ML18347B145

LER 1978-021-00 for Palisades Nuclear Plant, Containment Purge Supply Valve CV-1808 Failed to Open During Monthly Test

ML18347B145
Person / Time
Site:	Palisades
Issue date:	08/10/1978
From:	Hoffman D Consumers Power Co
To:	James Keppler NRC/RGN-III
References
Download: ML18347B145 (2)

Text

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

• Area Code 517 788-0550 August 10, 1978 Mr James G Keppler (**.*

Office of Inspection and Enforcement ,.,, -

• r_ 1 Region III l

• * .1 r* . ;.:-J US Nuclear Regulatory Commission '; ... ,_

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799 Roosevelt Road ---;

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Glen Ellyn, IL 60137 --:* .. ~-;

DOCKET )~LICENSE DPR-20 ],")

PALIS.llJ)ES PLA!'JT - UPDATED LER-78-021 Attached is an updated licensee event report for the Palisades Plant .

• David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement AUG 1<~ 1978

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Update Report - Previous Report Date 07/22/76

• NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: ~I-~--~--~-,!'6 1

0 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~ I MI I I PI A IL I 1 101 o Io I - I o I o I o I o I o I - I o I o 101 4 I l I 11 l I 1 101 I I0 7 B 9 LICENSEE CODE 14 ~5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

[iliJ  :;~~~~ W© I o I o 1 51 6 1 o I 2 I 51 5 101 o I 6 1 2 I 7 I 7 I 6 I© I o 18 I 11 o I 7 I 8 IG) 7 B 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

[]JI] I The containment purge supply valve CV-1808 failed to open during the monthly test. This violates Containment Integrity Requirements (TS 1.4.d) which require all automatic containment isolation valves to be!

operable or locked closed. This valve was tagged closed to meet the reauirements for containment integrity.

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7 8 9 80

• SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SU8CODE COMPONENT CODE SU8CODE SUBCOOE

[ill] I SI :t:ll@ w@ w@ 1v1A111 v1E1x1e ~ ~@

7 B 9 10 11 12 13 18 19 20 CVI 7 I 6 I SEQUENTIAL OCCURRENCE RE.PORT REVISION'

(.::;'\ LE A/RO ENT YEAR REPORT NO. CODE TYPE NO.

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REPORT NUMBER 21 22 23 I 1012111 24 26 1.....-1 27 10131 28 29 30 1=J 31 L2J 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT . METHOD HOURS ~ SUBMITTED FORM ~UB. SUPPLIER MANUFACTURER W@W@ W@ ~ !O 1010 IOI40 LJU@ L.!J@ W@ IF jl 12 15 I@

33 34 35 36 37 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

DJ)) I The CV-1808 internals were reworked in 1978. Inspection of the valve showed no apparent reason for the 1976 failure. During return-to-service testing, normal opening was observed. The cause of failure remains un-known and no further follow-up reports for this failure will be made.

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IJJil8 7 9 80 FACILITY STATUS  % POWER OTHER STATUS @ METHOD OF DISCOVERY DISCOVERY DESCRIPTION @

[ill]~@ 111o101@1 N/A W@I Operator Observation 8 9 10 12 13 44 45 - 46 80 ACTIVITY CONTENT RELEASED OF RELEASE - AMOUNT OF ACTIVITY @ LOCATION OF RELEASE @)

IIliJ L!.I @ W@I N/A N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES ~

NUMBER @TYPE DESCRIPTION 39

[2l2J I 0 I 0 I 0 I 37 ~@ . NA 7 8 9 11 12 13 PERSONNEL INJURIES @ 80 NUMBER DESCRIPTION 41

[Ifil Io I o I ci I@ NA 8 9 11 12 BO LOSS OF OR DAMAGE TO FACILITY@

TYPE DESCRIPTION

[2E l.!J@ N/A 7 B 9 10 so PUBLICITY @ NRC USE ONLY ISSUED@ DESCRIPTION 45

[I[2J L1Ll 44 N/A I I I I I II II I I I I B 9 10 68 69 80