ML20248H257

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Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed
ML20248H257
Person / Time
Site: Rancho Seco
Issue date: 10/06/1989
From: Keuter D
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Knighton G
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AGM-NUC-89-145, NUDOCS 8910110235
Download: ML20248H257 (1)


Text

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])SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.o. Box 15830. Sacramomo CA 958521830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA AGM/NUC 89-145 October 6, 1989 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 REACTOR VESSEL VENT VALVE (RVW) TESTING Attention: George Knighton

Reference:

NRC to SMUD letter dated May 8, 1989, Addendum to Safety Evaluation Supporting Amendment No. 92 to Facility Operating License The referenced letter granted an extension to the surveillance interval for the reactor vessel vent valve testing to allow testing no later that November 1989. This testing is required pursuant to Rancho Seco Technical Specification Surveillance Standard 4.1.2, Table 4.1-2, Item 13.

The reactor vessel vent valves are required to relieve pressure developed in the core region post LOCA to facilitate emergency core ccolant injection. A LOCA is not a postulated accident in the cold shutdown or refueling conditions. Therefore, pursuant to the applicability statement associated with Technical Specification 4.1.2, the reactor vessel vent valves are not required to be OPERABLE in cold shutdown or refueling plant conditions.

The District will not perform testing of the reactor vessel vent valves since the plant is not in, nor does it intend to enter, a condition where the reactor vessel vent valves are required to be OPERABLE. In this case, as in other cases (High Pressure Injection, Reactor Building Spray, Core Flood System, etc.), the Surveillance Standard defined testing is not being performed since the plant is not in a condition where the equipment is required to be OPERABLE. Should the decision be made to return Rancho Seco to power operations, Technical Specification Surveillance Standard testing will be performed prior to entering the plant condition where the equipment is required to be OPERABLE.

Members of your staff with questions requiring additional information or p

clarification may contact Dave Swank at (209) 333-2935, extension 4920.

Sincerely,

_ v Dan R. Keuter Assistant General Manager 8910110235 841006 Ag e; DOCK 0500 2 Nuclear fDR 1

cc: J. B. Martin, NRC, Walnut Creek A. D' Angelo, NRC, Rancho Seco RANCHO SECC NUCLEAR GENERATING STATION D 1444o Twin Cities Road, Herald, CA 95638-9799; Go9) 333-2935