ML18347B210

License Event Report 1980-011-00 Re Improper Return-to-Service of Porv'S

ML18347B210
Person / Time
Site:	Palisades
Issue date:	05/14/1980
From:	Hoffman D Consumers Power Co
To:	James Keppler NRC/RGN-III
References
LER 1980-011-00
Download: ML18347B210 (2)

Text

,. 8 0052006 91 consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

• Area Code 517 788-0550 May 14, 1980 Mr James G Keppler Office of Inspection & Enforcement Region III U S Nuclear Regulatory Commission 199 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 80-011 - IMPROPER RETURN-TO-SERVICE OF PORV's On the reverse side is Licensee Event Report 80-011 which is reportable under Technical Specification 6.9.2.B.3 and 3.1.8.

David P Hoffman (Signed)

David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades

NRC FORM 366

• PALISADES PLANT U.S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT I

CONTROL BLOCK: ...._,___.__~_.__,.__...JI 1 6 CD (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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CODE 14 ~5 LICENSE NUMBER ~5 26 LICENSE TYPE 30 57 CAT 58 CON'T

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~~~~~ LLJ© I o 15 60 61 I oDOCKET I o Io I 2 I5 I 5 6810169a I 4EVENT NUMBER h I E1 s I ol©lo I 5 I 1 I 41 s I a 10 DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I Following modifications to PORV power supplies, the valves were stroked perf C2:IfJ ~re-op test procedure and declared operable. However, because required ad-CQID ministrative reviews of the modification package had not been completed,thel

[Q))] fORVs should not have been declared operable. Subsequent administrative rej

[QJ:[] fiews revealed no discrepancies in the modification package; therefore, the I

~ ~alves were capable of performing their intended safety function during

[)))) IDeriod in question. Tech Spec 3.1.8 and Tech Spec 6.9.2.B.3 apply. I 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION, r:;., LER/RO CVENT YEAR REPORT NO. CODE TYPE NO.

~ ~~~~~~ 1821 Io 221 I I 23 I o I l Il I 24 26 I.....-1 27 I oI 3 I 28 29 l1.J 30 I I 31 LQJ 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LHJ@W@ LI@

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44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

~isunderstanding of administrative review requirements by plant management 1JJJJ (Personnel. Upon discovery (-"'-' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after test completion) one valve was I

[IJ:lJ ~agged open to satisfy T/S 3.1.8 requirements. Management personnel involv1 o::IIJ jed have reviewed administrative requirements related to returning safety-ITJI] !related systems to service.

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FACILITY STATUS  % POWER OTHER STATUS ~

METHOD OF DISCOVERY DISCOVERY DESCRIPTION

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RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE @

12::0a lzJ @ W@'-'IN=A=---_ _ _ _ _ __.

7 9 10 11 44 45 NA 80 PERSONNEL EXPOSURES Q.,

NUMBER ~TYPE DESCRIPTION fil7.J lo I0 I ol0u@~N=A..____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __J 7 8 9 11 12 13 80 PERSONNEL INJURIES Q DESCRIPTION~

E:TIJ lo NUMBER I olo l@)~NA;.;._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-----1 1 a 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY t4:J'I TYPE DESCRIPTION i.::::J

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ISSUED(,;\ DESCRIPTION~ NRC USE ONLY u::I£Ja 1..!.Jei 1

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