ML20024H076

Monthly Operating Rept for Apr 1991 for Hope Creek Generation Station Unit 1.W/910513 Ltr

ML20024H076
Person / Time
Site:	Hope Creek
Issue date:	04/30/1991
From:	Hagan J, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9105210118
Download: ML20024H076 (12)

Text

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CPSIEG Public Service Electric rad Gas Company P.O. Box 236 Hancocks Bridge, flew Jersey 08038 Hope Creek Generating Station May 13, 1991 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT HOPE CREEK GENERATION STATION UNIT 1 DOCKET NO. 50-354 In-compliance with Section.6.9, Reporting Requirements for l

the Hope Creek Technical Specifications, the operating statistics.for April are-being forwarded to you with the-summary of changes, tests, and experiments for April 1991

. pursuant to the requirements of 10CFR50.59(b)..

Sincerely yours, 1 l

m ._ _

. J. a an 4 Genera anager -

Hope Creek Operations

% R:ld 4 Attachments ~

C ' Distribution pb[ k!iOC 34 b

i The Energy People f 7 I ( wwy, u w

INDEX NUMBER SECTION OF PAGES Average Daily Unit Power Level. . . . . . . . . . . 1 Operating Data Report . . . . . . . . . . . . . . . 2 Refueling Information . . . . . . . . . . . . . . . 1 Monthly Operating Summary . . . . . . . . . . . . . 1 Summary of Changes, Tests, and Experiments. . . . . 5

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 5.0-354 UNIT l{oce Creek DATE 5/13/91 CORPLETED BY ya Zabielski 1ELEPHONE (609) 339-3506 MONTH April 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 1922 17. 1056

2. 1086 18. 1066

3. 1078 19. 1063

4. 1070 20. 1041

5. 1060 21. 1083

6. 1000 22. 1069

7. 1008 23, 1051

8. 1052 24. 1045

9. 1044 25. 1069

10. 1057 26. 1067

11. 1951 27. 1041 12, 1HE5 28. 1048

13. 1046 29. 1053

14. 1064 30. 1046

-- 15 , 1068 31. lilA 16 . - 1055 1

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OPERATING DATA REPORT DOCKET No. 50-354 UNIT Hope _Ercek DATE 5/13/91 COMPLETED BY V. Zabielski TELEPHONE (609) 339-3506 OPERATING STATUS

1. Reporting Period ADril 1991 Gross Hours in Report Period 212

2. Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 1031 Design Electrical Rating (MWe-Net) 1067

3. Power Level to which restricted (if any) (MWe-Net) None

4. Reasons for restriction (if any)

This Yr To Month Date pumulative

5. No. of hours reactor was critical 719.0 1578.8 31,360.3

6. Reactor reserve shutdown hours 222 2x2 2x2

7. Hours generator on line 719.0 1497.7 30.790.8

8. Unit reserve shutdown hours 922 222 0.0

9. Gross thermal energy generated 2.366.890 4.663.622 97.206.030 (MWH)

=10. Gross electrical en0<gy 789.010 1.547.590 32.169,263 generated (MWH)

11. Not electrical energy generated 759.565 1.470.700 30.727.384 (MWH)

12. Reactor service factor 100.0 54.8 82.0

13. Reactor availability factor 100.0 11t8 82.0

14. Unit service factor 100.0 52.0 80.5

-15. Unit availability factor 100.0 1212 80,5

16. Unit capacity factor (using MDC) 102.5 49.5 7S,0

17. Unit capacity factor 99.0 47.9 75.3 (Using Design-MWe)

18. Unit forced outage rate 0.0 12.3 521 1 19. Shutdowns scheduled over-next 6 months (type, date, & duration):

! None

20. If shutdown at end of report period, estimated date of start-up:

N/A i

i OPERATIlfG DATA REPORT i

UNIT Sil0TbOWNS AND POWER REDUCTIONS ,

l DOCKET NO. 50-354 UNIT Rope Crg.c};

DATE .5/13/91 ,

COMPLETED BY V. Zabig.laki TELEPil0NE 16.09) 339-3506 MONTil April 1991 MET 110D OF S!!UTTING DOWN Tile TYPE REACTOR OR  ;

F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S=SCllEDULED (llOURS) (1) POWER (2) ACTION / COMMENTS T

NONE i

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T REFUELING INFORMATION la DOCKET No. 50-354 UNIT llope creek DATE 5/13/9:

COMPLETED BY _S. Hollingsworth 1 TELEPHONE

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(609) 339-1051 MONTH Anril 1991

1. Refueling information has changed from last month:

Yes No X

3. Scheduled dato for next refueling: 9/5/92

3. Scheduled date for restart following refueling: 11/3/92

4. A. Will Technical Specification changos or other license amendments be required?

Yes No X B. Has the reload fuel design boon reviewod by the Station Operating Review Committoo?

Yes No X If no, when is it scheduled? not currently scheduled .

5. Scheduled dato(s) for submitting proposed licensing action: HIA ,

6. Important licensing considerations associated with refueling:

- Amendment 34 to the Hopo Crook Toch Spoca allows the cycle specific operating limits to bo incorporated into the CORE OPERATING LIMITS REPORT; a submittal is therefore not required.

7. Number of Fuel Assemblies:

A. Incore  ?QA B. In Spont Fuel Storage (prior to refueling) .Rs C. In Spont Fuel Storago (after refueling) lig

8. Prosent licensed spent fuel storage capacity: 4006 Future spent fuel storage capacity: 1 ADS.

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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4 IIOPE CREEL ( GENERATING STATION MONTitLY OPERATING

SUMMARY

APRIL 1991 llopo Creek entered the month of April at approximately 100% power and operated for the entiro month without experiencing any shutdowns or any reportable power reductions. On April 30th, the unit completed its 59th day of continuous power operation.

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SUMMARY

OF CIIANGES, TESTS, AND EXPERIMENTS  :

FOR Tile Il0PE CREEK GENERATING STATION APRIL 1991 I

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The following Design Change Packages (DCP's) have been evaluated l to determines j

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 then any evaluated previously in the safety analysis '

report ma/ be created; or i

3. If the margin of safety as defJ,ned in the basis for any i technical specification is reduced.

The DCP's did not create a new safety hazard to the plant nor did

, they affeet the safe shutdown of the reactor. The DCP's did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unroviewed safety or environmental questions are involved, l

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, ace Description of Design chance Package I 4EC-3108 This DCP added two platforms at elevation 888 in I the Reactor Building. The platforms are supported off the Drywell wall and are hung from the elevation 99' 5" floor framing steel. The platforms will enhance personnel safety.

I 4HC-0171 This DCP added two permanent domineralizer systems, one for each of the Safety Auxiliaries Cooling System loops. The DCP will help to maintain low conductivity water for the Safety Auxiliaries Cooling System Domineralized Water.

4HC-0316 This DCP installed a Halon storage rack, bottles, and a piping, lose pipe It reel. supports, penetration also replaced nozzles seals,he in t Halon i Fire Suppression system. This DCP allows the cylinders to be permanently mounted in the Control Area. Computer Room and will improve fire-fighting capabilities by reducing the response time.

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4 The following proceduro revisions have boon ovaluated to ,

determino:

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 bo i increased; or i

2. If a possibility for an accident or malfunction of a differont type than any evaluated previously in the safoty analysis report may be created; or ,

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

The procedure revisions did not croato a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. The procedure revisions did not change the plant effluont releases and l did not alter the existing environmental impact. The Safety Evaluations datormined that no unroviewed safety or environmental questions are involved.

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Procedure Revision Egacription of Procedure RevisiDD ,

HC. oP-IS . EA-00 01 (Q) This proceduro revision provides a now Rev. 10 attachment to datormine if service water ,

pump flow is bypassing through the ,

discharge and strainer of the 'C' .Sorvico Water Pump. It also adds instructions to isolate 'A' Loop Servico Water Dilution Flow to the liypochlorination System prior to the test, ensuring that all flow is accounted for during the inservice test.

The revision adds stops to isolato the  !

Strainer Koop Fill during the insarvico  !

test and changes the flow referenco point and the required pressures for the pump.

These changes comply with the ASME code.

!!C. SA-AP. ZZ-0002 (Q) This procedure revision changes the Rev. 15 position titles of personnel in the operations Department (Nuclear Shift Technical Advisor to Shift Technical

. Advisor and Radwaste Senior Shift Support Supervisor to Senior Operations Support Suporvisor). It also changes tho reporting relationship of the Project Manager -

outages and-the Shift Support Supervisor.

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