ML20197H698

Monthly Operating Rept for Apr 1986

ML20197H698
Person / Time
Site:	Pilgrim
Issue date:	04/30/1986
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-064, 86-64, NUDOCS 8605190242
Download: ML20197H698 (7)

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OPERATING DATA REPORT DOCKET NO.

50-293 DATE 5/15/86 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.

Unit Name Pilgrim 1 2.

Reporting Period April 1986 Notes 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 (Not 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 719.0 2879.0 117383.0

12. Number Of Hours Reactor Was Critical 138.0 1715.5 79791.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 116.0 1646.0 77229.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 177888.0 3094416.0 134999880.0

17. Gross Electrical Energy Generated (MWH) 59760.0 1068000.0 45444604.0

18. Net Electrical Energy Generated (MWH) 57330.0 1027531.0 __43675429.0

19. Unit Service Factor 16.1 57.2 65_.8

20. Unit Availability Factor 16.1 57.2 65.8

21. Unit Capacity Factor (Using MDC Net) 11.9 53.3 55.5 t

22. Unit Capacity Factor (Using DER Net) 12.2 54.5 56.8

23. Unit Forced Outage Rate 83.9 41.6 10.0

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 5/16/86

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I

(9/77)

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8605190242 860430 PDR ADOCK 05000293 R

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AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO.

50-293 UNIT Pilgrim 1 DATE 5/15/86 COMPLETED BY P. Hami1 ton TELEPHONE (617)746-7900 I

MONTH April 1986 3

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (f%Ie-Net)

(MWe-Net) 1 116.

17 0.

2 521.

18 0.

3 653.

19 O.

4 428.

20 O.

5 O.

21 0.

6

.O.

22 O.

7 0.

23 0.

8 0.

24 0.

9 0.

25 O.

10 125.

26 O.

11 544.

27 O.

12 2.

28 O.

13 0.

29 0,

14 0.

30 O.

15 0

31 N/A 16 O.

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.

l REFUELING INFORMATION The following refueling information is included in the Monthly Report as requesteo 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, 'ocket Number s

50-293.

2.

Scheduled date for next Refueling Shutdown: October 1986 3.

Scheduled date for restart following refueling:

January 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 GE6B-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.

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for April 1986 i

The Unit was restarted on the first after completion of repairs on the "A" reactor water level instrumentation line.

Power was increased to an average daily level of 97% on the third. On the fourth the unit was removed from service to repair a i

turbine control valve oil leak. While shutting down the main steam line isolation valves (MSIV's) closed resulting in a reactor scram.

After the scram operations personnel experienced difficulty in opening the outboard MSIV's (ref. LER 86-008).

The unit was returned to service on the tenth following repair work on the turbine j

control valve and MSIV's.

On the eleventh a controlled shutdown was initiated and an unusual event declared when two in series primar,v containment isolation valves indicated seat leakage. While shutting down the MSIV's again unexpectedly closed resulting in a reactor scram (ref. LER 86-008).

The unit remained shutdown through the end of the reporting period.

Restart of the reactor is pending NRC authorization in accordance with Confirmatory Action Letter 86-10.

Safety Relief Valve Challenges Month of April 1986 l

i There were no safety relief valve challenges during the month.

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i Month April 1986 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER RHR MO LOO 1-36A Seat Leakage Broken Installed new New Seat ordered, N/A Valve Seat temporary seat scheduled for installation during next refuel Main Outboard Would not Pilot poppet Replace Pilot Plan to modify 86-08-01 Steam isolation reopen after disassociated poppets method of (To be issued) valves scrams from stem attaching pilot 4/4 & 4/12 Salt "A"

Pump Noisy Normal Replaced bearings /

N/R N/A Service Bearings wear Balanced Unit Water.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-293 UNIT NAME Pilgrim 1 DATE 5/15/86 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 REPORT MONTH __. April 1986 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO NO.

DATE TYPEI (HOURS) REC 9??

DOWN REACTOR 3 REPORT #

CODE 4 CODES PREVENT RECURRENCE 06

'3/15/86 F

393.0 A

1 86-006 JC PSF Cause - Weld leak on Rx. water level 06 4/1/86 F

11.0 A

1 86-006 JC PSF instru. line.

(continued)

Corrective Action

-repair and sleeve affected area of line 07 4/4/86 F

137.5 A

1,3 86-008 ZZ ZZZ Unplanned MSIV isolation and 08 4/12/86 F

454.5 A

1,3 86-008 ZZ ZZZ reactor scram -

cause and corrective action under investigation 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) i w -

BOSTON EOlBON COMPANY BDO BOYLBTON STREET BOSTON, MASSACHUSETTS 02199 WILLIAM D. H ARRtN GTON m..............,

Y u.6 4.

BECo Ltr. #86-064 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:

April 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, e

i W. D. Harrington PJH:vep Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 s

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