ML20077F863

Monthly Operating Rept for May 1991 for Hope Creek Generation Station Unit 1

ML20077F863
Person / Time
Site:	Hope Creek
Issue date:	05/31/1991
From:	Hagan J, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9106200273
Download: ML20077F863 (12)

Text

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I.g pggg Public Service Electoc and Gas Compaay P.O. Box 236 Hancocks Bridg3, New Jersey 08038 Hope Creek Generating Station June 14, 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- j the--Hope Creek Technical Specifications, the operating statistics for May are being forwarded to you with the summary

-of changes, tests, and experiments for May 1991 pursuant to the requirements of-10CFR50.59(b).

i Sincerely yours, J

enefal anager -

Hop k Operations 4kRAR:ld Attachments C Distribution iC h4 The Energy People M i g

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4 INDEX NUMBER SECTIQH 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 4-4

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-354 UNIT H. ope Creek DATE 6/14/91 COMPLETED BY V. Zabielski TELEPHONE (609) 339-3506 MONTH May 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Not) (MWe-Net)

1. 1060 17. 1022*

2, 1070 18. 1021*

I 3. 1062 19. 1062

4. 1946 20. 1063

5. 1053 21. 1041

6. 1081 22. 1040

7. 121 23. 1941

8. 2 24. 1067

9. a 25. 221

10. 2 26. 1211

11. 2 27. 1074

12. 694 28, 1033

13. 1007 29. 1018

14. 1031 30. 1037

15. 1060 31. 1911

16. 1044

• Due to an error in recording the meter readings, the exact average daily power level for May 17 and 18 is unknown. The listed averages for those two days represent the average of the two-day total.

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OPERATING DATA REPORT DOCKET NO. 50-354 UNIT Hope Creek DATE 6/14/91 COMPLETED BY V. Zabielski TELEPHONE (609) 339-3506 OPERATING STATUS

1. Reporting Period May 1991 Gross Hours in Report Period 744

2. Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 1031 Design Electrical Rating (MWe-Net) 1057

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

4. Reasons for restriction (if any)

This Yr To Month Date Cumulative

5. No. of hours reactor was critical 664.0 2242.8 32.024.3

6. Reactor reserve shutdown hours 0.0 21Q 94p

7. Hours generator on line 646.8 2144.5 31.437.6

8. Unit reserve shutdown hours Az2 220 0.0

9. Gross thermal energy generated 14 108.415 6.772.038 99,314.446 (MWH)

-10. Gross electrical energy- 691.080 2.239.111 32.860.784 generated (MWH)

.11.= Net electrical energy generated 662.175 2.133.3L5 31.389.999 (MWH)

! 12. Reactor service factor 89.2 51.9 82 2 l

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13. Reactor availability factor 89.2 61 9 82,2

14. Unit service factor 86.9 59,2 80.7 l 15. Unit availability factor 86.9 59.2 80 2 I

16. Unit capacity factor (using MDC) 86.3 57.1 78.1

17. Unit capacity factor 83.4 55.2 75.5 (Using Design MWe)

18. Unit forced outage rate 13.1 12.5 f22

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

None

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

i N/A

4 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-354 UNIT Hone Creek DATE s/14/9:

COMPLETED BY V. Zab:.elski TELEPHONE (609) 339-3506 MONTH May 1991 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S= SCHEDULED (HOURS) (1) POWER (2) ACTION / COMMENTS 7 5/7 F 97.2 G 3 Scram on Low Reactor Water Level due to-Personnel Error During Surveillance (LER 354/91-008)

Summary

REFUELING INFORMATION DOCKET NO. 50-3Ei UNIT Hope Creek DATE 6/14/91 COMPLETED BY S. Hollincsworth TELEPHONE (609) 339-1051 MONTH May 1991 l

1. Refueling information has changed from last month:

Yes No X

2. Scheduled date for next refueling: 9/5/92

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

4. A. Will Technical Specification changes or other license l

amendments be required?

Yes No X l

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

If no, when is it scheduled? not currently scheduled I

5. Scheduled date(s) for submitting. proposed licensing action: HLA

6. Important licensing considerations associated with refueling:

- Amendment 34 to the Hope Creek Tech Specs allows the cycle specific operating limits to be incorporated into the CORE l

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

7. ' Number of Fuel Assemblies:

A. Incore- 764 B. In Spent Fuel Storage (prior to refueling) 496 C. In Spent Fuel Storage (after refueling) 760

8. Present licensed spent fuel storage capacity: 4006 l Future spent fuel storage capacity: 4006

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

licensed capacity:

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HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

MAY 1991 Hope Creek entered the month of May at approximately 100% power.

On May 7, the unit automatically shutdown after completing 65 days of continuous power operation. The automatic scram occurred due to low level in the reactor vessel caused by personnel error during the performance of a surveillance test. The unit was returned to service on May 12, ar.d operated for the remainder of the month without experiencing any other shutdowns or reportable power reductions. On May 31, the plant completed its 19th day of continuous power operation.

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MAY 1991 l

The following Design Change Packages (DCP's) 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 DCP's did not create a new safety hazard to the plant nor did they affect 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 unreviewed safer.y or environmental questions are involved.

DCE Rescriotion of Desian Chanae Packace 4EC-3012 This DCP routed a caustic discharge line form the Caustic Pump House to the Circulating Water Discharge Canal. It also modified an existing line and added heat tracing. These modifications will increase the system reliability.

4HC-0204/24 This DCP installed test switches on the outside of the Feedwater Control System Panel. The test switches will facilitate Technical Specification surveillances by providing an accessible location for the interruption of the reactor level signals.

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The following Temporary Modification Requests (TMR's) 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 possi.bility 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 defi..ed in the basis for any 1 technical specification is reduced. I i

The TMR's did not create a new safety hazard to the plant nor did they affect the-safe shutdown of the reactor. The TMR's did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no I unreviewed safety or environmental questions are involved. I l

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IMB Descrintion of Temoorary Modification Recuest 91-020 This TMR installed a jumper across the High Bearing 91-024 Oil Temperature Trip Switch in the 'A' Control Room Chiller. The jumper will disable the chiller's High Bearing 011 Temperature Trip until the defective parts can be replaced. The oil temperature will be monitored locally as a compensatory measure.91-021 This TMR installed electrical jumpers across the #2 Feedwater Heater High High Level Trip Switches.

These switches cause spurious high level trip signals during low power levels. The jumpers will be removed after the level signals stabilize.91-022 This TMR removed the overload heaters from the breakers for the Reactor Water Cleanup Discharge to Condenser Valve and the Reactor Water Cleanup Discharge to Equipment Drain Valve. Removing the overload heaters from the breakers will prevent the valves from inadvertently opening during an Appendix R fire.91-023 This TMR unpinned a sway strut hanger on the High Pressure Coolant Injection Steam Supply Line to prevent the strut from bending or breaking during the High Pressure Coolant Injection System Steam Line warmup.91-025 This TMP installed a jumper acrose a slot sensor to the High Motor Temperature Trip Module of tht

'C' Turbine Building Chiller. The jumper will permit the chiller to operate with a defective thermistor until a replacement part can be installed. The motor temperature will be monitored as a compensatory measure.91-027 This TMR lifted a lead and installed two jumpers to eliminate a nuisance alarm. A failed transmitter in the Main Turbine Sealing Steam System was causing a " Turbine Scaling Stear Trouble" alarm.

This TMR will eliminate the falca high/high signal.

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