ML17223A069

Amendments Regarding Extension of Technical Specification 3.14, Service Water Flow Path Allowed Outage Times and Deletion of Expired Temporary Service Water Jumper Requirements

ML17223A069
Person / Time
Site:	Surry
Issue date:	09/06/2017
From:	Cotton K Plant Licensing Branch II
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
Cotton K, NRR/DORL/LPL2-1, 415-1438
References
CAC MF7746, CAC MF7747
Download: ML17223A069 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 6, 2017 Mr. Daniel G. Stoddard President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glenn Allen, VA 23060-6711

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2, INADVERTENT OMISSION OF BASIS PAGE TS 3.14-4 FROM AMENDMENT NOS. 289 AND 289, REGARDING EXTENSION OF TECHNICAL SPECIFICATION 3.14, "SERVICE WATER FLOW PATH ALLOWED OUTAGE TIMES AND DELETION OF EXPIRED TEMPORARY SERVICE WATER JUMPER REQUIREMENTS" (CAC NOS. MF7746 AND MF7747)

By letter dated May 31, 2017 (Agencywide Document Access and Management System Accession No. ML17100A253), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 289 to Renewed Facility Operating License No. DPR-32 and Amendment No.

289 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station (Surry),

Unit Nos. 1 and 2, respectively. The amendments changed the Technical Specifications (TSs) in response to your application dated May18, 2016, as supplemented by letters dated February 10 and March 1, 2017; and March 10, 2017.

These amendments revised Surry, Unit Nos. 1 and 2, TS 3.14, "Circulating and Service Water Systems," to extend the Allowed Outage Time (AOT) from 24 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for only one operable service water (SW) flow path to the Charging Pump Service Water (CPSW) subsystem and to the Main Control Room/Emergency Switchgear Room (MCR/ESGR) air conditioning (AC) subsystem. The changes also deleted the Operating License conditions, TS requirements, and TS 3.14 Basis discussion for the temporary SW jumper to the Component Cooling Heat Exchangers.

An administrative error on the part of the NRC occurred in the issuance of Amendments 289.

TS Basis 3.14-4 page was omitted inadvertently from the safety evaluation package. The enclosed TS Basis 3.14-4 page will be added, and TS Basis page 3.14-4a will be deleted from the NRC authority file. The NRC does not approve changes to the TS Basis and the incorporation of these changes does not change the NRC approval as noticed previously in the Federal Register.

D. Stoddard If you have any questions please contact Karen Cotton Gross at Karen.Cotton@nrc.gov or 301-415-1438.

Sincerely,

~(J;lt;:J ~

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

Enclosure:

Replacement Page

TS 3.14-4 including replacement of an Emergency Service Water pump without forcing dual unit outages, yet limits the amount of operating time without the specified number of pumps.

When one Unit is in Cold Shutdown and the heat load from the shutdown unit and spent fuel pool drops to less than 25 million BTU/HR, then one Emergency Service Water pump may be removed from service for the subsequent time that the unit remains in Cold Shutdown due to the reduced residual heat removal and hence component cooling requirements.

A minimum level of + 17 .2 feet in the High Level Intake canal is required to provide design flow of Service Water through the Recirculation Spray heat exchangers during a Joss-of-coolant accident for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the water level falls below +23' 6",

signals are generated to trip both unit's turbines and to close the nonessential Circulating and Service Water valves. A High Level Intake canal level of +23' 6" ensures actuation prior to canal level falling to elevation +23'. The Circulating Water and Service Water isolation valves which are required to close to conserve Intake Canal inventory are periodically verified to limit total leakage flow out of the Intake Canal. In addition, passive vacuum breakers are installed on the Circulating Water pump discharge lines to assure that a reverse siphon is not continued for canal levels less than +23 feet when Circulating Water pumps are de-energized. The remaining six feet of canal level is provided coincident with ESW pump operation as the required source of Service Water for heat loads following the Design Basis Accident.

References:

UFSAR Section 9.9 Service Water System UFSAR Section 10.3.4 Circulating Water System UFSAR Section 14.5 Loss-of-Coolant Accidents, Including the Design Basis Accident Amendment Nos. 289 and 289

ML17223A069 OFFICE NRR/DORL/LPLll-1/PM N RR/DORL/LPLI 1-1 /LA NRR/DORL/LPLI 1-1/PM NRR/DORL/LPLll-1/BC NAME KCotton KGoldstein KCotton MMarkley DATE 08/28/17 08/17/17 & 08/23/17 08/28/17 09/06/17