ML20217N653

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Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With
ML20217N653
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/30/1999
From: Bezilla M, Ritzman R, Todd F
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99456, NUDOCS 9910290100
Download: ML20217N653 (6)


Text

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sj "s J ' O PSEG Public Service Electr! and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit DCT 141999 LR-N99456 U. S. Nuclear Regulatory Commission Document Control Desk F 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 September 1999 are being forwarded. Also

- being forwarded, pursuant to the requirements of 10CFR50.59(b), is the summary of cha%es, tests, and e.rperiments that were in plemented during September 1993.

Sincerely, 4U6 E Mark B. Bezilla Vice President- Operations RAR.

Attachments t

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INDEX NUMBER SECTION OF PAGES

. Ope rating Data Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Monthly Operating Su mmary ....... ...... .......... ... .. .. ... ... ..... ......... . .. ...... ...... 1 Summary of Changes, Tests, and Experiments ... ...... ...................... .. ... 2

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DOCKET NO.: 50-354 UNIT: Hope Creek l

DATE: 10/11/99 COMPLETED BY: F.Todd TilLEPHONE: (609)339-1316 Reporting Period September 1999 OPERATING DATA REPORT Design Electrical Rating (MWrs-Net)

Maximum Dependable Capacity (MWe-Net) 1031 l Month Year-to-date Cumulative  ;

No. of hours reactor was critical 720 l 5389 l 94518 l No. of hours generator was on line (service 713 5329 92938 hours)

Unit reserve shutdown hours 0 l0 l0 l ;

Net Electrical Energy (MWH) 717988 l 5415657 l 94013178 l i i

UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE ACTION /

F= FORCED (HOURS) (1) SHU1 TING COMMENT S= SCHEDULED DOWN THE REACTOR (2) 2 9/1/99 S 7 hrs. B 4 Recirculat'on Pump Seal Repair (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 / License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H - Other

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DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 10/11/99 COMPLETED BY: R. Ritzman TELEPHONE: (609)339-1445 Summary Of Monthly Operating Experience

. At the beginning of September, Hope Creek was shut down for the completion of a maintenance outage. 4

. On September 1, Hope Creek was brought back on line, and reached 100%

reactor power on September 3. l

. Hope Creek continued to operate at approximately 100% reactor power for ,

the remainder of the month.

. At the end of the month, Hope Creek completed 29 days of continuous power operation.

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DOCKET NO.:50-354 UNIT: Hope Creek DATE:10/11/99 COMPLETED BY:R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS,' AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH September 1999 The following items comp!ated during September 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 be 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 margirs 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 plant 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. l Design Changes Summary of Safety Evaluations 4HE-0294, Liquid Radwaste Flow Switch Replaced with Flow Indicating Switch.

This design change replaced a flow switch in the Liquid Radwaste system with a flow indicating switch. This design change will result in more reliable system performance.

The portion of the liquid radwaste system that is being modified is non-safety related, non-seismic, and does not impact any of the accidents discussed in the SAR. This design change does not introduce any new failure mechanisms. This design change j does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and, therefore, does not involve an Unreviewed Safety Question.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS

,_ FOR THE HOPE CREEK GENERATING STATION - Cont'd Temporary Modifications Summary of Safety Evaluations TMR 99-020, Control Room Temporary Electrical Power for Upgrade Work. The purpose of this temporary modification was to supply 480 VAC electrical power to operate a concrete cutting saw in the Control Room during the Control Room upgrade project. The temporary modification consisted on removing the doorknob, placing gasket material over the opening, slicing a slit in the center of the gasket material, and routing cable through the gasket material. This temporary modification was evaluated in accordance with 10CFR50.59 because the door in question is a Control Room Envelop boundary door. The 10CFR50.59 Safety Evaluation determined that there is no increase in unfiltered in-leakage through the door as a result of this temporary modification.

This temporary modification does not introduce any new failure mechanisms. This temporary modification does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety; and; therefore, does not involve an Unreviewed Safety Question.

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

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

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