ML20095A326

Monthly Operating Rept for Mar 1992 for Pilgrim Unit 1.W/

ML20095A326
Person / Time
Site:	Pilgrim
Issue date:	03/31/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-043, 92-43, NUDOCS 9204160261
Download: ML20095A326 (7)

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. BOSTON EDISON Pdgnm Nucicar Power Sta+'

Porky He!! Road Plymouth, Massachusetts 02360 E. Thomas Boulette, PhD

%ce President Nuclear Ope'ations and Staton Director April 14, 1992 BECo Ltr. #92-043 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293

Subject:

March 1992 Honthly Report 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. Should you have any questions concerning this report please contact me directly.

0h. )$LO & , 1-E. Thomas ule'tke l' HJH/bal Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19405 Mr. R. B. Eaton Div. of Reactor Projects I/II Office of NRR - USNRC One White Flint North : Hail Stop 14D1 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspe-tor 16001G 9204160261 920331 1 DR ADOCK 0500 3 I i _ _ _ . _ _ _ _ _ _ _ _

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 UNIT Pilarim 1 DATE Anril 14. 1992 COMPLETED BY _H. Hunro TELEPHONE (508) 747-8474 HONTH March 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (HWe-Net) 1 666 . 17 667 2 666 18 665 3 667 19 665 4 666 _ 20 665 5 666 21 665 6 616 2? 665 _,_

7 665 23 665 8 665 24 665 9 665 25 665 10 665 26 109 11 664 27 0 12 665 28 0 13 664 29 0 14 665 30 0 15 665 31 0 16 665 This fo*mt lists the average daily unit power level in HWe-Net for each day in the - 3rting month, computed to the nearest whole megawatt.

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, OPERATING DATA REPORT 4 .

DOCKET NO. 50-293 DATE Anr 14. 1992 COMPLETED BY H. honro TELEPHONE _1528) 747-8474 >

OPERATING STATUS Notes

1. Unit Name Pilarim 1

2. Reporting Period March 1992 __ s

3. Licensed Thermal Power (MHt) 1928

4. Nameplate Rating (Gross HHe) 678

5. Design Electrical Rating (Net MWe)___ 655

6. Maximum Dependable Capacity (Gross HHe) 696

7. Maximum Dependable Capacity (Net MHe) 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 HHe) None

10. Reasons For Restrictions, If Any N/A '~

This Month Yr-to-Data Cumulative

11. Hours In Reporting Period 744.0 2184.0 169272.0

12. Number Of Hours Reactor Has Critical 614.6 2054.6 100415.2

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line (Lat6 2050.6 96553.5

15. Unit Reserve Shutdown Hours 0.0 0.Q Q1Q 16, Gross Thermal Energy Generated (MHH) 12034QH2O 4039992.0 167744472.0

17. Gross Electrical Energy Generated (MHH) 415950.0 1397500.0 56603914.0

18. Het Electrical Energy Generated (MHH) 400576.0 _1335773.0 54396721.Q

19. Unit Service Factor 82.1 93.9 57 9

20. Unit Availabliity Factor 82.1 9122 57.0

21. Unit Capacity Factor (Using MDC Net) 80.4 92.0 48.0

22. Unit Capacity Factor (Using DER Net) 82.2 94.1 49.1

23. Unit Forced Outage Rate 17.9 6.1 1115

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 4/9/92 4

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BOSTON EDISON COMPANY

, PILGRIM NUCLEAR P0HER STATION DQCKET NO. 50-293 '

Qaqa tional Summary for March 1992 The unit started tne reporting period at approximately 100 percent core 4 thermal power (CTP) and maintained that level until March 25 with the exception of a brief downpower on March 6 to perform turbine testing and control rod exercising. On March 25 while performing post work testing following replacement of the RCIC EGR unit, erratic indication of the RCIC Inboard Steam Isolation Valve H01301-16 was noted. The valve was declared inoperable and the RCIC Outboard Steam Isolation Valle H01301-17 was closed and deenergized. The decision was made to shut the plant down to investigate ar.d repair the H01301-16 valve. On March 26 the turbine was tripped and the main generator was taken off the grid at 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br />. At 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> the reactor was manually shutdown. There were two Engineered Safety Feature (ESF) actuations on March 26 and one on March 27 during the controlled shutdown.

High water icvel spiking occurred on the reactor water lovel instruments which caused two of the Group 1 isolations. The other Group 1 isolation was caused when the Main Steam Isolation Valves were opened causing a pressure transient resulting in a level increase. A root cause analysis team was formed to investigate the cause of the spiking. The unit ended the reporting period in cold shutdown with a forced out ge in progress iaaking repairs that could not be performed on line. Hinor power reductions were iniitated on March 13 and 20 to perform control rod exercises.

Safety Relief Valve Challenges tiQnth of March 1992 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during this reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo ltr. #81-01 dated 01/05/81.

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REFlJELING- INFORMATIQti 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: April 3, 1993

3. Sch..duled date for restart following next refueling: June 8, 1993

4. Due to their similarity, requests 4, 5, & 6 are respor.ded to collectively under #6.

5. See #6.

6. The new fuel loaded during the 1991 refueling outage was of the same design as loaded In the previous outage and consisted of 168 assemblies.

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

(b) There are 1489 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 831 fuel assemblies.

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Honth March 1992 '

PILGRIM NUCLEAR P0HER STATION 1 MAJOR SArETY RELATED MAINTENANCE ,

SYSTEM COMPONENT HALFUNCTION CAUSE MAINTENANCE CORRECTIVE A^ TION TO ASSOCIATED PREVENT RECURREN_CE_ LER No Major Safety Related Maintenance was completed during the reporting period. Per the guidelines in CDHi 3.02-03 Major Safety Related Maintenance is reported only after the work has been completed and the Maintenance Request is closed.

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UNIT SHUTDOWNS AND POWER REDUCTIO';5 DOCKET NO. 50-293 NAME Pilorim 1 - '.

DATE April 14, 1992

COMPLETED BY H. Munro_

TELEPHONE (508) 747-8474 REPORT HONTH Harch 1992 ,

METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT COM ACTION TO PREVENT SYSTEg NO. DATE TYPEI (HOURS) REASON 2 DOHN REACTOR 3 REPORT # CODE COD]>NENT E RECURRENCE 92-003-00 BN ISV Failure of MOV 1301-16 03 3/26/92 F 133.4 A 1 valve. Forced outage.

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1 2 2 3 4&5 l F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Haint or Test G-Oper Error 2-Manual Scram Instr'Jctions for C-Refueling- H-Other 3-Auto Scram Preparation of D-Reculatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event' Report

& License Examination 9-Other (LER) File (NUREG-1022) l I

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