ML20212E745

Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With

ML20212E745
Person / Time
Site:	Farley
Issue date:	08/31/1999
From:	Bezilla M, Ritzman R, Todd F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99422, NUDOCS 9909270132
Download: ML20212E745 (5)

Text

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O PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit w.

SEP151999 LR-N99422 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 DOCKET NO. 50-354 in compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for August 1999 are being forwarded. Also being forwarded, pursuant to the requirements of 10CFR50.59(b), is the summary of changes, tests, and experiments that were implemented during August 1999.

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Sincerely, Mark B. Bezilla Vice President - Operations RAR.

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. SECTION OF PAGES Ope rati ng Data Repo rt............................................................................ 1 1

Monthly Operating Su mma ry.................................................................... 1 Summary of Changes, Tests, and Experiments........................................ 2 1

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DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 09/10/99 COMPLETED BY: F.Todd TELEPHONE: (609) 339-1316 Reporting Period August 1999 OPERATING DATA REPORT Design Electrical Rating (MWe-Net)

Maximum Dependable Capacity (MWe-Net) 1031 Month Year-to-date Cumulative No. of hours reactor was critical 664 l 4669 l 93798 l

No. of hours generator was on line (service 650 4616 92225 hours)

Unit reserve shutdown hours 0

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Net Electrical Energy (MWH) 666367 l 4697669 l 93295190 l

UNIT SHUTDOWNS NO.

DATE TYPE DURATION REASON METHOD OF CORRECTIVE ACTION /

F= FORCED (HOURS)

(1)

SHUTTING COMMENT S= SCHEDULED DOWN THE l

REACTOR (2) 2 8/28/99 S

94 hrs.

B 2

Recirculation Pump Seal Repair 8/31/99 (1) Reason (2) Method A-Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip / Scram C - Refueling 3 - Automatic Trip / Scram D - Regulatory Restriction 4 - Continuation E - Operator Training /Ucense Examination 5 - Other (Explain)

F-Administrative G - Opetational Error (Explain)

H - Other

DOCNF.T NO.: 50-354 UNIT: Hope Creek DATE: 09/10/99 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445 Summary Of Monthly Operating Experience At the beginning of August, Hope Creek was operating at approximately 100% reactor power.

On August 2,8, and 15, power was reduced to perform turbine control valve testing. Each time, power was restored to 100% the same day.

On August 20, there was an intermediate reactor runback due to a lightning strike on a transmission line. Power was restored to 100% on August 21.

On August 28, the reactor was shutdown for "A" Recirculation Pump Seal replacement and Main Turbine balancing. The outage continued through the end of the month.

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DOCKET NO.:50-354 UNIT: Hope Creek DATE:09/10/99 COMPLETED BY:R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH August 1999 The following items completed during August 1999 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may te increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the piant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmentalimpact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations 4HE-0390, Removal of the Station Service Water System Vacuum Breaker Valves.

This design change removed the Station Service Water System Vacuum Breakers and replaced them with piping. The piping meets the code requirements of the Station Service Water System and provides a continuous vent path at the high point of the Station Service Water System downstream of the heat exchangers. The removal of these valves will also contribute to increased system availability.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION - Cent'd

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I System response to operational transients or postulated design basis accidents remains bounded by the previous and is improved for sorne cases. This design change does not introduce any new failure mechanisms. This design change does not increase l

the possibility or consequences of any accident or malfunction, does not reduce the I

margin of safety, and, therefore, does not involve an Unreviewed Safety Question.

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l Temporary Modifications Summary of Safety Evaluations J

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There were no reportable changes in this category implemented during August 1999.

Procedures Summary of Safety Evaluations There were no reportable changes in this category implemented during August 1999.

UFSAR Change Notices Summary of Safety Evaluations There were no reportable changes in this category implemented during August 1999.

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