ML20004D474

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Comments on NRC 810225 Request Re Licensee Review of Station Blackout Events.Total Loss of Ac Power Was Not Considered as Dba.Specific Procedures & Operator Training in Prescribed Course of Action Are Not Necessary
ML20004D474
Person / Time
Site: Rancho Seco
Issue date: 06/01/1981
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-44, REF-GTECI-EL, TASK-A-44, TASK-OR TAC-43938, NUDOCS 8106090440
Download: ML20004D474 (2)


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$ SACRAMENTO MUNICIPAL UTILITY DISTRICT SMUD 95813; (916) 452 3211

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June 1, 1981

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$Mr Itw DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION DARRELL G EISENHUT DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT N0 1 STATION BLACK 0UT EVENTS The Sacramento Municipal Utility District has reviewed your letter of February 25, 1981, requesting our review of plant operating and emer-gency procedures and operator training for staticn blaciout events.

At the time Rancho Seco Unit No. I was licensed, a total loss of all AC power was not considered as a design basis for the plant. A discussion is presented in the Final Safety Analysis Report of this hypothetical event to show that the environmental effects of this accident are acceptable.

Since this event is not a design basis accident, the District does not feel it is proper to have specific precedures or to train operators in a prescribed course of action for this event. Depending upon the cause of this event and concurrent plant conditions, we feel strongly that the licensed plant operators should have the prerogative of pursuing a course of action appropriate for the specific event. We feel that training in the areas of emergency systems and power distribution systems, including operation of the emergency diesel generators, is adequate to allow the operators to determine a procer course of action. We also feel that training is adequate for the operators to properly remove decay heat by natural circuhtion, using the steam-driven auxiliary feedwater pump.

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AN ELE 0iRfC $Y37EM 3E9VfNG MJ9E 7HAN 4;2.000 tN THE HEART OF C Alt F O R N I A

e DARRELL G EISENSUT June 1, 1981 The District is aware of the NRC staff review of Unresolved Safety Issue A-44.

If the results of this study indicate that modifications should be made to our plant design or operator training, we will, of course, reevaluate our present position.

fd John J Mattimoe Assistant General Manager and Chief Engineer Subscribed and sworn to before me this

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1st day of June,1981*

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