ML18346A247

LER 1981-020-00 for Palisades Nuclear Plant, Pcs Unidentified Leakage Greater than 1.0 Gpm

ML18346A247
Person / Time
Site:	Palisades
Issue date:	06/19/1981
From:	Johnson B Consumers Power Co
To:	James Keppler NRC/RGN-III
References
LER 1981-020-00
Download: ML18346A247 (2)

Text

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consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 June 19, 1981 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT NO Sl-020 -

PCS UNIDENTIFIED LEAKAGE GREATER TH.A..."l' 1. 0 GPM On the reverse side is Licensee Event Report No 81-20 (PCS Unidentified Leakage Greater Than l.O GPM) which is reportable under Technical Specification 6*.9.2.b. (2).

Brian D Johnson Senior Licensing Engineer CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector-Palisades Plant

~JUN .2 2 1981

PALISADES NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7-771 LICENSEE EVENT REPORT CONTROL BLOCK: ._I_ . . _ _........_.....__..._..._-ii G) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!

1 6

[il2J IM Ir I PIA 1111 101olo1-1 olo Iola lo I-lo lo 1014 11111111101 I 10 7 8 9 LICENSEE CODE 14 . ~5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T WJJ

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~~~~~~ ~10 I 5 I o I o I I 215 I 5 GI o I 5 I 21 2 I 60 61 DOCKET NUMBER o 68 69 EVENT DATE a11 74 IG)lo I 6 I l I 9 I 8 I i IG) 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

[))))I During normal plant operation, results of daily PCS leak rate calculation!

[)))) I indicated PCS unidentified leak;age to be 8,l)proximately 1.2 gpm which r::Q:EJ exceeds the limit of TS 3.1.5. Containment entry resulted in finding

[QTIJ leak from packing on auxiliary spray line stop valve (CV 2117). Leak

[ill] isolated by closure of isolation valve in leakoff line. Event reportable I

[IT2J per TS 6.9.2.B2. No threat to public health or safety resulted.

ITill 1 a s BO SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE . SUBCODE COMPONENT CODE SUBCODE SUBCODE

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7 B 9 10 11 12 13 1B 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION r.:;-,, LE RIRO CVENT YEAR REPORT NO. CODE TYPE NO.

l..:.:,J REPORT NUMBER I 8 I1 I I I Io I 2 Io I I/I I o I 31 LlJ 1=l LQ.J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN r:;::;., ATTACHMENT NPAD-1 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FOAM SUB. SUPPLIER MANUFACTURER Lx.J@W@

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43 IB 1212 I 047 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

I Leakage attrubuted packing degradation. Valve scheduled to be repacked during 1981 refueling outage.

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1 a s BO METHOD OF (.;::;\

FACILITY STATUS  % POWER OTHER STATUS @ DISCOVERY DISCOVERY DESCRIPTION ~

[ill] l_]J@ I 0 I 9 I 3 l@l.___--=N=A_ _ __. lJLl~l.._~P~C~S"'--"L~e~ak=-~R~a~t~e'--"'C~a=l~cu~l~a~t~i~*o~n""-~~--r a 9 10 12 13 44 45 46 80 ACTIVITY RELEASED OF RELEASE CONTENT AMOUNT OF ACTIVITY e Q._

LOCATION OF RELEASE@

[2:EJ Ul@) ~@I NA I NA 7 B 9 10 11 44 45 BO PERSONNEL EXPOSURES r:;;:;..,

NUMBER (.;':;\TYPE DESCRIPTION ITI?J I ol ol ok~_:.,Lz_J@.____ _ _ _ _ _~,,.___ _ _ _ _ _ _ _ _ _ _ _ _ _- - . . J 7 B 9 11 12 13 80 PERSONNEL INJURIES ~

NUMBER DESCRIPTION~.

r:2:liJ I 01 01 0 l@.____ _ _ _ _ _ _ _. . . . =!N:. :.A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _---J a 9 11 12 80 LOSS O< OR DAMAGE TO FACILITY t4j\

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DESCRIPTION

____________NA B 9 10 BO PUBLICITY C\ NRC USE ONLY ISSUED DESCRIPTION~

I2I£] Ll!..J{§)._____________. . . . .,A_ _ _ _ _ _ _ ___. II IIIIIIII II I a 9 10 68 69 BO

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