ML20210C473

Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With

ML20210C473
Person / Time
Site:	Hope Creek
Issue date:	06/30/1999
From:	Bezilla M, Ritzman R, Todd F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99339, NUDOCS 9907260072
Download: ML20210C473 (7)

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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 JUL 151999 LR-N99339 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l

Gentlemen:

kdONTHLY 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 June 1999 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 June 1999. l Sincerely, l

Mark B. Be: .lla /

General Manager -

Hope Creek Operations , l RAR /

Attachments /

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- - INDEX NUMBER SECTION OF PAGES Ope rating Data Re po rt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Monthly Operating S umma ry . . . ....... .. ... ... . . . .... . . . .... . . .. ......... . . .. . .... . ,. .....,, ,,,,, 1 Summary of Changes, Tests, and Experiments ............. .......................... 3

DATE: 07/12/99 COMPLETED BY: F.Todd TELEPHONE: (609) 339-1316 Reporting Period June 1999 OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1067 Maximum Dependable Capacity (MWe-Net) 1031 Month Year-to-date Cumulative No. of hours reactor was critical 720 l 3262 l92391 l No. of hours generator was on line (service 720 3221 l 90831 hours) l Unit reserve shutdown hours 0 l0 l0 l Net Electrical Energy (MWH) 732272 l 3270948 l 91868469 l UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE ACTION / ,

F= FORCED (HOURS) (1) SHUTTING COMMENT l S= SCHEDULED DOWN THE 1 REACTOR (2) 1 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 O - Regulatory Restriction 4 -Continuation i E - Operator Training / License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H - Other

DOCKET NO.: 50-3FA UNIT: Hooe Greek DATE: 07/12/99 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445 Summary Of Monthly Operating Experience

. Power was reduced on June 5 for work on the condensate pre-filter system.

Power was restorea to 100% on June 6.

. Power was reduced on June 26 and again on June 27 for control rod pattern adjustment and scram time testing. Power was restored to 100% on June 27.

. At the end of the month, Hope Creek had been online for 91 days.

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i DOCKET NO.:50-354 UNIT: Hope Creek DATE:07/12/99 COMPLETED BY:R. Ritzman TELEPHONE: (609)339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH June 1999 The following items completed during June 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 j

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 environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations 4EC-3526, Package 1, installation of the Condensate Pre-filter System. This )

design change installed a condensate pre-filter system upstream of the condensate demineralizers between the primary condensate pumps, the steam packing exhauster, and the eteam jet air ejector in the condensate system flow stream. The pre-filter I system removes insolubles, primarily iron, from the condensate water. {

l The purpose of the iron removal is to reduce the occupational exposure and crud l loading on the downstream deep bed condensate demineralizers and brings the facility in conformance with the condensate water purity requirements consistent with EPRI

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION - Cont'd The condensate pre filter system is not safety-related, and the installation of this system did not impact the performance of any safety related system, structure, or component.

Therefore, this design change does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and does not involve an Unreviewed Safety Question.

4EE-0436, High Pressure Coolant injection (HPCI) Condensate Storage Tank Suction Valve Automatic Swapover instrument Setpoint Change to Account for Vortexing. This design change raised the low level setpoint in the condensate storage tank. The setpoint controls the transfer of the High Pressure Coolant Injection (HPCI) suction flowpath from the condensate storage tank to the suppression pool. The change is needed to prevent vortexing at low water levels in the condensate storage )

tank, which could have allowed air entrainment into the HPCI pump suction. 1 l

The ace' 'ent analysis parameters (including pump initiation time, flowrate, volume, and I duratio, o flow delivered to the reactor vessel) remain satisfied. The current design, as implemented by this design change, is bounded by the original analysis. This design change 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.

1 4EE-0439, Setpoint Revision for Chilled Water. This design change increased the  !

chilled water output temperature setpoint of the control room chiller from 47 F to 50 F (nominal). This design change also increased the safety related panel room chiller setpoint from 45'F to 48 F (nominal). The plant computer alarm points were also changed to correspond with these setpoint changes.

This design change did not affect the design of any systems, structures, or components. The new setpoints ensure that the areas served by the chillers remain below their design limits. This design change does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and; theref0re, does not involve an Unreviewed Safety Question.

Temporary Modifications Summary of Safety Evaluations The:e were no reportable changes in this categor; implemented during June 1999.

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

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION - Cont

UFSAR Change Notices Sun. mary of Safety Evaluations H99-30, Reactor Heat Balance at Rated Power. A non-conservative error in the core thermal power calculation was discovered. A portion of the control rod drive system flow was diverted to the recirculation pump seals for purge flow. Some of this flow is allowed to leak to the drywell equipment drain sump; however, most of it passes along the pump shaft into the reactor coolant. This was not accounted for in the core thermal power calculation. The UFSAR change revises the core thermal power calculation methodology.

No changes are being made to the plant as a result of this UFSAR change notice. The change notice updates the UFSAR only. Therefore, this UFSAR change does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and does not involve an Unreviewed Safety Question.

H99-31, Combine Operating Experience with Program Manager- Nuclear Review Board. This UFSR change notice is an administrative change that combines the Operating Experience group with the Nuclear Review Board under a common manager.

The existing functions and responsibilities of each group will be maintained; only the reporting relationships changed. This change is administrative in nature, and does not introduce any new elements to either group. )

l Because the change is administrative in nature, this UFSAR change 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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