ML20134P615

Monthly Operating Rept for Jan 1997 for Oyster Creek Nuclear Generating Station

ML20134P615
Person / Time
Site:	Oyster Creek
Issue date:	01/31/1997
From:	Egan D, Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-97-2048, NUDOCS 9702260047
Download: ML20134P615 (6)

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GPU Nuclear, Inc.

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U.S. Route 79 South NUCLEAR Post Office Box 388 Forked River, NJ 08731-0388 Tel 609-9714000 February 12, 1997 6730-97-2048 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 - January,1997 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, l

5136FA Michael B. Roche Vice President & Director Oyster Creek i

MBR/BDeM/gl Enclosures I

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Administrator, Region I (2 copies)

I NRC Project Manager fpb J

NRC Resident Inspector 9702260047 970131 PDR ADOCK 05000219i R

PDR

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SUMMARY

JANUARY,1997 i

The plant operated at full load until January 24,1997 when power was reduced to perform quarterly MSIV testing. The plant returned to full power on January 26, 1997 following successful test completion, and remained at full power for the remainder of the month. During the month, the plant generated 470,346 MWh net electric which was 102.1% ofits MDC rated capacity.

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i MONTHLY OPERATING REPORT L

Licensee Event Reports - Januarv.1997 k-t LER 96-014 was filed January 8.1997 4

. On November 13,1996, it was discovered that mounting bolts were missing from a seismic restraint frame around

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. Motor Control Center (MCC) DC-2. The MCC was declared inoperable and a Technical Specification LCO was l

- entered. The four missing bolts were reinstalled and the MCC subsequently declared operable.

This condition was caused by personnel error. The seismic restraint was disassembled to support recent l

moddication work. A final MCC walkdown at the completion of the work overlooked the bolts not being installed.

The safety significance of this occurrence is minimal since the equipment powered by this MCC is not relied upon j

to prevent or mitigate the consequences of an accident.

Required Reading will be issued and job orders provided with speedic instructions to prevent recurrence i

LER %-015 was filed January 20.1997 1

On December 20,1996, during a review of a vendor service letter, it was identified that the thennal overloads for the starters for the Reactor Water Clean Up (RWCU) Isolation Valves were not sized for a revised Reactor Building environment following a High Energy Line Break (HELB) from the RWCU System. This condition is considered reportable under 10 CFR 50.73(a)(2)(ii). The root cause of this deficiency is that previous HELB l

analyses were performed without using the most conservative assumptions.

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The safety significance of this condition has been determired to be minimal. The reactor is normally operated at 100% power. Above approximately 88% power, a reactor scram is icceived with any break size larger than approximately 50% of the cross sectional area of the pipe. Below 50% break size, the analysis is bounded (both

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temperature profile and offsite release) by existing analyses. Immediate corrective actions were taken to provide Q

. the opemtors with guidance on addressing the potential line break. The thermal overloads were bypassed to m aue the ability to isolate the system. A re-analysis for other potentially affected Safety Related equipment was coarmh;cd to ensure continued operability for required systems. Modifications to provide an automatic RWCU isolation on a line break will be evaluated for possible installation.

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l OPERATING DATA REPORT l

OPERATING STATUS I

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1. ' Docket:

50-219

2. Reporting Period:

January,1997 3.

Utility Contact John D. Dougher (609)-971-2130

4. Licensed Thermal Power (MWt):

1930

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5. Nameplate Rating (Gross MWe):

687.5 x 0.8 = 550

6. Design Electrical Rating (Net MWe) 650 i

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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 l

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

None l

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11. Reason For Restriction, If Any:

None Month Year Cumulative

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12. Report Period Hours 744.0 744.0 237648.0 t

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13. Hours RX Critical 744.0 744.0 162332.8

14. RX Reserve Shutdown Hours 0.0 0.0 918.2 i

15. Hours Generator On-Line 744.0 744.0 158661.8 i

16. UT Reserve Shutdown Hours 0.0 0.0 0.0

17. Gross Thermal Energy (MWH) 1415602 1415602 27532 % 82

18. Gross Electric Energy (MWH) 487500 487500 92416767

19. Net Electric Energy (MWH) 470349 470349 88678915

20. UT Service Factor 100.0 100.0 66.8 l

21. UT Available Factor 100.0 100.0 66.8

22. UT Capacity Factor (MDC Net) 102.1 102.1 60.9

23. UT Capacity Factor (DER Net) 97.3 97.3 57.4

24. UT Forced Outage Rate 0.0 0.0 9.7

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25. Forced Outage Hours 0.0 0.0 17137.4

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

27. Currently Shutdown, Estimated Startup Date:

N/A

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Oyster Creek Station #1

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Docket No. 50-219 REFUELING INFORMATION - JANUARY.1997 Name of Facility:

Oyster Creek Station #1 Scheduled date for refueling shutdown:

September 1998 i

Scheduled date for restart following refueling:

October 1998 Will refueling or resumption of operation thereafter require No a Technical Specification change or other license amendment?

j 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 560

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(b) in the spent fuel storage pool 2236

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(c) in 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:

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 was lost aller the 1996 refueling outage.

DOCKET NO:

50-219 UNIT NAME:

Ovster Creek DATE:

Febniary 6.1997 COMPLT'D BY:

David M. Enan TELEPHONE:

609/971-4818 REPORT MONTH:

January 1997 TYPE METIIOD OF CORRECrlVE ACTIONS / COMMENTS No.

DATE F: Forced DURATION REASON (1)

SilUTTING DOWN S: Scheduled (hours)

TIIE REACTOR OR REDUCING POWER (2) 1 970124 S

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I Power was manually reduced to perform quarterly MSIV testing.

StJMMARY.

(1) REASON (2)MlilljQQ n Eq.npment Fulure (Explun)

e. Operator Trauung A Lic Exam I Manual h MaintqunceorTest f Admuustrauve

2. ManualScram

c. Refuelag g OperauonalError(Explam)

3. Automatic Scram d Regulatosy Restnctacn h Other(Explam)

4. Other(Explam) o 4