ML20084H335

Ro:Rise in Rate of Pressure for MSIV Observed & Shutdown Planned by 700201 to Retest Valves

ML20084H335
Person / Time
Site:	Oyster Creek, 05000000
Issue date:	12/24/1969
From:	Ritter G JERSEY CENTRAL POWER & LIGHT CO.
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084H313	List: ML20084H318 ML20084H323 ML20084H335
References
99272, NUDOCS 8305030630
Download: ML20084H335 (2)

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'v Jersey Cen tral Powe$, & Ligh t Co m pa ny M ADISON AVENU E AT PUNCH DOWL Ro AD e M o R R IS T o W N, N. J. 0 79t;0 e 5 33 - 611 f ac December 24, 1969 A A }j. ,-

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','- ^o Dr. Peter A. Morric pj q 1.),/ Nej Afya \,.d -1 Director, Division of Reactor Licensing-United States Atomic Energy commission (..J, ei., , s r' Washington, D. C. 2051,5 y' fe,]

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Subject:

Ovster Creek I;o.1 Fain Steam Isolation Valvea . , ,

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Docket g. 50-219

Dear Dr. Morris:

Confirming car telephone conversation of last Tuesday on the above subject, it was obcerved during the test program after operation at 800,1200, and 1600 Mdt that the rate of pressure rise in the volume between the icolation valves and the turbine stop and bypass valves after valve clocure was higher when isolation valve US03B was clossa ,y and USO4B was opened thtn when any other cc.sbination of icolation valycy. ~ < -

was used to effect isolation. For example, check measuremento :ade ca December 13, 1969, indicated the rate of pressure rice waa about 90 pai per minute (from 180 pcig to 360 poig in tuc minutes) under taase conditions with reactor pressure at about 880 paig whereas with other valva com-binations typical pressure rise rate was 20 to 30 pai per minute.

4 There are a number of reasons why the pressure rise may occur, -~T ldh g such as, the transfer of sensible heat fron the larere ra.ca of hotatcam g%y pipes to tli U eTatively smaller mass of cooler atean in the closed n4 s g e or such as the leak back of fluid from connected systema other than the reactor vessel or such as leakage fr a the reactor vessel into 46%Q  :

the volume through the icolation valves. With the tect data at hand, h '

it ic not poscible to tell which of thece mechanicas (~or perhapa othera) '

j is most influential. However, because of the differencea in the rate of preasure rise with different isolation valve closure combinationa as indicated above, it could be inferred that valve HSO3B is leaking.

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8305030630 700603 PDR ADDCK 05000219 OEc 0 I7969 G PDR -

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l Dr. Peter A. Morris Decen.Ler 2)i, 1r,j O)

Consequently, after review by the Plant Operationc Review Cocunittee and the General Office Review Board, a decision uac rade that at the nent shutdown planned for rah.tenance and in any event f o 'l ti e r -r. . n . L t than Feb:uary 1,1970, the unit will be shutdown and all rain atecen isolation valves retected to establich conformance with applicable provisions of the Technical Specifications before the un'it ia rectarted.

Very truly yours, 7, ,

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Geo. H. Ritter '

^; Db, c :) i' Vice President .,.4

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g iv,e .' .); L g Copy to Pr. Robert W. Kirluran, Director

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Division of Compliance, Regicn 1 t 1, f j Dj ,f!' k'T f

United States Atomic Enercy Commission s \ ' . . Q' ,' k , >,

970 Broad Street s ,

I!ewark, IIew Jerce-/ 07102 .

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