LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1

Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1

ML20237C514
Person / Time
Site:	Hope Creek
Issue date:	07/31/1998
From:	Bezilla M, Ritzman R, Todd F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N980401, NUDOCS 9808210233
Download: ML20237C514 (6)

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

AUG 131998 l LR-N980401 {

i U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 i

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 July 1998 are being forwarded. Also being forwarded to you, pursuant to the requirements of 10CFR50.59(b), is the summary of changes, tests, and experiments that were implemented during July 1998, i Si erely,

%Q_In.BG&uh Ma B. Bezilla General Manager -

Hope Creek Operations RAR/mw Attachments i

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INDEX NUMBER SECTION OF PAGES Ope rating Data Re po rt. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Montbly Operating Su mma ry. . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . .. . . 1 l-Summary of Changes, Tests, and Experiments... ...... ... ......... ... ......... .. 2 l

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i. DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 08/13/98 COMPLETED BY: F.Todd TELEPHONE: (609) 339-1316 l

Reporting Period July 1998 OPERATING DATA REPORT l

Design Electrical Rating (MWe-Net)

Maximum Dependable Capacity (MWe-Net) 103 l Month Year-to-date Cumulative No. of hours reactor was critical 744 l 5087 l 85627 l No. of hours generator was on line (service 744 5087 84157 hours)

Unit reserve shutdown hours 0 l0 l0 l Net Electrical Energy (MWH) 761671 l5260248 l 85157400 l I

i UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F= FORCED (HOURS) (1) SHUTTING ACTION / COMMENT S= SCHEDULED DOWN THE l REACTOR (2)  !

N/A i (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 i- E - Operator Training / License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

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DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 08/13/98 COMPLETED BY: R. Ritzman TELEPHONE: (609)339-1445 Summary Of Monthly Operating Experience

. Hope Creek entered the month of July at approximately 100% reactor power.

. At the end of the month, Hope Creek had completed its 230th consecutive day of continuous power operation.

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l DOCKET NO.; 50-354 UNIT: Hope Creek DATE: 08/13/98 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS

! FOR THE HOPE CREEK GENERATING STATION 1

l MONTH JULY 1998 The following items completed during July 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 l

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 2

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

The 10CFR50.59 Safety Evaluations showed that these items did not create a new l 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 i unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations 4HE-0274, Package 2, Change "B" Residual Heat Removal / Core Spray Permissive from Individual Series Circuits to a Joint One Out of Two Taken Twice Circuit.

This design change rearranged contacts in auxiliary relays in the 4160 volt Class 1E

. Channel"B" bus undervoltage relaying logic from two individual series circuits to a one 4 out of two taken twice circuit. These contacts provide closing voltage permissive circuits for the Channel "B" Residual Heat Removal (RHR) and Core Spray pump motors.' The pump motors are protected because they can only be started if voltage is  !

adequate. This design change makes the closing permissive circuit more reliable.

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This design change rearranged the wiring of the existing components to increase the

. reliability of the circuitry. The increased reliability is achieved by allowing both RHR and Core Spray to operate if any one of the four auxiliary relays fails. Failure of the fuse feeding the closing permissives would result in the loss of the "B" channel RHR and Core Spray channel, but does not violate the separation or independence requirements.

This design change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this design change.

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

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

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

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

Other Summary of Safety Evaluation There were no reportable changes in this category implemented during July 1998.