ML20207G970

Monthly Operating Rept for Jul 1988 for Oyster Creek.W/

ML20207G970
Person / Time
Site:	Oyster Creek
Issue date:	07/31/1988
From:	Baran R, Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
To:	NRC
References
NUDOCS 8808240304
Download: ML20207G970 (7)

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. MONTHLY OPERATING REPORT - JULY 1988 At' the beginning of the report ' period, Oyster reek was operating at. full capacity with an average gross generator load. of 640 We.

Minor power reductions were made on July 5.for turbine valve testing and on ' July 6' to ' return the cleanup system to service. ~ The cleanup system,

was 7 previously. removed from service ~ to reduce heat transfer load : on Reactor Building Closed Cooling Water while performing work on a service water pump.

On July 9,

power was reduced to approximately 40% full power.to accommodate core flux shaping and Main Steam Isolation Valve (MSIV) full closure testing.

During testing MSIV NS03A failed to close.

MSIV-NS04A was closed and disabled until the operability of NS03A could be established.

After several attempts, NS03A appeared to close and open within 'the normally expected stroke times.

An evaluation of NS03A's performance indicated the valve was operating nomally.

After e.ttempting to open both MSIVs, no steam flow was indicated in the "N' steam line.

A si utdewn of the reactor was initiated to determine the cause of no steam flaw w the 'A' Steam Line Header and make appropriate repairs. The generator was taken off-line at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> and the reactor was manually scrammed from about 10% power at -1956 hours.

The plant was in a cold shutdown condition at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on July 10 and remained so through the end of the report period.

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MONTHLY OPERATING REPORT JULY 1988 i

The following Licensee Event Report was submitted during tne month of July 1988 LER 88-011 - CONTAINMENT SPRAY INAPPROPRIATELY RETURNED TO SERVICE 0UE TO IMPROPERLY PERFORMED SURVEILLANCE TEST A Containment Spray System (EIIS Code BE) System I Surveillance Test was.

- i performed on June 19, 1988, following system maintenance that began on June 14, 1988.

The surveillance test was performed incorrectly and on June 22, 1988 it was determined that System I had been inappropriately placed in i

service on June 19, 1988.

During this period, the reactor was in operation in violation of Technical Specification 3.4.C.3 An engineering evaluation performed later that c3y concluded the system was, in fact, operable since June 19,1988. The cause was a poorly human factored labelling design for the delta P instrumentation.

This unnecessarily challenged the operator resulting in the instrument ifne-up error. Actions taken to prevent recurrence included procedure revision and clear labelling of system components.

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AVERAGE DAILY POWER LEVEL NET MWe' i

DOCKET f.........

50219-UNIT........... 0YSTER CREEK #1

~ REPORT DATE.......AUCUST 2,'

1988 COMPILED BY..

. JOHN H. S EDAR. JR. '

TELEPHONE #......

609-971-4698 MONTH JULY, 1988 DAY MW DAY MW 1.

622 17 0

2.

624 18 0

1 3.

622 19 0

4 4.

613 20 0

5.

611 21 0

6.

607 22 0

7.

609 23-0 8.

602 24 0

9.

163 25 0

1 10.

0 26 0

l 11.

0 27 0

12.

0 28 0

13.

0 29 0

14.

0 30 0

15.

0 31 0

16.

0 i

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'a Oyster Creek Station #1 Docket No. 50-219 -

REFUELING INFORMATION - JULY, 1988 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: October 15, 1988 Scheduled date for restart following refueling: January 9, 1989 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:

Technical Specification Change Request No.166 was submitted March 30, 1988.

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

new or different fuel design or supplier, unreviewed design or performance analysis methode, 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.

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

The number of fuel assemblies (a) in the core i.

560

=

(b) in the spent fuel storage pool = 1$41 (c) in dry storage 91

=

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

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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 pool assuming the present licensed capacity:

Reracking 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.

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OPERATING DATA REPORT OPERATING STATUS 1.

DOCKET:

50-219 2.

REPORTING PERIOD: JULY, 1983 3.

UTILITY CONTACT:

JOHN H. SEDAR, JR.

609-971-4698 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 CAPACITi (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 MONTH YEAR CUMULATIVE 12.

REPORT PERIOD RRS 744.0 5111.0 163104.0

13. HOURS RX CRITICAL 211.9 4578.9 105035.3 14.

RX RESERVE SHTDWN KRS 0.0 0.0 918.2 15.

HRS GENERATOR ON-LINE 111.7 4578.7 102371.6 16.

UT RESERVE SHTDWN HRS 0.0 0.0 1208.6 17.

GROSS THERM ENER (MWH) 383500 8683500 171331289

18. GROSS ELEC ENER (MWH) 126590 2958220 57876574

19. NET ELEC ENER (MWH) 118908 2848830 55569826 20.

UT SERVICE FACTOR 28.5 89.6 62.8 21.

UT AVAIL FACTOR 28.5 89.6 63.5 22.

UT CAP FACTOR (MDC NET) 25.8 89.9 55.0 23.

UT CAP FACTOR (DER NET) 24.6 85.8 52.4 24.

UT FORCED OUTAGE RATE 71.5 10.4 11.4 25.

FORCED OUTAGE HRS 532.3 532.3 13218.6 26.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION): Cycle 12 refueling outage scheduled for October 15, 1988 through January 9, 1989.

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IF CURRENTLY SilUTDOWN ESTIMATED STARTUP TIME: August 10, 1988 1

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S0-219 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Oyster Creek August 1988 QATE COMPLETED BY

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July" 1988 TELEPHONE REPORT MONTII s

METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER (21-CORRECTIVE ACTIONS / COMMENTS 68 7/9/83 F

532.4 A

2 Plant shutdown was required after MSIV "NS03A" failed to operate properly during routine testing.

The Rx was manually scrammed after the generator was taken off the line.

e mary:

(2) METHOD (1) PEASON A:

Equipment Failure (Explain)

E: Operator Training &

1: Manual 8: Haint. or Test License Examination 2: Manual Scram C:

Refueling F: Adatinistrative 3: Automatic Scram D:

Regulatory Restriction G: Operational Error (Explain) 4: Other (Explain)

H: Other (Explain)

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Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

Director Office of Management Information August, 15, 1988 U.S. Nuclear Regulatory Commission Washington, DC 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 Oyster Creek Nuclear Generating Station.

If you should have any questions, please contact Mr. Joseph D. Kowalski, Oyster Creek Licensing Manager at (609)971-4643.

ery truly yours, j E,

Fi zpatrick Vice President and Director Oyster Creek EEF:KB:dmd(0841A)

Enclosures cc: Director (10)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 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 Divisfor, of Reactor Projects I/II Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station

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f' 0841 A/dmd I l GPU Nuclear Corporation is a subsidiary of the General Pubkc Utihties Corporation

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