ML20071H462

Monthly Operating Rept for June 1994 for Pilgrim Nuclear Power Station

ML20071H462
Person / Time
Site:	Pilgrim
Issue date:	06/30/1994
From:	Munro W, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-078, 94-78, NUDOCS 9407150177
Download: ML20071H462 (7)

Text

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Tech. Spec. 6.9.A.2 G

Boston Edison Pilgon Nuclear Power Station Rocky Hdt Road Plymouth, Massachusetts 02360 L. J. Olivier Vice President Nuclear Operations Julv 14 , 1994 and station Director BECo atr. #94- 078 l

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 JUNE 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.

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y J. Olivier WJM/ lam /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 9407150177 940630 p i PDR ADOCK 05000293 ,

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. OPERATING DATA REPORT DOCKET NO. 50-293 l DATE July 14, 1994  ;

COMPLETED BY: W. Munro i TELEPHONE (508) 830-8474

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OPERATING STATUS NOTES

1. Unit Name Pilgrim I

2. Reporting Period May 1994

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 12H

5. Design Electrical Rating (Net MWe) HEE

6. Maximum Dependable Capacity (Gross MWe) HRH

7. Maximum Dependable Capacity (Net MWe) 510

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 720._Q 4343.0 118975.0

12. Hours Reactor Critical 720.0 4050.0 116991.5

13. Hours Reactor Reserve Shutdown 0.0 Q1H 0.0

14. Hours Generator On-Line 720.0 3930.8 112719.8

15. Hours Unit Reserve Shutdown Em0 0.0 2Q

16. Gross Thermal Energy Generated MWH) 1419936.0 7453368.0 198606312.0

17. Gross Electrical Energy Generated (MWH)487010.0 2556260.0 67202194.H .

18. Net Electrical Energy Generated (MWH) 468820.0 2460133.0 64593827.0

19. Unit Service Factor 100.0 90.5 59.,6

20. Unit Availability Factor 100.0 90,5 59.6

21. Unit Capacity Factor (Using MDC Net) 97.2 84,5 51.0

22. Unit Capacity Factor (Using DER Net) 99.4 86.5 52.2  ;

23. Unit Forced Outage Rate R20 4.6 11,6

24. Shutdowns scheduled over next 6 months (type, date, and duration of each) - MCO-10 October (30 Days)

25. If shutdown at end of report period, estimated date of startup - UNIT OPERATING .

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AVERAGE DAILY UNIT POWER LEVEL I l

DOCKET NO. 50-293 '

DATE: July 14, 1994 f

COMPLETED BY: W. Munro TELEPHONE: (508) 830-8474 MONTH June 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 661 17 659 2 660 18 661 3 660 19 525 4 658 20 660 5 659 21 660 6 660 22 661 7 662 23 660 8 660 24 658 9 660 25 659 10 558 26 660 11 659 27 630 12 660 28 662 13 660 29 661 14 662 30 661 15 661 16 659 i

I This format lists the average daily unit power level in MWe-Net for each l day in the reporting month, computed to the nearest whole megawatt. l 1

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 OPERATIONAL

SUMMARY

FOR JUNE 1994 The unit started the reporting period at approximately 100 percent core thermal power (CTP). This power level was essentially maintained until  ;

June 10, 1994. At 1054 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.01047e-4 months <br /> cr June 10, 1994, the "A" Recirculation Pump 1 Motor Generator (MG) Set tripped, and power was reduced to approximately 41 percent CTP at 1141 hours0.0132 days <br />0.317 hours <br />0.00189 weeks <br />4.341505e-4 months <br />. At 1432 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.44876e-4 months <br />, following troubleshooting, the "A" Recirculation Pump MG Set was restarted and reactor power was increased. AT 1914 hours0.0222 days <br />0.532 hours <br />0.00316 weeks <br />7.28277e-4 months <br />, 100 percent power was attained, and was essentially maintained until June 19, 1994, when power was reduced to j approximately 47 percent CTP to facilitate a planned thermal backwash of the main condenser. Following completion of the backwash, power was increased to 100 percent CTP at approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> where it was essentially maintained until June 27, 1994. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on June 27, 1994, power was reduced to approximately 73 percent CTP due to a malfunction of the "A" 3rd Point Feedwater Heater Level Control]er.

Following maintenance to restore the feedwater heater to service, power was increased, reaching 100 percent CTP at approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, where it was maintained for the remainder of the reporting period.

SAFETY RELIEF VALVE CHALLENGES MONTH OF JUNE 1994 Requirement: NUREG-0737 T.A.P. II.K.3.3 l

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).

Reference BECo Ltr. #81-01 dated January 5, 1981.

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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  !

Number 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 lc Jied 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.

03) There are 1629 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 3859 spent fuel assemblies. The actual usable spent fuel storage capacity is 2320 fuel assemblies.

03) 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 691 fuel assemblies.

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MONTH JUNE 1994 . .

f PILGRIM N'JCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE -

CORRECTIVE ACTION TO ASSOC SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER Salt Service SSW Pump Degraded Age related Replaced P-208A None N/A Water (SSW) P-208A Motor performance degradation motor with new ,

System motor of improved design. (Mfr.

Reliance Electric)

Balanced motor and pump per Procedure 3.M.1-15 r -

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-y UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-293 DOCKET NO: 50-293 '.

NAME: Pilgrim I DATE: July 14, 1994 COMPLETED BY: W. Munro TELEPHONE: (508) 830-8474 REPORT MONTH: June 1994 l 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

• 7 6/19/94 S 0.0 B N/A N/A N/A N/A Power reduction to facilitate a thermal i backwash of the main condenser i

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 l C-Refueling 3-Auto Scram Preparations of  ;

D-Regulatory Restriction 4-Continued Data Entry Sheet i E-Operator Training 5-Reduced Load Licensee Event Report l

& License Examination 9-Other (LER) File (NUREG-1022)

F-Admin  :

G-Operator Error H-Other o

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