ML20126M674

Monthly Operating Rept for May 1985

ML20126M674
Person / Time
Site:	Pilgrim
Issue date:	05/31/1985
From:	Hamilton P, Harrington W BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-106, NUDOCS 8506200422
Download: ML20126M674 (8)

Text

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 UNIT Pilgrim 1 DATE June 13, 1985 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 I

MONTH May 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i L

1 667, 17 660.

2 659. 18 666.

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3 641. 19 666.

4 298. 20 667.

5 401. 21 666.

6 650. 22 665.

7 659, 23 655, 8 608. 24 660.

9 657. 25 662.

10 665. 26 554.

i 11 667. 27 667.

12 666. 28 666, i

13 662. 29 646.

14 666. 30 660.

15 628. 31 664.

I 16 575.

INSTRUCTIONS On this format, list the average daily unit pmaer level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

8506200422 850 DR ADOCK O p 3 gg 9.

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- OPERATI30G DATA REPORT DOCKET 20. 50-293 DATE Je=e 13, 1955 COPFLETED BY P. Hamilton TELEPHOAE (617)746-7900  ;

OPERATING STATUS

1. Unit Name Pilgris 1 Motes

2. Reporting Period Ptar 1985

3. Licensed Thermal Power ( N t) 1998 ~

4 Maseplate Rating (Gross Ptie) 678

5. Design Electrical Rating (Eet N e) 655

! 6. Ptasimus Dependable Capacity (Gross Ftse) 690

7. Ptaximus Dependable Capacity (het Ftde) 670

8. If Changes Occur in Capacity Ratings (Itees Number 3 Through 7) Since Last  ;

Report, Give Reasons:

Revised POC Gross / Det Upward per Planaaeeent Directive, dated 5/2/85. ,

9. Power Level To insich Restricted, If Any (Net Ftue) Ecce r

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

I, This Month Y Nto-Cate Cumulative

11. Hours In Reportirw3 Period 744.0 3523.0 109367.0- '

12. Nueber Of Mours Reactor idas Critical 744.0 3176.0 73092.6

13. Reactor Reserve Shutdoesn Hours 0.0 0.0 00 14 Hours Generater On-Li w 744.O 3079.t 70648.3

15. Unit Reserve Shutdennt Hours 0.0 0.0 0.0

16. Gross Thermal Erergy Generated (ftH) 1415712.0 5549532.0 1225016aO.O 17." Gross Electrical Energy Generated (PtM) 4594a0.0 1909990.0 41142204.0

18. Det Electrical Energy Generated (PtN) 470229.0 1836937.0 39533864.0 -

19. Unit Service Factor 100.0 95.0 64.6

20. Unit Availability Factor 100.0 95.0 64.6

21. Unit Capacity Factor (Using POC Met) 94.3 75.7 54.0

22. Unit Capacity Factor (Using DER Eet) 96.5 77.4 55.2

23. Unit Forced Outage Rate 0.0 14.2 9.5 '

24 Shutdomass Scheduled Over heat 5 Months (Type, Date, and Daratico of Each):

hoce  :

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25. If Shut Doman At Erd Of Report Period, Estimated Date 'of Startup -

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

Forecast Achieved INITIAL CRITICALITY. t i INITIAL ELECTRICITY CCrf1E9CIAL C9EBATIOtt

! (9/77).

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i REFUELING INFORMATION 1

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.

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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 j P80RB282 assemblies. In addition, 32 GE6D-P8DRB282 assemblies were also j loaded.

7. (a) There are 580 fuel assemblies in the core.

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(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 l assemblies at present..

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

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j 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 May 1985 The month commenced with the unit at approximately 100% power which was maintained until the third when power was reduced to facilitate cleaning of the condenser waterboxes which became fouled due to rough seas. On the fourth and fifth, both sides of the condenser were backwashed and heat treated and the "B" recirculation Motor Generator (MG) set brushes were changed out.

Full power was achieved on the sixth and essentially maintained until the eighth when a slight power reduction was made in response to high differential pressure across the condensate demineralizers. Subsequent to maintenance on the demineralizers, power was increased and maintained at an average daily level between 98% and 100% until the fif teenth. During that time frame, a control rod exercise was performed and hydrogen injection testing was successfully completed.

On the sixteenth, a slight power reduction was made to perform a condenser backwash. Also on the sixteenth, the "B" Emergency Diesel Generator was declared inoperable when the pre-lube pump tripped and would not restart. This, combined with the discovery of several potentially degraded pipe hangers in the HPCI, RCIC, and RHR systems, resulted in the commencement of a shutdown and the declaration of an Unusual Event at 2219 hrs. At 0017 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> on the seventeenth, the "B" Diesel lube oil pump trouble shooting was completed, the Diesel declared operable, and the shutdown and Unusual Event were secured. The hanger discrepancies were also resolved on the seventeenth and the unit was returned to full power.

On the eighteenth, the HPCI system was declared inoperable (Ref.: LER 85-012) when a turbine exhaust line snubber was found broken af ter the start of a HPCI surveillance test. Power level was maintained between 98% and 100% until the twenty-sixth. During that time frame, the "B" Diesel was declared inoperable on the twenty-third when the pre-lube pump again tripped and would not restart. This, combined with an inoperable HPCI system, resulted in the initiation of a shutdown and the declaration of an Unusual Event. The pre-lube pump / motor unit was replaced and the "B" Diesel was returned to service on the same day. At that time, the shutdown and Unusual Event were secured. The HPCI system was declared operable on the twenty-fourth.

On the twenty-sixth, power was reduced to perform a condenser backwash and to investigate a suspected turbine control valve oil leak in the condenser compartment. power was increased on the twenty-seventh and maintained between 96%

and 100% until the end of the month. During that time frame, the HPCI system was declared inoperable on the twenty-ninth when the system isolated as the result of a HPCI steam line flow differential pressure switch failure (Ref.: LER 85-013 to be issued). The HPCI system was returned to service on the twenty-ninth.

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

UNIT SHUTD0bEIS AND POWER REDUCTIONS DOCKET NO. 50$-293 .

. UNIT NAME. Pilerie 1

DATE. June 13, 1985-COMPLETED BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH May'1905 METHOO 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 13, 5/4/85 F O.0 8 5 N/A ZZ ZZ- . Reduced power to clean condenser waterboxes-and backwash.

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 .

l 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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. - _.m -- - r -. + ,

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Month May 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE' MAINTENANCE TO PREVENT ASSOCIATED i

RECURRENCE LER

' Closed MOV-40608 Noisy Worn Motor Installed new Routine N/R Cooling Pinion Gear gears. Maintenance Water & Shaft Gear Diesel "B" Diesel Would not pump Broken Teeth Installed new Routine N/R Generator Pre-Lube Oil oil, on Pump Gear pump and motor. Maintenance Pump & Motor RHR MOV-lool-37 Would not open Valve was in Manually closed Routine N/R from Control mid-position. valve & adjusted Maintenance Switch. Limit Switch so valve would complete cycle.

RHR MOV-lool-34A Would not Motor Installed new Routine N/R operate. Windings motor and new Maintenance Shorted heaters.

RHR RHR Flow Indicator Instrument Recalibrated; Routine N/R Indicator -Reading Upscale Drift returned to normal. Maintenance Main 1705-2A & 2C Low Calibration Minor Set Recalibrated Routine N/R Steam Main Steam & Recorder Point Drift drawer & recorder. Maintenance Line Radiation Monitors Salt "C" SSW Pump Reduced Pump Impeller & Overhauled pump. Routine N/R Service Head Wearing Ring Maintenance Water Wear

r Month May 1985 l

i PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE l

CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED l RECURRENCE LER HVAC Damper Cracked Gear Aging Gear Replaced gear. Routine N/R l Secondary AON 81 Maintenance I

Contain. (New Design Isolation Dampers on Order) l HVAC Damper Gears Unmeshed Adjustment Re-Adjustment Routine N/R Secondary AON 83 & Cracked Aging Gear Replaced gear. Maintenance Contain. (New Design Isolation Dampers on Order)

HPCI DPIS 2353 Isolated HPCI None Found Replaced internal Routine LER 85-013 System parts of switch. Maintenance (To be issued.)

HPCI HPCI Snubber Broken Snubber Anomalous Rebuild snubber & Routine LER 85-012 A-8661 Extension Event (Water- redesigned Maintenance (To be Hammer) installation. issued.)

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BOSTON ED15DN COMPANY 800 EDYLSTON STREET BOSTON, MASSAcr4UEETTs 02199 WILLIAM D. HARRINGTON Cemesa vees essessant e m EAR June 13,1985 BECo Ltr. #95-106 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:

May 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, W. D. Harrington

caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 7/