ML20154G520

Monthly Operating Rept for Apr 1988

ML20154G520
Person / Time
Site:	Oyster Creek
Issue date:	04/30/1988
From:	Baran R, Fitzpatrick E, Sedar J GENERAL PUBLIC UTILITIES CORP.
To:
References
NUDOCS 8805240409
Download: ML20154G520 (7)

Text

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' %TILY OPERATING RETURT - AFRIL 1988 a

At the beginning of the report pericd, Oyster Creek was operating at approximately 662 She.

Brief power reductions were required during the month to perform Turbine Valve testing.

On April 4, plant load was reduced to 528 SMe to correct a malfunction of the Stain Flash Tank Level Control System.

While at reduced power,

'B' reactor recirculation pump motor gene rator (50-Set) was removed from service to facilitate brush replacement.

Load was increased to 665 5Ke en April 5, after completion of repairs.

Load was reduced to 633 She on April 13 to accommodate brush and collector ring preventive maintenance on

'A' reactor recirculation ptstp 50-Se t.

Full load (665 She) was achieved on April 15, following completion of 50-Set preventive maintenance.

On April

~.9, plant load was reduced approximately 5 She to reduce the frequency of spurious oustic monitor alarms associated with reactor safety valve NR28J and electromatic reif ef valve NR108C.

On April 20, load was reduced to 400 5fde to allow replacement of 'A' condensate ptop mechanical seals.

On April 21, load was further ieduced to 227 5Me to perform a full closure test on Stain Steam Isolation Valve NS03A.

The full closure test required to confirm operability after the valve failed to move off was After passing the full its open seat while p(erforming a 5% closure test.

closure test, three

3) consecutive 5% closure tests were satisfactorily performed and the valve wa., considered operable.

Load wns then increased to 430 bhe and held at that level pending completion of ' A' condensate pump repair.

Full load (658 'Me) was achieved on April 22 after completion of condensate pump repairs and maintained at that level for the balance of the report period.

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MONTHLY OPERATING REPORT APRIL 1988 The following Licensee Event Reports were submitted during the month of April 1988:

LER 88-006 - PAST MODIFICATION CAUSES FOUR ISOLATION CONDENSER PIPE BREAK SENSORS TO BE OUT OF SPECIFICATION DURING SURVEILLANCE During a surveillance test on March 25,1988 at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, four of eight isolation condenser pipe break sensors trip tested at a differential pressure greater than the maximum allowable trip setpoint specified in the technical specifications.

At the time of the occurrence the plant was in the RUN mode at 100% power.

The cause of the event is a combination of a 1980 field modification on the switches and various switch component problems.

The safety significance is minimal due to the operability of other pipe break sensors, area radiation monitors and area temperature monitors.

Immediate corrective action was taken to adjust the switches to trip within Technical Specification limits.

Long term corrective action is to replace up to four reactor protection system digital sensors during the plant's next refueling outage (fourth quarter 1988), monitor their performance over the subsequent operating cycle, and replace the isolation condenser pipe break sensors during the following refueling outage provided the operation of the new sensors proves acceptable.

LER 88-005 - DEGRADED STANDBY GAS TREATMENT SYSTEM DUE TO PERSONNEL ERROR On March 24, 1988, at approximately 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br />, it was disccvered that a tagging error caused components of both Standby Gas Treatment Systems (SGTS) to be inoperable due to personnel error.

At the time, the reactor was operating at 100% power.

SGTS train one (1) had its fan breaker de-energized which rendered it totally inoperable while SGTS train two (2) had an instrument power fuse pulled for maintenance which placed it in a degraded moh.

It was actually intended that SGTS train two (2) fan breaker be de-energized but the operator preparing the paperwork made an error that was not identified by subsequent independent review.

Operation of SGTS train two (2) in this degraded mode would result in lower air flow from the Reactor Building and lower iodine removal efficiency by the charcoal filter.

The total time the systems were in this configuration was about two (2) hours. A previous evaluation shows that, in this degraded mode, the charcoal efficiency is still adequate to control releases of iodine within 10CFR100 limits.

The reduction in flow rate would have been limited by restricting orifices te approximately 100 cubic feet per minute.

Even with this reduction of flow, the system would still have been above the minimum required flow to perform its function.

Therefo*e, the safety significance is considered minimal.

Corrective action includes management reinforcement of expected performance and required reading for licensed operators, dod:0841A

OPERATItG DATA REPORT OPERATItG STA'IUS 1.

DOCKET:

50-219 2.

REPORTItE PERIOD: APRIL, 1988 3.

UTILITY COtEACT:

JOHN H. SEDAR, JR.

609-971-4698 4.

LICENSED THERMAL POWER (Mdt):

1930 5.

NAPIPLATE RATItG (GROSS Kde):

687.5 X 0.8 = 550 6.

DESIGN ELECTRICAL RATItG (NET Mde):

650 7.

MAXIMUM DEPENDABLE CAPACITY (GROSS Mde):

642 8.

MAXIMUM DEPENDABLE CAPACITY (NET Mde):

620 9.

IF CHA!GES OCCUR ABOVE SINCE LAST REPORT, GIVE REASOt1S:

MDC GROSS IS CHANGED TO REFLECT SUMMER GENERATIOtl, !KTT WItEER.

10.

POWER LEVEL TO WHICH RESTRICIED, IF ANY (NET Mde):

11. REASON FOR RESTRICTION, IF ANY: tJ0 tie MOtlTH YEAR CUMULATIVE 12.

REPORT PERIOD HRS 719.0 2903.0 160896.0

13. HOURS RX CRITICAL 719.0 2903.0 103359.4 14.

RX RESERVE SHTDWN HRS 0.0 0.0 918.2

15. HRS GENERATOR Oti-LINE 719.0 2903.0 100695.9 16.

UT RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. GROSS THERM ENER (MdH) 1356000 5516000 168163789

18. GROSS ELEC ENER (KdH) 464380 1899770 56818124

19. NET ELEC ENER (!NH) 447695 1831844 54552840 20.

W SERVICE FACTOR 100.0 100.0 62.6 21.

Ur AVAIL FACIOR 100.0 100.0 63.3 22.

Ur CAP FACIOR (MDC NET) 100.4 101.8 54.7

23. Ur CAP FACIOR (DER NET) 95.8 97.1 52.2

24. Ur FORCED OUTAGE RATE 0.0 0.0 11.2 25.

FORCED OUTAGE HRS 0.0 0.0 12686.3 26.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION): Cycle 12 refueling outage scheduled for October 1 through December 29, 1988 27.

IF CURREtELY SHUTDOWN ESTIMATED STARTUP TIME: N/A py

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Oyster Creek Station il Docket No. 50-219 REFUELI!G INFORMATION - APRIL, 1988 Name of Facility: Oyster Creek Station il Scheduled date for next refueling shutdown: October 1, 1988 Scheduled date for restart following refueling: January 1, 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.

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

new or different fuel design or supplier, unreviewed design or performnce analysis methods, signif'. cant changes in fuel design, new operating procedures:

fuel design and performnce

1. General Electric Fuel Assemblies analysis methods have been approved by the imC.

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

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

=

(b) in the sg nt fuel storage pool = 1392 20 (c) in dry storage

=

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 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 raracking is cocpleted, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.

16198

AVERAGE DAILY PG4ER LEVEL NET Mie DOCKET 4........

50219 UNIT........... OYSTER CREEK i1 REPORT DATE.......May 03, 1988 COMPILED BY....... JOHN H. SEDAR JR.

TELEPHONE #......

609-971-4698 FOtml APRIL, 1988 DAY M4 DAY M?

1.

640 17 640 2.

641 18 641 3.

613 19 636 4.

600 20 511 5.

634 21 415 6.

641 22 611 7

639 23 634 i

8.

642 24 634 9.

643 25 635 10.

642 26 634 11, 641 27 631 12.

641 28 631 13.

633 29 633 14, 611 30 633 15, 634 l

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50-219 METNO.

UNIT 5flUTDOWNS AND POWER REDUCTIONS Oyster Creek UNITNAME - My 1988 DATE l

l REPORT MONTil Aori1 1988 COMPLETED BY '

R. Baran TELEPHONE 971-4640 l

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Maintenance outage following forced shutdown - September 10 to November 24.

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Metimit Exhible G.instrectione 5: Sche 4uled A-Equipment Fellwe(Emplain) 1-Mead tw Preperstles of Deta E44eleienence etTest 244easelscree.

Entry Sheets for IJeansee C. Refueling 3 Aelematic5 cree.

Event Report (l.ERI F5e tNUREG-0.Reguleswy Restriction 44)tiwr(Emplehi) 0161)

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GPU Nuclear Corporation 3 : Nuclear

en:r388 Forked River.New Jersey 08731-o388 609 971 4000 Writer's Direct Dial Number:

Director Of fice of ManaCement Information May 12, 1988 U.S. Nuclear Regulatory Comission 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. OPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) copies 1

of the Monthly Jperating Data (gray book information) for the Oyster Creek Nu & r r.erating Station.

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

Very truly yours, eems or E. E. Fitz atrick l

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 Comission 475 Allendale Avenue King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Comission 7q Division of Reactor Projects I/II A

Washington, DC 20555

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NRC Resident Inspector Oyster Creek Nuclear Generating Station GPU Nuclear Ccrperation is a suosid.ary ct the General Pubhc Utiht es Corporation