ML20005G807

Monthly Operating Rept for Dec 1989 for Oyster Creek Nuclear Generating Station

ML20005G807
Person / Time
Site:	Oyster Creek
Issue date:	12/31/1989
From:	Fitzpatrick E, Yeager J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9001230117
Download: ML20005G807 (6)

Text

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.m GPU Nuclear Corporet6on NUCIMr i

Post Office Box 388

)

Route 9 South Forked River, New Jersey 087310388 609 971-4000 i

Writer's Direct Dial Number:

f January 15, 1990 U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C.

20555

Subject:

Oyster 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 l

Oyster Creek Nuclear Generating Station.

If you should have any questions, please contact Kathy Barnes, Oyster Creek Licensing at (609) 971-4390.

1 Very truly yours, E. E. Fitz trick Vice President and Director Oyster Creek i

EEF KF0 dmd (0841A)

Enclosures cc:

Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 475'Allendale Avenue King of Prussia, PA 19406

-Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission-Washington, DC 20555 NRC Resident Inspector i

Oyster Creek Nuclear Generating Station a

I 9001230117 glggy l

PDR ADOCK 00000219 R

PDC

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GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation

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MONTHLY OPERATING REPORT - DECEMBER 1989 4

At the beginning of the report period, oyster Creek was operating at a gross generator load of approximately 650 MWe.

on December 5, plant load was reduced to approximately 460 MWe to remove a circulating water pump from service to facilitate helium leak testing of a main condenser due to a significant salt leak. The condender half was isolated and the pump was returned to service, power accension commenced on December 6 and full load was achieved on December 7.

on December 7,

a plant shutdown commenced to satisfy regulatory concerns regarding a transient low vacuum condition in one section of a main condenser.

Operations management determined on the day of the transient and an NRC augmented inspection team subsequently determined that actions taken by operators during the transient were proper.

Tests conducted while the plant was shutdown verified that the reactor protection system would have functioned as designed.

Plant restart commenced on December 14.

Low intake water level conditions caused by westerly winds and unusual tide conditions delayed returning the plant to full power until December 19.

Maximum generator load was maintained for the balance of the report period except for brief power reductions to support turbine valve testing and to facilitate return of the cleanup system to service.

b

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• OPERATING DATA REPORT OPERATING STATUS i

l i

1 1.

DOCKET:

50-219 i

l 2.

REPORTING PERIOD:

12/89 3.

UTILITY CONTACT:

JEFF YEAGER 609-971-4585 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):

642 8.

MAXIMUM DEPENDABLE CAPACITY (NET MWe):

620 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 ggjiIg yl&B CUMULATIVE 12.

REPORT PERIOD HRS 744.0 8760.0 175536.0 13.

POURS RX CRITICAL 575.4 5015.2 111260.6 l

14.

RX RESERVE SHTDWN HRS 0.0 0.0 918.2 15.

HRS GENERATOR ON-LINE 551.3 4688.3 108231.8 l

16.

UT RESERVE SHTDWN HRS 0.0 0.0 1208.6 17.

GROSS THERM ENER (MWH) 995000 7752170 181273059

18. GROSS ELEC ENER (MWH) 334470 2518556 61122740

19. NET ELEC ENER (MWH) 320830 2395110 58654978 20.

UT SERVICE FACTOR 74.1 53.5 61.7 21.

UT AVAIL FACTOR 74.1 53.5 62.3 22.

UT CAP FACTOR (MDC NET) 69.6 44.1 53.9-

23..UT CAP FACTOR (DER NET) 66.3 42.1 51.4 24.

UT FORCED OUTAGE RATE 25.9 16.1 11.7 25.

FORCED OUTAGE HRS 192.7 899.4 14410.1 26.

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

None 27.

IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: N/A 1619B/9

' a AVERAGE DAILY POWER LEVEL NET MWe DOCKET #.

.50219 UNIT.

. OYSTER CREEK #1 REPORT DATE.

. JANUARY 4, 1990 COMPILED BY.

.'.JEFF YEAGER TELEPHONE #.

.609-971-4585 MONTH-DECEMBER, 1989 Ehl E

P.h1 E

1.

630 17.

430 2.

631 18.

449 3.

631 19.

583 4.

632 20.

631 5.

542 21.

631 6.

502 22.

630 7.

456 23.

631 8.

0 24.

631 9.

0 25.

632 10.

0 26.

631 11.

0 27.

630 12.

0 28, 628-13.

0 29.

631 l

14.

0 30.

630 15.

25 31.

631 16.

331 1619B/10

o 1

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

REFUELING 7NFORMATION - DECEMBER, 1989 Name of Facility:

Oyster Creek Station #1 i

Scheduled data for next refueling shutdown: January 11, 1991 pending necessary state approval.

scheduled date for restart following refueling: May 19, 1991 l

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

Yes Scheduled date(s) for submitting proposed licensing action and supporting information:

July 15, 1990 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 proceduree i

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

l

2. Exxon Fuel Assemblies - no major changes have been made nor are there any anticipated.

l The number of fuel assemblies (a) in the core 560

=

(b) in the s, pent fuel storage pool 1595

=

(c) in dry storage 37

=

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: 2600 The projected date of the last refueling that can be discharged to the spent fuel poc1 assuming the present licensed capacity:

Rsracking of the fuel pool is in progress.

Nine (9) out of ten (10) racks have been installed to date.

When reracking is completed, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.

1619B l

o UNIT SHUTDONNS AND POWER REDUCTIONS DOCKET NO.

_.50-219 UNIT NADE Ovster Creek DATE January. 1990 i

COIN %ETED BY R. Baran TELEPHOOOE 971-4640 REPORT NOttTE December, 1989 TYPE NETHOD OF SEUTTING F: Forced DURATION DONN THE REACTOR OR NO.

DATE St Scheduled (Bours)

REASON (1)

REDUCING PONER (2)

CORRECTIVE ACTIONS /COOWNDrTS 89 12/5/89 F

37 B

1 A power reduction to approximately 490NNe was made to remove a circulating water pump from service to facilitate helium leak testing of a main condenser due to a salt leak.

90 12/7/89 F

192.7 B

1 A reactor shutdown was made to facilitate testing / calibration of RSCS switches and vacuum trip bellows assemblies as a result of a condenser

• B* vacuum transient.

Summary :

(1) REASON NETHOD a.

Equipment Failure (Explain) e.

Operator Training & License Exam 1.

Manual b.

Maintenance or Test f.

Administrative 2.

Manual Scram c.

Refueling g.

Operational Error (Explain) 3.

Automatic Scram d.

Regulatory Restriction h.

Other (Explain) 4.

Other (Explain)

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