ML19259A586
| ML19259A586 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/26/1978 |
| From: | Edelhauser J JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19259A585 | List: |
| References | |
| NUDOCS 7901080133 | |
| Download: ML19259A586 (2) | |
Text
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Initial Telephone Date of
Report Date:
December 22, 1978 Occurrence:
December 22, 1978 Initial Written Time of Report Date:
December 26, 1978 Occurrence:
12:45 p.m.
0YSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Reportable Occurrence Report No. 50-219/78/35-lP IDENTIFICATION Violation of the Technical Specifications, paragraph 3.5.A.1.C.1, 0F OCCURRENCE:
when the suppression pool water temperature exceeded 95 F. during power operation.
This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.A.2.
CONDITIONS PRIOR X
Steady State Power Routine Shutdown TO OCCURRENCE:
Hot Standby Operation Cold Shutdown Load Changes During Refueling Shutdown Routine Power operation Routine Startup Other (Speci' Operation Power: Generator 665 MWe Reactor 1918 MWth Flow:
Recirculating 15.5 x 104 GPM Feedwater 7.169 x 106 #/hr Reactor Pressure:
1020 psig 4
Stack Gas:
2.95 x 10 pCi/sec.
DESCRIPTION At approximately 12:45 p.m. on Friday, December 22, 1978, the OF OCCURRENCE:
suppression pool water temperature was found to be in excess cf the Technical Specification for the limiting condition for power operation. The average value for the four suppression pool thermocouples at the time of the incident was 95.35 F.
Containment spray system I was initiated at 1:20 p.m. in the suppression pocl cooling mode and the suppression pool water temperature was subsequently brought below 95 F.
7 9 010 8 0 g2,
deportableOccurrence Page 2 6
Report No.* 50-219/78/35-1P APPARENT CAUSE Design Procedure 0F OCCURRENCE:
Manufacture Unusual Service Condition Installation /
Inc. Environmental Construction Component Failure X
Operator Other (Specify)
The apparent cause of the occurrence was the failure of station ptirsonnel to recognize that the suppression pool water temperature was approaching the Tachnical Specification limit for that parameter.
ANALYSIS OF The suppression pool water temperature limits were cstablished OCCURRENCE:
to reduce the affects of the steam quenching vibration phenomenon which may occur at elevated suppression pool water temperature during a loss-of-coolant accident.
The requirement for reactor scram for suppression pool water temperature in excess of 110 F. was developed to prevent exceeding 160 F. during relief valve operation. The 95 F. limit for power operation is intended to provide a 10 F. allowance for testing which adds heat to the suppression pool and still provide a 5 F. margin below the scram requirement.
Since the suppression pool water temperature did not exceed the 110 F. limit during this incident, there appears to be minimal safety significance. Additionally, the time the suppression pool temperature exceeded the 95 F. limit was minimal.
CORRECTIVE The torus water temperature was reduced to less than 95 F. by ACTION:
operation of the containment spray system.
FAILURE DATA:
None a _, 4 Date:
De c 2 G
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- 7 fr Prepared by:
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J. E. ETelhau'5e?
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