LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With

Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With

ML20154R510
Person / Time
Site:	Hope Creek
Issue date:	09/30/1998
From:	Bezilla M, Todd F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N980491, NUDOCS 9810270053
Download: ML20154R510 (6)

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 OCT 151998 LR-N980491 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 September 1998 are being forwarded. No changt s, 'wN, and experiments were implemented during September 1998 that reaid ; summary to be forwarded to you pursuant to the requirements of 100Fn50.59(b).

Sin rely,

, ib(Lm A%%LLA Mark B. Bezilla General Manager -

Hope Creek Operations RAR/mw Attachments i

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1 INDEX NUMBER SECTION OF PAGES 4 Operating Data Report..... .... ............. ............ ...............................1 Month ly Operatin g S u mma ry.. . . . . . . . . . ... . .. . . . . . . . . . . . . . . . .. . . . . . .. . . . ... . . . . ... . . . . . . 1 4-Summary of Changes, Tests, and Experiments................ . . .......2 d

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DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 10/12/98 l

COMPLETED BY: F.Todd '

TELEPHONE: (609) 339-1316 {

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Reporting Period September 1998 l OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1067 W49Ashs9B$9 * *fS B " d Maximum Dependable Capacity (MWe-Net) 1031 @NdisWMn ims t#C*"""Oj$

Month Year-to-date Cumulative No. of hours reactor was critical 720 6551 87091 1 No. of hours generator was on line (service 720 6551 85621 hours)

Unit reserve shutdown hours 0 0 0 Net Electrical Energy (MWH) 734972 6735954 86633106 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE ACTION /

F= FORCED (HOURS) (1) SHUTTING COMMENT S= SCHEDULED DOWN THE REACTOR (2)

N/A (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 l

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DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 10/12/98 COMPLETED BY: R. Ritzman TELEPHONE: (609) 330-1445 Summary Of Monthly Operating Experience Hope Creek entered the month of September at approximately 100% reactor power.

. On September 12, power was reduced for condenser water box tube leak repairs. Power was restored to approximately 100% reactor power on September 13.

. At the end of the month, Hope Creek had completed its 291st day of continuous power operation.

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DOCKET NO.:50-354 UNIT: Hope Creek DATE:10/1~ o COMPLETED BY:R. Etwrun TELEPHONE: (609) 355% 545  ;

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS l

FOR THE HOPE CREEK GENERATING STATION MONTH SEPTEMBER 1998 The following items completed during September 1998 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 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 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.

Design Changes Summary of Safety Evaluations There were no reportable changes in this category implemented during September 1998.

Temporary Modifications Summary of Safety Evaluations There were no reportable changes in this category implemented during September 1998.

4 Procedures Summary of Safety Evaluations There were no reportable changes in this category implemented during September 1998.

UFSAR Change Notices Summary of Safety Evaluations There were no reportable changes in this category implemented during September 1998.

Deficiency Reports Summary of Safety Evaluations There were no reportable changes in this category implemented during September 1998.

Other Summary of Safety Evaluation Engineering Evaluation H-1-GJ-MEE-1264, Safety-Related Chiller Operation and River Water Temperature. This engineering evaluation revises the initiation of the back-up air / gas supply to the safety-related chiller Safety Auxiliaries Cooling System (SACS) flow control valves from a part-time temperature-dependent service to a full-time service. This will ensure that the Control Room chillers will not trip due to low SACS temperatures, and that SACS will be able to provide sufficient flow to the Residual Heat Removal (RHR) heat exchangers for all cross tied configurations during l periods of high SACS temperatures.

Under the existing design condition, without the back-up air / gas supply system, a plant loss of Instrument Air could cause the Control Room and 1E Panel Room chillers to trip on low evaporator refrigerant pressure when SACS temperature is s70 F. SACS would not be able to provide sufficient flow to the RHR heat exchangers for all cross-tied configurations during periods of high SACS temperatures under all accident conditions.

i This proposal revises the back-up air / gas supply system from a part-time temperature-dependent service to a full-time service. The change increases the reliability of the Control Area Chilled Water System and will not adversely affect the design function of the system, nor does it increase any probabilities or consequences of any malfunctions of equipment important to safety or accidents as described in the UFSAR accident analyses. There is no USQ and the UFSAR is changed to reflect the back-up air / gas supply to a full-time service.