ML20028G199

RO 3-83-6/IP:on 830131,test Valve Between Penetration Boundary,Inboard & Outboard Containment Isolation Valve Exceeded Tech Spec Leak Rate.Caused by Improper Seating of Manual Valve.Penetration Isolated

ML20028G199
Person / Time
Site:	Peach Bottom
Issue date:	02/01/1983
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RO-3-83-6-IP, NUDOCS 8302070513
Download: ML20028G199 (2)

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DESIGNATED ORIGIUiTJ ,d.I[k Certified By U[ *t-PHILADELPHIA ELECTRIC COMPANY }

peach soTToM ATOMIC POWER STATioM

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I, oSLTA.PENMs7LVahla 17314  ;

February 1, 1983 I i

Mr. R. C. Haynes l 3

Administrator i, U.S. Nuclear Regulatory Commissiott . -

j Region I T 631 Park Avenue S King of Prussia, PA 19406 't

SUBJECT:

REPORTABLE OCCUR 3.*NCE - P!CMPT NOTIFICATION i Confirming S. R. Roberts's telephone conversation with A. R. Blough, l Region I, United States Nuclear Regulatory en==4asion on 2/01/83. l t

Reference:

Docket No. 50:-278 l' Peach Bottom Unit 3 .

Technical Specification 3.7.D.2 and 10CFR 50 Ap==diw J III C3 Report No. 3-83-6/1P  !

occurrence Date: 1/31/83 j

. 1 Identification of Occurrences i i

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At approximately 5 00 p.m. on 1/31/83, during local leak testing of the [

B CAD nitrogen injection penetration (N211B) into the torus, the test *I valva between the faha=2d and outboard con *= h nt isolation valve on  !

the penetration boundary exceeded a leak rate of approximately 80 SCFN. j Leak rate total for containment, when using the'can==rvative calculation 3 method of ignoring the integrity of the best valve in each penetration,  !

=====d= 10CFR50 limit of 0.60 La. The manual valve in series with the y leakage path was immediately closed and blocked. -

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_ Conditione Prior to Occurrence Unit 3 was operating at its raanri==== capability during EQL coast-down (approalmately 860 MWe).

Apparent Cause of Occurrences l A

=====1 valve did not seat properly. Further investigation will be done j when the valve is disasse:nbled for repair. .j i

Analysis of Occurrences j' The test valve wnich 1= *=d is an ou*haard contain - t isolation boundary.

The valve test connection had been capped since the prsvious test froer the  ;

last refuel cycler t-harefore, actual leakage through the valsa front priziary  ?

con *=4 a==at to the secondary contain==nt would be prevented by the threaded cap. l t

t 8302070513 830201 $

PDR ADOCK 05000278 PDR Mc\i A

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l)f In additien, the inboard isolation valve, with a leak rate of 5000 sec/ ming in in series with the test valve which leaked Therefore, primary .

containmenc wa:r never loat. and the leak rate tiotal would be approximately 41000 sec/ min out of the 0.60 La limit of 71193 sec/ min when credit is given for the irboard isolation valve on this penetration only. Therefore, the actual prizr.ary containment leak rate which would be seen during accident ccaditions would safety significanco is minim not i.have increased due to this event and the Corrective Action:

• o The prescribed Technical Specification act. ion was taken to isolate the penetration due to the inoperability of an isolation valve. Further.

corrective as possible. action to repair and retest the valve will be done as soon Very txuly yours, 9.

W. T. Ullrich Station Superintendent"

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