ML20217A493

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

ML20217A493
Person / Time
Site:	Hope Creek
Issue date:	10/31/1990
From:	Hollingsworth, Clay Johnson, Zapolski M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9011210116
Download: ML20217A493 (14)

Text

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~QPSEG Public Scrvice Electric and Gas Cornpany P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station November 15, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sir MONTilLY OPERATING REPORT llOPE CREEK GENERATION STATION UNIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the llope Creek Technical Specifications, the operating statistics for October are being forwarded to you with the summary of changes, tests, and experiments for October 1990 pursuant to the requirements of 10CFR50.59(b).

Sincerely.yours, C. P ohnson Gen 1 Manager -

11op Creek Operations gt M R:1d Attachments C . Distribution Tho Fnntov POODl0 9011210116 90)o31 gon nootg osoooyu

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INDEX i

NUMBER  ;

SECTION OF PAGES i 1

- Average Daily Unit Power Level. . . . . . . . . . . 1  !

- Operating Data Report . . . . . . . . . . . . . . . 2  !

Refueling Information . . .. . . . . . . . . . . . 1 Monthly Operating Summary . . . . . . . . . . . . . 1 1

. Summary of changes, Tests, and Experiments. . . . . 7 l l

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AVERAGE DAILY UNIT POWER LEVEL i

l DOCKET NO. 50-354 UNIT Bope Creek l DATE 11/15/90 1

,. CONPLETED BY L_3apolski l I

TELEPHONE -(609) 339-3738 '

i NONTH October 1990 I. DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (WWe-Net) (NWe-Met)

1. H1 17. 1052 '

2. 1115 18. 1039

3. 1036 19. 1097

4. 1039 20. 1017

'5. 19JJ, 21. 1045

6. 1031 22. 19J1

7. Mk 23. LQip

8. 1911 24. 1014 l

9. 1054 25. 1078

10. 1009 26. 1043 l' 11. 1070 27. 1058 ,

l 12 . .- 1911 28. 1108

13. 19J1 29. 1065 l

14. 1047 30. 1052 '

15. 1911 31. 1018

16. 1047

F OPERATING DATA REPORT DOCKET NO. 50-354 UNIT Hope Creek DATE 11/15/90 COMPLETED BY M. Empolski TELEPHONE (609) 339-3738 ,

OPERATING STATU5

1. Reporting Period October 1990 Gross Hours in Report Period 111

2. Currently Authorized Power Level (NWt) 3293 Max. Depend. Capacity (MWe-Net) 1911 Design Electrical Rating (MWe-Net) 1067.

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3. Power Level to which restricted (if any) (NWe-Net) Hang

t. P.aasons for restriction (if any)

This Yr To MADih Date quatulative

5. No. of hours reactor was critical 745.0 6980.0 28,742.3

6. Reactor reserve shutdown hours 112 921 AAA i

7. Hours generator on line 745.0 6944.3 28,295.5

8. Unit reserve shutdown hours gig 02 1 111 9.. Gross thermal energy generated 2,437,f56 22,470,624 89.427,000 (MWH)

10. Gross electrical energy 808,020 7,417.330 29,573,593 generated (NWH)

11. Net electrical energy generated 774,011 7,105,020 28,261,569

! (MWH) ,

12. Reactor service factor 11A11 95.7 1121

13. Reactor availability factor 100.0 1111 84.8

14. Unit service factor 11Rt1 95.2 11x1

15. Unit availability factor 100.0 95.2 11th

16. Unit capacity factor (using MDC) 100.8 94.5 80.9

17. Unit capacity factor 97.4 91.3 78.2 l (Using Design MWe)

18. Unit forced outage rate 119 lit 111

19. Shutdowns scheduled over next 6 months (type, date, & duration): ,

Refueling, 12/26/90, 50 days

20. If shutdown at and of report period, estimated date of start-up N/A

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. OPERATING DATA REPORT Uti1T SHUTDOWNS AllD POWER REDUCTIONS DOCRET NO. 50-354 UNIT t!ppe__C r e ek DATE 11/15L9.0 COMPLETED BY li. Zapolski TELEPHONE 1509) 339.3738 MONTH October 119_0 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE HO. DATE S= SCHEDULED (HOURS) (1) POWER (2) ACTIO!!/ COMMENTS 10 10/7 S 0 B 5 "A" Recire M-G Set Drushoe Maintenance Summary

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. l REFUELING INFORMATION DOCKET No. 50-354 UNIT None Creek  :

DATE 11/15/90 COMPLETED BY s. Hollingsworth TELEPHONE (609) 339-1051 NONTH October 1990

1. Refueling information has changed from last month Yes X No

2. Scheduled date for next refueling: 12/26/90 l 3. Scheduled date for restart following refueling: 02/11/91

4. A. Will Technical specification changes or other license amendments be required?

Yes No X B. Mas the reload fuel design been reviewed by the Station Operating Review Committee?

l Yes No X l

If no, when is it scheduled? not currently schniq114

5. Scheduleil date(s) for submitting proposed licensing action: MfA

6. Importar.t licensing considerations associated with refuelingt

- Amendment 34 to the Hope Creek Tech specs allows the cycle spec!.fic operating limits to be incorporated into the CORE

. OPERATING LIMITS REPORT; a submittal is therefore not L required.

1 1 7. Number of Fuel Assemblies A. Incore 111 B. In Spent Fuel Storage (prior to refueling) 111 C. In Spent Fuel Storage (after refueling) lig

8. Present licensed spent fuel storage capacity 4006 Future spent fuel storage capacity 400(

9. Date of last refueling that can be discharged July 22, 2007 to spent fuel pool assuming the present licensed capacity: ,

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HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

OCTOBER 1990 I

Hope Creek entered the month of October at approximately 100% '

power. On october 7th, power was reduced to perform maintenance on the "A" Recirculation Motor / Generator set Brushes. Power was returned to approximately 100%. The unit operated throughout the '

remainder of the month without experiencing any shutdowns or other reportable power reductions. On October 31st, the plant completed its 21sth day of continuous power operation.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS ,

FOR THE HOPE CREEK GENERATING STATION OCTOBER 1990 i

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The following Design Change Packages (DCP's) have been evaluate.

to determine

1. If the probability of occurrence or the consequences of an l accident or malfunction of equipment important to safety j previously evaluated in the safety nalysis report may be increased; or

2. If a possibility for an accident or matfunction of a different type than any evaluated previously in *:he 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 DCP's did not create a new safety hasard to the plant nor did I they affect the safe shutdown of the reactor. The DCP's did not change the plant affluent releases and did not alter the existing environmental impact. The Safety Evtluations determined that no -:.

unreviewed safety or environmental questions are involved.

-. pgg pg.agrintion of Desian Chance Packace 4EC-3184 This DCP added tees, isolation valves, and tubing to lines leading to the Process Sampling Panel.

This will allow samples to be taken upstream of the pressure regulating valves and will result in more z representative samples being taken.

4HC-0077/02 This DCP installed three Condensate Cooling Heat Exchangers to act as heat sinks for condensate from the Plant 8 team Heating System. It also installed additional piping in the Turbine AuAlliaries cooling System and the condensate System. This DCP will reduce the hasard of non-condensed steam escaping from the vents in the condensate Collection Tanks.

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The following Temporary Modification Request (TMR) has been evaluated to determines

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 anslysis report may be created; or

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

The TMR did nct create a new safety hasard to the plant nor did it affect the safe shutdown of the reactor. The TMR did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluation determined that no unreviewed safety or environmental questions are involved.

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e THE D9scription of Temporary Modification Request 90-051 This TMR removed the input signals from defective reed switches for Control Rod 38-03. The input signal was removed by modifying the Rod Position Information System Probe Multiplexor Card to electronically disconnect the input.

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e The following procedure revisions 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 procedure revisions did not create a new safety hasard to the plant nor did they affect the safe shutdown of the reactor. The procedure revisions did not change the plant effluent releases and did not alter the existing environmental impact. The safety L Evaluations determined that no unreviewed safety or environmental questions are involved.

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.- Procedure Revision Descriotion of Proqadure Revision HC.IC-GP.ZZ-0103(Q) This is the original issue of a new Rev. O Controls Maintenance procedure, "Rosemount Transmitters Neck Seal Requirements." This procedure provides a test of the integrity of a Rosemount Model 1153 transmitter located in a harsh environment located 4

outside of the Drywell.

HC.RE-FR.ZZ-0004(Q) This procedure revision removes all spray

=Rev. 10 or misting fire hose nozzles from the araa of fuel receipt, includes the metal shipping container as a storage area for and provides nonconforming bundles,ing instructions for chang flow nozzles on hose stations on the Refuel Floor.

HC.SE-PR.EG-0001(Q) This procedure revision changes the

'Rev. 1 frequency of performing the Safety Auxiliarles Cooling System Heat Exchanger Performance Test from monthly to annually.

This is being done to reduce the challenges to the plant that arise-from swapping Turbine Auxiliaries Cooling System channels as required by this procedure.

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