ML19345C341

Nonroutine Environ Operating Rept 50-219/80-10:on 801111,ETS Limiting Condition Exceeded When Less than Two Dilution Pumps Worked for 25 Minutes W/Ambient Intake Water Temp at Less than 60 F.Caused by Unusual Svc Condition

ML19345C341
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-50-219-80-10, NUDOCS 8012040445
Download: ML19345C341 (4)

Text

l OYSTER CREEK NUCLEAR GENERATING STATION cT Z 9 'f p g S g g (609) 6931951 P.O. BOX 388

• FORKED RIVER

• NEW JERSEY

• o8731 c M E.cu u oseem November 21, 1980 i

a Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue 3

King of Prussia, Pennsylvania 19406 a

SUBJECT:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Nonroutine Environmental Operatinn 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, M

Ivan R. Finfrock, Vice President-Ge rati 3

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, DDC, ADM coo 3 l

8012040'lYS 5

^

c-o OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Nonroutine Environmental Operating Report No. 50-219/80-10 Report Date l

-November 21, 1980 l

Occurrence Date November ll,1980 Identification of Occurrence Exceeding a limiting condition as defined in the Environmental Technical Speci-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 than 60.0*F..The event was immediately identified at the time of non-compliance.

This event is considered to be a Ncn-Routine Environmental Operating Report as defined in the Technical Specifica.fons, Appendix "B", Paragraph 5.6.2.

Conditions Prior to Occurrence f

Steady State Power Dilution Pump Flow:

5.20 E5 GPM Circulating Water Pump Flow 4.60 ES GPM Prior to the occurrence, the ambient water temperature in the intake canal was 45.8*F.

The condenser discharge water temperature was 67.5*F and the US Route 9 Discharge Bridge temperature was 52.3 F.

Description of Occurrence.

Beginning on November 10, 1980, gale force winds churned up debris in Barnegat.

Bay which soon piled up against the Dilution Pump Intake Structure.

Eventually, debris was drawn into the dilution pump seal water strainers.

The clogged y

strainers resulted in a reduced seal water pressure which in turn tripped Dilution Pump 1-2 at 1802 on Novembe'- 11, 1980.

Plant operators cleared the strainers and the intake lines and returned the pump to operation at 1827 on November ll,1980.

Apparent Cause of Occurrence Unusual Service Condition Including Environmental Component Failure l

,.~

e

Nonroutine Environmental Operating Report No. 50-219/80-10 Page 2 Analysis of Occurrence Dilution Pump 1-2 tripped due to low seal water pressure 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 Qyster Creek. This pump operation will encourage fish to migrate south rather i

than remaining in the discharge canal during winter.

One (1) dilution pump was out of operation for 25 minutes, which resulted in a temperature increate 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 Inmediate corrective action involved clearing the seal water intake lines and strainers of debris and restarting the pump. A long term 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 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.

O t

l c

U. S. NUCLEAR CEGULATORY COMMISSION NRC FORM 364

~

LICENSEE EVENT REPORT CONTROL BLOCK: l l

i I

i (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) rm1 i i

i i

i i

ei i

i i

i i

i i

i i

i iei i

i i i Jei i

ie 7

6 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO Si GAT 14 CON'T 101 1 OUT I

@lOISlololol'Al /19'GI I

I I I I

@ l/1/131/I 6161@

J 8

60 61 DOCKET NUMSER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h I

F6Tf1 1 IO lai I

$6E bG

[

l l

10141l l

10151l I

lTTs l l I

ITITl I 1

101811 80 DE CODE S SC DE COMPONENT CODE S 8 CODE SU E

O 9 I

I l@ U @ Lj@ l I

i l

I l

I@ LJ@ L_J @

7 8

9 10 ti 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LE EVENT YEAR REPORT NO.

CODE TYPE NO.

@,aj =R RO11r 101 l-l 101/ I of id i

I I

LJ l-J l

I r

21 22 23 24 26 27 28 29 30 31 12 KN AC O PL T ME HOURS S8 IT POR S.

S PPLI MANUPAC RER U@l l@

LJ@

l l@

l iI I

I LJ@

L_JO LJ@

l I

i i I@

JJ 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1

I i 101 l I

It til l l

mi I

U_LJ l 1

[ED 1 80 4 7

8 9 STA 3

% POWER OTHER STATUS ISS O RY DISCOVERY DESCRIPTION LM5Jl l@ l I

I l@l l

I l@l I

ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OP ACTIVITY LOCATION OF RELEASE L'_LeJ l l@l l@l I

I I

PERSONNEL EXPOSURES NUM8ER TYPE DESCRIPTION ii ni i i

i i@ u @i i

PERSONNEL tNJURIES NUYBER DESCRIPTION 1

ii ia i i i

i f81 80 7

8 9 11 12 i

l TYPE DESCR PT ON i

u @i l

, e 80 7

8

'J 10 ISSUEi@ DESCRIPTION L_

l i

Illlillililli!

2 O 68 69 80 S f

1 8 9 10 NAVE OF PREPARER PHONE:

l