BECO-LTR-96-034, Monthly Operating Rept for Mar 1996 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Mar 1996 for Pilgrim Nuclear Power Station

ML20101Q930
Person / Time
Site:	Pilgrim
Issue date:	03/31/1996
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-96-034, BECO-LTR-96-34, NUDOCS 9604150339
Download: ML20101Q930 (7)

Text

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, Tech. SpGc. 6.9.A.2 Boston Edison Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 L J. Olivier Vice President luclear operat;ons April 11, 1996 and station u rector BECo Ltr. #96-034 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 MARCH 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. . Olivier RLC/dmc/9458 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 i

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l 9604150339 960331 PDR ADOCK 05000293 '

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. . OPERATING DATA REPORT .

DOCKET NO. 50-293 1 NAME: Pilorim DATE: .A_pril 11.1996 COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH March.1996 OPERATING STATUS NOTES

1. Unit Name Pilgrim 1

2. Reporting Period -

March 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. Maximurn Dependable Capacity (Net MWe) 670

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

No Chages 4

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 2184.0 204336.0

12. Hours Reactor Critical 744.0 2184.0 128450.1

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 2184.0 124007.9

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0 ~

. 16. Gross Thermal Energy Generated (MWH) 1486057.0 4258685.0 220560855.0

17. Gross Electrical Energy Generated (MWH) 512900.0 1469740.0 74747064.0

18. Net Electrical Energy Generated (MWH) 494961.0 1417614.0 71861236.0

19. Unit Service Factor 100.0 100.0 60.7

20. Unit Availability Factor 100.0 100.0 60.7

21. Unit Capacity Factor (Using MDC Net) 99.3 96.9 52.5

22. Unit Capacity Factor (Using DER Net) 101.6 99.1 53.7

23. Unit Forced Outage Rate 0.0 0.0 11.8

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)- PLANNED MAINTENANCE. OUTAGE, APRIL 19,1996 FOR APPROXIMATELY SEVEN DAYS.

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

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 NAME: Pilarim DATE: April 11.1996 COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH March 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 666 17 665 2 665 18 666 3 666 19 665 4 666 20 666 5 666 21 665 6 666 22 665

, 7 665 23 665 3

8 665 24 665

9 666 25 666 10 665 26 665 l- 11 665 27 665 12 665 28 665 13 666 29 665 14 664 30 664 15 665 31 664 16 666 This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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. OPERATIONAL

SUMMARY

DOCKET NO. 50-293

, NAME: Pilarim DATE: April 11.1996 COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH March.1996 i

Th3 unit started the reporting period at 100 percent core thermal power (CTP) where it was maintained until th] end of the reporting period.

SAFETY RELIEF VALVE CHALLENGES

. MONTH OF MARCH 1996 4

Raquirement: 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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, REFUELING INFORMATION DOCKET NO. 50-293 NAME: Pilarim DATE: April 11.1996 COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH March.1996 .

Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo,-

. d:t: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 fuel loaded during the 1995 refueling cutage (RFO-10) is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies. i

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 fuel locations cannot be used due to

, refuel bridge liraitations. >

(b) The planned spent fuel storage capacity is 3859 fuel assemblies, 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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,8 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE .

DOCKET NO.~ 50-293 -

NAME. Pilorim ' -

DATE. April 11.1996 -

COMPLETED BY: R.L. Cannon *'

TELEPHONE- (508) 830-83_2_1 REPORT MONTH March.1996 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER I. PREVENT RECURRENCE l

N3 major safety related maintenance was completed during this reporting period.

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-a UNIT SHUTDOWNS AND POWER REDUCTIONS s.

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DOCKET NO.' '50 293 -

NAME:. Pilorim - -

DATE:. April 11.- 1996 *-

COMPLETED BY: R. L. Cannon * *

- TELEPHONE- - _ (508) 830-8321- i REPORT MONTH March.1996 i:

METHOD OF LICENSE. SYSTEM COMPONENT CAUSE & CORRECTIVE TYFE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO. DATE 1 (HOURS) 2 REACTOR REPORT 4- 5 RECURRENCE' >

V There were no unit shutdowns or significant power reductions during the reporting period. ,

1- 2 3 4&S'

~ 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 i

& License Examination 9-Other (LER) File (NUREG-1022) -i F-Admin i G-Operator Error H-Other e t

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