BECO-LTR-96-056, Monthly Operating Rept for May 1996 for Pilgrim Nuclear Power Station

Monthly Operating Rept for May 1996 for Pilgrim Nuclear Power Station

ML20112H073
Person / Time
Site:	Pilgrim
Issue date:	05/31/1996
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-96-056, BECO-LTR-96-56, NUDOCS 9606140323
Download: ML20112H073 (7)

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Boston Edison Pilgnrn Nuclear Power Staton Rocky Hill Road Plymouth. Massachusetts 02360 L J. Olivier -

Vice President Nuclear Operations June 12, 1996 and station Director BECo Ltr.#96 056 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 MAY 1996 MONTHLY REPORT in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. Should you have any questions conceming this report, please contact me directly, l

tVl r?& /5)h L. J. Olivier RLC/dmc/9458 l

Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector l

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140050 9606140323 960531 PDR ADOCK 05000293 R PDR

OPERATING DATA REPORT DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L.Cannoi ,

TELEPHONE: (508) 830-8321 REPORT MONTH May 1996 i OPERATING STATUS NOTES

1. Unit Name Pilgrim i

2. Reporting Period May 1996

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678

5. Design Electrical Rating (Net MWe) 655

6. Maximum Dependable Capacity (Gross MWe) 696

7. Maximum Dependable Capacity (Net MWe) 670

8. If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give Reasons:

No Chanaes I

9. Power Level To Which Restricted, If Any (Net MWe): None

10. Reasons For Restrictions, If Any: N/A This Month ,Yr-to-Date Cumulative

11. Hours in Reporting Period 744.0 3647.0 205799.0

12. Hours Reactor Critical 744.0 3532.5 129798.6

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 3513.9 125337.8

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0 l

16. Gross Thermal Energy Generated (MWH) 1485549.0 6851239.0 223153409.0 i

17. Gross Electrical Energv Generated (MWH) 507940.0 2357080.0 75634404.0 l

18. Net Electrica! Energy Generated (MWH) 489530.0 2272779_.0 72716401.0

19. Unit Service Factor 100.0 E6 4 60.S

20. Unit Availability Factor 100.0 96.4 60.9

21. Unit Capacity Factor (Using MDC Net) 98.2 93.0 52.7

22. Unit Capacity Factor (Using DER Net) 100.5 95.1 53.9

23. Unit Forced Outage Rate 0.0 0.0 11.7

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)- NONE PLANNED

25. If Shutdown at End of Report Period, Estimated Date of Startup - UNIT OPERATING j

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 NAME: Pilarim ,

COMPLETED BY: R.L. Cannon l TELEPHONE: (506) 830-8321 REPORT MONTH May 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 661 17 658 2 660 18 658 3 662 19 657 4 660 20 658  !

l 5 660 21 658 6 660 22 656 23 657 l 7 661 8 662 24 655 9 661 25 654 10 660 26 654 11 660 27 654 12 660 28 654 13 660 29 654

! 14 659 30 655 t

15 659 31 655

' 16 658

! This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed l to the nearest whole megawatt.

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OPERATIONAL

SUMMARY

l DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH May 1996 l The unit started the reporting period at 100 percent core thermal power (CTP) where it was maintained until tha end of the reporting period.

SAFETY RELIEF VALVE CHALLENGES MONTH OF MAY 1996 Requirement: NUREG-0737 T.A.P. II.K.3.3 Th:re were no safety relief valve challenges during the reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure signal (ADS) or control switch (manual). Reference BECo Ltr. #81-01 dated January 5,1981.

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I REFUELING INFORMATION DOCKET NO. 50-293 l NAME: Pilorim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH May 1996 Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dat:d January 18,1978:

For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.

1. The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.

2. Scheduled date for next refueling shutdown: February 1,1997.

3. Scheduled date for restart following next refueling: March 14,1997.

4. Due to their similarity, requests 4,5, & 6 are responded to collectively under #6.

5. See #6.

6. The new fuelloaded during the 1995 refueling outage (RFO-10)is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies.

7. (a) There are 580 fuel assemblies in the core.

(b) There are 1765 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 3859 spent fuel assemblies. The spent fuel storage capacity is 2891 fuel assemblies. However,23 spent fuellocations cannot be used due to refuel bridge limitations.

i (b) The planned spent fuel storage capacity is 3859 fuel assemblies. 1 1

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1103 fuel assemblies.

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PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE .

DOCKET NO. 50-293 .

NAME- Pdorim COMPLETED BY: R.L. Cannon

TELEPHONE: -(508) 830-8321 REPORT MONTH May 199E -

SYSTEM COMPONENT MALFUNCTION CAUSE- MAINTENANCE CORRECTIVE ASSOCIATED -

ACTION TO LER PREVENT RECURRENCE Salt Service "D Salt Service Decreasing total Decreasing pump Pump rebuilt. New N/A N/A- t Wtter Water Pump dynamic head. head due to normal bowl assembly pump wearin installed.

operation.

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UNIT SHUTDOWNS AND POWER REDUCTIONS '.

DOCKET NO. 50-293 NAME- Pilorim COMPLETED BY: R. L Cannon TELEPHONE- (508) 830-8321-

- REPORT MONTH May 1996.

METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT l NO. DATE 1 (HOURS) 2 REACTOR REPORT 4 5 RECURRENCE Ther0 were no unit shutdowns or significant power reductions during the reporting period.

1 2 3 4&5

, F-Forced A-Equip Failure 1-Manual Exhibit F & H S-Sched B-Main or Test 2-Manual Scram instructions for  !

. C-Refueling 3-Auto Scram Preparations of D-Regulatory Restriction 4-Continued Data Entry Sheet ,

E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-1022)

F-Admin G-Operator Error H-Other

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