ML20132D101

Monthly Operating Rept for Nov 1996 for Oyster Creek Nuclear Generating Station

ML20132D101
Person / Time
Site:	Oyster Creek
Issue date:	11/30/1996
From:	Edelmann P, Egan D, Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-96-2369, NUDOCS 9612190185
Download: ML20132D101 (8)

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GPU Nuclear, Inc.

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U.S. Route #9 South NUCLEAR Post Offnce Box 388 Forked River, NJ 087310388 Te! 609-9714000 t

December 12, 1996

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6730-96-2369 U. S. Nuclear Regulatory Commission i

Attention: Document Control Desk Washington, DC 20555 i

Dear Sir:

SUBECT:

Oyster Creek Nuclear Generating Station Docket Nc. 50-219 Monthly Operating Report - Nvember,1996 In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1, enclosed are two (2) copies of the Monthly Operating Data (Gray Book information) for the Oyster Creek Nuclear Generating Station.

If you should have any questions, please contact Ms. Brenda DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.

Very truly yours, h'

0 ec Michael B. Roche t '

Vice President & Director d

Oyster Creek

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MBR/BDeM/gl Enclosures cc:

Administrator, Region I (2 copies)

NRC Project Manager NRC Resident Inspector 9612190185 961130 PDR ADOCK 05000219 R

PDR

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SUMMARY

November,1996 Oyster Creek was off-line at the begining of November The plant was placed on-line at 0927 on l

11/7/96 and reached full load at 1000 on 11/8/96. The plant remained at full load for the remainder of the month.

The plant generated 353,051 net MWH during the month and achieved an MDC net capacity factor of 79.2%.

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MONTHLY OPERATING REPORT Licensee Event Reports - November,1996 LER 96-008. filed November 25.1996:

On October 25,1996 at approximately 1159 hours0.0134 days <br />0.322 hours <br />0.00192 weeks <br />4.409995e-4 months <br /> a manual scram of the reactor was initiated in accordance with plant procedures due to a confirmed Main Generator Runback. Plant response to the generator mnback and manual scram was nonnal. All control rods inserted fully, and plant response ms as designed. Initial troubleshooting did not identify the initiating component.

However, subsequent monitoring identified an invalid temperature switch actuation, which were then disconnected pending funher analysis. Corrective actions include continued fault analysis on the existing temperature sensing switches. New temperature sensing devices will be evaluated and tested prior to returning the temperature portion of the main generator runback circuit to service.

LER 96-009. filed November 25.1996:

On October 27,1996 at 2358 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.97219e-4 months <br />, power to the 4160 VAC ID bus was lost due to a ground fault on the cable between Diesel Generator 2 and the ID bus. The plant was in a cold shutdown condition for a maintenance outage prior to this event.

The loss of the bus led to: 1) a trip of Reactor Protection System Channel 2; and 2) a full reactor scram signal and main steam line isolation, which isolated the reactor vent path being used, as designed.

Immediate actions were taken to restore the actuated systems, and reestablish the reactor vent path. Additional corrective actions were taken to replace the faulted cable and test the other diesel cables. Long term corrective actions include sending the failed cable to an outside testing laboratory for fault analysis LER 96-010. filed November 26.1996:

On October 16,1996, while performing a routine refueling outage surveillance on the Appendix R Remote Shutdown Panel (RSP) during the 16R Refueling Outage, one valve of the Isolation Condenser System did not operate as expected. This valve is designed to achieve an open position when an RSP relay is activated. The apparent cause of the occurrence was diny contacts on the control relay for this valve in the RSP. The contacts on the affected relay were cleaned and the valve circuit was retested satisfactorily. The safety significance of this occurrence is considered minimal because other systems were available to remove decay heat from the reactor and keep the core covered during en Appendix R fire in the Control Room. Engineering is evaluating the problem with the contacts on the relays used in the Remote Shutdown System to determine the appropriate action to take to prevent recurrence.

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l LER 96-011. filed November 26.1996

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On October 26,1996, a pressure drop test indicated primary containment leakage was above the i

Technical Specification limit. A Torus to Drywell vacuum breaker valve cover was found to be

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leaking. The valve cover was repaired and gross containment leakage was calculated to be below

- technical specification allowable leakage. Containment integity was required for a five day period j

prior to discovery.

3 The cause of this event was determined to be less than adequate self-checking which resulted in failure to correctly reassemble V-26-005 valve cover during the 16R outage. Procedure changes will require emphasis on self-checking to ensure that the cover plate is level during and after the torquing sequence. An evaluation ofthe methodology used in performing Local Leak Rate Testing (LLRT) of the torus /drywell vacuum breakers will be done.

i Additionally, this specific human perfomiance error, as well as others, will be discussed at weekly

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craft / management interface meetings now in progress i

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AVERAGE DAILY POWER LEVEL NET MWe i

DOC KET #.............

50-219 UNIT................

Oyster Creek #1 REPORT DATE..........

12/2/96 COMPILED BY...........

Paul G. Edelmann TELEPHONE #...........

(609) 971-4097 Month: November,1996 t

DAY MW DAY MW 1

0 16 639 2

0 17 639 4

3 0

18 640 4

0 19 638 5

0 20 638 6

0 21 640 7

134 22 640 8

580 23 641 9

630 24 639 10 633 25 641 11 634 26 640 12 637 27 639 13 637 28 641 14 636 29 641 15 638 30 641

_.m Oyster Creek Station #1 4

Docket No. 50-219 i

Refueling Information - November.1996 Name of Facility:

Oyster Creek Station #1 i,

't Scheduled date for next refueling shutdown:

September 1998 Scheduled date for restart following refueling:

October 1998 i

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

No 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 i

procedures:

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

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The Number of fuel assemblies:

(a) in the core 560

=

(b) in the spent fuel storage pool 2236

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(c) in the new fuel storage vault 8

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The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

i Present Licensed Capacity: 2645 The projected date of the last refueling that can he discharged to the spent fuel pool assuming the present licensed capacity:

Full core discharge capacity to the spent fuel pool was lost after the 1996 refueling outage.

' OPERATING DATA REPORT OPERATING STATUS

1. Docket:

50-219

2. Reporting Period:

November,1996 3.

Utility Contact Paul G. Edelmann (609)-971-4097

4. Licensed Thermal Power (MWt):

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):

641

8. Maximum Dependable Capacity (Net MWe):

619

9. If Changes Occur Above Since Last Report, Give Reasons:

None

10. Power 1.evel to Which Restricted, If Any (Net MWe):

None

11. Reason For Restriction, If Any:

None Month Year Cumulative

12. Report Period Hours 720.0 8040.0 236160.0

13. Hours RX Critical 595.1 6511.9 160844.8

14. RX Reserve Shutdown Hours 0.0 0.0 918.2 I

15. Hours Generator On-Line 566.6 6363.1 157173.8

16. UT Reserve Shutdown Hours 0.0 0.0 0.0

17. Gross Thermal Energy (MWH) 1075438 11960758 272480251

18. Gross Electric Energy (MWH) 367432 4017711 91435286

19. Net Electric Energy (MWH)

M3051 3862906 87732071

20. UT Service Factor io./

79.I 66.6

21. UT Available Factor 78.7 79.1 66.6

22. UT Capacity Factor (MDC Net) 79.2 77.6 60.6

23. UT Capacity Factor (DER Net) 75.4 73.9 57.2

24. UT Forced Outage Rate 21.3 8.6 9.8

25. Forced Outage Hours 153.5 599.2 17137.4

26. Shutdowns Scheduled Over Next 6 Months (Type, Date, Duration) None

27. Currently Shutdown, Estimated Startup Date:

N/A j

3 UNIT SHUTDOWNS AND POWER REDUCTIONS

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DOCKET NO: 50-119 UNIT NAME: Ovster Creek DATE:

December 5.19%

COMPLTD BY: David M. Ecan TELEPHONE: 609/971-4818 REPORT MONTII: November 1996 TYPE METHOD OF SHUTTING CORRECTIVE ACTIONS / COMMENTS No.

DATE F: Forred DURATION REASON DOWN THE REACTOR OR S: Scheduled (hours)

(1)

REDUCING POWER (2) 7 10/25/96 F

153.4 a

2 Manual Scram at 1200 on 10/25/% in response to a Generator Runback. Plant on-line on 11/7/96 at 0927.

SUMMARY

(1) REASON (2) METHOD

a. Equipment Failure (Explain)

e. Operator Training & Lic Exam

1. Manual L

b. Maintenance or Test

f. Administrative

2. Manual Scram

c. Refueling

g. OperationalError(Explain)

3. Automatic Scram r

d. Regelatory Restriction

h. Other(Explain)

4. Other(Explain)

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