ML17250A835

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Safety Evaluation of Inadvertent Safety Injection During Cooldown.Facility Could Withstand More than 50 Inadvertent ECCS Actuations Since Not All Actuations Will Result in Cold Water Injection Into Hot RCS
ML17250A835
Person / Time
Site: Ginna 
Issue date: 12/05/1980
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17250A834 List:
References
NUDOCS 8012290503
Download: ML17250A835 (2)


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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION INADVERTENT SAFETY INJECTION DURING COOLDOWN DIVISION OF OPERATING REACTORS Inadvertent actuation of the emergency core cooling system (ECCS) had

.occurred at a number of PWR facilities. If, at the time of inadver-tent actuation, the reactor coolant system (RCS) pressure is less than the ECCS discharge pressure and the RCS temperature is significantly above the ECCS water temperature, then the regions of the injection nozzles can be subjected to thermal stresses.

We have performed analyses using conservative assumptions to obtain an upper bound for these stresses and conclude that a typical nozzle could withstand at least fifty (50) injection events with the temper-ature differential as high as about 500'F.

These results are con-sistent with those reported by Westinghouse on the Salem docket.

It is likely that a facility could withstand more than 50 inadvertent actuations of the ECCS because

1) not all inadvertent actuations will result in cold water injection into a hot RCS, 2) if injection does occur, the temperature differential will most likely be less than that assumed in our analyses, and 3) there is additional margin to failure because the ASME Code limit is itself conservative.

IE Circular 78-05 dated Hay 23, 1978 on this subject advised facility owners of specific actions that could be taken to minimize the fre-quency of inadvertent safety injections.

We conclude that no additional licensing action is required at this time.

It would be prudent, however, for facility owners to continue to monitor the frequency of these events.

If a particular PWR facility should experience more than about 25 inadvertent safety injections, then a plant specific analysis should be considered.

GEC $ 0 1980