IR 05000361/1986025

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-361/86-25 & 50-362/86-26.Util Responses Re Application of Lessons Learned at Other Plants Discussed

ML20215H717
Person / Time
Site:	San Onofre
Issue date:	04/30/1987
From:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Baskin K SOUTHERN CALIFORNIA EDISON CO.
Shared Package
ML20215H721	List: IR 05000361/1986025 ML20215H735
References
RTR-NUREG-1154 NUDOCS 8705070006
Download: ML20215H717 (3)

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APR 3 01987 ,

Docket-Nos. 50-361, 50-362 c

! Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue

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Rosemead, California 91770

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Attention: Mr. Kenneth P. Baskin, Vice President-Nuclear Engineering, Safety ~and Licensing Department

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Gentlemen: .

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We have received your letter dated February _ 13, 1987, which responded t inspection items identified in inspection report numbers'50-361/86-25 and 50-362/86-26. The associated inspection focused on assessing your

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organization's ability to apply lessons learned at other-facilities to the

operation of your facility. -The' intent of this type of inspection is to encourage. licensee's to be aggressive'in following industry problems and taking action where appropriate to. prevent the occurrence ~of similar problems

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at their plants. Our review concluded that your industry operating experience i program was generally effective, with several weak areas'note Your response, in regard to those weaknesses, appears to' question'the degree

to which it is appropriate for your staff to review events at other facilities

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and apply the lessons learne Your response further indicates that the NRC i or INP0 should bear the responsibility for determining which specific aspects-of events should be reviewed in detail by the nuclear industry. We-agree that each facility throughout the nation should not be expected to independently identify critical details associated with large, complex, multi-faceted.

l events. In general, we conclude that those details.are available to you via

NRC Information Notices, Bulletins, Generic Letters, and NUREGs, in. addition

to that information available through INPO. ~We maintain that it is the

- licensee's responsibility to review the available industry information and J determine which details are applicable to their facility. In this' regard, we i

also note that a recent assessment of your review program by our resident '

4 staff indicated a need for more comprehensive and timely reviews of NRC i. . Information Notices (Inspection Report 50-206/87-03, paragraph 8.c).

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With regard to your response to our team inspection, NUREG-1154, " Loss of Main q and Auxiliary Feedwater Event at the Davis-Besse Plant on June 9, 1985," did

] provide detailed-information concerning that~ specific event. NUREG-1154 was-

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available to your; staff and we further understand that it was reviewed by your'

j Independent Safety' Engineering Group (ISEG). OurJinspection concern was that your review was not in sufficient detai For ' example, our inspection ,

questioned your actions with regard to problems experienced at Davis-Besse in resetting the Auxiliary Feedwater pump turbine overspeed trip mechanism. Item: '

4 V of your response indicates that problems with the Auxiliary Feedwater pump

! turbine trip mechanism were not addressed at San Onofre,--in part', due to the -

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fact that the INPO Davis-Besse SOER did not' include details _concerning latch i

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-2- APR 301987 reset problems. However, our review of NUREG-1154 indicates that a detailed description of the problem was provided in the NUREG, and therefore available for your consideratio With regard to readiness of plant equipment for manual operation and operator training in this area, several significant events, which have recently occurred, have indicated that the availability of plant equipment for local manual operation may be beneficial where multiple failures occur during an event, such as was the case during the Davis-Besse and Rancho Seco events. We concur with your position that emergency operating instructions be based upon industry-wide guidance and careful consideration. We do not expect you to significantly revise your procedures or training in emergency operations, based on our inspection. We are, however, encouraging you to ensure your operations personnel are sufficiently trained in the basic design and operation of selected equipment, so that, in the event that operations personnel should determine the need to operate equipment locally due to circumstances not anticipated by your procedures, those personnel will have the knowledge to perform such function It follows that we continue to encourage you to ensure that maintenance of and access to plant equipment not normally expected to be operated locally during an event be such that local operation may be performed, if needed, with assurance, based upon a knowledge that the equipment has been maintained in a condition to operate as the manufacturer intende With regard to local operation of equipment which is required by procedure, we continue to expect that operator training, equipment accessibility, and equipment maintenance ensures that those actions identified by procedure can be accomplished with certaint Should you have any questions concerning this letter, we will be pleased to discuss them with you. Your actions with regard to the subject inspection will be reviewed during a future inspectio

Sincerely,

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/ [)bf Dennis F. Kirsch, Director Division of Reactor Safety and Projects bcc w/ copy of letter dated 2/13/87:

Resident Inspector Project Inspector State of California docket file B. Faulkenberry J. Martin bec w/o copy of letter dated 2/13/87:

M. Smith J. Zollicoffer

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