ML20073A707

RO 83-4:on 830211,during Controlled Reactor Shutdown,One Dilution Pump Remained in Svc When Intake Canal Water Below Tech Spec Limit.Caused by Personnel Error.Procedures Will Be Revised to Provide More Explicit Directions

ML20073A707
Person / Time
Site:	Oyster Creek
Issue date:	03/23/1983
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RO-83-4, NUDOCS 8304110843
Download: ML20073A707 (3)

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OPU Nuclear g g7 P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Wnter's Direct Dial Number:

March 23, 1983 Mr. Ronald C. itaynes, Administrator Region I U.S. Nuclear Pegulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Ilaynes:

Subj ect: Oyster Creek Nuclear Generating Station Docket No. 50-219 Nonroutine Environmental Operating Report No. 8 3-4 This submittal forwards two copies of the subject Nonroutine Environmental Operating Report in accordance with the OCNGS Technical Specifications, Appendix B, paragraph 5.6.2. Please note that this report is being sulxnitted pa st the thirty day limitation as a result of the need to further investigate this matter.

Very truly yours, 1

Nw A<.)

Peter H. Fiedler Vice President and Director Oyster Creek PBF:jal cc: Director (17 copies)

Of fice of Nuclear Reactor Regulations U.S. Nuclear Regulary Commission Washington, D.C. 20555 N.J. Bureau of Radiation Protection Attention: Chief Division of Environmental Quality United Sierra Building 380 Scotch Road West Trenton, NJ 08625 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River. NJ 08731 8304110843 030323 PDR ADDCK 05000219 0 PDR lear is a part of the General Public Utilities System g

O se OYSTER CFEEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Nonroutine Environmental Operating Report No. 50-219 83-4 Report Date March 23, 1983 Occur re nce Dat e Feb ruary 11, 1983 Identification of Occurrence Violation of Paragraph 2.1.5 in the Environmental Technical Specifications entitled Rate of Change of Discharge Canal Temperature During Winter Shutdowns. One dilution pump remained in service during a controlled reactor shutdown of the station when the intake canal water temperature was less than 10.00 C (50.00 F) and the station operated at less than 70% of full rated power.

This event is considered to be a Nonroutine Environmental Report as defined in the Technical Specifications, Appendix "B", Paragraph 5.6.2.

Conditions Prior to Occurrence Dilution Pump Flow 2.60 E5 GPM Circulating Water Pump Flow 3.45 E5 GPM Prior to the occurrence, the ambient water temperature in the intake canal was 30.20F. The condenser discharge water temperature was 41.10F, and the U.S.

Route 9 Discharge bridge temperature was 34.60F.

Description of Occurrence A controlled reactor shutdown of the station commenced at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on 11 February 1983, with the station operating at a thermal power of 754 MWT and a generator load of 227 MWb. At this time, dilution pump 1-1 remained in service with the intake canal water temperature below 10.0 C0(50.0 F).0 Dilution pump 1-1 was removed from service at 0012 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on 12 February 1983.

Apparent Cause of Occurrence Procedure 324 Thermal Dilution Pumps (Section 3.0 Plant Operating Requirements; Paragraph 3.3) specifies the requirements for operating the dilution pumps during a controlled reactor shutdown. However, station personnel failed to follow the requirements of the procedure by leaving dilution pump 1-1 in service during the shutdown.

Nonroutine Environmental Operating Report . Page 2 Report No. 50-219 83-4 9

Analysis of Occurrence The shutdown of dilution pumps is required during controlled shutdowns in the winter when the first circulating pump is turned off or when 70% of full rated power is reached (whichever comes first). The objective of operating the dilution pumps in the' prescribed manner is to minimize thermal stress to aquatic organisms in Oyster Creek and contiguous waters due to sudden changes in water temperature. There were no harmful biological ef fects observed from 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on 11 February 1983 to 0012 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on 12 February 1983 when dilution pump 1-1 continued to operate during the controlled reactor shutdown.

Corrective Action

Procedure 324 Thermal Dilution Pumps (Section 3.0 Plant Operating Requirements) addresses shutdowns for power levels greater than 70% power.

This procedure will be revised to provide more explicit directions for dilution pump operation during shutdowns. These directions will encompass all operating power levels to account for shutdowns from power levels less than 70% as recently occurred.

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