ML19345B436
| ML19345B436 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/21/1980 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RO-80-010, RO-80-10, NUDOCS 8012010319 | |
| Download: ML19345B436 (3) | |
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OYSTER CREEK NUCLEAR GENERATING STATION E4CM *l:3 ]
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- FORKED RIVER
- 08731 November 21, 1980 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
SUBJECT:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Nonroutine Environmental Operating Report No. 50-219/80-10 This letter forwards two copies of Nonroutine Environmental Operating Report No. 50-219/80-10 in compliance with paragraph 5.6.2 of Appendix B to the Technical Specifications.
Very truly yours,
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Ivan R. Finfrock, . p Vice President-Ge rat 2 IRF:dh Enclosures cc: Director (17 copies)
Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Washington, D. C. 20555 -
c/o Distribution Services Branch, ODC, ADM ~
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6 i OYSTER CREEK NUCLEAR GENERATING STATION
Forked River, New Jersey 08731
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Nonroutine Environmental Operating Report No. 50-219/80-10
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Report Date November 21, 1980 j Occurrence Date
, . November 11, 1980 Identification of Occurrence - !
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- - Exceeding a limiting condition as defined in the Environmental Technical Speci-j fication, Paragraph 2.1.4.2, when less than two dilution pumps were operating
! for a period of 25 minutes while the ambient intake water temperature was less i
. than 60.0*F. The event was imediately filentified at the' time of non-compliance.
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l This event is considered to be a Non-Routine Environmental Operating Report as ;
defined in the Technical Specifications, Appendix "B", Paragraph E.6.2.
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l Conditions Prior to Occurrence
, Steady State Power i
Dilution Pump Flow: 5.20 E5 GPM !
- Circulating Water
! Pump Flow. 4.60 E5 GPM Prior to the occurrence, the ambient water' temperature in the intake canal was 45.8'F. The condenser discharge wate.- temperature was. 67.5 F and the US Route 9 Discharge Bridge: temperature was 52.37
< Description of Occurrence Beginning on November 10, 1980, gale force wind: churned up debris in Barnegat 4
Bay which soon piled up against the Dilution Pump Intake Structure. Eventually,
. debris was drawn into the dilution pump seal water strainers. The clogged strainers resulted in a reduced seal water pressure which in turn tripped Dilution Pump 1-2 at 1802 on November 11, 1980. Plant operators cleared the strainers and the intake lines and returned the pump to operation at 1827 on
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November 11, 1980.
Apparent Cause of Occurrence Unusual Service Condition Including Environmental
- Component Failure *
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Nonroutine Environmental Operating Report No. 50-219/80-10 Page 2 Analysis of Occurrence Dilution Pump 1-2 tripped due to low seal water cressure which was caused by clogged seal water intake strainers.
Continuous operation of two (2) dilution pumps when the intake temperature is below 60*F will reduce attraction of fish from accumulating and building up in Oyster Creek. This pump operation will encourage fish to migrate south rather than remaining in the discharge canal during winter.
One (1) dilution pump was out of operation for 25 minutes, which resulted in a temperature increase of 3.0*F as measured in Oyster Creek at the US Route 9 Bridge. Minimal adverse biological effects accompanied this temperature transient.
Corrective Action Immediate corrective action involved clearing the seal water intake lines and strainers of debris and restarting the pump. A long tenn proposal presently being considered would be to replace the present cooling / seal water pumps, located on the Dilution Structure, with two new cooling / seal water pumps of 4
greater capacity which tentatively would be located at the facility's fresh water fire pond.
The seal water strainer and filter differential pressure alarms will be repaired to alert the operator prior to pump trip.
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U. S. NUCLEAR RESULATC'sY COMMISSION C5: FORM 386 47 77)
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