ML20134E255

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Monthly Operating Rept for July 1985
ML20134E255
Person / Time
Site: Pilgrim
Issue date: 07/31/1985
From: Hamilton P, Harrington W
BOSTON EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-150, NUDOCS 8508200108
Download: ML20134E255 (8)


Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-293 UNIT Pilgrim 1 DATE 8/14/85 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH July 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 663.

17 666.

2 662.

18 664.

3 657.

19 664.

4 558.

20 663.

5 663.

21 601.

6 663.

22 664.

7 663.

23 641.

8 664.

24 631.

9 662.

25 644.

10 664.

26 665.

11

660, 27 595.

12

651, 28 554.

13 663.

29 664.

14 663.

30 665.

l 15 663.

31 665.

l 16 665.

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

8508200108 850731 PDR ADOCK 05000293 R

PDR Ss>\\\\

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OPERATING DATA REPORT DOCKET NO.

50-293 DATE 8/14/85 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.

Unit Name Pilgrim 1 Notes 2.

Reporting Period July 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 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 5087.0 110831.0
12. Number Of Hours Reactor Was Critical 744.0 4613.5 74530.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 4500.3 72068.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1456032.0 8249400.0 125201208.0
17. Gross Electrical Energy Generated (MWH) 501770.0 2837830.0 42070044.0
18. Net Electrical Energy Generated (MWH) 483196.0 2730133.0 40427060.0
19. Unit Service Factor 100.0 88.5 65.0
20. Unit Availability Factor 100.0 88.5 65.0
21. Unit Capacity Factor (Using MDC Net) 96.9 80.1 54.4
22. Unit Capacity Factor (Using DER Net) 99.2 81.9 55.7
23. Unit Forced Outage Rate 0.0 10.2 9.3
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
26. Units In Test Status (Prior to Commercial Operation):

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

l 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:

August 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 GE68-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 spent fuel storage capacity is 1770 fuel assemblies at present.

(b) The planned spent fuel storage capacity is 2320 tus assemblies.

9.

With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 642 fuel assemblies.

UNIT SHUTDOWils AND POWER REDUCTIONS

. DOCKET NO.'

50-293 UNIT NAME Pilgrim 1

-DATE 8/I4/UD COMPLETED BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH July 1985 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS) REASON 2 DOWN REACTOR REPORT #

CODE 4 CODES PREVENT RECURRENCE 3

NO.

DATE TYPE 1 No repo'rtable shutdowns or power reductions occurred during July 1985.

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)

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for July 1985 The month commenced with the unit at 100% power. This power level was maintained until the third when a power reduction was made for a condenser backwash.

On the fourth, the unit was returned to 100% power.

Full power was essentially maintained until the twenty-first when power was reduced in response to loss of steam to the Augmented Off-Gas (AOG) jet compressor.

Subsequent to A0G repairs, the unit was returned to full power on the twenty-second.

On the twenty-third, power level was reduced in response to an increase in the AOG system temperature upstream of the recombiner. The unit was returned to full power on the twenty-fifth after resolution of the AOG temperature increase.

Full power was maintained until the twenty-seventh when power was reduced for a condenser backwash. While at reduced power, maintenance was performed on the "B" reactor feed-pump minimum flow valve. Subsequent to completion of maintenance, the unit was returned to full power on the twenty-eighth and maintained at that level through the end of the month.

Safety Relief Valve Challenges Month of July 1985 Requirement:

NUREG-0737 T.A.P.

II.K.3.3 There were no safety relief valve challenges during the month.

Month July 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER RCIC RCIC Vac.

Received Overload Replaced with new Routine N/R Pump (P-222)

Overload Alarm Heater overload heater.

Maintenance While Running Blown HPCI Hanger Bent Paddle Improper Replaced with new Re-emphasize proper N/R H-23-1-15SS on Snthuer Installation paddle.

installation of Attachment of Attachment hanger attachments.

Containment TRU-9045 TE Failed Age Installed Temporary Replace TE during N/R Atmospheric Modification 85-35.

next opening of Control torus.

Aux.

"A" Diesel Shutdown on sSetpoint Recalibrated Routine N/R Electrical High Jacket Drift instrument.

Maintenance Water Temp.

Aux.

"A" Diesel Water in Fuel Unknown Pumped water out.

Increased sampling LER to be Electrical Oil Storage frequency.

issued.

Tank Aux.

"B" Diesel Leaking Drain Age Rowelded drain PDC 84-41 will N/R Electrical Line to Muffler line.

replace drain line with new design.

Month July 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER HVAC Damper Gears Loose Realigned gears New dampers on LER to be Secondary

. AO/N 83 Misaligned Linkage and tightened

order, issued.

Containment linkage.

Isol.

HVAC Damper Gears Worn Gears Realigned gears New dampers on LER to be Secondary AO/N 82 Misaligned and replaced worn order.

issued.

Containment gears.

Isol.

HVAC Damper Gears Worn Gear Realigned gears New dampers on LER to be Secondary AO/N 90 Misaligned and replaced worn o rder.

issued.

Containment gears.

Isol.

BOSTON EDISON COMPANY B00 BOYLSTON STREET BOSTON, MASSACHUSETTS 02199 wiu. Au o. MARRINGTON cc.............s =

9 BECo Ltr. #85-150 m.6...

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:

July 1985 Monthly Report

Dear Sir:

In accordance with PNPS Technical Specification G.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

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