ML18347B145
| 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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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 Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET )~LICENSE DPR-20 PALIS.llJ)ES PLA!'JT -
UPDATED LER-78-021
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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
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AUG 1 <~ 1978
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Update Report - Previous Report Date 07/22/76 NRC FORM 366 (7-77)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: ~I -~--~--~-,!' 0 1
6 (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 I 0 7
B 9
LICENSEE CODE 14
~5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T
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B
- ~~~~ 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 1 8 I 11 o I 7 I 8 I G) 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
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7 B
- SYSTEM CODE I SI :t:ll@
9 10
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LE A/RO CV ENT YEAR
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REPORT I 7 I 6 I NUMBER 21 22 CAUSE CAUSE COMP.
CODE SU8CODE COMPONENT CODE SU8CODE w@ w@ 1v1A111 v1E1x1e ~
11 12 13 18 19 SEQUENTIAL OCCURRENCE RE.PORT REPORT NO.
CODE TYPE I
I 1012111 1.....-1 10131
~
23 24 26 27 28 29 30 VALVE SUBCOOE
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20 1=J 31 80 REVISION' NO.
L2J 32 ACTION FUTURE EFFECT SHUTDOWN
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ATTACHMENT NPRD-4 TAKEN ACTION ON PLANT.
METHOD HOURS ~ SUBMITTED FORM ~UB.
W@W@ W@
~ !O 1010 IOI LJU@
L.!J@
PRIME COMP.
SUPPLIER COMPONENT MANUFACTURER 33 34 35 36 37 40 41 42 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
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43 IF jl 12 15 I@
44 47 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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IJJil 7
8 9
80 FACILITY OTHER STATUS @
METHOD OF DISCOVERY DESCRIPTION @
STATUS
% POWER DISCOVERY
[ill]~@ 111o101@1 N/A W@I Operator Observation 8
9 10 12 13 44 45 -
46 80 ACTIVITY CONTENT AMOUNT OF ACTIVITY @
LOCATION OF RELEASE @)
RELEASED OF RELEASE IIliJ L!.I @ W@I N/A N/A 7
8 9
10 11 44 45 80
[2l2J PERSONNEL EXPOSURES
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NUMBER
@TYPE DESCRIPTION 39 I 0 I 0 I 0 I 37 ~@.
N A 7
8 9
11 12 13 80 PERSONNEL INJURIES 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