ML19332G373

Monthly Operating Rept for Nov 1989 for Pilgrim.W/891214 Ltr

ML19332G373
Person / Time
Site:	Pilgrim
Issue date:	11/30/1989
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-89-177, NUDOCS 8912210173
Download: ML19332G373 (7)

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Pilgrim Nuclear Power station Rockj Hill Road Plymouth, M issachusetts 02360 -

K. L. Highfill station Director December 111, 1989 BECo Ltr. #B9- 177 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293

- Subj ect: November 1989 Honthly Report

Dear Sir:

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.

f' L'A K.L. Highfill HJM:bal

. Attachment cc: Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector MY.

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. . AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-293 UNIT Pil ori m_ _1 DATE December 14. 1989 COMPLETED BY H. Munro TELEPHONE (508) 747-8474-940fiTH _Bovember 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 621 2 0 18 622 3 0 19 621 4 0 20 621 5 0 21 622 6 0 22 623 7 0 23 623 8 37 24 622 9 237 25 624 10 557 26 6R2 11 ti25 27 622 12 619 28 622 13 617 29 622 14 623 30 623 15 620 31 N/A 16 622 __

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

'. - . OPERATING DATA REPORT l

- DOCKET NO. 50-293 DATE December 14. 1989.

COMPLETED BY H. Hunro TELEPHONE (508) 747-8474 OPERATING STATUS Notes

1. Unit Name Pilorim 1

2. Reporting Period November 1989

3. Licensed Thermal Power (MHt) 1998

4. Nameplate Rating (Gross MHe) _ 678

5. Design Electrical Rating (Net MHe) %5

6. Maximum Dependable Capacity (Gross MWe) Og

7. Maximum Dependable Capacity (Net MWe) 670

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

None ,_,_

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

10. Reasons for Restrictions, If Any __ N/A i

This Month Yr-to-Datit Cumulative

11. Hours In Reporting Period 720.0 80lLO 148824.0

12. Number Of Hours Reactor Has Critical 587.9 4968.0 84759.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 534.3 4264.1 81493 4

15. Unit Reserve Shutdown Hours __

0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) _95352L.0 _A325112.0 139324992.0

17. Gross Electrical Energy Generated (MHH) =331540.0 _1392500 0 _46B3110L.0

18. Net Electrical Energy Generated (MHH) 318406.0 1323654.0 44999081.0

19. Unit Service Factor 74.2 53.2 54.8 *

20. Unit Availability factor 74 2 53.2 54.8

21. Unit Capacity factor (Using MDC Net) 6.L0 24.6 45.1

22. Unit Capacity Factor (Using DER Net) 67.5 25.2 46.2

23. Unit forced Outage Rate 0.0 25.3 12.9

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

Mittatenance Outage Marf,h 9.1990 for a duration of 39 days.

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 I

forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY  ;

COMMERCIAL OPERATION l

(9/77)

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- - - BOSTON EDISON COMPANY ,

PILGRIM NUCLEAR POWER STATION 4

DOCKET NO. 50-293 Operational Summary for November 1989  :

The unit remained in cold shutdown for scheduled maintenance until November 6, 1989 when at 1208 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.59644e-4 months <br /> the reactor was made critical. The unit was synchronized to the grid on November 8, 1989 at 1743 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.632115e-4 months <br /> and remained on line, limited to approximately 94 percent core thermal power for the remainder :

of the reporting period, due to scoop tube lockout of the "A" Recirculation  !

Pump Motor Generator Set.  !

Safety Relief Valve Challenges Month of November 1989 Requirement: NUREG-0737 T.A.P. II.K.3.3 ,

Date: November 8, 1989 i

Valve #203-3A and 3C.

Reason: Performed Procedure 8.5.6.2 for SRV #203-3A and SRV #203-3C; Post work testing.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or co1 trol switch (manual). Ref. BECo Ltr. #81-01 dated 01/05/81.

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REFUELING INFORMATION

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l The following refueling information is included in the Monthly Report as I' 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: Second Quarter 1991

3. Scheduled de for restart following refueling: Second Quarter 1991 .

4. Due to the'o .imilarity, requests 4, 5, & 6 are responded to collectively under #6.

5. See #6.

6. The new fuel loaded during the 1966/87 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.

(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 1000 fuel assemblies, i

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Month November 1989 PILGRIM NUCLEAR PONER STATION MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER Automatic Automatic Failed accept- Collective For accumulator T-221C, Refer to associated LER 89-032-00 Depressuriza- Depressuriza- ance criteria leakage at check valve (CK-372C) LER.

tion tion System during perfor- portions of each soft seat, and relief System (ADS) mance of Proc. accumulators valve (HO-373C) were Accumulators. 8.7.1.10 " ADS pressure replaced.

T-221C. Accumulator boundary. For accumulator T-221D, T-221D Pressure Drop check valve (CK-372D)

Test". soft seat, and relief (F&MR 89-403) valve (RV-3730) were replaced, and drain valve (HO-3730) seat area was re-worked (lapped).

Automatic Safety Relief Valves dis- Valve body Removed insulation. N/A N/A Depressuriza- valves covered leaking flange gaskets Disassembled valves tion #203-3A and during Reactor deteriorated. Replaced gaskets.

System #203-3C. Vessel Press- Replaced insulation.

ure Test Successfully perform-TP89-92. ed Procedure 8.5.6.2 for SRV #203-3A and 3C.

High Gland seal Blower motor Horn motor 810wer motor P-223 Refer to associated LER 89-036-00 Pressure condenser failed to start brushes. replaced and LER. (to be issued)

Coolant blower motor. when control satisfactorly tested Injection P-223 switch was System placed in Start position.

(F&MR 89-453) 4 2

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UNIT SHUTDONNS AND PONER REDUCTIONS DOCKET !E). 50-293 NAME Pilgril 1 DATE_ December 14. 1983 COMPLETED BY M. Munro TELEPHONE (508) 747-8474 REPORT MONTH November 1989 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENTIVE-NO. DATE TYPEI (HOURS) REASON 2 DONN REACTOR 3 REPORT # CODE 4 CODES RECURRENCE 14 1/11/89 S 185.7 B 1 N/A N/A N/A Contint!ation of (continued) scheduled maintenance outage.

1 2 2 3 4&5 F-Forced A-Equip Failure 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) File (NUREG-1022) l e

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