ML20078P133

Monthly Operating Rept for Jan 1995 for Pilgrim Nuclear Power Station

ML20078P133
Person / Time
Site:	Pilgrim
Issue date:	01/31/1995
From:	Munro W, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-021, 95-21, NUDOCS 9502160278
Download: ML20078P133 (7)

Text

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., Tech. Sp;c. 6.9.A.2

, h Boston Edison Pdgrim Nuclear Power Station Rocky Hill Road Plyrnouth. Massachusetts 02360 L. J. Olivier vice President Nuclear Operations February 14 1995 l and station oirector BECo Ltr. #95-021 l U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPk_.35 l

l JANUARY 1905 MONTHLY REPORT in accordance with PNPS Technical S1ecification 6.9 A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Stction is ateched for your information and planning. Should you have any questions conceming this report please contact me directly.

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. Olivier WJM/ lam /9458 l l

Attachment cc: Mr. Thomas T. Martin ,

Regional Administrator, Region l l U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident inspector r

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9502160278 950131 PDR ADOCK 05000293 R PDR

CPERATING DATA REPORT DOCKET NO. 50-293 DATE COMPLETED BY: W. Munro TELEPHONE (508) 830-8474 i

CprS3 TING STATUS NOTES

1. UrCName Pilgrim i

2. Reporting Period January 1995 ,

3. Licensed Thermal Power (MWt) 1998 i

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 MW2) 670

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

NONE

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 744.0 744.0 194136.0

12. Hours Reactor Cntical 744.0 744.0 119974.1 l

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 744.0 115605.1

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1485600.0 1485600.0 204240816.0

17. Gross Electrical Energy Generated (MWH) 513420.0 513420.0 69133094.0

18. Net Electrical Energy Generated (MWH) 494219.0 494219.0 66451996.0 l

19. Unit Service Factor 100.0 100.0 59.6

20. Unit Availability Factor 100.0 100.J 59.6

21. Unit Capacity Factor (Using MDC Net) 99.1 99.1 51.1

22. Unit Capacity Factor (Using DER Net) 101.4 101.4 52.3

23. Unit Forced Outage Rate 0.0 0.0 12.4

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each) RFO-10, March 25,1995 for 55 days

25. If Shutdown at End of Report Period, Estimated Date of Startup - Unit Operating l

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

COMPLETED BY: W. Munro TELEPHONE: (508) 830-3474 l

MONTH January 1995  ;

i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net) 1 664 17 664 2 664 18 663 3 665 19 664  ;

4 664 20 664 5 665 21 664  !

6 664 22 664 .

I 7 665 23 664 f

8 665 24 664 -

9 665 25 664 10 685 26 664 11 665 27 664 12 66S 28 664 13 665 29 663 14 664 30 664 ,

t 15 664 31 665 I 16 664 i f

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. j

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION

. DOCKET NO. 50-293 OPERATIONAL

SUMMARY

FOR JANUARY 1995 The unit started the reporting period at approximately 100 percent Core Thermal power and essentially maintained this level for the entire reporting period.

SAFETY RELIEF VALVE CHALLENGES MONTH OF JANUARY 1995 Requirement: NUREG-0737 T.A.P. II.K.3.3 There 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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. REFdELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo,  ;

d"ted January 18,1978:

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

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

2. Scheduled date for next refueling shutdown: March 25,1995.

3. Scheduled date for restart following next refueling: May 19,1995. i

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

5. See #6.

6. The new fuelloaded during the 1993 refueling outage was of the same design as loaded in the >

previous refueling outage and consisted of 140 assemblies.

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

(b) There are 1629 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 2878 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.

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1226 fuel assemblies. ,

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MONTH JANUARY 1995 s

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER Primary Differential During Root cause was installation of a plug Maintenance personnel 94-O'07-00 Containment Pressure performance of utility non-licensed for the Differential received directions from System

• Transmitter Procedure l&C Technician, Pressure the Maintenance Manager (PTD-5021) 8.M.2-6.2 primary Supervisor and Transmitter the Plant manager and the containment Nuclear Watch PTD-5021 Site Director regarding the pressure Engineer (NWE) requirements for procedure boundary was error. Inattention to signoffs and verifications.

degraded due to detail by the l&C The NWE received an uninstalled Technician who directions from the plug on performed and the Operations Section Differential Supervisor and Manager, Plant Manager, Pressure NWE who reviewed and the Site Director Transmitter the previous regarding his PTD-5021 calibration of the responsibilities for sign-off transmitter on of procedures. Refer to November 22,1994 associated LER for additional details Reactor Core Oil temperature Broken wire Undetermined Broken wire To be determined N/A Isolation Cooling switch TS-1300-10 discovered during replaced (RCIC) System system walkdown Containment Solenoid valve Actuation of the Loose fuse in the Fuse clip tension Refer to associated LER 95-001-00 Vccuum Relief SV-5040B fuse. reactor-to-torus control circuit of was increased and Syst::m train "B" Vacuum Solenoid Valve new fuse installed Relief System SV-5040B while operating at 100 percent power

• Ev nt was discovered December 28,1994; LER sent out 1/27/95

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-293 -

• DOCKET NO: 50-293 NAME: Pilarim i DATE: .

COMPLETED BY: W. Munro . '

7 TELEPHONE: (508) 830-8474 ~

REPORT MONTH: January 1995 METHOD OF LICENSE SYSTEM COMPONEN CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE ACTION TO PREVENT NO. DATE 1 (HOURS) 2 REACTOR REPORT 4 CODE RECURRENCE-5 Th:re were no unit shutdowns or significant power reductions to report 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 L__--_____.___--__.-._-- _ - -- _. . - _ . - - - - - - - . . - -- - _. - - - .

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