ML20012D289

Monthly Operating Rept for Feb 1990 for Pilgrim Nuclear Power Station.W/900314 Ltr

ML20012D289
Person / Time
Site:	Pilgrim
Issue date:	02/28/1990
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-037, 90-37, NUDOCS 9003270151
Download: ML20012D289 (7)

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BOSTON EDeSON Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts o236o En D r&

%ce Presdent, Nuclear Operstons March 14 1990 BECo Ltr. #90- 037 U.S. Nuclear Regulatory Commission-Attention: Document Control Desk

-Hashington, DC 20555 License No. DPR-35 '

Docket No. 50-293

Subject:

February 1990 Monthly Report Dear Siri-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.

s . f. hg '

K.L. Highfin

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Attachment cc: Regional Administrator, Region 1.

-U.S. Nuclear. Regulatory-Commission

' ' 47S Allendale Rd.

King of Prussia, PA 19406 '

Senior Resident Inspector 9003270151-900228 PDR. ADOCK 0500o293

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v _7 I ;[ - 57 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.- 50-293 6' . UNIT Pilorim 1 1 DATE March 14. 1990 COMPLETED.BY H. Munro TELEPHONE (508) 747-8474 MONTH February 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 (MHe-Net) (MHe-Net).

I 665 17 662 2 665 18 662 3 663 19 663

-4 666 20 663 5 664 21 663 6 664 22 663 7 665 23 663 8 665 24 661 9 622 25 663 .i 10 423 26 664 11 647 27 664 12 663 28 664 13 663 29 N/A 14 663 30 N/A  ;

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15 663 31 N/A l 1

16 660 l l

This format lists the average daily unit power level in MHe-Net for each day  !

u in the reporting month, computed to the nearest whole megawatt.

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c. . , . OPERATING DATA REPORT 4 ,

DOCKET NO. 50-293 DATE March 14. 1990 (b8 74 -8474 OPERATING STATUS 1 L Notes

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1. Unit Name Pilarim 1

2. Reporting Period February 1990 j

3. Licensed Thermal Power (MHt) 1998 i I

-4. Nameplate Rating (Gross MHe) 678

5. Design Electrical Rating (Net MHe) 655-

6. Maximum Dependable Capacity (Gross HHe) 696  ;

7. Maximum Dependable Capacity (Net MHe) 670

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

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

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

11. Hours In Reporting Period 672.0 1416.0 150984.0 '

12. Number Of Hours Reactor Has Critical 672.0 1416.0 86821.2

-13. Reactor Reserve Shutdown Hours -

0.0 0.0 0.0

14. Hours Generator On-Line ,_

672.0 1416.0 83545.3 15.. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) 1321392.0 2806056.0 143290968.0 .

17. Gross-Electrical Energy Generated (MHH). 455670.0 970270.0 48207094.0 18 Net' Electrical Energy Generated-(MHH)

. 438641.0 934090.0. 46317274.0

19. Unit Service Factor 100.0- 100.0 55.3

20. Unit Availability Factor 100.0 100.0 55.3 ~

21. Unit Capacity Factor (Using MDC Net) 97.4 -98.5 45.8 22.. Unit Capacity Factor (Using DER Net) 99.7 100.7 4 6 ~. 8

23. Unit Forced Outage Rate 0.0 0.0 12.7

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

Maintenance Outaae March 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 Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

-, . - BOSTON EDISON COMPANY-9' ' .' ' ' ' .

PILGRIM NUCLEAR POWER STATION .

DOCKET NO. 50-293 -l d

' Operational Summarv~ for February 1990 -

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The unit remained on line at approximately-100 percent thermal power "D throughout the reporting period. Power was. reduced to approximately 46 percent thermal. power on 2-10-90 to perform a backwash of the' main condenser ,

due to macrofouling. I The "A" Recirculation Motor Generator Set remained ~in manual control throughout the reporting period.

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l Safety Relief Valve Challenges Month of February 1990 1 l

1 Requirement: NUREG-0737 T. A.P. II .K 3.3 U There were-no safety relief valve challenges during the reporting period.-

An SRV'cha11enge 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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N" "' REFUELING INFORMATION The following refu4 ling information is included inLthe Monthly Report as-q 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-date for restart following refueling: Second Quarter 1991

4. Due to their similarity, requests 4, 5, & 6'are: responded to collectively ^b under #6.

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5. See #6.

6. The-new fuel loaded during the 1986/87 refueling outage was of the same

- deeign 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 4 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. -q

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- man 990 PILGRIM NUCLEAR PONER-STATION

• g MAJOR SAFETY.RELATED MAINTENANCE' ,

SYSTEM COMPONENT MALFUNCTION ~ CAUSE ' MAINTENANCE CORRECTIVE' ACTION ~TO. -ASSOCIATED PREVENT RECURRENCE LER Feedwater Feedwater Reg. FCV-642A' . Faulty Manual Replaced M/A station; -N/A' 1N/A System Valve oscillating / Automatic re-calibrated ,

(FH) FCV-642A in automatic Station- .I/P.642A converter, mode.. M/A-640-19A and replaced airlock at' Panel relay (AL642A).

C905.

Residual RHR Outboard Stem key sheared ' Root cause Replaced: damaged stem N/AL -N/A Heat Injection off, set. screw under- -key, set screw and Removal Valve damaged and set . investigation set screw locking nut.

(RHR) M01001-28A screw locking (FRN 90-03-04) '

nut missing.

(F&MR 90-19) r D

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'UN T SHOTDONNS AND..PO NC REDUCTIONS DOCKET NO. 50-293 NAME Pilaris 1

, DATE March 14, 1990 COMPLETED BY M. Munro TELEPHONE (508) 747-8474 REPORT (DiTH _.Egbruary 1990 F4THCD OF LICENSE CAUSE & CORRECTIVE-NO. DATE TYPEI DURATION (HOURS) REASON 2 Stt0TTIN'i DOMN REACTOR 3' EVENT REPORT #

SYSTEg CODE g ENT ACTION TO PREVENTIVE RECURRENCE 17 02/10/90 S 0.0 N/A ~5 N/A N/A N/A Power reduction due to backwash of main condenser.

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2 2 3 45 i F-Forced A-Equip r allure F-Admin 1-Manual Exhibit F & H i S-Sched B-Maint or Test G-Oper Error 2-Manori Siram Instructions for i C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continaea Data Entry Sheet E-Operator Training 5-Feduced Load Licensee Event Report

& License Examination W0ther (LER) File (NUREG-1022) l

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