ML20141E254

Monthly Operating Rept for Mar 1986

ML20141E254
Person / Time
Site:	Pilgrim
Issue date:	03/31/1986
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-044, 86-44, NUDOCS 8604210276
Download: ML20141E254 (7)

Text

u AVERAGE D'ILY UNIT POWER LEVEL DOCKET NO.

50-293 UNIT Pilgrim 1 DATE April 14, 1986 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH March 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Ne-Net)

(Ne-Net) 1 667.

17 0.

2 666.

18 0.

3 668.

19 0.

'4 668.

20 O.

5 668.

21 0.

6 667.

22 0.

7 573.

23 0.

8 8.

24 0.

9 0.

25 O.

10 0.

26 0.

11 0.

27 0.

12 0.

28 0.

13 194.

29 0.

14 604.

30 0.

15 198 31 0.

16 0.

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

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OPERATING 05TO REPORT DOCKET NO.

50-293 DATE April 14, 1986 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.

Unit Name Pilgrim 1 Notes 2.

Reporting Period March 1986 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 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)

Nono

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

11. Hours In Reporting Period 744.0 2160.0 116664.0

12. Number Of Hours Reactor Was Critical 250.0 1577.5 79653.1

13. Reactor Reserve Shutdown Hours 0.0

0. 0,

0.0

14. Hours Generator On-Line 229.0 1530.0 77113.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 407424.0 2916528.0 134821992.0

17. Gross Electrical Energy Generated (MWH) 139430.0_

1008240.0 45384844.0

18. Net Electrical Energy Generated (MWH) 133971.0 970201.0 43618099.0

19. Unit Service Factor 30.8 70.8 66.1

20. Unit Availability Factor 30.8 70.8 66.1

21. Unit Capacity Factor (Using MDC Net) 26.9 67.0 55.8

22. Unit Capacity Factor (Using DER Net) 27.5 68.6 57.1

23. Unit Forced Outage Rate 69.2 27.1 9.4

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 4/1/86

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C0ft1ERCIAL OPERATTON (9/77)

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v 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: September 1986 3.

-Scheduled date for restart following refueling: November 1986 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 P8DRB282 assemblies.

In addition, 32 GE60-P8DRB282 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 DOCMET NO. 50-293 Operational Summary for March 1986 The month commenced with the Unit at full power. On the seventh the Unit was removed from _ service due to' a leak in the Reactor Vessel Head Spray line (ref. LER 86--005).

The Unit was returned to service on the thirteenth after successful resolution of the Head Spray problem.

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While' increasing power an increase in unidentified drywell leakage has observed on the fifteenth and a controlled shutdown was initiated.

Investigation revealed that the increased drywell leakage resulted from a weld leak in the "A" reactor water level instrument line_(Ref LER 86-006).

The Unit remained shutdown through the end of the~ month pending completion of the instrument line repair.

Safety Relief Valve Challenges Month of March 1986 There were no safety relief valve challenges during the month.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-293 UNIT NAME Pilar Le 1 DATE April :.4,1986 COMPLETED BY-P. Hamilton TELEPHONE (617)746-7900 REPORT MONTH Mard 1986 1

METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO NO.

DATE TYPEI (HOURS) REASON 2 DOWN REACTOR 3 REPORT #

CODE 4 CODES PREVENT RECURRENCE l

l 10 3/7/86 F

122.0 A

1 86-005 80 PSF Cause - Weld Leak on Head Spray Sys.

Corrective Action

-Cut and Cap Head Spray line l

11 3/15/86 F

393,0 A

1 86-006 JC PSF Cause - Weld leak on Rx. water level instru. line.

Corrective Action

-repair and sleeve affected area of line 1

2 2

3 4&5 F-Fcreed 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-lO22)

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e; Month March 1986 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER RHR Head Spray Weld Leak Pressure Cut and Cap Cut and cap 86-005 Line Surge line line-evaluate similar systems for susceptibility to this problem j

Reactor Reactor Wold Leak Faulty root Reweld and Inspection of 86-006 Protection Water Level pass on sleeve / restore similar nozzles and System Instrument original weld / bound up permanent replacement Line bound up hanger of Nozzle 16A in RFO 7 hanger Instru-IRM D Would not faulty replaced Routine P.M.

N/R l

mentation indicate drive drive during

& Control module module refuel (IEC)

I&C IRM A reading low broken inserted repair drive N/R drive cable detector cable during manually RFO 7 IEC IRM G caused unknown performed N/R N/R unplanned functional test half scram discovered that people were working in drywell close to IRM G Cable Main MSIV timing low oil replaced oil and N/R N/R Steam 203-1B slow set timing HPCI ST-4 Steam leak faulty replaced gasket N/R N/R gasket

BOSTON EDISON COMPANY 500 BOYLSTON STRatT 505 TON, MA55ACHustTTs 02199 wtLLIAM O. HARRtNGTON co = = v.a s=== = + **.a P

BEco Ltr. #86 044

.6m Director Office of Inspection and Enforcement Ll.S. Nuclear Regulatory Commission Wachington, D.C.

20555 Attn: Document Control Desk License No. OPR-35 Docket No. 50-293 1

Subject:

March 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, W. D. Harrington PJH: caw Attachment t

cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 I

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