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Monthly Operating Rept for Mar 1994 for Pilgrim Nuclear Power Station
	ML20065J010
Person / Time
Site:	Pilgrim
Issue date:	03/31/1994
From:	Boulette E, Munro W; BOSTON EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	94-041, 94-41, NUDOCS 9404150255
	Download: ML20065J010 (8)
	v • d • e

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J BOSTON EDISON Pilgnm Nuclear Power Station

. Rocky Hill Road Plymouth, Massachusetts 02360 E. T. Boulette, PhD Senior Vice President-Nuclear April 14, 1994 BECo Ltr. #94-041 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 MARCH 1994 MONTHLY REPORT 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.

A E. T. Boulette PhD WJM/dmc/9447 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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eononr, 9404150255 940331 PDR ADOCK 05000293

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j . , OPERATING DATA REPORT l

I DOCKET NO. 50-293 _,.

DATE April 14, 1ss4 COMPLETED BY: W. Munro TELEPHONE (508) 830-8474 OPERATING STATUS NOTES

1. Unit Name Pilgrim I

2. Reporting Period March 1994 l 3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678 I

5. Design Electrical Rating (Net MWe) 111

6. Maximum Dependable Capacity (Gross MWe) 121

7. Maximum Dependable Capacity (Net MWe) 122

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

11. Hours In Reporting Period 744.0 2160.0 186792.0

12. Number of Hours Reactor Was Critical 671.8 2006.2 114947.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 i

14. Hours Generator On-Line 639.0 1916.9 110705.9

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1204200.0 3668760.0 194813496.0

17. Gross Electrical Energy Generated (MWH) 411640.0 1262170.0 65908104.0

18. Net Electrical Energy Generated (MWH) 396128.0 1215101.0 _fl348795.0

19. Unit Service Factor 85.9 88.7 59.3

20. Unit Availability Factor 85.9 88.7 59.3

21. Unit Capacity Factor (Using MDC Net) 79.5 84.0 50.6

22. Unit Capacity Factor (Using DER Net) 81.3 85,9 51.8 -

23. Unit Forced Outage Rate 3.3 1.1 l'1. 7

24. Shutdowns 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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, AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 l DATE: April 14, 1994 COMPLETED BY: W. Munro TELEPHONE: (508)'830-8474 NOifn! March 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l l (MWe-Net) (MWe-Net) 1 l

l 1 0 17 664 l

2 0 18 664 3 0 19 664 1

108 20 664 4

5 532 21 664 6 663 22 663 7 666 23 664 8 666 24 664 l 9 664 25 664 10 664 26 663 11 291 27 663 12 124 28 664 13 182 29 663 14 663 30 664 15 664 31 664 j 16 664 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 PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 j

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OPERATIONAL

SUMMARY

FOR MARCH 1994 j The unit started the reporting period in cold shutdown condition to complete the scheduled outage activities which were originated on February 23, 1994. On March 4, 1994 at 0012 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months the reactor was made critical and the unit was synchronized to the grid at 1057 hours0.0122 days 0.294 hours 0.00175 weeks 4.021885e-4 months . Reactor power was increased and at 1007 hours0.0117 days 0.28 hours 0.00167 weeks 3.831635e-4 months on March 5, 1994, the unit attained 100 percent core thermal power (CTP), where it was essentially maintained until March 11, 1994. On March 11, 1994 reactor power was reduced to approximately 45 percent CTP to facilitate maintenance on the Augmented Offgas System. On March 12, 1994, reactor power was further reduced to approximately 10 percent CTP, and the main generator was taken off-line to perform a leak repair on the stator cooling system. Following the repair, the main generator was synchronized to the grid at 1055 hours0.0122 days 0.293 hours 0.00174 weeks 4.014275e-4 months on March 13, 1994. Reactor power was increased and the unit attained 100 percent CTP at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on March 13, 1994, where it was essentially maintained throughout the end of the reporting period.

SAFE'IT RELIEF VALVE CHALLENGES MONTH OF MARCH 1994 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, 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. !

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

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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.

MOEqTH MARCH 1994 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED TO PREVENT LER RECURRENCE TURBINE , STATOR COOLING CRACKED WELD INCORRECT PARTS NEEDED TO DURING RFO-10 A N/A GENERATOR AND PPESSURE TAP CAUSING INSTALLATION OF PROPERLY INSTALL NEW PRESSUPE TAP AUXILIARIES FOR VALVE Y-37 PRESSURE TAP TO THE PRESSURE TAP NEW PRESSURE TAP WILL BE INSTALLED SYSTEM

AND PRESSURE LEAK. FOR Y-37 AND WERE NOT USING A SOCKET GAUGE YGA-11. (PR94.9110) YGA-11 DURING AVAILABLE. WELD FITTING.

INITIAL TEMPORARY GAUGE YGA-11 WILL CONSTRUCTION. MODIFICATION BE REPLACED WITH A 94-07 WAS SMALLER GAUGE TO IMPLEMENTED TO REDUCE STRESS ON REMOVE THE THE WELD.

PRESSURE TAP, (MR 19400698).

VALVE AND GAUGE.

A PATCH WAS WELDED OVER THE REMAINING HOLE .

HIGH PPESSURE HPCI MOTOR VALVE FAILED ANALYSIS OF THE ELECTRICAL INSTALLATION OF A LER COOLANT OPERATED MONTHLY FAILED PIN FOUND MAINTENANCE NEW SPRING PACK 94-002-00 INSPECTION INJECTION SURVEILLANCE IT TO BE LESS THAN PERSONNEL PESISTAh7 TO (HPCI) SYSTEM. VALVE OPERABILIT'I OPTIMUM DESIGN. IMPLEMENTED GREASE BUILDUP, MO-2301-09 TEST DUE TO CONTRIBUTING CAUSE TEMPORARY AhT REPLACEMENT OF FAILURE OF THE INCLUDED HARDENED MODIFICATION THE TORQUE SWITCH VALVE MOTOR GREASE IN THE 94-05 TO PERMIT WITH ONE OF AN OPERATOR MOTOR OPERATOR MO-2301-09 TO BE IMPROVED DESIGN (LIMITORQUE) SPRING PACK. MAINTAINED IN PRIOR TO RETURNING TORQUE SWITCH THE OPEN THE VALVE TO DRIVE PINION POSITION. HPCI SERVICE.

GEAR ROLL PIN. SYSTEM WAS HPCI DECLARED SUCCESSFULLY INOPERABLE. TESTED AND WAS (PR94.9104) DECLARED OPERABLE.

O NOT SAFETY RELATED BUT CAUSED SIGNIFICANT ECONOMIC IMPACT.

3.. . m. . . _ . . _ _ . . . . . .. _ . . ~ . . . - _ . ~ . _ . . _ _ _ _ _ . - . . - _ - - ., ._m.-= . . . . . . ~..-.-- _ _. _ .._ _ _._ . _

a f MONTH MARCH 1994 PIIGRIM NUCLEAR POWER STATION. MAJOR SAFETY RELATED MAINTENANCE _ , ,

CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED ,

SYSTEM COMPONENT ' MALFUNCTION TO PREVENT LER

- RECURRENCE MCTIOR OPERATED INABILITY TO LIMIT SWITCH OUT' ADJUSTED LIMIT PERFORMANCE _OF N/A REACTOR WATER PREVENTIVE-VALVE OPEN VALVE FROM OF ADJUSTMENT. SWITCH 'IO CLEANUP-(RWCU) MAINTENANCE /

~MO-1201-80 THE CONTROL ACHIEVE PROPER SYSTEM SURVEILLANCE RETURN ROOM. . GAP BETWEEN

~ L-BRACKET AND ' PROGRAM.

ISOLATION VALVE. CONTACT FINGER

5 IN-ACCORDANCE WITH 4 PROCEDURE 8.Q.3-8.

PERFORMED POST WORK TEST PER

' PROCEDURE 8.6.5.2.

SUCCESSFULLY.

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

Pilcrim I* .-

NAME:

DATE: April 14. 1994 COMPLETED BY: W. Munro ,

TELEPHONE: (508) 830-8474 REPORT MONTH MARCH 1994 LICENSE CAUSE & CORPECTIVE METHOD OF EVENT SYSTEM COMPONEUT ACTION TO PREVENT DURATION SHUTTING REPORT # CODE CODE RECURRENCE TYPE (HOURS) REASON DOWN REACTOR NO. DATE 4 5 1 2 3 1 N/A N/A N/A Continuation of 3-04-94 5 82.9 B 1 Main Steam Isolation Valve Maintenance Outage.

N/A N/A Reduced power to F 0.0 B - N/A 2 3-11-94 perform maintenance on Augmented Offgas System.

N/A N/A N/A Main Turbine 3-12-94 F 22.1 B -

3 Generator was taken off line to repair leak on Stator Cooling System.

3 4&S 2 2 1

4 F-Admin 1-Manual Exhibit F&H F-FORCED A-Equip Failure Instructions for G-Oper Error 2-Manual Scram S-SCHED B-Main or Test Preparations of C-Refueling H-Other 3-Auto Scram 4-Continued Data Entry Sheet D-Regulatory Restriction Licensee Event Report E-Operator Training 5-Reduced Load 9-Other (LER) File (NUREG-1022)

& License Examination

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ML20065J010

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SUMMARY

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