments eliminate the Steam Generator Water Level Low Coincident with Steam Flow/Feedwater Flow Mismatch Reactor Trip Function from Technical Specification (TS) Table 3.3.1-1, Item 15. A Steam Generator narrow range level Median Signal Selector (MSS) was installed in the North Anna Unit 2 feedwater control system which addresses control/protection channel interactions consistent with IEEE-271, 1979. A similar change is being made on North Anna Unit 1 during the fall 2013 refueling outage The TS Bases were revised to delete the discussion on the Steam Generator Water Level Low Coincident with Steam Flow/Feedwater Flow Mismatch Reactor Trip Function for North Anna Unit 2 and add a functional description of the MSS as it relates to the Steam Generator Water Level-Low Low reactor trip function in TS Table 3.3.1-1, Item 14.

The Bases changes noted above were submitted to the NRC by Dominion submittals dated April 2, 2012 and August 6, 2012 and incorporated into the Bases for North Anna Unit 2 on April 22, 2013 upon NRC approval and implementation of the associated Technical Specification changes (Amendments 268 for Unit 1 and 249 for Unit 2 issued on November 20, 2012).

Revisions to Steam Generator Tube Inspection and Reporting as Described in TSTF-510, Revision 2 The amendments revised the steam generator tube inspection and reporting requirements. Specifically, Technical Specification (TS) 3.4.20, Steam Generator Tube Integrity, TS 5.5.8, Steam Generator (SG) Program, and TS 5.6.7, Steam Generator Tube Inspection Report were revised to be consistent with TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.

The TS Bases changes summarize and clarify the purpose of the Technical Specifications.

The Bases changes noted above were submitted to the NRC by Dominion submittals dated July 30, 2012 and December 13, 2012 and incorporated into the Bases for North Anna Units 1 and 2 on March 27, 2013 upon NRC approval and implementation of the associated Technical Specifications (Amendments 269 and 250 for North Anna Units 1 and 2 issued on January 28, 2013).

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