ML20151D283

Monthly Operating Rept for June 1988 for Oyster Creek

ML20151D283
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1988
From:	Fitzpatrick E, Sedar J GENERAL PUBLIC UTILITIES CORP.
To:	NRC
References
NUDOCS 8807250044
Download: ML20151D283 (8)

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

LER 88-003:

CONTAINMENT PARTICULATE MONITOR SAMPLE LINE ISOLATION VALVES -

POTENTIAL FAILURE TO OPERATE DUE TO DESIGN DEFICIENCY The plant's containment Particulate Monitor sample line isolation valves' control circuitry does not meet single failure criteria as required by 10CFR50, Appendix A, General Design Criterion.

This condition was determined reportable on May 20, 1988, while the plant was operating at rated output.

The apparent cause of the condition is a design deficiency which has been present since the Containment Particulate Monitor was installed in 1976.

This condition is significant in that it could place the plant outside its design basis containment leak rate during a design basis accident.

A conservative analysis indicates that under the design basis loss of coolant accident with thf s single failure present, operators would have to diagnose and take corrective action within 6.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to prevent exceeding 10% of the 10CFR100 limits. Direction by means of a standing order has been provided to operators to deenergize the power supply to close these valves upon a reactor low-low water level or a high drywell pressure alarm.

Corrective action will be taken in accordance with the Integrated Living Schedule for the Oyster Creek plant.

LER 88-009:

ISOLATION CONDENSER ACTUATION PRESSURE SENSORS EXCEED SETPOINT LIMIT DUE TO LIMITATIONS OF INSTALLED INSTRUMENTS During routine surveillance testing, the Isolation Condenser automatic actuation pressure sensors REISA and RE15C tripped at values greater than those specified in Technical Specification 2.3.E.

The sensors were adjusted to trip within the desired setpoint limits.

This event had no effect upon public health or safety.

The installed sensors have a designed accuracy of + 7.5 psig and have a history of setpoint drif t.

Engineering studies have been performed on these sensors and an analog trip system has been selected as the most appropriate way to minimize setpoint drift and improve setpoint repeatability.

The sensors being considered for the analog system will have an accuracy that will significantly improve setpoint repeatability.

The analog trip system is, planned to be installed in accordance with the Integrated Living Schedule.

LER 88-010:

PERSONNEL ERROR WHILE PLACING AUGMENTED OFFGAS SYSTEM IN SERVICE LEADS TO MANUAL STANDBY SAS INITIATION On June 1,1988 at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> the Standby Gas Treatment System (SGTS) was manually initiated due to rising radiation levels at the reactor building ventilation radiation monitor.

Prior to this time the reactor was operating at full power, the Augmented Offgas System ( A0G) was in service, and an electrical storm was in progress. An electrical disturbance (1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />) caused an automatic transfer switch in the plant's unit substation '1El' to change to an alternate power supply.

This caused the A0G 'B' recombiner to 9807250044 880630

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i LERS - June 1988 Page 2 i

trip on a momentary loss of power.

In the process of restoring the A0G system to service, pressure oscillations were experienced.

The control room received a high hydrogen alarm and isolated A0G. When plant ventilation stack area ventilation radiation monitor readings were observed to increase, the control room manually initiated SGTS (1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br />) in anticipation of an automatic initiation.

Radiation levels never reached the automatic initiation setpoint.

Reactor building ventilation was restored to normal at 1949 hours0.0226 days <br />0.541 hours <br />0.00322 weeks <br />7.415945e-4 months <br />.

The cause of the occurrence was personnel error in failing to provide adequate guidance to opertors following a previous similar event.

The safety significance is minimal. As corrective actions, personnel involved in the event were counseled on the importance of draining the offgas inlet line before placing ADG in service, and on the importance of prompt completion of corrective actions intended to preclude recurrence of previous events.

An operating procedure revision was completed, and the minimum sump level was raised to increase its pressure suppression capacity.

This report will be j

made required reading for site supervisory and operations personnel.

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Morm1LY OPERATING REf0RT - JUNE 1988 i

At the beginning of the report period, Oyster Creek was operating at ' full power with an average gross generator load of 648 We, Brief power reductions t

-were required during the month to perform turbine valve testing, core flux shaping and to repair a recirculation pump motor generator set.

On June 22, Containment Spray / Emergency Service Water System I was declared l

inoperable due to heat exchanger differential pressure in excess of that specified in the surveillance procedure.

Power was reduced to. approximately i

90% in anticipation of a 30-hour reactor shutdown in accordance with Technical t

Specifications.

Power reduction was terminated following receipt of technical.

i data confirming that design heat exchanger differential pressure was 3 1/2 times the conservative acceptance criteria in the surveillance procedure. The 30-hour clock was secured and a 7-day LCO clock was entered.

Both heat exchangers were subsequently opened and cleaned.

Following satisfactory operability testing, System I was declared operable on June 23.

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i At the end of the report period, the plant was operating at a maximum j

generator load of 630 We, limited by increaN intake canal water temperature

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and its effect on condenser efficiency.

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-i AVERAGE DAILY POWER LEVEL l

NET MWe DOCKET f......... 50219 UNIT..

.0YSTER CREEK #1 REPORT DATE....... July 05, 1988 COMPILED BY....... JOHN H. SEDAR JR.

TELEPHONE #......

609-971-4698 MONTH JUNE, 1988 4

DAY MW DAY g

1.

620 17 609 2.

620 18 600 3.

622 19 612 4.

626 20 608 5.

625 21 607 6.

626 22 584 7.

624 23 605 1

8.

625 24 613 9.

624 25 609 10.

627 26 611 1

11.

505 27 618

)

12.

620 28 615 I

13.

622 29 616 14.

619 30 616 15.

614 30 616 16.

610 1968B o

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OPERATING DATA REPORT OPERATING STATUS 1.

DOCKET:

50-219 2.

REPORTING PERIOD: JUNE, 1988 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 j

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 AbY (NET MWe): None 4

11.

REASON FOR RESTRICTION, IF Urt: NONE MONTH YEAR CUMULATIVE 12.

REPORT PERIOD HRS 720.0 4367.0 162360.0

13. HOURS RX CRITICAL 720.0 4367.0 104823.4 14.

RX RESERVE SHTDWN HRS 0.0 0.0 918.2 i

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15. HRS GENERATOR ON-LINE 720.0 4367.0 102159.9 16.

UT RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. GROSS THERM ENER (MWH) 1376000 8300000 170947789

18. GROSS ELEC ENER (MWH) 457200 2831630 57749984 l

19. NET ELEC ENER (MWH) 440538 2729922 55450918 i

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20. UT SERVICE FACTOR 100.0 100.0 62.9 21.

UT AVAIL FACTOR 100.0 100.0 63.7

22. UT CAP FACTOR (MDC NET) 98.7 100.8 55.1 23.

UT CAP FACTOR (DER NET) 94.1 96.2 52.5 a

24.

UT FORCED OUTAGE RATE 0.0 0.0 11.0

)

25.

FORCED OUTAGE KRS 0.0 0.0 12686.3 J

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

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IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: N/A 1

i Doc.1965B/ Disk 0045X l

A Oyster Creek Station il Docket No. 50-219 REFUELING INFORMATION - JUNE,1988 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:

October 1,1988 Scheduled date for restart following refueling: January 1, 1989 Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?

Yes Scheduled date(s) for submitting proposed licensing action and support!cg inf ormation:

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

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

new or dif fere nt fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedurest

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

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

The number of fuel assemblies (a) in the core 560 (b) in the spent fuel storage pool = 1541 (c) in dry storage 91

=

The prese nt 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 capacityt Reracking of the fuel pool is in progress.

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

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

1619B

DOCKET NO.

50-219 UNIT SHUTDOr!NS AND POWER REDUCTIONS UNIT NAME Ovster Crook QATE July 1988 COMPLETED BY C.

Gavdos June 1988 TELEPHONE 971-4640 REPORT MON Fil MFTHOD OF SHUTTING DOWN TYPE F: FORCED DURATION THE REACTOR OR NO.

DATE S: SCHEDULED (HOURS)

REASON Ul REDUCING POWER (2)

CORRECTIVE A7 67 6/11/8 3 S

3.4 H

N/A Power reduction to 420 54He (gross for rod swao 1

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4 SuesMARY:

(2) METHOD (1) REASON A:

Equipnent Failure (Explain)

E: Operator Training &

1: Manual B: Maint. or Test License Examination 2: Manual Scram i

C:

Refueling F:

Administrative 3: Automatic Scram D:

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

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a GPU Nuclear Corporation gggf Post Otisce Box 388 Route 9 South

.m Forked Arver.New Jersey 08731-0388 609 971 4000 Writer's Direct Dial Number:

Director July 15, 1988 Office of Management Information U.S. Nuclear Regulatory Commission Washington, DC 20555 Dear Sir-Subj ect: Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Creet 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, plea.se contact Mr. Joseph D. Kowalski, Oyster Creek Licensing Manager at (609)971-4643.

Very truly yours.

E. E. Fitz;ptrickaaX eeta p

Vice President and Director Oyster Creek l

EEF:KB: dad (0841 A)

Enclosures f

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 Division of Reactor Projects I/II Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station i

GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation N