BECO-LTR-96-004, Monthly Operating Rept for Dec 1995 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Dec 1995 for Pilgrim Nuclear Power Station

ML20096C273
Person / Time
Site:	Pilgrim
Issue date:	12/31/1995
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-96-004, BECO-LTR-96-4, NUDOCS 9601170198
Download: ML20096C273 (7)

Text

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Tech. Spic. 6.9.A.2

. O Boston Edison Filgrirn Nuclear Power Station Rocky Hill Road Plymouth. Massachusetts 02360 i

L J. Olivler Vice President Nuclear operations January 12, 1996 l and station oirector BECo Ltr. #96-004 I

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U.S. Nuclear Regulatory Commission Attention: Document Control Desk l

Washington, DC 20555 i

Docket No. 50-293 License No. DPR-35 l l

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DECEMBER 1995 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 concerning this report please contact me directly. I e ->

L.J. Olivier l RLC/nas/9458 Attachment l 1

cc: Mr. Thomas T. Martin l Regional Administrator, Region I ,

U.S. Nuclear Regulatory Commission  !

475 Allendale Road l King of Prussia, PA 19406 l Senior Resident inspector i

9601170198 DR 951231 ADOCK 05000293 PDR 170 0 rs Y

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, e OPERATING DATA REPORT

• * . DOCKET NO. 50-293 NAME: Pilarim DATE: January 12.1996 COMPLETED BY: R.L. Cannon TELEPFONE: (508)830-8321 REPORT MONTH December.1995 OPERATING STATUS NOTES

1. Unit Name Pilgrim i

2. Reporting Period December 1995

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,

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 1

11. Hours in Reporting Period 744.0 8760.0 202152.0

12. Hours Reactor Critical 744.0 7066.0 126266.1

13. Hour Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 6962.8 121823.9

15. Hours Unit Reserve Snutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1472498.0 13546954.0 2163C2170.0

17. Gross Electrical Energy Generated (MWH) 510310.0 4657650.0 73277324.0

18. Net Electrical Energy Generated (MWH) 492451.0 4485845.0 70443622.0

19. Unit Service Factor 100.0 79.5 60.3

20. Unit Availability Factor 100.0 79.5 60.3 2'i . Unit Capacity Factor (Using MDC Net) 98.8 76.4 52.0

22. Unit Capacity Factor (Using DER Net) 101.1 78.2 53.2

23. Unit Forced Outage Rate 0.0 3.6 12.0

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

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

0 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 i NAME. Pilarim DATE: January 12.1996 COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321

> REPORT MONTH December.1995 4 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) l 1 668 17 668 1-l 2 668 18 668 3 668 19 667 4 668 20 667 i

5 667 21 667 j 6 668 22 669 7 669 23 669 <

< 8 668 24 668 9 667 25 669

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, 10 482 26 668 i

l ~11 668 27 669 i

12 668 28 G69 4

13 669 29 668 14 668 30 369 15 661 31 669  ;

16 669 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: January 12.1996 .

COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH December.1995 l l

The unit started the reporting period at 100 percent core thermal power (CTP) where it was maintained until l 0136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br /> on December 10,1995, when reactor power was reduced to 50% CTP to perform a thermal I backwash of the main condenser. Following the backwash, reactor power was increased and the unit i obtained 100 percent CTP power at 2320 on December 10,1995, where it was maintained for the remainder of the reporting period. 1 l

SAFETY RELIEF VALVE CHALLENGES l l

MONTH OF DECEMBER 1995 l

, 1 Requirement: NUREG-0737 T.A.P. (i K.3.3 l

There were no safety relief valve challenges during the reporting period. 1 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: January 12.1996 COMPLETED BY: R.L. Cannon TELEPHONE: (508)830-8321 REPORT MONTH December.1995 The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated 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 fuel locations cannot be used due to refuel bridge limitations.

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

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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

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DOCKET NO. 50-293 -

NAME- Pilarim _

DATE: January 12.1996 COMPLETED BY: R.L.Cann'on TELEPHONE: (508) 830-8321 REPORT MONTH December.1995 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT r RECURRENCE Sta Water Monitoring Traveling screens The original Plant Design New bubbler tubes, new None and Salt Instrumentation clogged with monitoring system Change 94-31A transmitters, and a new S rvice Water seaweed, etc., provided minimal implemented to panelwere installed in '

Systems causing water monitoring of install new the Screenhouse to levels in the sea parameterin the instrumentation provide localindication of water and salt Screenhouse. Cape Code Bay level, service water bays Sea Water Bay levels, to lower to below Salt Service Water Bay normal levels. levels, and Traveling  :

Screen differential levels.

In addition, an Emergency Plant Information Computer (EPIC) graphic was  !

created to display all  !

parameters on EPIC terminals.

No major safety related maintenance was completed during this reporting period. ,

UNIT SHUTDOWNS AND POWER REDUCTIONS ,

DOCKET NO. 50-293 .

NAME: Pilorim DATE- January 12.1996 COMPLETED BY: R.L. Cannon-TELEPHONE: ~ (508) 830-8321 REPORT MONTH December.1995 METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO. DATE 1 (HOURS) 2 REACTOR REPORT 4 5 RECURRENCE 10 12/10/95 S 0.0 H N/A N/A N/A N/A Power Redu:: tion to facilitate -

a backwash of the main condenser Thtre were no unit shutdowns 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 I

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