ML20081B274

Monthly Operating Rept for Feb 1995 for Pilgrim Nuclear Power Station

ML20081B274
Person / Time
Site:	Pilgrim
Issue date:	02/28/1995
From:	Munro W, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-#95-03, BECO-LTR-#95-3, NUDOCS 9503160114
Download: ML20081B274 (7)

Text

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t , Tcch. Spec. 6.9.A.2 0 .

Boston Edison l

Pdgnm Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 L J. Olivier Vice President Nucleat Operations March 13 ,1995 ,

and station Director BECo Ltr. #95-034 l

U.S. Nuclear Regulatory Commission Attention: Document Control Det.x Washington, DC 20555 Docket No. 50-293 License No. DPR-35 FEBRUARY 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. 3hould you have any questions concerning this report please contact me directly.

A.

L.J. Olivier WJM/ lam /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 9503160114 950228 PDR ADOCK 05000293 R PDR s'

• i ' OPERATING DATA REPORT DOCKET NO. 50-293 DATE u nlos COMPLETED BY: W. Munro TELEPHONE (508) 830-8474 OPERATING STATUS NOTES

1. Unit Name Pilgrim I

' 2. Reporting Period February 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:

NONE

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

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

11. Hours in Reporting Period 672.0 1416.0 194808.0

12. Hours Reactor Critical 672.0 1416.0 120616.1

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 672.0 1416.0 116277.1

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1306584.0 2792184.0 205547400.0

17. Gross Electrical Energy Generated (MWH) 450680.0 964100.0 69583774.0

18. Net Electrical Energy Generated (MWH) 433548.0 927767.0 66885544.0

19. Unit Service Factor 100.0 100.0 59.7

20. Unit Availability Factor 100.0 100.0 59.7

21. Unit Capacity Factor (Using MDC Net) 96.3 97.8 51.2'

22. Unit Capacity Factor (Using DER Net) 98.5 100.0 52.4

23. Unit Forced Outage Rate 0.0 0.0 12.3

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each) RFO-10, March 25,1995 for 55 days.

25. If Shutdown at End of Report Period, Estimated Date of Startup - Unit Operating t

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-293 DATE: 3/13/95 COMPLETED BY: W. Munro TELEPHONE: (508) 830-8474 MONTH February 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 666 17 664 2 665 18 663 3 664 19 663 4 664 20 663  ;

5 664 21 663 l 6 665 22 663 7 664 23 664 8 665 24 663 I 9 665 25 351 10 663 26 452 11 663 27 663  ;

12 664 28 665 13 664 I

14 664 l 15 664 16 663 1 1

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

I

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 OPERATIONAL

SUMMARY

FOR FEBRUARY 1995 Tha unit started the reporting period at 100 percent Core Thermal Power (CTP) where it was maintained until February 25,1995. On February 25,1995, reactor power was reduced to approximatley 48 percent (CTP) cnd the Augmented Offgas System was secured and isolated to facilitate leak repairs to the "B" Recombiner Preheater drain line. While at reduced power a backwash of the main condenser was accomplished.

Following repairs to the AOG system, power was increased. On February 26,1995, at 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> the unit attained 100 percent CTP where it was essentially maintained for the remainder of the reporting period.

SAFETY RELIEF VALVE CHALLENGES MONTH OF FEBRUARY 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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R8FdELING INFORMATION Th3 following refueliryg information is included in the Monthly Report as requested in an NRC letter to BECo, i dited January 18,1978:

. For your convenience, the information supplied has been enumerated so that each nurnber corresponds to j 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: March 25,1995.

3. Scheduled date for restart following next refueling: May 19,1995.

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

5. See #6. t

6. The new fuel loaded during the 1993 refueling outage was of the same design as loaded in the previous refueling outage and consisted of 140 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 2878 fuel assemblies. However,23 spent fuellocations cannot be used due to 1 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 1226 fuel assemblies.

• Includes 136 new fuel assemblies for RFO-10.

6 MONTH FEBRUARY 1995 ,

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE .

SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACBON TO LER -

PREVENT RECURRENCE High Pressure HPCI inverter Inverter tripped. Root cause under Replaced HPCI Failed inverter sent to 95:002-00 ,

Coolant injection 2340-13 HPCI declared investigation. Inverter with manufacturer, Abacus (HPCI) System inoperable. identical spare Controls, Inc., for further .

inverter. HPCI evaluation. Refer to System was associated LER.

successfully tested and declared operable.

Reactor Core RCIC Inverter Inverter tripped. Root cause under Replaced RCIC Failed inverter sent to 95-002-00 Isolation Cooling 1340-16. RCIC declared investigation. Inverter with manufacturer, Abacus (RCIC) System inoperable. identical spare . Controls, Inc., for further inverter. RCIC evaluation. Refer to System was associated LER.

successfully tested and declared operable.

Augm nted Off- AOG Preheater Thru-wall leak at To be determined. Removed old piping To be determined. N/A Gas (AOG) E305B steam drain discharge side of and existing steam Systam* line. Pressure Safety trap due to errosion Valve of piping. Installed (PSV-FO938) Temp. Mod. TM95-and steam trap 13 which provided ST-9219 on the for a temporary steam drain side spool piece to of AOG Preheater replace the steam E305B. trap. Also installed a new gasket on the outlet of PSV-F093B.

Temp. Mod. will be removed when new steam trap is available and during an AOG outage.

• Syst:m Not Safety Related But Required Extensive Power Reduction To Facilitate Repairs.

r s-4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-293 .

DOCKET NO: 50-293 NAME: Pilarim 1 -

DATE: '

COMPLETED BY: W. Munro ' '

TELEPHONE: (508) 830-8474 ,

REPORT MONTH: February 1995 l

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 1 02/25/95 S 0.0 B N/A N/A N/A N/A Power reduction to facilitate Augmented Off Gas System "B" preheater repair, and perform a main condenser backwash.

1 2 3 4&S 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