ML20107L388
| ML20107L388 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/25/1996 |
| From: | Bowling M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20107L390 | List: |
| References | |
| 96-210, NUDOCS 9604290291 | |
| Download: ML20107L388 (2) | |
Text
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t VIRGINIA ELucTRIC AND Powna COMPANY RIcitMOND,VINGINIA 200 61 l
April 25, 1996 U.S. Nuclear Regulatory Commission Serial No.
96 210 Attention: Document Control Desk NAPS /DCH:
R3 Washington, D.C. 20555 Docket Nos.
50 338 50-339 License Nos.
NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SUPPLEMENTAL INFORMATION REGARDING l
PROPOSED TECHNICAL SPECIFICATIONS CHANGE l
FOR PUMP SWITCHING DURING SHUTDOWE l
By letter dated July 26,1995 (Serial No.95-377), Virginia Electric and Power l
Company requested changes to the Technical Specifications for North Anna Power Station Units 1 and 2. The proposed changes clarify the Technical Specifications to allow switching of charging and low-head safety injection pumps during unit shutdown l
conditions. The proposed changes also allow additional methods of rendering these same pumps incapable of injection into the reactor coolant system when required for low-temperature conditions.
In a telephone conference call on April 8,1996, the NRC staff requested clarification of one of the methods proposed to render the pumps inoperable (i.e., not capable of injecting water into the reactor coolant system) during reactor coolant system solid l
water operations. Specifically, the NRC staff requested additional administrative i
controls be utilized during solid water operating conditions if a single pump discharge valve is to be used as the method of rendering the pump inoperable. Therefore, if the pump discharge valve is used to render the pump inoperable during water solid operation, the valve will also be deenergized and tagged in the closed position. This action will ensure that, for this method of rendering the pump inoperable, a single operator action would not cause an accidental mass addition into a solid water reactor coolant system.
t The attached Technical Specifications Bases pages have been revised to reflect this additional administrative control. These clarifications do not change the basis for our determination that the proposed change does not involve a significant hazards 1
consideration.
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-4a 2--m-Should you have any questions or require additional information, please contact us.
Very truly yours, M. L. Bowling, Manager Nuclear Licensing and Operations Support Attachments cc:
U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station i
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