ML20207C322

Monthly Operating Rept for June 1986

ML20207C322
Person / Time
Site:	Pilgrim
Issue date:	06/30/1986
From:	Hamilton P, Lydon J BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-100, NUDOCS 8607210337
Download: ML20207C322 (7)

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l- 1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 UNIT Pilgrim 1 DATE COMPLETED BY P. Hamilton

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TELEPHONE (617)746-7900 i

i MONTH June 1986 i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0. 17 0, i

2 0. 18 0.

l 3 0. 19 0.

4 0. 20 0.

J 5 O. 21 0.

6 0. 22 0.

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7 0. 23 0.

i i 8 0. 24 0.

l 9 0. 25 O. l 1

10 0. 26 0.

11 0. 27 0.

I 12 0. 28 0.

13 0. 29 0.

14 0. 30 0.

15 0 31 N/A

, 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.

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i 8607210337 860630 PDR ADOCK 0D000293 R PDP -.

OPERATING DATA REPORT DOCKET NO. 50-293 DATE COMPLETED BY P. Hamilton l

TELEPHONE (617)746-7900 OPERATING STATUS

1. Unit Name Pilgrim 1 Notes

2. Reporting Period June 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 (Not MWe) None

10. Reasons For Restrictions, If Any N/A T

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 720.0 4343.0 118847.0

12. Number Of Hours Reactor Was 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 4

16. Gross Thermal Energy Generated (MWH) 0.0 3094416.0 134999880.0

17. Gross Electrical Energy Generated (MWH) 0.0 1068000.0 45444604.0 1

18. Not Electrical Energy Generated (MWH) 0.0 1027531.0 43675429.0

19. Unit Service Factor 0.0 37.9 65.0

20. Unit Availability Factor 0.0 37.9 65.0

21. Unit Capacity Factor (Using MDC Net) 0.0 35.3 54.8

22. Unit Capacity Factor (Using DER Net) OO 36.1 56.1

23. Unit Forced Outage Rate 100.0 61.5 11.5

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 -

August 1986.

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

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

REBLELING_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: 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 P8DRB282 assemblies. In addition, 32 GE68-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 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 June 1986 r

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The Unit remained shutdown throughout the month to address various hardware and '

administrative items. On the sixteenth a new contract was ratified by Boston Edison union personnel after a four week work stoppage. Startup is tentatively planned for August 1986 pending completion of RHR pump inspections, local leak rate

testing, and NRC authorization (ref. Confirmatory Action Letter 86-10).

Safety Relief Valve Challenges Month of June 1986 l Requirement: NUREG-0737 T.A.P. II.K.3.3

There were no safety relief valve challenges during the month.

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UNIT SilVTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-293 UNIT NAME Pilgrim 1 DATE COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 REPORT MONTH June 1986 NETilOD 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 08 6/1/86 F 720.0 4 N/A N/A N/A The unit remained (continued) shutdown to address various hardware and ad-ministrative items including RilR pump wear ring inspect-ions and local leak rate testing.

1 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-lO22)

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l Month June 1986 PILGRIM NUCLEAR POWER STATION

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I MAJOR SAFETY RELATED MAINTENANCE i

CORRECTIVE ACTION r i SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED

! RECURRENCE LER

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I Excessive Routine Salt Pump P-208B Worn bearings Replaced upper / N/A 2

Service vibration lower bearings maintenance j Water and four bolts  :

Replaced L.O.

Auxiliary "A" Emergency Lube oil temp Faulty Routine N/A .

Electrical Diesel out of spec L.O Heater Heater maintenance I I

f 1

j Secondary Damper Gears Design Realign New dampers N/A Containment AO/N 95 misaligned on order i Isolation ,

4 f HPCI Area Temp Set point Set Point Drift Recalibrate Trend surveillance N/A Switches higher than results and take

2370C & 2372C Watch Engineer action as required i limits I

l Primary MO-lool-28A Indicated As found testing Refurbished -Additional admin 86-009-01 -

l Containment seat leakage indicated leakage valve controls to be issued

Isolation within limits. -Enhanced i System Indicated leak- instrumentation j age discussed -Addition of j in response to controlled leakoff I CAL 86-10. in secondary system l

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1 Executive Oikea '

800 Boytston Street l l Boston, Massachusetts 02199 Julyl4 , 1986 ..

James M. Lydon ' I BECo Ltr. #86- 100\

Chief Operating Officer '

l Director Office of Inspection and Enforcement' U.S. Nuclear Regulatory Commission Washington, D.C. 20555 .

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1 Attn: Document Control Desk s Lice'nse No. DPR-35 l \ Docket Ng 50-293 l 1 ,

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Subject:

June 1986 Monthly Report 1

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Dear Sir:

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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. '

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, Respec*:. fully submitted, l \

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J. M. Lydon ,

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Attachment

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i cc: Regional Administrator, Region I '

U.S. Nuclear Regulatory Commission 631 Park Avenue \

King of Prussia, PA 19406 i

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