ML19330C282

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RO 50-219/80-2:on 791125-26,during Routine Startup,Less than Two Dilution Pumps Were Operating for 9-h & 47 Minutes While Ambient Water Temp Was Less than 60.0 F.Caused by Error in Plant Procedures.Plant Procedures Were Revised
ML19330C282
Person / Time
Site: Oyster Creek
Issue date: 07/29/1980
From: Baran R, Weigle D
JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19330C281 List:
References
NUDOCS 8008080174
Download: ML19330C282 (2)


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. Dates of November 25,~1979'and-

, Initial Telephone

. November 26, 1979 1 June 16,1980 Occurrence:

3 }ReportDate:

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Time of

Written .  ! July 29,' 1980 Occurrence: 2316 to 0903 P,eport : Date: - ,

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0YSTE CREEK NUCLEAR GENERATING STATION -

- FORKED RIVER, NEW JERSEY 08731-P! Non-Routine Environmental Operating Report Report No. 50-219/80-2

. IDENTIFICATION Exceeding a limiting condition as' defined in the Environmental 0F OCCURRENCE:

Technical. Specifications, Paragraph 2.1.4.2. when less than two_ dilution pumps.were operating for a period of 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and ~

47 minutes;.while the ambient water temperature was less than 60.0 F.1This event was discovered during a routine inhouse Quality Assurance Audit held on June 12, 1980, and confirmed as a non-compliance by the plant staff on June 17, 1980.

'L This event is considered to be a Non-Routine Environmental Operating Report as defined in the Technical Specifications . .

. Appendix "B", Paragraph 5.6.2.

Stead'y State Power _ Routine Shutdown CONDITIONS PRIOR. '

Hot Standby' Operation tTO.0CCURRENCE: < Load Changes During Cold Shutdown -

Refueling' Shutdown Routine Power Operation '

-X Routine Startup Other (Sp'ecify).

Operation', . '

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Dilution Pump Flow: 2.60 E~5 GPM 7

' ' Circulation Water Pump

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Flow: i . 4.60 E 5 GPM

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. Prior to the occurrence, the ambient water temperature in l~ -

'the. intake canal was 56.1 F. The condenser discharge temperature.and the US Route #9 discharge bridge t.emperature

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'- .was 57.5 F and 58.8 F respectively.

s 1 DESCRIPTION-

"A reactor scram occurred at 1703 on November 23, 1979. At the ~

OF OCCURRENCE: ,,1 time. of-the- scram ithe ~ intake water temperature was 56.9 F and I ,

J Dilution' Pumps 1-l' and 1-2 were in operation.

- Both dilution

. ' pumps were shut down-127_ minutes following the' scram.- Reactor

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startup commenced on November 25, 1979 with the reactor.-

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achieving criticality at 0553. Dilution Pump 1-1 had been started at 0056 the same date. At 2316 on November 25, 1979, Lthe reactor'~ mode switch was placed in the run mode at a power;

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level of ap' proximately 19 MW thermal. At 0903 on November 26, L

T 1979, Dilution Pump 1-2 was started. During the operating .

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Page 2' I Non-Routine' Environmental-Operating Report a' .. Report'No. 50-219/80-2:

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period from 2316 on November 25,1979, to 0903. on November. 26,.

1979, the intake temp'erature did not rise above 56.1 F. For

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9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and 47 minutes, only one dilution pump was in operation

. while' the: intake water temperature was below 60.0 F.

! Design >' X Procedure JAPPARENT CAUSE' Manufacture . Unusual Service Condition

~&F:0CCURRENCE:- _

Inc. Environmental

-Installation /

Construction Component failure Operator. Other (Specify)

. Plant procedures did not include provisions governing dilution 3 . pump operation during reactor startup.

Continuous operation of'two dilution pumps when the intake i

ANALYSIS OF OCCURRENCE:

water. temperature is below 60.0 F during plant operation will reduce attraction of fish from accumulating and building 1

up in the discharge canal. Proper pump operation will encourage fish to migrate south rather than remain in the discharge canal y_

during the winter. ,

I' At the time the second dilution pump was started, the reactor

!.I power level was only 32% of rated power. The corresponding intake, discharge, and discharge bridge temperatures were L

- 56.3 F, 61.6 F, and 61.1 F. . Failure to operate.the dilution

,l pumps' i.n accordance with ' Technical Specification 2.1.4.2 had minimal, if any, ' adverse biological effects on' aquatic

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' organisms.

- Plant react'or startup procedures will be revised to incorporate ~

CORRECTIVE '

criteria governing dilution pump operation as per Technical.

ACTION:

Specification, Appendix "B", Section 2.1.4.-

FAILURE DATA:

Not Applicable.:

Date: 7 Bo Prepared.by: - / 'e _

, Oduglas WeigleC /

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M A Date: 7 PO lApprovedbp:

Ror,ald Baran L1# '

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