ML20034F880

Monthly Operating Rept for Jan 1993 for Oyster Creek Nuclear Generating Station

ML20034F880
Person / Time
Site:	Oyster Creek
Issue date:	01/31/1993
From:	J. J. Barton, Krall J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-93-2052, NUDOCS 9303050135
Download: ML20034F880 (8)

Text

.

t GPU Nuclear Corporation 3 U duclear

en:r 8' Forked River, New Jersey 08731-0388 609 971-4000 t

Writer's D: rect D:al Nurnber:

t C321-93-2052 February 18, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555

Subject:

Dyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16. Appendix A, Section 6.9.1.C, 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 Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.

Sincerely,

%~

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'W Q_VicePresidentandDirector J.J. Ba on Oyster Creek JJB/BDEM: jc Attachment j

(MOR-RPT.JAN) i cc:

Administrator, Region 1 Senior NRC Resident inspector DysterCreekNRCPro$'ectManager 04005 9303050135 93021

{DR ADOCK 05000 19 g

ena GPU Nuclear Corporaton is a subsidiary cif General Pubhc Utsties Corporation

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I Honthly Operating Report.

i January 1993-

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Oyster Creek continued the 14th refueling outage during.' the month of -

January.

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HONTHLY OPERATING REPORT LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of January, 1993:

LER 92-014 - VOLUNTARY A hole in the Service Water System piping on the outlet of the Reactor Building Closed Cooling Water heat exchanger was discovered on December 9, 1992. The plant was shut down at the time, but it is not known how long the conditir, existed prior to discovery.

The hole was discovered by a technician working 1 the area who heard a sound like rushing air and reported it to the Control Room.

A Control Room supervisor cut away a piece of wetted insulation from the pipe and exposed a hole approximately four inches in diameter.

No water leaked from the pipe because the system discharge is at a vacuum. A patch was placed over the hole. The apparent cause of the occurrence is piping erosion due to failure of the pipe's internal coating. Additional piping sections were inspected and the failed section was replaced.

Service water piping will be added to an existing inspection program. This hole may have affected secondary containment, which is designed to minimize ground level release of radioactive materials. An evaluation is being performed to assess the effects of a radioactive release with this piping hole and a revision to this report will be submitted when the evaluation is complete.

LER 92-015 On December 31, 1992, at 2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br />, a partial Primary Containment isolation, Reactor Building Ventilation isolation, Secondary Containment isolation and Standby Gas Treatment System (SGTS) initiation occurred when a lifted, energized electrical lead was grounded. The plant was shutdown for a refueling outage at the time with the reactor core offloaded.

Contractor personnel were working inside a Control Room panel connecting wires for a plant modification when an energized wire contacted ground and blew c fuse which supplies power to containment isolation and SGTS initiation circuits.

Plant electricians were contacted to find the cause of the actuations, and they replaced the blown fuse.

The isolations were reset and SGTS operation terminated at 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br />. The cause of the event was personnel error.

The safety significance of the event is minimal.

Corrective action is not required because this was an isolated incident.

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Monthly Operating Report January, 1993 (Continued) i

)

LER 93-001 On January 1, 1993, at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> a lightning arrestor on an offsite power line failed, causing power perturbations in the plant electrical system.

A Standby Gas Treatment System (SGTS) initiation signal was generated by a high level trip of the Reactor Building Ventilation radiation monitor resulting from the power perturbations. The plant was shut down and defueled at the time and part of the electrical distribution system was out of service for maintenance. The offsite line's breaker was manually opened until repairs could be made to the lightning arrestor (1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br />). The Reactor Building i

Ventilation system was returned to operation and the SGTS was secured at 1140 hours0.0132 days <br />0.317 hours <br />0.00188 weeks <br />4.3377e-4 months <br />. The safety significance of the event is minimal because it represented l

only an unnecessary challenge to Secondary Containment isolation and SGTS initiation circuits.

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Oyster Creek Station #1 i

Docket No. 50-219

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REFUELING INFORMATION - JANUARY, 1993 l

j Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: Currently projected for October, 1994 l

t Scheduled date for restart following refueling currently projected for January,1995 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

N

(

i Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant I

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

=

(b) in the spent fuel storage _ pool 1870 j

=

(c) in dry storage 8

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

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

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Present Licensed capacity:

2600 i

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

I Full core discharge capacity to the spent f uel pool will be available through the 1

1996 refueling outage.

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8 AVERAGE DAILY POWER LEVEL

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Ii DOCKET #.

.50-219 f

UNIT.

. OYSTER CREEK #1 1

l REPORT DATE.

02-10-93 COMPILED BY JIM KRALL

.609-971-4115 TELEPHONE #.

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j MONTH:

JANUARY, 1993

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i OPERATING DATA REPORT 4

OPERATING STATUS i

1. DOCKET:

50-219

2. REPORTING PERIOD:

01/93

3. UTILITY CONTACT:

JIM KRALL (609)971-4115

4. LICENSED THERMAL POWER (MWt):

1930

5. NAMEPLATE RATING-(GROSS MWe):

687.5 x 0.8 = 550

6. DESIGN ELECTRICAL RATING (NET MWe):

650

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7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

632 f

8. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

610

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

i NONE

10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):

NONE 1

11. REASON FOR RESTRICTION, IF ANY:

NONE

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I MONT4 YEAR CUMULATIVE'

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12. REPORT PERIOD HOURS 744.0 744.0 202584.0 l

13. HOURS RX CRITICAL 0.0 0.0 131908.4

14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2'

15. HRS GENERATOR ON-LINE 0.0 0.0

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16. UT RESERVE SHTDWN HRS 0.0 0.0 1208.6.

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17. GROSS THERM ENERGY (MWH) 0 0

218468635

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18. GROSS ELEC ENERGY (MWH) 0 0

73396138

19. NET ELEC ENERGY (MWH)

-3392

-3392 70432124 1

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20. UT SERVICE FACTOR 0.0 0.0 63.5

21. UT AVAIL FACTOR 0.0 0.0 64.1

22. UT CAP FACTOR (MDC NET) 0.0 0.0 56.2 l

23. UT CAP FACTOR (DER NET) 0.0 0.0 53.5

24. UT FORCED OUTAGE RATE 0.0 0.0 11.0

25. FORCED OUTAGE HRS 0.0 0.0 15957.3

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

HONE l

27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:

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