ML19253B997

Requests Submittal of OL Application Amend Detailing Program Which Demonstrates Active Valve Operability Under Normal & Superimposed Loadings Simulating Seismic Vibratory Responses

ML19253B997
Person / Time
Site:	Crane
Issue date:	01/03/1973
From:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
To:	John Miller METROPOLITAN EDISON CO.
References
NUDOCS 7911040006
Download: ML19253B997 (2)

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l Docket No. 50-289 i

JAN 3 157; I

l Metropolitan Edison Company ATTN:

Mr. John C. Miller I

Vice President P. O. Box 542 Reading, Pennsylvania 4ntlemen:

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n most analyses of nuclear power plant accidents, safe recovery from t;uch accidents or containment of radioactive materials depends on the l

proper function of active valves. In many cases these valves would i

be required to operate properly while at high temperature, against l

maxiassa pressure differentials, and while subjected to a severe accident j

or seismic vibratory environment. The number of valve malfunctions that have been encountered during inservice tests in operating plants, j

suggests that we have not yet established adequate preservice and inservice test programs to assure the operability of active valves. We have reviewed the Final Safety Analysis Report, FSAR, for Three Mile Island Unit 1 as it applies to active valves, and have concluded that the limited dynamic analytical and testing procedures used to confirm the operability l

of all active valves as specified are insufficient.

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An acceptable program would be in-situ ralve testing where the operability of valves is demonstrated in the plant during the preoperational testing I

of those systems designed to Seismic Category I criteria. You are requested to provide as an Amendment to your Application, the details of such a program which would demonstrate operability under normal system j

operation, as well as under superimposed loadings, that appropriately simulate seismic vibrr. tory responses, and accident (LOCA) vibratory responses, as applicable to the system. This program may include either l

the application of vibratory devices to superimpose the vibratory i

seismic and accident loadings or an equivalent combinacion of analytical and testing methods that confirm operability. %e test program may be based upon selectively testing a representative number of active valves j

in the piping system according to valve type, seicuic and accident load level, site, etc. on a prototype basis.

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Form AEC-518 (Rev. 9-53) AECM 0240 o u s covanwewv mHT*.o omet 1972-466-983 kO

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l Metropolitan Edison Company i Eeeause of the scope and the generic nature of the program requested, l

you are invited to discuss this request with the AEC staff at the i

earliest opportunity.

Sincerely, i

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R. C. DeYoung, Assistant Director I

for Pressutized Water Reactors l

Directorate of Licenairg cc: General Public Utilities Service Corporation l

ATIN:

Mr. R. W. Reward Project Manager Safety and Licensing 260 Cherry Hill Enad j

Parsippany, New Jersey 07054 i

General Public Utilf_ ties Service Corporation ATIN: Mr. T. Crir, ins, Manager Safety and Licensing 260 Cherry Hill Road Parsippany, New Jersey 07054 Cerald Charnoff, Esquire Shaw, Pittman, Potte, Trowbridge & Madden 910 - 17th Street, NW Washington, D. C.

20006 Distribution:

AEC PDR Local 2DR Docket file RP Reading R. C. DeYoung PWR Branch Chiefs R. W. Klecker H. Schierling R. Maccary PWR-2 Reading MXXE E. Goulbourne 5

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