ML20073R935

Monthly Operating Rept for Jan 1994 for Pilgrim Nuclear Power Station

ML20073R935
Person / Time
Site:	Pilgrim
Issue date:	01/31/1994
From:	Kraft E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-018, 94-18, NUDOCS 9402160001
Download: ML20073R935 (8)

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g BOSTON EDISON i Pdgrim Nuclear Power Station ,

Rocky Hill Road J l

Plymouth, Massachusetts 02360 E. S. Kraft, Jr.  !

.%ce President Nuclear Operations '

cnd Station Director February 11, 1994 i

I BEco Ltr. #94-018 ,

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

Washington, DC 20555 License No. DPR-35 Docket No. 50-293 l

JANUARY 1994 MONTHLY REPORI In accordance with PNPS 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.

N E. S. Kr - JH

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WJfi/dmc/9407 Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region I U.S. Nuclear Regulstory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector t

l 1 Gn0: 1. f 9402160001 940131 J t PDR- ADOCK 05000293 1

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OPERATING DATA REPORT DOCKET NO. 50-293 DATE February 11, 1994 l

COMPLETED BY: W. Munro TELEPHONE 1108) 830-8474 OPERATING STATUS l NOTES l

! 1. Unit Name Pilgrim I

( 2. Reporting Period January 1994

( 3. Licensed Thermal Power (MWt) 1998 l 4. Nameplate Rating (Gross MWe) 128 l 5. Design Electrical Rating (Net MWe) ill

6. Maximun Dependable Capacity (Gross MWe) 121 l 7. Maximura Dependable Capacity (Net MWe) 121 '

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

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

10. Reasons For Restrictions, If Any: N /A l

l This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 744.0 185376.0

12. Number of Hours Reactor Was Critical 744.0 744.0 113685.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 744.0 109533.0 >

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1478496.0 1478496.0 192623232.0

17. Gross Electrical Energy Generated (MWH) 511480.0 511480.0 65157414.0

18. Net Electrical Energy Generated (MWH) 492681.0 492681.0 62626375.0

19. Unit Service Factor 100.0 100.0 59.1

20. Unit Availability Factor 100.0 100.0 59.1

31. Unit Capacity Factor (Using MDC Net) 98.8 98.8 50.4

22. Unit Capacity Factor (Using DER Net) 101.1 101.1 51.6

23. Unit Forced Outage Rate 0.0 0.0 11.7

24. Snutdowns scheduled over next 6 months (type, date, and duration of each) - None

25. If shutdown at end of report period, estimated date of startup - Unit operating

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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 DATE February ll, 1994 CO.MPLETED BY: W. Munro TELEPHONE (508) 830-8474 MONTH January 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net) 1 665 17 666 2 667 18 666 3 665 19 667 4 666 20 667 5 665 21 667 6 664 22 667 7 663 23 668 8 601 24 667 9 620 25 667 10 665 26 666 11 663 27 665 12 665 28 665 13 666 29 667 14 665 30 666 15 666 31 666 16 665 j 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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BOSTON EDISON COMPANY ,

l PILGRIM NUCLEAR POWER STATION l DOCKET NO. 50-293 .

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OPERATIONAL

SUMMARY

FOR JANUARY 1994 l 1 i

The unit started the reporting period at 100 percent core thermal power (CTP) and this  :

power level was essentially maintained for the entire reporting period. There was a brief power reduction on January 8, 1994 to approximately 47 percent to facilitate a main l condenner backwash. I t -

i SAFETY RELIEF VALVE CHALLENGES MONTH OF JANUARY 1994 l

Requirement: NUREG-0737 T.A.P. II.K.3.3 j There were no safety relief valve challenges during the reporting period. f

An SRV challenge is defined as anytime an SRV has received a signM to operate via reactor

! pressure, auto signal (ADS) or control switch (manual). Ref. BECo ltr. #81-01 date 01/05/81.

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, REFUELING INFORMATION 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 Pumber 50-293.

2. Scheduled date for next refueling shutdown: April 1, 1995

3. Scheduled date for restart following next refueling: May 26, 1995

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 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 2320 spent fuel assemblies. The actual usable spent fuel storage capacity is 2320 fuel assemblies.

(b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9.

With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 691 fuel assemblies.

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NONTH JANUARY 1994 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE -

SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED TO PREVENT LER RECURRENCE DIESEL "B" EMERGENCY FAILED TURBO AIR ASSIST DISASSEMBLED TO BE DETERMINED. N/A GENERATORS AND DIESEL SURVEILLANCE SOLENOID VALVES SOLENOID AUXILIARIES GENERATOR ACCEPTANCE SV4570B AND SV4569B VALVES, CLEANED X-107B. CRITERIA FAILED IN CLOSED AND (PR94.9033) CONCERNING POSITION DUE TO REASSEMBLED.

STARTING TIME. MOISTURE RESIDUE IN PERFORMED PROCEDURE 8.9.1 THE VALVES. PROCEDURE 8.9.1 SATISFACTORILY.

SALT SERVICE "A' SSW PUMP CHECK VALVE ROOT CAUSE UNDER DISASSEMBLED WHEN REMAINING SSW N/A WATER (SSW) P-208A FAILED IN THE INVESTIGATION VALVE. CHECK VALVES ARE SYSTEM DISCHARGE CLOSED POSITION INSPECTED VALVE DISASSEMBLED, CHECK VALVE AND INTERNALS. COPPER GASFETS 29-CK-3880A REPLACED WILL BE REPLACED (PR94.9023) LEAKING HINGE WITH GRAPHITE PIN COPPER GASKETS.

GASKETS (4)

WITH GRAPHITE GASKETS.

(DCN 94-89723)

POST WORK TESTING COMPLETED SATISFAC'IORILY.

STANDBY LIQUID "A" AND "B" PUMPS LEAKING WORN PACKING REMOVED AND NONE. N/A CONTROL (SBLC) SBLC PUMPS REPLACED SYSTEM P-207A AND B EXISTING PACKING ON BOTH PUMPS WITH CHEVRON TYPE PACKING PER FRN 93-03-77.

DRAINED AND REPLACED OIL, AND CHANGED OUT

, CRANKCASE COVER GASKET. THE THREE PLUNGERS 2 IN PUMP P-207A WERE REPLACED (THEY WERE SLIGHTLY PITTED AND CORRODED).

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-293 DOCKET NO: 50-293 NAME: Pilorim I DATE: February 11, 1994 COMPLETED BY: W. biunro TELEPHONE : (508 ) 830-8474 REFORT MONTH JANUARY. 1994 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENT NO. DATE TYPE (HOURS) REASON DOWN REACTOR REPORT # CODE CODE RECURRENCE 1 2 3 4 5 There were no Unit Shutdowns or reportable Power Reductions during the reporting period.

1 2 2 3 4&S F-FORCED A-Equip Failure F-Admin 1-Manual Exhibit F & H S-SCHED B-Main or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparations of i 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)

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