ML20107C388

Monthly Operating Rept for Jan 1985

ML20107C388
Person / Time
Site:	Pilgrim
Issue date:	01/31/1985
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-032, 85-32, NUDOCS 8502210296
Download: ML20107C388 (7)

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AVERAGE DAILY UNIT POWER LEVEL t a DOCKET NO. 50-293 UNIT Pilarim 1 DATE February 13, 1985 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH January 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 97. 17 314.

2 0. 18 428.

3 0. 19 600.

4 0. 20 652.

5 O. 21 644.

6 0. 22 659.

7 0. 23 657.

8 0. 24 537.

9 23. 25 512.

10 164. 26 666.

11 182. 27 667.

12 285. 28 640.

13 293. 29 494.

14 316. 30 668.

15 461. 31 670.

16 474.

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.

8502210296 850131

- QDR ADOCK 05000293 PDR 8A  !

4 ks

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OPERATING DATA REPORT DOCKET NO. 50-293 DATE February 13. 1985 COMPLETED 8Y P. Hamilton (617)746-7900 TELEPHONE OPERATING STATUS

1. Unit Name Pilaris 1 Notes

2. Reporting Period January 1985

3. Licensed Thermal- Power (Wt) 1998

4. - Nameplate Rating (Gross MWe) 678

5. Design Electrical Rating (Net MWe) 655

6. Maximum Dependable Capacity (Gross Me) 683

7. Maximum Dependable Capacity (Net Me) 663

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 l

1-This Month Yr-to-Date Cumulative

11. Hours'In Reporting Period 744.0 744.0 106488.0'

j. .12. Number Of Hours Reactor Was Critical 600.0 600.0 70516.6-

-13E Reactor Reserve Shutdown Hours 0.0 0.0 0.0 I 14. Hours Generator On-Line 557.0 557.0 68125.5

.15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 1 *'16. Gross Thermal Energy Generated (MWH) '822504.0' 822504.0 -117774312.0 l- { 17.' Gross Electrical Energy Generated (MWH). 278060.0 278060.0 39510274.0 l 18. Net Electrical Energy, Generated (WH) -266497.0 266497.0 37963424.0

.19. Unit Service Factor 74.9 74.9 64.0 120. Unit-1.vailability Factor. 74.9 74.9 64.0

21. Unit Capacity Factor'(Using MDC Net) 54.0 54.0 53.8 L 22. Unit Capacity. Factor (Using DER Net) 54.7 54.7 54.4 t 23. Unit Forced Outage Rate 25.1 25.1 9.4-l 24. Shutdowns Scheduled Over Next 6' Months (Type, Date, and Duration of Each)

l L ,

- 25.TIf' Shut Down At End Of Report Period, Estimated Date of Startup -

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

Forecast Achieved

[ INITIAL CRITICALITY L -INITIAL ELECTRICITY i l COMMERCIAL OPERATION

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(9/77)

This: item was misstated in the December 1984 Operating

( 1* --

L Data-Report. The' correct figures for December are 19176.0 MWt I for.the month,119176.0 MWt for-the year-to-date, and 116951808.0 MWt cumulative.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-293 UNIT NAME Pilgrim 1 DATE rebruary 13, 1985 COMPLETED BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH January 1985 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 1- 1/1/85 F 187.0 H 1 85-001-00 BR N/A Cause of the SLCS Inop l

, due to debris in system. Corrective action was to drain, clean, and/or flush the

, system.

i 2 1/17/85 S 0.0 B N/A N/A N/A N/A N/A - Power reduced for testing and maintenance.

T 3 1/29/85 F 0.0 B N/A N/A N/A N/A N/A - Power reduced for maintenance.

i 1

1 2 2 3 4&5 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H 4

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 l E-Operator Training 5-Reduced Load Licensee Event Report l & License Examination 9-Other (LER) File (NUREG-1022)

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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.

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

6. The new fuel, which.is being loaded this refueling outage, is of the same P8x8R design, as loaded the previous outage and consists of 160 P8DRB282 assemblies and 32 GE6B-P80RB282 assemblies.

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' fuel' assemblies.

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

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for January 1985 The unit was removed from service on the first of the month as a result of problems with the standby liquid control system. During the shutdown, work was also performed on the main condenser and the drywell to torus vacuum breakers. -

The_ reactor was made critical on the seventh, at which time the head spray check valve was found to be leaking. The valve was repaired and, on the ninth, the generator was synchronized to the grid.

Between the twelfth and the eighteenth, power was maintained at an average daily level between 40% and 70% to facilitate operational and reactor engineering testing. Subsequent to the tests, power was reduced to approximately 38% to verify jet pump flow data and repaired the "A" feedwater regulating valve.

Between the nineteenth and the twenty-eighth, the average daily power level ranged between 76% and 985. During this time frame, both recirculation pumps were tripped for testing.

On the twenty-ninth, power was reduced to approximately 74% due to a high dif ferential temperature between cooling water intake and discharge.

On the thirtieth, after resolution of the high differential temperature, power was increased to 100% and maintained at that level through the end of the month.

Safety Relief Valve Challenges Month of January 1985 Requirement: NUREG-0737 T.A.P. -II.K.3.3 Date: . January 8,1985 (Manually Opened Twice)

Valve #: RV-203-3A Reason: Check High Tail Pipe Temperature Test New Solenoid Valve

Month January 1985 -

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER SLCS Relief System declared Debris in Drained, cleaned, Locked / Bolted 85-001-00

. Valve inoperable. System and/or flushed, SLCS Tank the system. Covers HPCI 2301-3 Would not close Limit switch Adjust limit N/R N/R Steam during out f switch.

-Admission surveillance. adj .cment.

Valve HPCI- Y Strainer Leaking Bad Replaced N/R N/R 8048 Gasket gasket.

RPS PS-1001-23A Actuating Faulty Repaired N/R N/R High Drywell lever Pressure misaligned.

Switch RPS LIS-263-73B Out of Probable Recalibrated N/R N/R Reactor calibration. setpoint Water Level drif t.

Indication Switch RPS Main Steam Gut of Setpoint Recalibrated Increased N/R Line Low calibration. Drift calibration Pressure surveillance Switches frequency.

PS-261-30A&D Main Safety High Tail Faulty. Replaced Replaced solenoid N/R Steam Relief Valve Pipe Temp. Solenoid solenoid valve. valve.

RHR Head Spray Leaking Body To Furmanited N/R N/R Check Valve slightly. Bonnet Flange Leak

• EOSTON EDISON COMPANY B00 BOvLaTON STREET BOSTON, M AssACHUsETTs 02199 WILLIAM D. HARRINGTON I.'((."" ~"'"" February 13, 1985 BECo Ltr. #85- 032 Director Office of Inspection and Enforcement U.S. Nuclear Regulatary Commission Washington, D.C. 20555 Attn: Document Control Desk License No. DPR-35 Docket No. 50-293

Subject:

January 1985 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, I

[ ^^^^!'

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W. D. Harrington

caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 pzA g