ML20128K605

Monthly Operating Rept for June 1985

ML20128K605
Person / Time
Site:	Pilgrim
Issue date:	06/30/1985
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-128, NUDOCS 8507240175
Download: ML20128K605 (7)

Text

r AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 UNIT Pilgrim 1 DATE July 12, 1985 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH June 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 627. 17 476.

2 480. 18 611.

3 666, 19 666.

4 666. 20 665.

5 666. 21 665.

6 665. 22 664.

7 662. 23 572.

8 548. 24 667.

9 666. 25 666.

10 667. 26 664.

11 666. 27 358.

12 666. 28 294.

13 665. 29 608.

14 520. 30 662.

15 7. 31 N/A-16 13.

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.

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OPERATING DATA REPORT DOCKET NO. 50-293 DATE July 12, 1985 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS

1. Unit Name Pilgrim 1 Notes

2. Reporting Period June 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 NWe)_ 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 tWe) None

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

11. Hours In Reporting Period 720.0 4343.0 110087.0

12. Number Of Hours Reactor Was Critical 693.5 3869.5 73786.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator _On-Line 676.5 3756.3 71324.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1243536.0 6793368.0 123745176.0

17. Gross Electrical Energy Generated (MWH) 426070.0 2336060.0 41568274.0

18. Net Electrical Energy Generated (MWH) 410000.0 2246937.0 _39943864.0

19. Unit Service Factor 94.0 86.5 64.8

20. Unit Availability Factor 94.0 86.5 64.8

21. Unit Capacity Factor (Using MDC Net) 85.0 77.2 54.2

22. Unit Capacity Factor (Using DER Net) 86.9 79.0 55.4

23. Unit Forced Outage Rate 0.0 11.9 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 -

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C0fmERCIAL OPERATION (9/77)

F 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 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 fuel assemblies.

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

- e BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for June 1985 The month commenced with the unit at 100% power. On the first, power was reduced to approximately 50% to perform a condenser backwash. While at reduced power, maintenance was performed on the "A" travelling screen and a solenoid valve (SV 122) for control rod drive 10-23.

The unit was returned to 100% power on the second and maintained at that level until the eighth when power was reduced for main condenser backwashing and control rod scram timing. During this time frame, the HPCI system and a containment cooling sub-system valve (MO-1001-34A) were found inoperable. Licensee Event Report (LER)85-012 details the HPCI event.

On the eighth, MO-1001-34A was returned to service, the unit was returned to 100%

power and maintained at that level until the fourteenth. HPCI was returned to service on the tenth. On the fourteenth, a unit shutdown commenced for planned turbine maintenance. Several hours after the generator was taken off-line, the reactor scrammed on high water level (Ref.: LER 85-014). The generator was synchronized to the grid on the sixteenth af ter completion of turbine maintenance.

On the seventeenth, power was increased to an average daily level of 71%.

Maintenance was performed on the first point heater extraction valve and a control rod pattern exchange was completed.

From the eighteenth through the twenty-sixth, the unit essentially .naintained 100%

power with the exception of the weekend when a pmaer reduction was made for a condenser backwash. On the twenty-fourth, an electrical storm caused an audible surge (bump) on the main generator although power generation was not interrupted.

On the twenty-seventh and twenty-eighth, power was reduced to approximately 50% in response to fouling of the travelling screens due to heavy seas. The unit was '

returned to 100% power on the twenty-ninth and maintained at this level through the thirtieth. HPCI was removed from service on the thirtieth for maintenance on the turbine exhaust diaphragm. The system was returned to service on the same day.

Safety Relief Valve Challenges Month of June 1985 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during the month.

a UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-293 UNIT NAME Pilgrim 1 DATE July 12, 1985 COMPLETEU BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH June 1985 METHOO OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION.TO NO, DATE' TYPEI (HOURS)- REASON 2' DOWN REACTOR 3 REPORT # CODE 4 COOE5 PREVENT RECURRENCE

- 14 6/2/05 S O,0 H 5 N/A ZZ ZZ Reduced power to backwash main condenser.

15' 6/15'/85 S 43.5 B 3 85-014 ZZ ZZ Took unit off-line for planned turbine maintenance. RA scrammed on high level while off-line.

'16 .6/27/85 F O.0 H 5 N/A ZZ ZZ Reduced power due to fouled travelling screens from heavy seas.

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 (NOREG-lO22)

O

• e

Month June 1985 PILGRIM NUCLEAR POWER STATION.

MAJOR SAFETY RELATED MAINTENANCE I

l CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER l

HPCI Turbine Tripped and Control Valve Removed test Ref.: LER 85-12-01 Isolated Linkage equipment causing Binding binding, HPCI Turbine Ruptured. Fatigue Replaced disk. N/R - Routine N/A

-Exhaust' Maintenance Rupture Disk i RHR MO-1001-34A Overload Defective Replaced hand-wheel N/R - Routine N/A Alarm Hand-Wheel _ drive gear housing Maintenance Drive Gear K. limit switch Housing drive gear.

RWCU DPIS #1244 Out of Setpoint Recalibrated N/R N/A Calibration Drift HVAC - Damper AON-90 Broken Drive Aging Gear Replaced gear. Routine N/A Secondary Gear Maintenance Contain- (New Design ment Isol. Dampers on Order) 1J l

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BOSTON EDISON COMPANY 800 WayLaTON STREET WasTON, MARSAcHuSETTs 02199 WILLIAM D. HARRINGTON senseen wees peesseeest July 12,1985 BECo Ltr. #852128 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:

June 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 attaghed 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 h

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