ML20117E096

Monthly Operating Rept for Apr 1996 for Pilgrim Nuclear Power Station

ML20117E096
Person / Time
Site:	Pilgrim
Issue date:	04/30/1996
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9605150416
Download: ML20117E096 (5)

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Tech. Sp:c. 6.9.A.2 h

Boston Edison Pilgrim Nuclear Power Staten -

Rocky Hill Road Plymouth, Massachusetts 02360 i

l l L J. Olivier L

Vice President Nuclear operations May 10, 1996 and station oirector BECo Ltr. #96-049 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 APRIL 1996 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 l planning. Should you have any questions conceming this report, please contact me directly.

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• L. J. Olivier RLC/dmc/9458

- Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road '

King of Prussia, PA 19406 i Senior Resident Inspector l

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I i 9605150416 960430 PDR ADOCK 05000293 R PDR fg'

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OPERATING DATA REPORT DOCKET NO. 50-233  ;

NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH April 1996  :

OPERATING STATUS NOTE _S

1. Unit Name Pilgrim 1

2. Reporting Period April 1996

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678

5. Design Electrical Rating (Net MWe) 655 3

6. Maximum Dependable Capacity (Gross MWe) 6% 1

7. Maximum Dependable Capacity (Net MWe) 670

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

1 No Chanaes '

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

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

11. Hours in Reporting Period 719.0 2903.0 205055.0

12. Hours Reactor Critical 604.5 2788.5 129054.6

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 585.9 2769.9 124593.8

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1107005.0 5365690.0 221667860.0

17. Gross Electrical Energy Generated (MWH) 379400.0 1849140.0 75126464.0

18. Net Electrica! Energy Generated (MWH) 365635.0 1783249.0 72226871.0

19. Unit Service Factor 81.5 95.4 60.8

20. Unit Availability Factor 81.5 95.4 60.8

21. Unit Capacity Factor (Using MDC Net) 75.9 91.7 52.6

22. Unit Capacity Factor (Using DER Net) 77.6 93.8 53.8

23. Unit Forced Outage Rate 0.0 0.0 11.7

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

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

l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH April 1996 1

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Not) (MWe-Net) 1 665 17 664 l

2 664 18 616 3 664 19 136 q 4 664 20 0 5 658 21 0 6 664 22 0 1

7 636 23 0 I 8 664 24 2 9 664 25 228 10 664 26 578 11 665 27 661 l 12 665 28 570 l 13 663 29 529 14 664 30 660 l 15 663 16 664 l This format lists the average daily unit power levelin MWe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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s . I OPERATIONAL

SUMMARY

DOCKET NO. 50-293 i

NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 I REPORT MONTH April 1996 Tha unit started the reporting period at 100 percent core thermal power (CTP) where it was maintained until April 18,1996, at 2006 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.63283e-4 months <br /> when a planned power reduction to approximately 50 percent commenced in preparation for a thermal backwash of the main condenser and turbine testing. Following completion of the th:rmal backwash and turbine testing, reactor power continued to be reduced in preparation for a five to seven day planned maintenance outage. During the power decent on April 19,1996, at approximately 23 ptrcent power CTP a turbine vibration high alarm was received in the control room. At approximately 1016 hours0.0118 days <br />0.282 hours <br />0.00168 weeks <br />3.86588e-4 months <br />, on April 19,1996, an automatic reactor scram occurred from approximately 22 percent CTP. The l scram was the result of a load rejection initiated via the action of the turbine master trip solenoid. The

vibration trip signal originated from vibration associated with bearing #5 and #6 that increased rapidly to l approximately 12 mils. Following the planned maintenance outage on April 24,1996, the reactor was made l critical at 0441 hours0.0051 days <br />0.123 hours <br />7.291667e-4 weeks <br />1.678005e-4 months <br />. At 2326 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.85043e-4 months <br /> on April 24,1996, the main generator was synchronized to the power i grid. At 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br /> on April 26,1996 the reactor reached 100 percent CTP where it was maintained until April 28,1996, at 1607 hours0.0186 days <br />0.446 hours <br />0.00266 weeks <br />6.114635e-4 months <br /> when the plant power was reduced to approximately 60 percent CTP to perform a rod pattern change and conduct rod exercising. The reactor was retumed to 100 percent CTP on April 30 )

at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> where it was maintained until the end of the reporting period. 1 I

SAFETY RELIEF VALVE CHALLENGES MONTH OF APRIL 1996 l Requirement: NUREG-0737 T.A.P. II.K.3.3 i

l Date: April 19,1996 Valve: SRV-203-3C, and 3D (Manual Opening) l Reason: Reactor pressure control following a reactor scram. l l

Date: April 24,1996, at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, Valve: SRV-203-3B Reason: Was manually opened for post work testing.

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, l

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REFUELING INFORMATION l .

DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508)830-8321 1

REPORT MONTH April 1996 l The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo,

! dit:d 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.

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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.

l 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.

i 1 l (b) The planned spent fuel storage capacity is 3859 fuel assemblies. I

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 DOCKET NO. 50-293 ~

NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 -

REPORT MONTH April 1996 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT RECURRENCE R actorCore RCIC Pump Speed Pump discharge Malfunctioning EG-R replaced via The cause investigation 96-003-00  ;

Isolation Controller pressure, speed, speed control MR19600786 of the failed EG-R is l Cooling and flow, system hydraulic continuing System (RCIC) oscillations actuator (EG-R)

Othrt maintenance activities were performed in accordance with the preplanned maintenance outage schedule, plus emergent issue maintenance activities.

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UNIT SHUTDOWNS AND POWER REDUCTIONS -1 -

DOCKET NO. 50-293 .

NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 -

i REPORT MONTH April 1996 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 13 04/24/96 S 133.1 B 3 96-005-00 51 TG During a normal shutdown for pre-planned maintenance outage, an automatic scram occurred due to high turbine bearing vibration.

14 04/28/96 S 0.0 B N/A N/A N/A N/A Planned Power reduction to approximately 60%CTP to perform a rod pattem change and conduct rod exercising.

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

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