ML19332G326

Monthly Operating Rept for Nov 1989 for Oyster Creek Generating Station.W/891214 Ltr

ML19332G326
Person / Time
Site:	Oyster Creek
Issue date:	11/30/1989
From:	Fitzpatrick E, Yeager J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8912210068
Download: ML19332G326 (7)

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,;. 1 GPU Nuclear Corporation NggIgf Post Office Box 388 Route 9 South i

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Forked River,New Jersey 087310388 1 609 971 4000 Writer's Direct Dial Numbet December Ib, 1989 .

U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555

Dear Sir:

Subjects Oyster Creek Nuclear Generating Station Docket No. 50-219 Honthly 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 quastions, please contact Kathy Barnes, Oyster

' Creek Licensing at (609) 971-4390.

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Very truly yours,

, E. E. Fitz atrick f( (

l Vice President and Director I

Oyster Creek l

EEF:KFBij (MORNOV)

Enclosures I.

cc Mr. William T. Russell, Administrator p Region I U.S. Nuclear Regulatory Commission 475 Allendale Avonue King of Prussia, PA 19406 l Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Washington, DC 20555 NRC. Resident Inspector Oyster Creek Nuclear Generating Station 8912210068 891130 tPDR. ADOCK 05000219 s

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'R PDC GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation ,

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MONTHLY OPERATING ' REPORT - NOVEMBF:R 1989 At the beginning of the report period, the plant was operating at a gross generator load of approximately 650 MWe, On November 17, a load reduction ecmnenced due to an electrical fault on power cables to the dilution pumps. To meet environmental requirements, power was reduced to the differential temperature expected with the dilution pumps in service. Plant load was reduced to 242 MWe by November 18. Cable replacenent was completed on November 19 and the plant was returned to full power.

On November 20, the plant began to experience a low intake canal level due to high offshore winds associated with a storm system. During the next several days, as intake levels fluctuated, various power reductions were required and plant load was reduced as low as 230 MWe. Power ascension commenced on November 23 and full load was achieved on November 24.

On November 28, power was reduced to approximately 540 MWe to accommodate repairs to an auxiliary flash tank pump discharge valve. Repairs were ecmpleted and plant load was increased on November 29. Maximum plant load was achieved and maintained for the balance of the report period.

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MONTHLY OPERATING REPORT NOVEMBER, 1989 The following Licensee Event Reports were submitted during the month of November, 1989:

LER 89-022: TECHNICAL SPECIFICATION VIOLATION DUE TO ABSENCE OF AN SRO IN THE CONTROL ROOM CAUSED BY PERSONNEL ERROR October 5, 1989 at 2153 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.192165e-4 months <br />, the SRO licensed Group Shift Supervisor (GSS) left the GSS office without informing the SRO licensed Group Operating Supervisor (GOS). At 2154 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.19597e-4 months <br /> the CO3 lef t the control room without noticing the GSS was not in the control room. As a result, there was no SRO in the control room for a six minute period, until approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />. This is a violation of Technical Specification 6.2.2.c that requires a SRO be present in the control room at all times when there is fuel in the vessel except when

-the reactor is in COLD SHUTDOWN or REFUEL modes. This event is reportable based on 10CRF50.73(a)(2)(1)(B). Corrective actions included the immediate return of the GOS to the control room when it was discovered the GSS was not in the control room and Plant Operations Management discussing the occurrence with the individuals involved.

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OPERATIN3 DATA REPORT

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• OPERATING STATUS'

1. DOCKET: 50-219

~2. REPORTING PERIOD: 11/89

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 i l

6. DESIGN ELECTRICAL RATING (NET MWe): 650 1

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 WHICl! RESTRICTED, IF ANY (NET MWe): NONE

11. REASON FOR RESTRICTION, IF ANY: NONE  !

MONTH LEhB CUMULATIVE

12. REPORT PERIOD HRS 720.0 8016.0 174792.0 ;

13. HOURS RX CRITICAL 720.0 4439.8 110685.2

14. RX RESERVE SHTDWN HRS 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 720.0 4137.0 107680.5

16. UT RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. GROSS THERM ENER (MWH) 1305000 6757170 180278059

18. GROSS ELEC ENER-(MWH) 440606 2184086 60788270

19. NET ELEC ENER (MWH) 424614 2074280 58334148

20. UT SERVICE FACTOR 100.0 51.6 61.6

21. UT AVAIL FACTOR 100.0 51.6 62.3

22. UT CAP FACTOR (MDC NET) 95.1 41.7 53.8

23. UT CAP FACTOR (DER NET) 90.7 39.8 51.3

24. UT FORCED OUTAGE RATE 0.0 14.6 11.7

25. FORCED OUTAGE HRS 0.0 706.7 14217.4

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

I None l 27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: N/A i

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AVERAGE DAILY POWER LEVEL '

NET MWe 9

DOCKET #. . . . . . . . .50219 UNIT. . . . .. . . . . . OYSTER CREEK #1 "

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REPORT DATE . . . . . . . DECEMBER 6, 1989 e COMPILED BY . . . . . . .JEFF YEAGER TELEPHONE # . . . . . . 609-971-4585 ,

MONTH NOVEMBER, 1989 DAI HH DAY ME

1. 615 17, 603

2. 630 18. 279

3. 633 19. 465

4. 633 20. 632

5. 633 21. - 367

6. 632 22, 427 l

7. 632 23. 464

8. 633 24. 624 ,

9. 631 25, 628

10. 632 26. 627

11. 634 27. 625

12. 633 28. 613

13. 633 29. 617

14. 630 30. 627

15. 630

16. 631 1619B

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Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - NOVEMBER, 1989 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 Will- refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes i

Scheduled date(s) for submitting proposed licensing action and supporting  ;

informations i July 15, 1990 i

Important licensing considerations associated with refueling, e.g., new or j 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. l

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 storago 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 pool assuming the present licensed capacity: 4 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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UNIT SHUTDOWNS AND POWER REDUCTIONS 4 * .'

DOCKET NO. 50-219' ,

UNIT NAME Oyster Creek DATE December. 1989 COOG%ETED BY R. Baran REPORT MONTH Ncvember. 1989 TYPE NETHOD OF SHUTTING F Forced DURATION DOWN THE REACTOR OR NO. DATE St Scheduled (Hours) REASON (1) REDUCING POWER (2) CORRECTIVE ACTIONS /Crum8mTS 87 11/17/89 F 45.7 H 1 Load reduction to maintain less than a 23*F differential temperature between the Intake and Discharge canals.

Lowest point in the load drop was 223 MWe (Gross).

88 11/21/89 F 62 H 1 Low Intake level conditions due to' storm front in the area required a load drop in accordance with plant procedures. Lowest point in the load drop was 231 MWe (Gross).

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SUMMARY

I (1) REASON (2) 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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