ML20012D828

Monthly Operating Rept for Feb 1990 for Oyster Creek Unit 1. W/900314 Ltr

ML20012D828
Person / Time
Site:	Oyster Creek
Issue date:	02/28/1990
From:	Fitzpatrick E, Yeager J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003280424
Download: ML20012D828 (7)

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OPU Nuclear Corporation Ng f Post Office Box 3B8 Route 9 South Forked River.New Jersey 087310388 609 971 4000 Writer's Direct Dial Number; j March 14,1990 i i

U.S. Nuclear Regulatory Commission i ATTN Document Control Desk Washington, D.C. 20555 Dear Sir l i

Subject:

Oyster Croek Nuclear Cencrating 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 i (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 Kathy Barnes, oyster  !

Creek Licensing at (609) 971-4390.

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Vd resident and Director yater Creek EEF KFBidmd (MOR)

Enclosures cct Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission l 475 Allendale Avenue l King of Prussia, PA 19406

! r Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Washington, DC 20555 ,

NRC Resident Inspector oyster Creek Nuclear Generating Station w

9003280424 900228 \\

PDR ADOCK 05000219 R W pnr GPU Nuclet: Corporation is a subsid4ary of the General Public Utilities Corporation

MONTHLY OPERATING REPORT - FEBRUARY 1990 At the beginning of the report period, oyster Creek was operating at a gross generator load of approximately 635 MWo.

On February 6, due to increasing drywell unidentified leak rate, a plant shutdown commenced. Following replacement of a reactor recirculation pump seal, plant restart commenced on February 15. The generator was placed on-line February 17 and full power was achieved on February 18.

On February 20, the reactor was manually scrammed due to inadvertent actuation of the alternate rod injection system during the performance of a surveillance in the control Room. Following completion of the root cause analysis and evaluation of the plant condition, reactor startup commenced on February 21 and the generator was placed on-line. Full power was achieved on February 24 and maintained for the balance of the report period.

MONTHLY OPERATING REPORT FEBRUARY. 1990 The following Licensee Event Reports were submitted during the month of February, 1990.

LER 89 VOLUNTARY REPORT - SETPOINTS FOR 4 OF 6 LOW VACUUM SCRAM SENSORS OUT OF SPECIFICATION DUE TO INSTRUMENT DRLII On December 9, 1989, at approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, during a surveillance test, four out of six condenser low vacuum scram setpoints were found at values less conservative than the Technical Specification limit. The cause of this occurrence is attributed to sensing element drift, and lack of margin for drift in the "as left" setpoint in the calibration procedure. The surveillance test results demonstrated that the low vacuum scram function was operable, and would have responded as designed. Prior to this event, CPUN had initiated a program to review setpoints and instrume.it drift characteristics to determine if setpoint changes would be appropriate. The surveillance setpoint was changed and the setpoint review program will continue.

This condition is considered not reportable. This is a voluntary report.

LER 89 SIX OUT OF EIGHT SENSORS FOUND OUT OF SPECIFICATION ON Tile ISOLATION CONDENSER DUE TO EXCESSIVE DRIFT During a surveillance test on December 28, 1989 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, six of eight isolation condenser pipe break sensors were found to trip 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 full power. The cause of the event is excessive component drift experienced since a 1980 field modification on the switches. 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 will be to replace these sensors as presently committed in the Integrated Schedule.

LER 90 MISSED FIRE WATCH On January 23, 1990, a trouble alarm was received for a fire zone in the Cable spreading Room. Initial investigation could not determine the cause of the trouble alarm, but failure of the detector subsystem was not suspected.

Investigation on February 8, 1990, found that all detectors for the subsystem were disabled and therefore the deluge system for this zone would not have automatically initiated, making it inoperable. A continuous fire watch is required to be set when an automatic deluge system is inoperable, but this watch was not established until February 8th. The failure to set the fire watch was caused by inadequate procedural guidance. The failure to take prompt action to evaluate and correct the problem is attributed to personnel error.

This event is considered to have minimal safety significance because the three other fire detection subsystems in this room would have alarmed in the event of a fire. Operators investigating the alarm would still have initiated the affected deluge system manually. Applicable procedures will be revised as needed and a critique will be conducted to evaluate the human performance problems. In addition, this LER satisfies Technical Specification 3.12.A.2.b and 3.12.C.3 requirements that a Special Report be submitted if the instrument / system is not restored to operable status within 14 days. .

1 OPERATING DATA REPORT 1

I OPERATING STATUS

1. DOCKET: 50-219 .

2. REPORTING PERIOD: 02/90

3. UTILITY CONTACT: JEFF YEAGER 609-971-4585

4. LICENSED THERMAL POWER (MWt): 1930 1 5. NAMEPLATE RATING (GROSS MWe): 687.5 X 0.8 = 550 l

6. DESIGN ELECTRICAL RATING (NET MWe): 650

7. KAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 642

8. KAXIMUM 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 al. REASON FOR RESTRICTION, IF ANY: NONE MONTH XXhB CUMULATIVE

12. REPORT PERIOD HRS 672.0 1416.0 176952.0

13. HOURS RX CRITICAL 407.9 1151.9 112412.5

14. RX RESERVE SHTDWN HRS 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 362.6 1106.6 109338.4

16. UT RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. CROSS THERM ENER (MWH) 658800 1997800 183270859

10. GROSS ELEC ENER (MWH) 219410 669590 61792330

19. NET ELEC ENER (MWH) 209010 642712 59297690

20. UT SERVICE FACTOR 54.0 78.1 61.8

21. UT AVAIL FACTOR 54.0 78.1 62.5 L

22. UT CAP FACTOR (MDC NET) 50.2 73.2 54.0

23. UT CAP FACTOR (DER NET) 47.9 69.8 51.6

24. UT FORCED OUTAGE RATE 11.9 4.2 11.7 l 25. FORCED OUTAGE HRS 49.1 49.1 14459.2 i

26. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, DURATION): NONE j 27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: N/A 1

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Oyct:r Creek StCtion #1 Docket No. 50-219 i

REFUELING INFORMATION - FEBRUARY, 1990 t,

, Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown January 11, 1991 pending necessary state approval. >

Scheduled date for restart following refueling: May 19, 1991

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Will refue1ing 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 i information:

July 15, 1990 Important Aicensing 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 procedures

1. General Electric Fuel Assemblies -

fuel design and performance 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 = 1595 l (c) in dry storage = 37 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storace capacit) : hat has been requested or is planned, M 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:

Roracking of the fuel pool is in progress. Nine (9) out of ten (10) racks have been installed to date. When raracking is completed, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.

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i4.- - ';' ~ . l AVERACE DAILY POWER LEVEL i NET MWe ,

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DOCKET #. . . . . . . . .50219 )

UNIT. . .' . . . . . . . . OYSTER CREEK #1  :

REPORT DATE . . . . . . . MARCH 2, 1990 ,

i- COMPILED BY . . . . .. .JEFF YEAGER i TELEPHONE # . . . . . . .609471-385 l 1- I l' i MONTH FEBRUARY, 1990 P f i

DAX E DAI E

1. 613 17. 255

2. 612 18. 552

3. 611 19. 629

4. 615 20. 285

5. 619 21. 0

6. 168 22. 139

7. 0 23. 526

8. 0 24. 626

-9. 0 25. 630

10. 0 26. 635

11. 0 27. 633

12. 0 28. 635 t.

13. 0

14. 0

15. 0

16. 0

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