ML20148G748

Monthly Operating Rept for Feb 1988

ML20148G748
Person / Time
Site:	Oyster Creek
Issue date:	02/29/1988
From:	Baran R, Fiedler P, Sedar J GENERAL PUBLIC UTILITIES CORP.
To:	NRC
References
NUDOCS 8803290215
Download: ML20148G748 (7)

Text

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, ' MONTHLY OPERATING REPORT - FEBRUARY 1988 i

At the beginning of the report period, Oyster Creek was operating at approximately 666 We. Brief power reductions were required during the month to perform turbine valve testing. ,

On February 17 at 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br />, power was reduced to 633 We to return the Cleanup System to service. The system previously tripped on low pressure while filling the 'B' cleanup filter. The 'A' . system filter was subsequently returned to service and power was increased to maximum generator load at 1219 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.638295e-4 months <br /> on February 18.

On February 20 at 0612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br />, a planned power reduction to 220 We was perfomed to facilitate the following:

o Main steam isolation valve (MSIV) surveillance test o Control rod pattern change o Repair an MSIV 5% closure position indicator switch arm j o Repair steam traps on a steam jet air ejector condenser o Control rod drive acetnulator maintenance Following completion of required repairs and maintenance, plant load was increased at 1745 hour0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />.s.

Maximum generator load was maintained for the balance of the report-period except for a brief power reduction' to perfom an anticipatory scram turbine stop valve closure test.

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MONTHLY OPERATING REPORT FEBRUARY 1988 l i

The following Licensee Event Reports were submitted during the month of l February 1988. j i

LER 88-001: Reactor Building Internal Temperature Dropped Below Design Point Due to Inoperable Heating System On January 6,1988, several non-safety instrument indications exhibited abnormal characteristics. At the time, the reactor was operating at full rated power, the Reactor Building Heating System was out of service and outside temperatures were approximately six degrees Farenheit. The indications affected were in the Shutdown Cooling System (not in service at the time) and the number two (2) seal pressure on two of the reactor Recirculation Pumps. Operators suspected that low temperatures were affecting these indications. Temperatures obtained in the building using a portable monitor were in the low thirties in the vicinity of the affected instrument lines, and the middle forties in nearby areas. Normal Reactor Building ventilation was taken out of service and the Standby Gas Treatment System was started to minimize cold air being introduced into the building. The cause of the event is attributed to the building heating system being out of service, extremely low outside temperatures, and lack of sensitivity to the significance of low building temperatures by plant personnel. This event could have placed the plant into an unanalyzed condition as unacceptable stresses could have been imposed on concrete structures or affected other instrument lines. The FSAR indicates that normal building temperatures will be maintained above sixty degrees Fahreaheit. Evaluations of the concrete structure indicate that even though the low temperature limit in the Reactor Building was exceeded, the differential temperatures across the areas of concern did not create an unacceptable stress condition. To avoid this problem in the future, a program will be instituted to develop monitoring capability, action levels, and operator actions should temperatures drop below predetermined levels.

LER 88-002: Containment Rad Monitoring System Out of Specification On November 29, 1987 the plant's, containment high range radiation monitors failed to meet acceptance criteria for a one point calibration check of the detector with a calibrated radiation source. Detectors may not have actuated at the proper setpoint as defined by Technical Specifications during a Loss Of Coolant Accident. At the time of discovery the plant was in the REFUEL mode with reactor coolant temperature less than 212*F. The monitors were installed and tested in November 1986, with an acceptance criteria of +36% for a one point source calibration check. It was later discovered that the acceptance criteria should have been +10%. When the surveillance procedure with the correct acceptance criteria was performed, defectiva components were found in the monitors' preamplifiers which could have been detected by the post-installation testing had the +10% criteria been clearly established in the vendor manual. The cause of tWe event was unclear information for testing in the vendor's instruction manual. The most likely cause of the equipment failure was extended storage of the components at the licensee's facility.

The safety significance of this event is minimal. Imediate corrective action was taken to repair the monitors and return them to service. Since the equipment was purchased, the licensee has established a vendor document control program which periodically reviews vendor's surveillance procedures against vendor manuals and adds vendor updates to the plant's vendor manuals.

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1 OPERATING DATA REPORT OPERATING STATUS

1. DOCKET: 50-219

2. REPORTING PERIOD: FEBRUARY, 1988

3. UTILITY CONIACT: JOHN H. SEDAR, JR. 609-971-4698

4. LICENSED THERMAL POWEP ( Wt): 1930  ;

5. NAREPLATE RATING (GROSS We): 687.5 x 0.8 = 550 l

6. DESIG4 ELECTRICAL RATING (ter We): 650

7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 650

8. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 620

9. IF CHANGES OCCUR ABOVE SINCE IAST REPORT, GIVE REASONS: NONE

10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): N/A

11. REASON FOR RESTRICTION, IF ANY: NONE MONTH YEAR CUMULATIVE

12. REPORT PERIOD HRS 696.0 1440.0 159433.0

13. HOURS RX CRITICAL 696.0 1440.0 101896.4

14. RX RESERVE SHTDWN HRS 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 696.0 1440.0 99232.9

16. (Tr RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. GROSS THEPR ENER (KM ) 1310000 2739000 165386789

18. GROSS ELEC ENER (ME) 452000 945070 55863424

19. NET ELEC ENER (MWH) 435786 911349 53632345

20. (Jr SERVICE FACTOR 100.0 100.0 62.2

21. IJr AVAIL FACIOR 100.0 100.0 63.0 1

22. UT CAP FACIOR (MDC NET) 101.0 102.1 54.3

23. tJr CAP FACIOR (DER NET) 96.3 97.4 51.8

24. UT FORCED OUTAGE RATE 0.0 0.0 11.3

25. FORCED OUTAGE HRS 0.0 0.0 12686.3 l

26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONES (TYPE, DATE, DI*ATION): N/A

27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: N/A I

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4 AVERAGE DAILY POWER LEVEL NET MWe DOCKET f. . . . . . . . 50-219 UNIT. . . . . . . . . . . OYSTER CREEK #1  !

REPORT DAIS . . . . . . . MARCH 01, 1988 COMPILED BY . . . . . . . JOHN H. SEDAR JR.

TELEPHONE # . . . . . . 609-971-4698 MCWTH FEBRUARY, 1988 W

DAY DAY W

1. 643 17, 629

2. 639 18. 641

3. 643 19. 642

4. 642 20. 368

5. 641 21. 502 >

l 6. 642 22. 622 1

7. 641 23. 641

8. 642 24, 641

9. 639 25 643

10. 641 26. 641

11. 641 27. 642

12. 642 28. 643

13. 639 29. 642

14. 642 15, 642

16. 640 19688 J

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4 Oyste Creek Station il Docket No. 50-219 REFUELING INFORMATION - FEBRUARY, 1988 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: N/A Scheduled date for restart following refueling:

Will refueling or resunption of operation thereafter require a Technical Specification change or other license amendment?

Yes Scheduled date(s) for submitting proposed licensing action and supporcing information:

May 1, 1988 Ir@ortant licensing considerations associated with refueling, e.g., new or different fuel decign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedares:

1. General Electric Fuel Assemblies - fuel design and performance analysis methods have been approved by the NRC.

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2. Exxon Fuel Asse211es - no major changes have been made nor are )

there any anticipated.

I 2e nunber of fuel assenblies (a) in the core = 560 (b) in the spent fuel storage pool = 1392 (c) in dry storage = 20 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 assenblies:

Present licensed capacity: 2600 l

1 Re 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 conpleted, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.

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50-219 -

DOCKETNO. ,

UNITSilUTDOWNS AND POWER REDUC 110NS UNIT NAME Oyster Creek

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DATE March 1988 COMPLETED BY R. Baran February 1988 971-4640 REPORT MONDI TELErtlONE

- jg } Y> Licensee Eg k3 Cause & Corrective Action to No. Date k Eg 3s& Event Report a g3 in O o Prevent Recussence F

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66 9/10/87 F 1804.4 A 1 Maintenance outage following forced shutdown - September 10 to November 24.

3 4 I 2 Exhibit C. Instructions F: Forced Reason: Method:

1-Manual for rieparation o(Data S: Scheduled A-Equipment Failure (Explain) Entry Slicens for Licensee 3-Maintenance of Test 2-Manual Scram.

3 AutosnaticScsain. Event Report (LER) File (NUREC-C-Refueling 4-Onlies (Emplain) 016l)

D-Regulatory Restricilon E-Operstor Training & Ucense Emandnation 5 .

F-Adeninistrative Extabit ! - Same Source G-Operational Ensus (Explain)

(9/77) 11 Ollies (Empleta)

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l GPU Nuclear Corporation NggIgf Post Office Box 388 Route 9 South Forked River, New Jersey 087310388 609 971 4000 Writer's Direct Dial Number:

Director )

Office of Management Information March 15,1988 j U.S. Nuclear Regulatory Comission i Washington, DC 20555 J

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.

Very truly yours, gt. A./

P 1ed$r Vice President and Director Oyster Creek PBF:KB:dmd(0841 A)

Enclosures cc: Director (10)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission Washington, DC 20555 Mr. Willicm T. Russell, Administrator Region I U.S. Nuclear Regulatory Comission l 475 Allendale Avenue King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Comission i Division of Reactor Projects I/II l Washington, DC 20555 NRC Resident Inspector j Oyster Creek Nuclear Generating Station g\

GPU Nuc ear Corporation is a subsidiary of the General Pubhc Utilities Corporation