ML20024F800

Monthly Operating Rept for Nov 1990 for Oyster Creek Nuclear Generating Station.W/901212 Ltr

ML20024F800
Person / Time
Site:	Oyster Creek
Issue date:	11/30/1990
From:	Fitzpatrick E, Sharma H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9012210043
Download: ML20024F800 (7)

Text

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GPU Nuclear Corporation Nuclear-c.r,

ger388 Forked River, New Jersey 087310388 609 971 4000 Wnters Direct Dia! Number.

December 12, 1990 1

U.S. Nuclear Regulatory Commission ATTN Document Control Desk )

Washington, D.C. 20555 l Dear Sire l i

Subject:

Oyster Creek Nuclear Generating Station J

. Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Creek Nuclear Generating .tation Operatir.g License No. DPR 16, Appendix A, Section 6.9.1.C, et.clcsed 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 Brenda DeMerchanc, Oyster Creek Licensing Engineer at (609) 971-4642.

Very truly yours, f

E. E. Fltzpatrick Vice President and Director Oyster Creek EEF:DDEM:jc (MOR)

Enclosures-

l. cci Mr. Thomas Martin, Administrator l Region I l U.S. Nuclear. Regulatory Commission 475 Allendale Road King of Prussia, PA ~19406-Mr. Alexander W.'Drorr9 rick, Project Manager l

l U.S. Nuclear Regulatory Comtnission l Washington, DC 20555 i

/

NRC Resident Inspector Oyster Creek Nuclear Generating Station 9012210043 901130 l

PDR ADOCK 05000219 l R PDR t

GPU Nuclear Corporat on is a subsidiary of General Public Utiltes Corporation y l

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MONTHLY OPERATING REPORT NOVEMBER 1990 The following Licensee Event Reports were submitted during the month of November, 1990:

LER 90-14: Flow Biased APRM Scram & Rod Block Setpoints Higher than Tech Spec Limits Due to Instrument Drift on October 8, 1990 a comparison was made between the indicated recirculation flow and the flow output of the flow converter units for the APRMs. Both flow converters indicated approximat-ely 7% higher than the other indications in the Control Room. Evaluation showed that the converter ur.its had drifted high, and that the as-found flow biased APRM rod block and scram setpointe had exceeded the limits required in the Technical Specifications. All APRMs were declared inoperable and a reactor shutdown was initiated until the APRM gain was adjusted to compensate for the high flow inputs. The cause of this event has been attributed to the break-in of new electronic components. This event is considered to have minimal safety significance because although the flow biased scram setting had drifted in the non-conservative direction, it was in all cases limited by the fiaed trip at 115.7%, which bounds the applicable analyzed transients. Some reduction in the margin to the safety limit resulted from the drift in the rod block setpoints, but analysis indicates that MCPR limits'would not have been reached for any rod withdrawal error transient. A monitoring program was set up for the flow converters and a change was put into the Technical Manual giving more direction on calibration after component replacement.

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MONTHLY OPERATING REPORT - NOVEMBER 1990 At the beginning of November, Oyster Creek was operating at full power. Power was reduced for about 14 days to repair a leak on a ,

feedwater minimum flow valve and to conduct inspections and repairs i to associated piping. At the end of November, Oyster Creek was operating at full power.

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4 s . 4 OPERATING DATA REPORT OPERATING STATUS

1. DOCrlT: 50-219

2. RP. PORTING PERIOD: 11/90

3. UTILITY CONTACT HARI S. SHARMA 609-971-4638

4. LICENSED THERMAL POWER (MWt): 1930 68*'. 5 X 0.8 = 5 50

^

5. HA'iEPLATE RATING (GROSS MWe):

6. DESIGN ELECTRICAL RATING (N2T MWe): 650

7. MAXIHUM DEPENDABLE CAPACITY (GROSS MWe): 642

8. MAXIHUM OEPENDABLE CAPACITY (HET MWe): 620

9. IF CHANGES'O*: CUR ABOVE SINCE LAST REPORT, GIVE REASONS: NONE

10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): None

11. REASON FOR RESTR*iCTION, IF ANY: None MONTH XIAB CUMULATIVE

12. REPORT PERIOD HRF 720.0 8016.0 183552.0

13. HOURS RX CRITICAL 720.0 7060.6 118321.2

14. RX RESERVE SitTDWN HRS 0.0 0.0 918.2

15. HRS GENERATOR ON-LINE 720.0 6937.2 115169.0

16. UT' RESERVE SHTDWN HRS 0.0 0.0 1208.6

17. GROSS THERM ENER (HWH) 1141932 122577'i0 193530829

18. GROSS ELEC ENER (HdH) 379760 4024980 65147720

19. NET ELEC ENER (MWH) 365042 3864054 62519032

20. UT SER\* ICE FACTOR 100.0 86.5 62.7

21. UT AVAIL FACTOR 100.0 86.5 63.4

22. UT CAP FACTOR (KDC NET) 81.8' 77.7 54.9

23. UT CAP FACTOR (DER HET) 78.0 74.2 $2.4

24. UT FORCED OUTAGE RATE 0.0 11.0- 11.7

25. FORCED OUTAGE HRS 0.0 859.9 15270.0

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

Cycle 13 Refueling Outage scheduled to begin on Feb. 15, 1991, scheduled to end May 31, 1991.

27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP DATE: N/A i

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1619B/44

r .n AVERAGE DAILY POWER LEVEL NET HWe DOCKET #. . . . . . . . .50219 UNIT. . . . . . . . . . OYSTER CREEK #1 REPORT DATE . . . . . . . DECEMBER 3, 1990 COMPILED BY . . . . . . .HARI S. SHARMA TELEPHONE # . . . . . . .609-971-4638 MONTH NOVEMBER, 1990 DAY. M El.1 M

1. 627 16. 292

2. 627 17. 316

3. 610 18. 468

4. 400 19. 626

5. 427 20. 630

6. 425 21. 631

7. 428 22. 631

8. 424 23. 630

9. 426 24. 631

10. 386 25, 631

11. 388 26. 618

12. 422 27, 630 13, 420 28. 629

14. 280 29. 629

15. 290 30. 630 s

e 1619D/43

, .a Oyster Creek Station #1

.. Docket No. 50-219 i

REFUELING INFORMATION - NOVEMBER, 1990 Hame of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdowns February 15, 1991 Scheduled date for restart following refueling: May 31, 1991 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes Technical Specit'ication Change Request 180 was submitted to the NRC on 5-07-90. This submittal was made in accordance with GL 88-16 to incorporate cycle specific parametern in a core operating limita report. l l

Important licensing considerations associated with refueling, e.g., new or ditforent fuel design or supplier, unreviewed design or performance analysie j methods, significant' changes in fuel design, new operating procedures:

1. 09neral Electric Fuel Aeoemblien - fuel design and performance analysis methods have been approved by t.he NRC.

2. Exxon Fuel Assembtion - 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 = 1605 (c) in dry storage = 147 The prenent 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:

The reracking of the-fuel pool is now complete. All ten (10) racks are now . installed. . Discharge- capacity to the spent fuel . pool will be available until 1994 refueling outage.

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1 UNIT SHUTDOWNS AND POWER REDUCTIONS. j DOCKET NO. 50-219 UNIT NAME Oyster Creek DATE December, 1990 COMPLETED BY R. Baran TELEPHONE 971-4640 REPORT MONTE November, 1990 TYPE METHOD OF SHUTTING l F: Forced DURATION DOWN THE REACTOR OR l NO. DATE S: Scheduled (Hours) REASON (1) REDUCING POWER (2) CORRECTIVE ACTIONS / COMMENTS 101 901103 F 0 A 4 Reduced plant load to 380 MWe to remove *A* Feedwater String l from service d*? to pin hole leak on 'A' Feedwater Minimum Flow valve. I I

102 901113 S O A 4 Reduced plant load to 295 MWe due to ALARA concerns during the q NDE inspection of feedwater minimum flow lines in the condenser bay.

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Sum.ary :

(1) REASON METHOD

a. Equipment Failure (Explain) e. Operator Training & License Exam 1. Manual

b. Maintenance or Test f. Administ rative 2. Manual Scram

. c. Refueling g. Operatiottal Error (Explain) 3. Automatic Scram

d. Regulatory Restriction h. Other (Explain) 4. Other (Explain) q .N e

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