BECO-LTR-95-116, Monthly Operating Rept for Oct 1995 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Oct 1995 for Pilgrim Nuclear Power Station

ML20094K353
Person / Time
Site:	Pilgrim
Issue date:	10/31/1995
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-95-116, NUDOCS 9511160306
Download: ML20094K353 (7)

Text

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Tech. Sp:c. 6.9.A.2 f -

Boston Edson Pilgrirn Nuclear Power Station j Rocky Hill Road j Plymouth, Massachusetts 02360 I

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L. J. Olivier i vice President Nuclear operations November 13,1995 1 and station oirmor BECo Ltr. #95-116 l

l U.S. Nuclear Regulatory Commission 1 Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 OCTOBER 1995 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 j you have any questions conceming this report please contact me directly.  !

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.J. Olivier RLC/nas/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 c

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9511160306 951031 PDR ADOCK 05000293

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OPERATING DATA REPORT '

DOCKET NO. 50-293

. DATE November 13.1995 COMPLETED BY: R.L. Cannon TELEPHONE (508) 830-8321 OPERATING STATUS NOTES i i

1. Unit Name Pilgrim l l

2. Reporting Period October 1995

3. Licensed Thermal Power (MWt) 1998 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 MWe) 670-

8. If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give Reasons: 1 I i NONE j i 9. Power Level To Which Restricted, if Any (Net MWe): None l

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

This Month . Yr-to-Date Cumulative t 11. Hours in Reporting Period 745.0 7296.0 200688.0

! 12. Hours Reactor Critical 745.0 5602.0 124802.1  !

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0  :

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14. Hours Generator On-Line 745.0 5498.8 120359.9 '

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH)- -1422216.0 10636137.0 213391353.0

17. Gross Electrical Energy Generated (MWH) 488360.0 3650230.0 72269904.0

18. Net Electrical Energy Generated (MWH) 470820.0 3513589.0 69471366.0

19. Unit Service Factor 100.0 75.4 60.0

20. Unit Availability Factor 100.0 75.4 60.0

21. Unit Capacity Factor (Using MDC Net) 94.3 71.9 51.7

22. Unit Capacity Factor (Using DER Net) 96.5 73.5 52.8

23. Unit Forced Outage Rate _

0.0 4.5 12.1

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 i

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/ AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 DATE: November 13.1995 I COMPLETED BY: R.L. Cannon I TELEPHONE: (508) 830-8321 )

MONTH October.1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1- 653 17 640 l i

2 654 18 661  !

3 653 19 666 4 647 20 664- I 5 468 21 665 6 535 22 665 7 643 23 666 i

8 664 24 668  ;

l 9 665 25 668~ 1 i

10 665 26 666 11 665 27 667 .i 12 665 28 667 l 13 659 29 665 14 136~ 30 665 15 594 31 667 16 666 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.

BOSTON EDISON COMPANY

, PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 OPERATIONAL

SUMMARY

FOR OCTOBER.1995 The unit started the reporting period at 100 percent Core Thermal Power (CTP) where it was maintained until October 5,1995 when reactor power was reduced to 50% CTP to perform a thermal backwash of the main condenser. Following the backwash, reactor power was increased and the unit attained 100 percent CTP  ;

carly on October 6,1995. Later on October 6,1995, a power reduction of 45% CTP was made in response to a seaweed intrusion in the east seawater bay. After completing backwashes of the main condenser, RBCCW and TBCCW heat exchangers, reactor power was increased and 100% CTP was attained on October 7,1995. A power reduction to approximately 18% CTP was commenced on October 13,1995 for backwash of the main condenser and performance of other maintenance activities. Following the backwash and completion of scheduled maintenance activities, reactor power was again returned to 100 percent CTP on October 15,1995 where it was maintained until October 17,1995, when reactor power was reduced to 60 parcent CTP to acccmmodate a control rod pattem change. On October 18, 1995, reactor power was retumed to 100% CTP where it was maintained for the remainder of the reporting period.

SAFETY RELIEF VALVE CHALLENGES MONTH OF OCTOBER 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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REFUELING INFORMATiON )

The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, -

' dated Janugry 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.

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5. See #6.

6. The new fuel loaded during the 1995 refueling outage (RFO-10) is of a differerst 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 'l capacity is 2891 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 1103 fuel assemblies.

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PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE e .

DOCKET NO: 50-293 .

NAME:- Pilarim t - - -

DATE: November 13.1995 COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH: October 1995 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT RECURRENCE No major safety related maintenance was completed during this reporting period.

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UNIT SHUTDOWNS AND POWER REDUCTIONS .: ..

DOCKET NO: 50-293 -

• NAME: Pilarim I * .

DATE: November 13.1995 COMPLETED BY: R. L Cannon .

TELEPHONE: (508) 830-8321 REPORT MONTH: October 1995 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 ,

08 10/05/95 S 0.0 H N/A N/A N/A N/A Fower reduction to facilitate a i thermal backwash of the  ;

main condenser. l 09 10/14/95 S 0.0 H N/A N/A~ N/A N/A Power reduction to facilitate a backwash of the main ,

condenser and performance of various maintenance <

activities. l There were no unit shutdowns during the reporting period.

1 2 3 4&S t i 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 j D-Regulatory Restriction 4-Continued Data Entry Sheet i E-Operator Training 5-Reduced Load . Licensee Event Report  !

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

F-Admin j G-Operator Error i H-Other i I

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