BECO-90-137, Monthly Operating Rept for Oct 1990 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Oct 1990 for Pilgrim Nuclear Power Station

ML20062E653
Person / Time
Site:	Pilgrim
Issue date:	10/31/1990
From:	Richard Anderson, Basilesco G BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-90-137, NUDOCS 9011210153
Download: ML20062E653 (7)

Text

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p' 80STON EDISON Pilgrim Nuclear Power Station j Rocky Hill Road  :

Plymouth. Massachusetts 02360 l

November 13, 1990 BECo Ltr. #90-137 j U.S. Nuclear Regulatory Commission 3 Attention: Document Control Desk  ;

Hashington, DC 20555 License No. DPR-35 .

Docket No. 50-293

Subject:

October 1990 Monthly Report

Dear Sir:

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. In ~accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational .i 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. j i

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Rt :' Erson j St tion Director and i (Jice President, Nuclear Operations GJB/bal f

Attachment cc:. Regional Administrator, Region i

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-U.S. Nuclear Regulatory Commission  !

475 Allendale Rd. ,

King of Prussia, PA 19406 l Senior Resident Inspector 96 I 0

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1 90.1121oisa 9010 gL w : f y e s e o ,3 1

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AVERAGE DAILY UNIT POWER LEVEL

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DOCKET N0. 50-293 i UNIT Pilarim 1 DATE November 13. 1990 COMPLETED BY G. Basilesco TELEPHONE (508) 747-8534 HONTH_Qcfeber1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (HHe-Net) 1 660 17 660 2 662 18 661 ___

3 660 19 662 4 661 20 663 5 662 21 663 6 660 22 663 7 661 23 662 8 662 24 663 9 662 25 661 10 ._ 662 26 659 11 660 27 662 12 660 28 665 13 659 29 665 14 659 30 663 15 659 31 663 16 661 This format lists the average daily unit power level in HHe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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OPERATING DATA REPORT DOCKET NO. 50-293

. DATE November 13. 1990 COMPLETED BY G. Basilesco TELEPHONE (508) 747-8534 OPERATING STATUS Notes

1. Unit Name Pilorim 1

2. Reporting Period October 1990

3. Licensed Tt:rmal Power (MHt) 1998

4. Nameplate Rating (Gross MWe) 678

5. Design Electrical Rating (Net HHe) 655

6. Maximum Dependable Capacity (Gross MHe) 696 7.= Maximum Dependable Capacity (Net HHe) 670

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

None

9. Power Level To Which Restricted, If Any (Net MHe) None

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

11. Hours In Reporting Period 745.0* 7296.0 156864.0 -

12. Number Of Hours Reactor Has Critical 745.0 5731.5 91136.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 i

14. Hours Generator On-Line 745.0 5322.8 87452.1 l 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 l 16. Gross Thermal Energy Generated (MHH) 1487064.0 10027512.0 150512424.0

17. Gross Electrical Energy Generated (MHH) 511770.0 3436660.0 50673484.0

18. Net Electrical Energy Generated (MHH) 3303512.0 1M99696.0 492705.0

19. Unit Service Factor 100.0 73.0 55.8

20. Unit Availability Factor 100.0 73.0 55.8 l 21. Unit. Capacity Factor (Using MDC Net) 98.7 67.6 46.3 1

22. Unit Capacity Factor (Using DER Net) 101.0 69.2 47.4

23. Unit Forced Outage Rate 0.0 13.4 12.9

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

L None

25. If Shut Down At End Of Report Period, Estimated Date of Startup -

N/A .

26. Units In Test Status (Prior to Commercial Operation):

N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

• Returned to E.S.T.

3 BOSTON EDISON COMPANY .

.. PILGRIM NUCLEAR P0HER STATION l

. DOCKET NO. 50-293  !

l Operational Summarv 'or October 1990 The unit started and ended the reporting period at approximately 100 percent power with minor power reductions to perform control rod exercises on October 6,13, 20 and 27. The net capacity factor for the month was 98.7 percent.

The High Pressure Coolant Injection (HPCI) System was tested on October 9, 1990 and was declared inoperable when the HPCI turbine tripped on overspeed.

A seven day LCO was entered and maintenance was performed on the HPCI turbine. HPCI was declared operable on October 16, 1990. Analysis and evaluation of HPCI data continued throughout the remainder of the reporting period.

Safety Relief Valve Challenges Month of October 1990 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during this 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 dated 01/05/81.

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,...' *- REFUELING INFORMATION The following refueling information is included in the Montnly 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. l l

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

2. Scheduled date for next Refueling Shutdown: Second Quarter 1991

3. Scheduled date for restart following refueling: Third Quarter 1991

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 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.

7. (a) There are 580 fuel assemblies in the core.

(b) There are 1320 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.

1 (b) The planned spent fuel storage cap; 'y is 2320 fuel assemblies.

9. With present spent fuel in storage, the speat fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.

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Month October 1990 PILGRIM NUCLEAR P0HER STATION

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MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER Primary Fuse (s) PPFU1 -Blown fuses Inadequate Replaced blown Under investigation LER 90-015-00 Contain- and FU-RADA resulting in work plan fuses.

ment automatic act-Isolation uation of PCIS Control (F&MR 90-314)

System (PCIS)

High HPCI Turbine Overspeed trip Mechanical / Replaced EG-R. Continun diagnostic LER 90-017-00 Pressure (F&MR 90-352) hydraulic mal- testing and monitoring Coolant function of of system.

Injection speed control (HPCI) system.

System l

l Salt SSH Pump "B" High Vibration Marginal deflec- Replaced shaft and None N/A Service tion in pump bushing; two bearings Hater shaft; worn also replaced.

(SSH) bushing in stuf-l System fing box.

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LMIT SHUTDONNS AND POWER REDUCTIONS DOCKET NO. 50-295 .

NAME P11aris 1 .

DATE Noved er 13. 1990 .

COMPLETED BY G. Bas 11esco TELEPHONE (508) 747-8534 REPORT MONTH October 1990 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTE5 ENT ACTION TO PREVENT NO. DATE TYPE I (HOURS) REASON 2 DOHN REACTOR 3 REPORT # CE- ] ODE C RECURRENCE Mo sht tdowns or power reductions during October 1990.

1 2 2 3 4&5 F-Forced A-Equip Fa*1ure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) Flie (NUREG-1022) 4 f

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