ML20058H867

Monthly Operating Rept for Nov 1993 for Pilgrim Nuclear Power Station

ML20058H867
Person / Time
Site:	Pilgrim
Issue date:	11/30/1993
From:	Kraft E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-155, NUDOCS 9312130251
Download: ML20058H867 (7)

Text

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[ j BOSTON EDISON i Pilgrim Nuclear Power Stauon ,

Pocky Hill Roso Plymouth, Massachusetts 02360 E. S. Kraft, Jr. >

Vice Presider.t Nuclear Operations and Staten Drector December 10, 1993  ;

BECo Ltr. #93- 155  !

U.S. Nuclear Regulatory Commission Attention: Document Control Desk  !

Washington, DC 20555 -l l

License No. DPR-35  !

. Docket No. 50-293' l

f NOVEMBER 1993 MONTHLY REPORT l i

In accordance with PNPS Technical Specification' 6.9.A.2, a copy of the Operational- l 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. l I

(J), , h.

E. S. Kr t Jb. .

WJM/bal  !

1 Attachment  !

cc: Mr. Thomas T. Martin  :

R?qional Administrator, Region I U.S. Nuclear Regulatory Commission  :

475 Allendale Road i King of Prussia, PA 19406 }

t Senior Resident Inspector  ;

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9312130251 931130'  !

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.[DR ADOCK 05000293-PDR 4

OPERATING DATA REPORT '

DOCKET NO. 50-293 I DATE December 10, 1993

( COMPLETED BY: W. Munro l TELEPHONE (508) 747-8474 y OPERATING STATUS NOTES ,

1. Unit Name Pilgrim I

2. Reporting Period November 1993 l

3. Licensed Thermal Power OKWt) 1998

4. Nameplate Rating (Gross MWe) fla .

5. Design Electrical Rating (Net MWe) ' fil l

6. Maximum Dependable Capacity (Gross MWe) fil

7. Maximum Dependable Capacity (Net MWe) fla

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

None 1

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

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

11. Hours In Reporting Period 720.0 8016.0 183888.0 l

12. Number of Hours Reactor Was Critical 643.3 6338.9 112197.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 j 14. Hours Generator On-Line 615.1 6138.6 108045.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1170360.0 11708736.0 189717552.0

17. Gross Electrical Energy Generated (MWH) 401170.0 4021150.0 64155144.0 I

18. Net Electrical Energy Generated OKWH) 386159.0 3868361.0 61661277.0

19. Unit Service Factor 85.4 76.6 58.8 l

20. Unit Availablility Factor 85.4 76.6 58.8 ,

21. Unit Capacity Factor (Using MDC Net) 80.0 72.0 50.0 l 22. Unit Capacity Factor (Using DER Net) 81.9 73.7 51.2

23. Unit Forced Outage Rate 0.0 4.4 11.9 ;

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 l

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 DATE Tin cnrnko v in '993 COMPLETED BY: W. Munro

[ TELEPHONE (508) 747-8474 MONTH November 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL >

(MWe Net) (MWe-Net) l 1 663 17 629 2 663 18 388 3 662 19 661 4 663 20 663 i 1

1 5 64 21 481  ;

6 0 22 665 l l

7 0 23 663 8 0 24 655 9 49 25 664 10 577 26 665 11 661 27 665 12 660 28 665 13 648 29 664 14 663 30 663 f

15 663 31 N/A 16 663  !

This format lists the average daily unit power level in MWe-Net for each day in the- 6 reporting month, computed to the nearest whole megawatt. ]

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. . r BOSTON EDISON COMPANY .

PILGRIM NUCLEAR POWER. STATION  !

DOCKET NO. 50-293 I OPERATIONAL

SUMMARY

FOR NOVEMBER 1993 The unit started the reporting period at 100 percent core thermal power (CTP) . This power level was essentially maintained until November 5, 1993, when at 0554 hours0.00641 days <br />0.154 hours <br />9.160053e-4 weeks <br />2.10797e-4 months <br /> the main turbine was manually tripped off line and a controlled shutdown of the reactor was  ;

initiated. The reactor mode switch was placed in shutdown at 1331 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.064455e-4 months <br /> on November 5, l 1993. The shutdown was initiated to facilitate a leak repair on the "A" train 4th Point Feedwater Heater. While in cold shutdown, Safety Relief Valve (SRV) 203-3A was replaced.

On November 9, 1993, at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, the reactor was made critical and the unit was synchronized to the grid at 1451 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.521055e-4 months <br />. Reactor power was increased and attained 100 percent CTP on November 10, 1993, at approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />. On November 12 and 13, i 1993, reactor power was briefly reduced to 95 percent and 60 percent CTP, respectively, to perfarm maintenance on Hydraulic Control Unit (HCU) 10-35. On November 17, 1993 at  ;

approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was reduced to approximately 58 percent CTP to facilitate a leak repair on the "A" train 2nd Point Feedwater Heater. Following maintenance reactor power was increased to 100 percent CTP at approximately 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on November 19, 1993. On November 21, 1993, at approximately 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, reactor power was reduced to 50 percent CTP to perform a scheduled thermal backwash of the main condenser, and accomplish maintenance on the 2nd Point Feedwater Heaters. The unit attained 100 ,

percent CTP at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br /> on November 21, 1993. On November 24, 1993, reactor power was  ;

briefly reduced in response to a problem with the "A" Recirculation Motor Generator Set. '

Following the brief power reduction, 100 percent CTP was achieved and was maintained for the remainder of the reporting period. l l <

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SAFETY RELIEF VALVE CHALLENGES  !

MONTH OF NOVEMBER 1993 l l i Requirement: NUREG-0737 T.A.P. II.K.3.3 l I l DATE: November 9, 1993 i l i l VALVE: #203-3A [

t REASON: Manually opened for testing purposes following replacement of the valve.  ;

i An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor l

pressure, auto signal (ADS) or control switch (manual). Ref. BECo ltr. #81-01 date  !

01/05/81.

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J REFUELING INFORMATION The follosing refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 18, 1978:

1 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: April 1, 1995  ;

t l 3. Scheduled date for restart following next refueling: June 5, 1995 ,

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 1993 refueling outage was of the same design as loaded in the previous refueling outage and consisted of 140 assemblies.  ;

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

l l (b) There are 1629 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies. The ,

actual usel?e 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 691 fuel assemblies.

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MONTH NOVEMBER. 1993 .

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED .

TO PREVENT LER-

• RECURRENCE MAIN STEAM (MS) SAFETY RELIEF DISCHARGE UNDER REMOVED.SRV 'IO BE DETERMINED. N/A SYSTEM VALVE (SRV) TEMPERATURE INVESTIGATION. BODY (SERIAL

1. 203-3A INCREASED FROM #008) AND PILOT 115 DEGREES 'IO VALVE (SERIAL 240 DEGREES #1207), AND (PR93.9340) INSTALLED BODY (SERIAL #1208).

AND PILOT VALVE (SERIAL #1040).

PERFORMED PROCEDURE 8.5.6.2 " MANUAL OPENING OF ADS VALVES" AT APPROXIMATELY 935 PSI, SUCCESSFULLY.

REACTOR CONTROL HCU 10-35 ACCUMUIATOR UNDER REPLACED TO BE DETERMINED. N/A ROD DRIVES (CRD) LEAKING. INVESTIGATION. ACCUMULATOR FOR AND HYDRAULIC HCU 10-35.

CONTROL UNIT POSTWORK TEST (HCU) SYSTEM PERFORMED SUCCESSFULLY.-

FEEDWATER (FW) "A" TRAIN 4TH TUBE LEAKS. UNDER' PERFORMED EDDY REFER 'IO 93-026-00 SYSTEM

• POINT HEATER (PR93.9450) INVESTIGATION . CURRENT ASSOCIATED LER.

E-102A. TESTING; 44=

LEAKING TUBES-WERE IDENTIFIED-AND PLUGGED.

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• NOT SAFETY '

RELATED'

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e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET 50-293 NAME; PILGRIM .

DATE: Qccomber 10. 1941 COMPLE W. MUNRO TELEPH (508) 747-8474 ,

REPORT NOVEMBER 1993 NO. DATE TYPE DURATION REASON METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION (HOURS) SHUTTING EVENT CODE CODE TO PREVENT RECURRENCE DOWN REPORT #

REACTOR 12 11-5-93 S 104.9 B 1 93-026-00 SJ HX 'A' TRAIN 4TH POINT FEEDWATER HEATER REPAIR OUTAGE.

13 11-18-93 F 0.0 B N/A POWER REDUCTION TO REPAIR LEAKS ON FLANGES OF 2ND POINT FEEDWATER HEATEF. 'A' TRAIN.

14 11-21-93 S 0.O B N/A POWER REDUCTION TO PERFORM A THERMAL BACKWASH OF THE MAIN CONDENSER AND TO COMPLETE MAINTENANCE ON THE 2ND POINT FEEDWATER HEATERS, A AND B TRAINS.

1 2 2 3 4&5 F-FORCED A-EOUIP FAILURE E-OPERATOR TRAINING & LICENSE EXAMINATION 1-MANUAL EXHIBIT F & H S-SCHED B-MAIN OR TEST F-ADMIN 2-MANUAL SCRAM INSTRUCTIONS FOR C-REFUELING G-OPER ERROR 3-AUTO SCRAM PREPARATIONS Of D-REGULATORY RESTRICTION H-OTHER 4-CONTINUED DATA ENTRY SHEET 5-REDUCED LOAD LICENSEE EVENT REPORT 9-OTHER (LER) FILE (NUREG-1022

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