ML20199D007

Monthly Operating Rept for May 1986

ML20199D007
Person / Time
Site:	Pilgrim
Issue date:	05/31/1986
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-078, 86-78, NUDOCS 8606180471
Download: ML20199D007 (7)

Text

f' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-293 UNIT Pilgrim i DATE 6/11/86 COMPLETED BY P. Hamiiton

-TELEPHONE (617)746-7900 MONTH May 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0.

17 0.

2 0.

18 0.

3 0.

19 0.

4 0.

20 0.

5 0.

21 0.

6 0.

22 0.

7 0.

23 0.

8 0.

24 9.

9 0.

25 0.

10 0.

26 0.

11 0.

27 0.

12 0.

28 0.

13 0.

29 0.

14 0.

30 0.

15 0

31 0.

16 0.

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

8606180471 860531 DR ADOCK 0500 3

r OPERATING DATA REPORT DOCKET NO.

50-293 -

DATE 6/11/86 ~~

COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.

Unit Name Pilgrim 1 Notes 2.

Reporting Period May 1986 3.

Licensed Thermal Power (MHt) 1998 4.

Nameplate Rating (Gross MWe) 678 5.

Design Electrical Rating (Net MHe) 655 6.

Maximum Dependable Capacity (Gross MWe) 690 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 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 744.0 3623.0 118127.0

12. Number Of Hours Reactor Has Critical 0.0 1715.5 -

79791.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 0.0 1646.0 ~

77229.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0.0 3094416.0 I34999880.0

17. Gross Electrical Energy Generated (MHH) 0.0 1068000.0 _45444604.0

18. Net Electrical Energy Generated (MHH) 0.0 1027531.0 _43675429.0

19. Unit Service Factor 0.0 45.4 65.4

20. Unit Availability Factor 0.0 45.4 65.4

21. Unit Capacity Factor (Using MDC Net) 0.0 42.3 55.2

22. Unit Capacity Factor (Using DER Net) 00 43.3 56.4

23. Unit Forced Outage Rate 100.0 53.8 10.8

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

None

25. If Shut Down At End Of Report Period, Estimated Date of Startup 7/13/86

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

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

REFUELING INFORMATION The following refueling information is included in the Monthly Report as 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:

January 1987 3.

Scheduled date for restart following refueling: March 1987 4.

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

5.

See #6.

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 P80RB282 assemblies.

In addition, 32 GE68-P80RB282 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 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 1192 fuel assemblies.

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for May 1986 The Unit remained shutdown throughout the month. During th'e month maintenance activity on RHR valves, main steam line isolation valves, and primary containment isolation system logic circuitry continued.

On the sixteenth a work stoppage by union personnel occurred when the existing contract expired and agreement on a new contract could not be reached. Qualifted management personnel have assumed the duties normally performed by union workers.

Restart of the unit is pending Boston Edison's supplemental response to Confirmatory Action Letter 86-10 and subsequent NRC authorization.

Existing plans are to maintain the unit in the shutdown condition for approximately six weeks beyond the completion of the current outage work to address additional hardware and administrative items.

Safety Relief Valve Challenges Month of May 1986 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during the month.

F UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET-NO.

50-293' i

UNIT NAME Pilcril 1 DATE 6/11/86 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 REPORT MONTH May 1986 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO NO.

DATE TYPE' (HOURS) REASON' DOWN REACTOR' REPORT #

CODE' CODE' PREVENT RECURRENCE 08 5/1/86 F

744.0 A

1,3 86-008 BD ISV The unit remained (continued)86-009 BD ISV shutdown for maintenance on RHR valves, MSIV's, and PCIS logic cli cul try.

I 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)

Month May 1986 PILGRIM NUCLEAR POWER STATION

~ '

MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER Salt Pump P-2038 Excessive Out of balanced routine N/R-Service Vibration balance maintenance Water Primary MO 1001-28B Indicated As found Refurbished

- additional admin 86-009-01 Containment seat leakage testing indica-valve controls (to be issued)

Isolation ted seat

- enhanced instru-System leakage within mentation limits.

- addition of Indicated leakage controlled discussed in leakoff in response to secondary system CAL 86-10 Core Spray MO 1400-4A 2 Motor Mount Insufficient Repaired in Modified design N/R bolts sheared design accordance via PDC 86-32 with PDC 86-32 Main Steam A0-203-IA Failed local Scale build-up Refurbished the Continued moni-86-011 Isolation A0-203-2A leak rate test on seats, 8 MSIV's toring and imple-Valves A0-203-ID normal wear, mentation (as A0-203-20 and/or pilot appropriate) of A0-203-18 poppet stem BWR owners group disassociation recommendations are probable causes Auxillary Differential Burnt Up The non-seismic Replaced coil Seismic relays86-013 Electrical Lock-out switch relay was of lockout to be installed via (to be issued) for Brkr 152-509 jarred when relay PDC 85-47 (A Diesel Generator) door to breaker cabinet was opened

EOSTON EDISON COMPANY 50D EOYLaTON STmtET 50sTON. MAssACHuarns 02199 WILLIAM D. HAMRINGTON esassen veas passement me.

June 11,1986 BECo Ltr. #86-078 Otrector Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn: Document Control Desk j

License No. DPR-35 Docket No. 50-293

Subject:

May 1986 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 your information and planning.

Respectfully submitted, H. D. Harrington PJH:vep Attachment cc: Regional Administrator, Regior I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19405

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