ML20059J738

Monthly Operating Rept for Aug 1990 for Hope Creek Generating Station Unit 1

ML20059J738
Person / Time
Site:	Hope Creek
Issue date:	08/31/1990
From:	Hagan J, Zapolski M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HSE-90-317, NUDOCS 9009200145
Download: ML20059J738 (12)

Text

{{#Wiki_filter:G PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station j t l September.14, 1990 HSE-90-317 .j U. S. Nuclear Regulatory Commission ' Document Control Desk Washington, DC 20555

Dear Sir:

-? HON 7.LY OPERATING REPORT HOPE CREEK GodERATANG STATION UNIT 1 DOCKET NO. 50-354 i ~ In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical-Specifications, the operating ~ statistics for August are being forwarded to you with the' -{ summary of changes, tests, and experiments'for August 1990 pursuant to the requirements of 10CFR50.59(b):. Sincerely yours. 1'Mb7-' 4 J. Hagan,, Ge ral-Hanager - Hop >-Creek Operations gj$skAR:ld Attachment i -C Distributien i nm i O su' v a u 'G2A i f s The Energy People - (dk ' 9009200145 900831 DR ADOCK 0500 4 $5 m3(25Mn2 58 7

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l j l AVERAGE DAILY UNIT POWER LEVEL 3 i DOCKET No. _50-354 l UNIT _ Hope Creek DATE-9/14/9_0 3 COMPLETED BY _M. Zapolski> TELEPHONE l(609) 339-3738 MONTH . August 1990:_ t l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE' DAILY POWER LEVEL' (MWe-Net) (MWe-Net) .i 1 1035 17 1025 2 -1026* 18 -1016 3 1027* 19 -1026 4 809 20 1079 5 1029 21 1041' 6 1040 22 1040 7 1026- '23 1044 i 8 1043 24 1040 t 9 1027 25 1028 10 1022 26 '1019' 11 1017 27; -1044-L 12 '1052 28 1016 [ t. t t 13 1027 29 ~1041 14 1031 30

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• Due-t'o an error in recording the meter. readings, the exact average-daily i

power: level for August 2 and 3 is unknown. The listed averages for'those t two days represent the1 average of~the.two-day total.. l 1 l L: -1r

i OPERATING DATA REPORT DOCKET NO. _50-354 UNIT Hope Creek DATE _9LL4/90 COMPLETED BY M. Zapolski TELEPHONE._(609) 339-3738 OPERATING STATUS 1. REPORTING PERIOD July 1990- GROSS HOURS IN REPORTING PERIOD 744 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEPEND. CAPACITY (MWe-Net) 1031 DESIGN ELECTRICAL RATING (MWe-Net). 1067 3. POWER LEVE!,TO WHICH RESTRICTED (IF ANY) (MWe-Net) None 4. REASONS FOR R3STRICTION (IF ANY) THIS YR TO MONTH DATE CUMULATIVE ?. NO. OF HOURS REACTOR WAS CRITICAL 744.0 5515,8 27277.3 6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 7. HOURS GENERATOR ON LINE 744.0 5479.3 _26,830.5 8. UNIT RESERtTE SHUTDOWN HOURS 0.0 0.0 0.0 9. GI'0SS THERMAL ENERGY GENERATED (MWH) __2,433,912. __17 666,457 84,622,833 10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 798,010 5,826,830 _27,983,093 11. NET ELECTRICAL ENERGY GENERATED (HWH) 763,866 5,581,446 _26,737,995 12. REACTOR SERVICE FACTOR 100.0 94.6 84.1 13. REACTOR AVAILABILITY FACTOR 100.0 94.6 84.1 14. UNIT SERVICE FACTOR 100.0 94.0 82.8 15. UNIT AVAILABILITY FACTOR 100.0 94.0 82.8 16. UNIT CAPACITY FACTOR (Using MDC) 99.6 92.8 80.0 17. UNIT CAPACITY FACTOR (Using Design MWe) 96.2 89.7 77.3 18. UNIT FORCED OUTAGE RATE 0.0 3.6 5.2 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION): Refueling, 12/26/90, 50 days 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP: ] N/A i i

l I OPERATING DATA REPORT f UNIT SHUTDOWNS AND POWER. REDUCTIONS < DOCKET NO. __50-354-i UNITL Hope Creek DATE, _9/14/,90 COMPLETED BY M. Zapolski j ' REPORT-MONTH Auaust 1990 TELEPHONE.(609) 339-3738 [ 'i METHOD OF-SHUTTING DOWN.THE -TYPE REACTOR'OR F FORCED DURATION-REASON . REDUCING CORRECTIVE' ACTION /. i NO. DATE-S SCHEDULED (HOURS) (1) POWER (2) COMMENTS' 9 8/3 F 0-B 5 'B' Recire M/G iset: brush repair -? I 1 [ a Y .r L

SUMMARY

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in i i g REFUELING-INFORMATION COMPLETED BY: -Chris Brennan . DOCKET NO:-50-354 1 UNIT NAME: Hope Creek Unit 1 DATE: _9L14/90 TELEPHONE: (609) 339;_1232 j EXTENSION: N/A Month August 1990 1. Refueling information has changed from last month: YES~ X-NO 2. Scheduled date forsnext refueling: - 12/26/90 - 3. ' Scheduled date for restart following refueling _02/13/91_ 4. A) Will Technical Specification' changes or other license amendments be required? ] YES NO X B) Has.the reload _ fuel design been reviewed by the Station Operating Review Committee? YES. NO X __ If no, when is it1 scheduled? not' currently scheduled j S. Scheduled date(s) for submitting proposed licensing action: NLA 6. Important licensing. considerations' associated with refueling: l -Amendment 34 to the Hope Creek Tech Specs allows the cycle -specific operating __ limits tq be incorporated-into the CORE -OPERATING LIMITS REPORT: a submittal is therefore not Eequired. i 7. Number-of Fuel Assemblies: A) Incore _764 B) In Spent Fuel Storage (prior to refueling) _496 C) In Sper.t Fuel Storage (after refueling) 760 i 8. Present licensed spent fuel storage l capacity: 4006 L Future spent fuel storage capacity: 4006 l-9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: July 2 2,- 2007 1 1

'1 (_ ':il ~ HOPE CREEK GENERATING STATION '\\- MONTHLY OPERATING

SUMMARY

). -AUGUST'1990 Hope Creek entered.the month of August at approximately 1004 power.- On August 3rd,-power was. reduced-to repair the "B"-Recirculation Motor / Generator Set Brushes. On; August 4th, power was returned to approximately 100%.- The unit operated-throughout.the remainder of' the month without experiencing'any' shutdowns or other-reportable powerizeductions.- On August-31,fthe plant completed its 157th day lof continuous power-operation. N i d i }L p

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q. - The following Design. Change Package (DCP) has 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 aiporsibility 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 ofusafety as defined'in the basis for any technica11 specification is reduced. The DCP did not create a new safety _ hazard to the plant nor:did it affect:the. safe shutdown of.the reactor. The DCP-did'not change the plant effluent releases and did not alter the existing environmental impact. The' Safety Evaluation determined that no unreviewed safety orLenvironmental questions are involved. o 4 5. l l; l ?[ o ey e w +

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s PS.P. Description of_Desion_ Chance _Packaco 4HM-0583 This DCP installed a new caustic addition system in-the Solid Radwaste System. The previous system was labor intensive; therefore, the installation of the new caustic addition system will result in more efficient use of manpower, I q l i i

i i m*~ ~ i ,The following procedure' revisions have been evaluated to determine: 1). if the probability of occurrence or the consequences.of an .I accident or malfunction of' equipment importantfto' safety 1 previously evaluated in.the safety: analysis report may be 'i increased; or l 2) if a possibility;for an accident or malfunction of a different ' type than any, evaluated previously in the safetycanalysis report-may be created; or i 3)- if the margin of safety!as-definednin the basis for any l technical; specification is reduced.. ~[ i The procedure ~ revisions:did not create'a new safety hazard to the ' plant nor did'they affect the safeLahutdownLof the reactor. The -procedure revisions.did not change the, plant effluent releases'and-did'not alter the existing environmental impact. The Safety i ~ Evaluations. determined.that no unreviewed safety or environmental l' questions are involved.- k '5 'I i h 't .j ~ t {> -[ i ,i s i'!

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I PROCEDURE i REVISION Description ~of__ Procedure' Revision l t t -HC.IC-GP.ZZ-0100(Q) This is the origina1Lissue of a new Controls ~ i Rev. O' Maintenance procedure, "Rosemount Transmitter l Time.Responss. Test.".The procadure provides instructions for performing time. response bench tests;on: replacement Rosemount Li transmitters prior to field installation and i obtains the required Technical Specification .i ' data from the applicable surveillance-procedure:to be-used during,the bench 1 calibration-process.. HC.SA-AP.ZZ-0002(Q) LThis procedure revised the' succession of' l Rev. 13 ' responsibility for the.overall-management of Hope Creek in the event of.an ueexpected contingency.

The; order of'succetsion is-Operations < Manager, Technical Mnnager, j

Maintenance' Manager,-~ Radiation t Protection /Chemi. r; Manager, and Operating. I Engineer. If an indiddual does not. meet--th'e-qualifications lfor Ganetel Manager, the, qualified. person.who13s'next on the succession, list shall assume authority'and responsibility. a t instead. 9 't J L J i. l q y l ~ ^'}}