ML061720499

Response to Request for Additional Information (RAI) on Proposed Technical Specification Change to Address Generic Safety Issue 191 (TAC Nos. MC9724 & MC9725)

ML061720499
Person / Time
Site:	Surry
Issue date:	06/21/2006
From:	Grecheck E Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-503, TAC MC9724, TAC MC9725
Download: ML061720499 (6)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 21, 2006 U. S. Nuclear Regulatory Commission Serial No.06-503 Attention: Document Control Desk NL&OS/PRW R1 One White Flint North Docket Nos. 50-280/281 11555 Rockville Pike License Nos. DPR-32/37 Rockville, MD 20852-2738 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAl)

ON PROPOSED TECHNICAL SPECIFICATION CHANGE TO ADDRESS GENE,RICSAFETY ISSUE 191 (TAC NOS. MC9724 AND MC9725)

In a letter dated January 31, 2006 (Serial No.06-014), Virginia Electric and Power Company (Dominion) requested an amendment to Operating License Numbers DPR-32 and DPR-37 in the form of changes to the Technical Specitications (TS) for Surry Power Station Units 1 and 2 (Surry). The proposed change was submitted as part of Dominions resolution to NRC Generic Safety Issue 191 (GSI-191).

In a letter dated June 9, 2006, the NRC provided a request for additional information (RAI) in order to complete its review of Dominions amendment requer jt .

The response to the RAI is provided in the attachment to this letter.

Should you have any questions regarding the response, please contact Mr. Paul R. Willoughby at (804) 273-3572.

Very truly yours, U

Eugerie S. Grecheck Vice President - Nuclear Support Services Attachment Commitments in this letter: None

Serial No.06-503 Docket Nos. 50-280/281 Response to Request for Additional Information Page 2 of 3 cc: U. S. Nuclear Regulatory Commission Region I I Sam Nunn Atlanta Federal Center Suite 23 T85 61 Forsyth Street, SW Atlanta, GA 30303-8931 Mr. S. R. Monarque Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 H 12 11555 Rockville Pike Rockville, MD 20852-2738 Mr. N. P. Garrett Senior Resident Inspector Surry Power Station

Serial No.06-503 Docket Nos. 50-280/281 Response to Request for Additional Information Page 3 of 3 COMhAONWEALTH OF VIRGINIA )

)

COUhlTY OF HENRICO 1 The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Eugene S. Grecheck, who is Vice Presid~ent- Nuclear Support Services, of Virginia Electric and Power Company.

He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me the 2 1 %r day of o&

u

,2006.

My Commission Expires: l. 31 do/n Notary Public (SEAL.)

Serial No.06-503 Docket Nos. 50-280/281 ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PROPOSED TECHNICAL SPECIFICATION CHANGE TO ADDRESS GENERIC SAFETY ISSUE 191 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION

Serial No.06-503 Docket Nos. 50-280/281 Response to Request for Additional Information Attachment Page 1 of 2 In a letter dated January 31, 2006 (Serial No.06-014), Virginia Electric and Power Company (Dominion) requested an amendment to Operating License Numblers DPR-32 and DPR-37 in the form of changes to the Technical Specifications (TS) for Surry Power Station Units 1 and 2 (Surry). The proposed change was submitted as part of Dominions resolution to NRC Generic Safety Issue 191 (GSI-191). In a letter dated June 9, 2006, the NRC provided a request for additional information (RAI) in order to complete its review of Dominions amendment request. The response to the RAI is provided below.

NRC QUESTION By letter dated January 31, 2006, Virginia Electric and Power Company (VEPCO) submitted proposed license amendments to address Generic Safety Issue 191 at Surry Power Station, Unit Nos. 1 and 2. VEPCO is requested to respond to the following questions.

1. Please confirm that the exclusion area boundary (EAB), low population zone (LPZ), and control room atmospheric dispersion factors (WQ)listed below are those used in the loss-of-coolant accident dose assessment in support of the proposed TS change to address Generic Safety Issue 191:

EAB and LPZ W Q Values:

2 hrs 1.76 x 10-3sec/m3 0 - 8 hrs 2.01 x sec/m3 8 - 24 hrs 1.22 x sec/m3 1 - 4 days 4.1 8 x I 0-5sec/m3 4 - 30 days 8.94 x 10-5sec/m3 Control Room W Q Values:

Unit 1 Containment 0 - 2 hrs 6.74 x 10-4sec/m3 (to turbine building fresh air 2 - 8 hrs 5.18 x sec/m3 air intake # I ) 8 - 24 hrs 2.22 x sec/m3 1 - 4 days 1.66 x 10-4sec/m3 4 - 30 days 1.20 x 10-4sec/m3 DOMINION RESPONSE The X/Q values listed above are the control room W Q values for the containment release and the LPZ W Q values that were used in support of the TS change to address Generic Safety Issue 191. The W Q value used to model the EAB was 1.79~-1Om3sec/m3. Subsequent analysis, documented in a letter dated May 23, 2006 (Serial No. 06-200A), determined that 1.79~1 0-3 sec/m3is conservative and

Serial No.06-503 Docket Nos. 50-280/281 Response to Request for Additional Information Attachment Page 2 of 2 a more appropriate value is 1.76~1 O3 sec/rn3. This small change in the EAB W Q will result in approximately a 1.7% reduction of the LOCA EAB dose consequence from that provided in Dominions letter of January 31, 2006.

Additionally, control room W Q values for the ECCS and RWST releases through Vent Stack No. 2 are as follows:

0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 6.95~1 0-4sec/m3 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 5.40~1 0-4sec/m3 8 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.30~1 0-4sec/m3 1 -4days 1.71XI 0-4sec/m3 4 - 30 days I .22x1o - sec/m3

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