ML20138J814

Monthly Operating Rept for Nov 1985

ML20138J814
Person / Time
Site:	Pilgrim
Issue date:	11/30/1985
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-221, NUDOCS 8512180057
Download: ML20138J814 (7)

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CVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 i UNIT Pilgrim 1 DATE- 12/13/85 CONPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH November 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 4'77. -17 563.

2 473. 18 665.

3 473, 19 666.

4 473. 20 665.

5 466. 21 665.

6 471. 22 665.

7 472. 23 665.

8 471. 24 666.

9 476. 25 666.

10 543. 26 666.

11 661. 27 666.

12 663. 28 535.

13 663. 29 654.

14 663. 30 526.

1G 663. 31 N/A 16 664.

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

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s. OPERATING DATA REPORT DOCKET NO. 50-293 DATE 12/IJ/UD COMPLETED BY P. Hamilton I. sTELEPHONE (617)746-7900

- OPERATING STATUS

1. Unit Name Pilgrim 1 Notes

2. ' Reporting Period __ November 1985

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) 690

, ..7. Maximum Dependable Capacity -(Net NWe) '670

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

None i

k 9. Power Level To Which Restricted, If Any (Net MWe) None l 10. Reasons For Restrictions, If Any N/A l

This Month Yr-to-Date Cumulative l'1. Hours In Reporting Period 720.0 8016.0 113760.0 '

12. Number Of Hours Reactor Was Critical 720.0 7415.0 77331.6 j 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 ,

14. Hours Generator On-Line 720.0 7270.8 74839.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1287456.0 13475688.0 130427496.0

17. Gross Electrical Energy Generated (MWH) 441280.0 4631530.0 43863744.0

18. . Net Electrical Energy Generated (MWH) _424995.0 4457200.0 _42154127.0

19. Unit Service Factor 100.0 90.7 65.8

20. Unit Availability Factor 100.0 90.7 65.8

21. Unit Capacity Factor (Using MDC Net) 88.1 83.0 55.3

22. Unit Capacity Factor (Using DER Net) 90.1 84.9 56.6

23. Unit Forced Outage Rate- 0.0 6.9 9.0

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

• None i

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

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 4

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-__._-_._I_m._. ___.m.-.____.__..s__.___ _.___-________I__________

REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to DECO, 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: September 1986

3. Scheduled date for restart following refueling: November 1986

4. Due to their similarity, requ2sts 4, 5, & 6 are responded to collectively under #6:

5. See M6.

6. The new fuel, which was loaded during the 1983-84 refueling outage, is of the same P8x8R design, as loaded the previous outage and consists of 160 P8DRB282 assemblies. In addition, 32 GE60-P8DRD282 assemblies were also loaded.

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

(b) There are 1,128 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies. The actual spent fuel storage capacity is 1770 fuel assemblies at present.

(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 642 fuel assemblies.

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for November 1985 The unit operated at an average daily -level of 73 percent power from the first until the tenth pending completion of-condensate pump repairs. On the fourth,

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an Unusual Event was declared due to a failure of the. suppression chamber -

cooling return valve coincident with an RHR pump beeing out of service for Equipment Qualification. On the fifth, repairs were completed on the valve; it was then successfully-tested.and the Unusual. Event was terminated.

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From the eleventh to the sixteenth, the unit operated at an average daily power level of 99 percent. On the seventeenth, there was a slight power i reduction to perform a backwash of the main condenser. The unit then. returned to an average daily power level of 99 percent and remained at that level until

] the twenty-r.eventh.

f On.the twenty-eighth through the thirtieth,' power was slightly reduced to perform feedwater regutenting valve maintenance and for main condenser j backwashing.

Safety Relief Valve Challenges Month of November 1985 1

i, Requirement: NUREG-0737 T.A.P. II.K.3.3.

There were no safety relief valve challenges during the month.

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Month November 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE-l

CORRECTIVE ACTION

{ SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER i

3 Scram Discharge Would not seat Unknown Replaced solenoid Solenoid will be N/R l CRD Volume properly. with qualified sent out for

! SV-302-200 solenoid, testing to determine EQ Solenoid failure mode.

I 261-2A,2D Setpoint Drift Unknown Recalibrated all Presently evaluating 85-032 to Main 2E, 2M, & 2N switches to proper calibration data. be issued.

Steam setpoint.

3 CRD Accumulator Leaking Leaking Replaced N/R - Routine N/R CRD 50-19 Piston Seal Accumulator Maintenance 10 MO-1001-36A Would not open. Wire Loose Tightened 2F Investigating for N/R RHR (2F) wire and motor root cause.

mounting bolts.

14 1" Drain Line Crack in (HAZ) Vibration Cut out weld; Engineering Service N/R Core Spray Downsteam of Nipple to 90* shorten nipple; Request submitted MO-1400-4A Elbow Weld roweld. for vibration 5

analysis.

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( UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-293

• UNIT NAME Pilgrim 1

. DATE 12/13/85 COMPLETED BY P. Hamilton l

TELEPHONE (617) 746-7900 REPORT MONTH November 1985 NETHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEN COMPONENT ACTION TO NO. DATE TYPEI (HOURS) REASON 2 DOWN REACTOR 3 REPORT # CODE 4 CODES PREVENT RECURRENCE 21 10/30/85 5 0.0 A 5 N/R SD P Continued power (Continued) reduction due to "A" condensate pump being inoperable.

1 2 2 3 4&5 F-Forced A-Egiip 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-lO22)

e e 50sTON EDISON COMPANY 800 movLaTON STREET WasTON, MA33ACHumETTs 02199 wlLLIAM D. HARRINGTON essesse wasa resotoont

= = = 'a^a December 13, 1985 BEco Ltr. #85-221 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Attn

Document Control Desk License No. DPR-35 Docket No. 50-293

Subject:

November 1985 Monthly 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 l your information and planning.

Respectfully submitted, I

W. D. Harrington PJH: caw Attachment f

cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission

} 631 Park Avenue King of Prussia, PA 19406 l

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