ML20115F856

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

ML20115F856
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1996
From:	Edelmann P, Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-96-2219, NUDOCS 9607180127
Download: ML20115F856 (7)

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3 GPU Nuclear Corporation Uhlhhf Post Office Box 388 Route 9 South Forked River,New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

July 11, 1996 6730-96-2219 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report - June,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

Michael B. Roche Vice President & Director i

Oyster Creek MBR/BDeM/gl Enclosures cc:

Administrator, Region I (2 copies)

NRC Project Manager r

NRC Resident Inspector g 9'd j 9607180127 960630 PDR ADOCK 05000219 R

PDR GPU Nuclear Corporation is a subsidiary of General Public Utihties Corporation

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SUMMARY

JUNE,1996 Oyster Creek operated the entire month of June at full load except for a few minor power reductions.

The minor power reductions included placing two Reactor Water Clean-Up pumps in service, Control Rod Drive maintenance, Rods for Flow swaps, and Core Spray System testing.

The plant generated 440,708 MWh net electric which was 98.9% ofits rated maximum dependable capacity (MDC) for the month.

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LICENSEE EVENT REPORTS SUBMITTED DURING JUNE 1996 96-005 On April 30,1996, with a reactor startup in progress, a reactor scram xcurred at 0256 hours0.00296 days <br />0.0711 hours <br />4.232804e-4 weeks <br />9.7408e-5 months <br />. When reactor level decreased to 139 inches above Top of Active Fuel (TAF), a Low Level reactor scram occurred as designed. Following the scram, water level further decreased to approximately 120 inches TAF before being restored to normal. The cause of the event was a failure on the part of the operator to properly control reactor water level, aggressively take action to restore level, and use the most conservative reactor water level indicator. A contributory cause was ineffective supervisory oversight in that two SRO licensed supervisors did not take positive action to halt startup activities until normal level control could be re-established.

The safety significance of this event was minimal. Adequate core cooling was maintained.

Immediate corrective action was taken to recover water level and place the reactor in a shutdown condition. A discussion of the event was issued to the operators. Guidance was issued to the operators on reactor water level control, and use of the most conservative level indicator during a reactor startup.

Additional long term corrective action will be taken to evaluate the transition point for feedwater control during a reactor startup.

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AVERAGE DAILY POWER LEVEL NET MWe DOCKET #............ 50 219 UNIT............... Dyster Creek #1 REPORT DATE.......... 71319 6 COMPILED BY........... Paul G. Edelmann TELEPHONE #........... (609) 971 4097 Month: June,1996 DAY MW DAY MW 1

619 16 607 2

622 17 608 3

625 18 606 4

628 19 610 5

621 20 613 6

820 21 612 7

615 22 613 8

612 23 611 9

607 24 614 10 610 25 611 11 606 26 601 12 605 27 613 13 606 28 605 14 611 29 605 15 611 30 618

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OPERATING DATA REPORT OPERATING STATUS

1. Docket:

50-219

2. Reporting Period:

June 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 level to Which Restricted, If Any (Net MWe):

None

11. Reason For Restriction, if Any:

None Mon _tli Year Cumulative

12. Report Period Hours 720.0 4367.0 232487.0

13. Hours RX Critical 720.0 4231.6 158564.5

14. RX Reserve Shutdown Hours 0.0 0.0 918.2

15. Hours Generator On-Line 720.0 4175.6 154986.3

16. UT Reserve Shutdown Hours 0.0 0.0 0.0

17. Gross Thermal Energy (MWH) 1384697 7814235 268333728

18. Gross Electric Energy (MWH 457641 2643647 90061222

19. Net Electric Energy (MWH 440708 2546940 86416105

20. UT Service Factor 100.0 95.6 66.7

21. UT Available Factor 100.0 95.6 66.7

22. UT Capacity Factor (MDC Net) 98.9 94.2 60.6

23. UT Capacity Factor (DER Net) 94.2 89.7 57.2

24. UT Forced Outage Rate 0.0 4.4 9.7

25. Forced Outage Hours 0.0 191.4 16729.6

26. Shutdowns Scheduled Over Next 6 Months (Type, Date, Duration) 16R Outage, September 7,1996; 45 to 55 Days

27. If Currently Shutdown, Estimated Startup Date:

N/A

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Oyster Creek Station #1 i

Docket No. 50-219 Refueline Information - June.1996 l

Name of Facility:

Oyster Creek Station #1 l

1 Scheduled date for nem efueling shutdown:

September,1996 l

I Scheduled date for restart following refueling:

Currently projected for November,1996 l

. Will refueling or resumption of operation thereafter require a Technical Specification change or other l

license amendment?

No l

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Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, i

unreviewed design or performance analysis methods, significant changes in fuel design, new operating i

procedures-t

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

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2236 (b) in the spent fuel storage pool

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8 (c) in the new fuel storage vault

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l The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity i

that has been requested or is planned, in number of fuel assemblies:

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

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

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i-p UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-219 UNIT NAME:

Ovster Creek DATE:

Julv 3.

1996 COMPLT*D BY:

David M.

Eaan TELEPHONE:

971-4818 I

REPORT MONTH:

June 1996 i

TYPE METHODS CORRECTIVE No.

DATE F:

Forced DURATION REASON (1)

SHUTTING DOWN ACTIONS / COMMENTS i

S: Scheduled (hours)

THE REACTOR OR REDUCING POWER l

(2)

There were no shutdowns or significant

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power reductions during this i

reporting period.

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SUMMARY

p (1) REASON (2) METHOD.

a.

Equipment Failure (Explain) e.

Operator Training & Lic Exam 1.

Manual i

b.

Maintenance or Test f.

Administrative 2.

Manual Scram

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c.

Re fueling g.

Operational Error (Explain) 3.

Automatic Scran f

d.

Regulatory Restriction h.

Other (Exp*ain) 4.

Other (Explain) i i

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