ML20246D047

Commission Response to J Bates Subcommittee on Energy & Power Question 11 from

ML20246D047
Person / Time
Site:	San Onofre
Issue date:	05/11/1989
From:	Zech L NRC COMMISSION (OCM)
To:	Bates J HOUSE OF REP.
Shared Package
ML20246C933	List: ML20246C943 ML20246C952 ML20246C956 ML20246C990 ML20246C995 ML20246D002 ML20246D017 ML20246D024 ML20246D033 ML20246D042 ML20246D047 ML20246D050 ML20246D080
References
BATES-890511, CCS, NUDOCS 8907110224
Download: ML20246D047 (1)

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ig OUESTION 11 San.Onofre I has also not been. required to-install proper instrumentation to detect inadequate reactor core cooling nor has NRC demanded that Edison complete testing and analysis for several safety-related valves and pipes associated with cooling.

L Why?

ANSWER The instrumentation to detect adequate core cooling is a reactor vessel water

. level instrument. It provides useful information to the operators in situa-tions involving loss of coolant (water) from the reactor coolant system. As.

discussed in the answer to Question 9, an NRC order dated May 10, 1989, requires SCE to install a reactor vessel water level instrument by the next refueling' outage (spring 1991).

On February 24, 1989, the NRC staff issued its Safety Evaluation regarding testing of relief and safety valves. The evaluation contained a few minor open items which will be audited by the NRC staff. Any additional actions required of the licensee will be completed by the next refueling outage.

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