ML18353A845

Licensee Event Report UE-75-13 - Pcs Leakage Slightly Greater than 1 Gpm for About Two Hours

ML18353A845
Person / Time
Site:	Palisades
Issue date:	12/22/1975
From:	Bixel D Consumers Power Co
To:	James Keppler NRC/RGN-III
References
LER UE-1975-013-00
Download: ML18353A845 (2)

Text

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• consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

• Area Code 517 788-0550 December 22, 1975 Mr James G. Keppler. Office of Inspection Region III US Nuclear Regulatory 799 Roosevelt Road Glen Ellyn, IL 60137 Enforcement Commission DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT, REPORTABLE OCCURRENCE UE-75-13 Attached is a reportable occurrence which relates to the Palisades Plant and has been classified as a condition leading to operation in a degraded mode. Plant Technical Specifications permit operation to continue for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with unidentified primary coolant system leakage between 1 and 10 gpm. Leakage was identified at a sample isolation valve. David A. Bixel Assistant Nuclear Licensing CC: File

... REPORT .NSEE EVENT **

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[PLEASE PRINT ALL REQUIRED INFORMATION)

LICENSEE .. NAME IM I I Ip I A I LI i I 8 9 14 CATEGORY 1 6 LICENSE NUMBER Io Io 1-1 o I o lo lo I o 1-1 o I o I 15 25 REPORT SOURCE DOCKET NUMBER LICENSE TYPE l411l1l1l1I 26 30 EVENT DATE EVENT TYPE I 31 32 REPORT DATE @IT!coN'T I* I* I 7 8 57 58 REPORT TYPE w 11.J lo Is Io I o I 2 I s I 5 I I 1l1 l2 l2 l1lsl 11 I 2 I 2 I 2 I 1 I s I 59 60 61 68 69 74 75 80 EVENT DESCRIPTION 10121 !During normal operation, 7 8 9 PCS leakage was observed to be slightly greater than 1 gpm 10131 I (unidentified) for about two hours. Leakage was subsequently identified at a sample 7 8 9 lol41 I isolation valve. 7 8 9 This occurrence was a condition leading to operation in a degraded lo15l !mode and is permitted for 7 8 9 a period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with plant operating.

lol0I I was com:i;>leted (UE-75-13). 7 8 9 SYSTEM CODE @0 I LI sl 7 8 9 10 ' CAUSE CODE w 11 CAUSE DESCRIPTION COMPONENT CODE I v I A I L I vi El x I 12 17 PRIME COMPONENT SUPPLIER 43 COMPONENT MANUFACTURER

• I 61 1 I 61 s 1 44 47 VIOLATION L!J 48 Valve repair I Valve leakage. 7 8 9 The valve type is SS-64-9-RS-AI-NC.

The valve has been temporarily

@:Jfil capped. 7 8 9 I 80 I 80 I 80 I 80 I 80 80 80 E FACILITY METHOD OF STATUS % POWER OTHER STATUS DISCOVERY EE] I 0 I 1 I 9 I NA l.!J 7 8 9 10 12 1 3 44 45 FORM OF ACTIVITY RELEASED CONTENT OF RELEASE AMOUNT OF ACTIVITY rn LzJ

___ N_A ___ __. 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION lo lo I LzJ 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION EE lo lo Io I 7 8 9 11 12 PROBABLE CONSEQUENCES None. 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE 7 8 9 DESCRIPTION NA 10 PUBLICITY

[2£1 NA 7 8 9

• ADDITIONAL FACTORS NA 7 8 9 GE 7 8 9 44 NA NA 45 DISCOVERY DESCRIPTION NA 46 80 LOCATION OF RELEASE NA 8D 80 80 80 80 80 80 80 I-. ' .......