ML20080A884

Monthly Operating Rept for Oct 1994 for Oyster Creek

ML20080A884
Person / Time
Site:	Oyster Creek
Issue date:	10/31/1994
From:	Edelman P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20080A882	List: ML20080A879 ML20080A884 ML20080A889
References
NUDOCS 9411220333
Download: ML20080A884 (6)

Text

I Monthly Operating Report October 1994 Oyster Creek continued the 15th refueling outage during the month of October.

9411220333 94111" PDR l

R ADOCK 05000219 PDR <

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MONTHLY OPERATING REPORT 1 1

LICENSEE EVENT REPORT i

The following Licensee Event Reports were submitted during the month of October,1994:

LER 94-016 On September 12, 1994, Local Leak Rate Testing (LLRT) results indicated that Main Steam isolation valve NSO4B exceeded the leak rate limit of 12.08 SCFH at 20 psig as specified in the plant Technical Specifications.

The leak rate was quantified as 36.91 SCFH at 35 psig. The LLRT program for the current outage has not been completed at this time. Any additional LLRT failures, and a complete evaluation of the prog- n results will be reported after the program has been completed this outage.

LER 94-017 On September 15, 1994, the reactor was in a cold shutdown condition during a refueling outage. While water flushing a reactor water level instrument reference leg line tap inside the reactor vessel, two reactor triple low water level sensors spuriously actuated causing an automatic reactor building closed cooling water system valve to isolate flow returning from the drywell at approximately 1034 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.93437e-4 months <br />.

This event was caused by a work packwe inadequacy. Prerequisites to disable the function of the instruments connected to the rei sence leg line were not communicated to the contractor perfonning the work.

This event was not safety significant since the isolation function of this valve is not required to be opemble during the present plant conditions.

The isolated valve was reopened and all instniments connected to the reference leg lines were isolated. Additional corrective actions will include communicating lessons learned from this event to appropriate personnel who have responsibility for work package preparation.

MONTIILY OPERATING REPORT LICENSEE EVENT REPORT (Continued)

LER 94-018 On September 24,1994 the reactor was defueled during a refueling outage. During perfonnance of the High Range Radiation Monitoring System calibration, the Channel I monitor function selector switch was inadvertently turned to the OFF position causing four automatic drywell torus nitrogen inerting exhaust isolation valves to close at approximately 1026 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.90393e-4 months <br />.

This event was caused by a fabrication deficiency. The monitor function selector switch knob does not have an indication on the side of the knob to show an accurate position reading.

This event was not safety significant since the isolation function of these valves are not required to be operable during present plant conditions.

The four isolated valves were reopened. Additional corrective action includes purchasing j monitor function selector switch knob with a position indicator.

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Oyster Creek Station #1 Docket No. 50-219 i

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l REFUELING INFORMATION - OCTOBER, 1994 }

l Name of Facility: Oyster Creek Station #1  !

Scheduled date for next refueling shutdown:

September, 1996 Scheduled date for restart following refueling: Currently projected for i November, 1996 -

Will refueling or resumption of operation thereafter require a Technical e Specification change or other license amendment?

Mo Important licensing considerations associated with refueling, e.g., new-or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

1. General Electric Fuel Assemblies - Fuel design and performance analysis methods have been approved by the NRC.

The number of fuel assemblies (a) in the core = 0 (b) in the spent fuel storage pool = 2600 (c) in dry storage = 32 The present licensed spent fuel pool storage capacity and the size of any 1 increase in licensed storage capacity that has been requested or is planned, in l number of fuel assemblies :

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Present Licensed Capacity: 2600 Planned Increase in Licensed Storage Capacity: 45 The actual fuel storage capacity of the spent fuel pool is 2645 assemblies. i 3

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Based on a reload of 172 bundles, full core discharge capacity to the spent fuel pool will be lost after the 1994 refueling outage.

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AVERAGE DAILY POWER LEVEL . -

NET MWe DOCKET #. . . . . . . . . . .50-219

• UNIT. . . . .

OYSTER CREEK #1 REPORT DATE. . . . . . . . 11-03-94 COMPILED BY . . . . . . PAUL G. EDELMANN TELEPHONE # . . . . . . .609-971-4097 MONTH: OCTOBER, 1994 E

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[fd DAY j M' I

1. 0 16. 0

2. 0 17. 0

3. 0 18. O

4. 0 I

19. O l

5. 0 20. 0

6. 0 21. 0

7. 0 22. 0

9. 0 23. 0

9. 0 24. 0

10. 0 25. 0

11. 0 26. 0

12. 0 27 0

13. 0 28. 0

14. 0 29. 0

15. 0 30. 0

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, OPERATING DATA REPORT .

OPERATING STATUS l' . DOCKET: 50-219

2. REPORTING PERIOD: 10/94 3'- UTILITY CONTACT: PAUL G. EDELMANN (609-971-4097)

4. LICENSED THERMAL POWER (MWC): 1930

5. NAMEPLATE RATING (GROSS MWe) . 687.5 x 0.8 = 550

6. DESIGN ELECTRICAL RATING (NET MWe)- 650 7 MAXIMUM DEPENDABLE CAPACITY (GROSS MWe). 632 1 8.

MAXIMUM DEPENDABLE CAPACITY (NET MWe) 610  !

9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:

j NONE

10. POWER 1JVEL TO WHICH RESTRICTED, IF ANY (NET MWe) .

NONE

11. REASON FOR RESTRICTION, IF ANY:

NONE MONTH XEM CUMULATIVE

12. REPORT PERIOD HOURS 745.0 7296.0 217896.0

13. HOURS RX CRITICAL 0.0 5776.0 145375.0

14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 0.0 5717.4 141919.1 16, UT RESERVE SHTDWN HRS 0.0 0.0 0.0

17. GROSS THERM ENERGY (MWM) 0 10785252 243898629

13. GROSS ELEC ENERGY (M*#rt ) 0 3571502 B1815816

19. NET ELEC ENERGY (MWH) -2372 3430807 78470521

20. UT SERVICE FACTOR 0.0 78.4 65.1 21, UT AVAIL FACTOR 0.0 78.4 65.1

22. tJr CAP FACTOR (MDC NET) 0.0 77.1 58.8

23. LT CAP FACTOR (DER NET) 0.0 72.3 55.4

24. UT FCRCED OUTAGE RATE 0.0 5.5 10.3

25. FORCED OUTAGE HRS 0.0 332.5 16289.8

26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION) <

NONE 2' IF CUDREN*LY SHL"rDOWN, ESTIMATED STARTUP DATE: 28 NOV 94 l

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