Letter Sequence Response to RAI |
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MONTHYEARML17066A1872017-03-0101 March 2017 Response to Request for Additional Information Regarding Supporting Probabilistic Risk Assessment for License Amendment Request for Emergency Service Water Pump Allowed Outage Extension Project stage: Response to RAI ML17075A2562017-03-10010 March 2017 Revised Response to Request for Additional Information Item #6.a Regarding Supporting Probabilistic Risk Assessment on Proposed License Amendment Request Emergency Service Water Pump Allowed Outage Time Extension Project stage: Response to RAI ML17170A1832017-07-28028 July 2017 Issuance of Amendments Regarding the Extension of the Emergency Service Water Pump Allowed Outage Time, Surry Power Station, Units 1 and 2 Project stage: Approval 2017-03-10
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Category:Letter
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[Table view] Category:Response to Request for Additional Information (RAI)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 10, 2017 10CFR50.90 U. S. Nuclear Regulatory Commission Serial No.: 17-0168 Attention: Document Control Desk SPS/LIC-CGL: R1 Washington, DC 20555-0001 Docket Nos.: 50-280/281 License Nos.: DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED LICENSE AMENDMENT REQUEST EMERGENCY SERVICE WATER PUMP ALLOWED OUTAGE TIME EXTENSION REVISED RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ITEM #6.a REGARDING SUPPORTING PROBABILISTIC RISK ASSESSMENT By letter dated July 14, 2016 (Serial No.16-263), Virginia Electric and Power Company (Dominion) submitted a license amendment request (LAR) to extend the allowed outage time (AOT} in Surry Technical Specification 3.14.B for one inoperable emergency service water (ESW) pump from 7 days to 14 days.
By letter dated March 1, 2017 (Serial No. 17-016A), Dominion responded to an NRC request for additional information (RAI) regarding the probabilistic risk assessment supporting the proposed LAR. Subsequent to that submittal, Dominion identified that Table RAl6a, "Scope of the 2012 Surry Peer Review," which was provided in response to NRC RAI #6.a, did not include the reviewed LE High Level Requirements as intended. Consequently, Dominion has revised the response to NRC RAI #6.a to include the updated Table. The revised response is provided in the attachment, and the revised information is indicated by revision bars located in the right margin.
The information provided in this letter does not affect the conclusions of the significant hazards consideration or the environmental assessment included in the July 14, 2016 LAR.
Should you have any questions or require additional Information, please contact Mr. Gary D. Miller at (804) 273-2771.
Respectfully,
~Cu{_-
Mark D. Sartain Vice President - Nuclear Engineering and Fleet Support COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mr. Mark D. Sartain, who is Vice President - Nuclear Engineering and Fleet Support, 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~ment are true to the best of his knowledge and belief.
Acknowledged before me this /(/7Jlday of '&Cb , 2017.
My Commission Expires: J'/Ay 3/, ".()18 .
j1;.L. ;(.J/ua.
Notary Public
Serial No. 17-0168 Docket Nos. 50-280/281 Corrected RAI Response Item #6.a Page 2 of 2 Commitments contained in this letter: None
Attachment:
Revised Response to NRC APLA RAI #6.a, Proposed License Amendment Request - Emergency Service Water Pump Allowed Outage Time Extension cc: U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 State Health Commissioner Virginia Department of Health James Madison Building - ih floor 109 Governor Street Suite 730 Richmond, VA 23219 Ms. K. R. Cotton Gross NRC Project Manager - Surry U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. B. L. Mozafari NRC Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 H-12 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station
Serial No. 17-0168 Docket Nos. 50-280/281 Attachment REVISED RESPONSE TO NRC APLA RAI #6.a PROPOSED LICENSE AMENDMENT REQUEST EMERGENCY SERVICE WATER PUMP ALLOWED OUTAGE TIME EXTENSION Virginia Electric and Power Company (Dominion)
Surry Station Units 1 and 2
Serial No. 17-0168 Docket Nos. 50-280/281 Page 1 of 2 Revised Response to NRC RAI APLA RAI #6.a Proposed License Amendment Request Emergency Service Water Pump Allowed Outage Time Extension Surry Power Station Units 1 and 2 APLA, RA/ #6: 2012 Focused Scope Peer Review of the submittal explains that a focused peer review was performed in June 2012 for the SPS internal events PRA. It states that a review was performed against the requirements of the ASMEIANS PRA standard RA-Sb-2005. Previous discussion from the 2010 Peer Review states that an evaluation was supported by Addendum to ASME/ANS PRA Standard RA-S-2008.
- a. Clarify which version of the standard the June 2012 peer review was performed against and provide a list identifying all the technical elements that were reviewed for this focused scope peer review.
The June 2012 Peer Review was performed against PRA standard RA-Sa-2009 and RG 1.200 Rev. 2. The SRs assessed in this peer review are documented in Table RAl6a below. This table was updated to include the final row of LE HLRs reviewed, which was inadvertently omitted from the original RAI response.
Table RAl6a: Scope of the 2012 Surry Peer Review High Level Technical Supporting Requirements (SRs)
Requirements Focused Scope Element Covered (HLR)
IE-A IE-A2, IE-AS Focused on the ISLOCA analysis.
IE-C3, IE-CS, IE-C6, IE-CS, IE-C9, This included consideration of IE-C IE-C10, IE-C11, IE-C12, IE-C14, IE- applicable AS SRs. However, since IE C1S not all event trees were reviewed, any issues identified with the IE-D IE-D1 I IE-D2, IE-D3 ISLOCA event tree were documented under the IE SRs.
Focused on modeling of common SY SY-8 SY-81, SY-82, SY-83, SY-84 cause failures.
DA-A DA-A1, DA-:A2, DA-A3, DA-D2, DA-D3, DA-DS, DA-D6, DA- Focused on data for common cause DA DA-D D7 failures.
DA-E DA-E1 I DA-E2, DA-E3 Focused on inclusion of state-of-QU-A QU-A3 knowledge correlation in the ISLOCA frequency analysis.
QU Focused on logic for removal of QU-8 QU-87 mutually exclusive CCF basic events.
Serial No. 17-0168 Docket Nos. 50-280/281 Page 2 of 2 Table RAl6a: Scope of the 2012 Surry Peer Review High Level Technical Supporting Requirements (SRs)
Requirements Focused Scope Element Covered (HLR)
HLR LE-A All HLR LE-B All HLR LE-C All LE HLR LE-D All Reviewed in entirety.
HLR LE-E All HLR-LE-F All HLR LE-G All