ML20245B737

Monthly Operating Rept for Mar 1989 for Pilgrim Nuclear Power Station

ML20245B737
Person / Time
Site:	Pilgrim
Issue date:	03/31/1989
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-055, 89-55, NUDOCS 8904260244
Download: ML20245B737 (7)

Text

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h  !+ ; w AVERAGE DAILY UNIT P0HER LEVEL' DOCKET NO. 50-293

< s - , UNIT Pilarim 1 DATE APr21 13, 1989 COMPLETED BY H. Munro TELEPHONE- (508) 747-8474 HONTH March 1989 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Net) (MHe-Net) 1 0 17 115 2 0 18 116

.3 0 19 119 4- 2 20 118 5 0 21 121

, 6 0 22 125 7 0 23 125

'8 0 24 125 9 0 25 122 10 0 26 119 11 0 27 118 12 24 28 120 13 110 29 124

14. 95 30 125 15 79 31 123 16' 100 This format lists the average daily unit power level in MHe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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OPERATING DATA REPORT DOCKET NO. 50-293 DATE April 13. 1989 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 OPERATING STATUS Notes

1. Unit Name Pilarim 1

2. Reporting Period March 1989

3. Licensed Thermal Power (MHt) ________ 1993

4. Nameplate Rating (Gross MHe) 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) 25% Core Thermal Power

10. Reasons For Restrictions, If Any Reaulatory Restriction. Confirmatory Action Letter 86-10. Power Ascension Phase.

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 2160.0 142963.0

12. Number Of Hours Reactor Has Critical 559.2 968.8 80760 tQ

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 450.8 450.8 77680.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) 223056.0 230664.0 135230544.0

17. Gross Electrical Energy Generated (MHH) 58210.0 58210.0 45502814.0

18. Net Electrical Energy Generated (MHH) 53379.0 53379.0 43728803.0

19. Unit Service Factor 60.6 20.9 54.3

20. Unit Availability Factor 60.6 20.9 54.3

21. Unit Capacity Factor (Using MDC Net) 10.7 3.7 45.7

22. Unit Capacity Factor (Using DER Net) 11.0 3.8 46.7

23. Unit Forced Outage Rate 29.5 29.5 12.2

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 E9/77) i m_______ _ l

. BOSTON EDIS0N COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Doerational Summary for March 1989 The unit remained critical in the STARTUP mode until March 4, when at 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br />, the mode switch was placed in RUN and reactor power was increased for turbine roll. The turbine was rolled to 1800 RPM, and the generator was synchronized to the grid at 1537 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.848285e-4 months <br />. At 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br />, after high vibration was noted on turbine bearings 3 and 4, it was decided to trip the turbine to allow investigation of the vibration. At 1749 hours0.0202 days <br />0.486 hours <br />0.00289 weeks <br />6.654945e-4 months <br />, while the turbine was coasting down at approximately 150 to 200 RPM, a full reactor scram occurred due to low reactor pressure (approximately 900 psig) with the mode switch in RUN. The low reactor pressure appeared to have been caused by a turbine control system pertubation which caused all three bypass valves to close (one and one-half were originally open) and subsequently re-open, depressurizing the reactor. Cause of the vacuum trip and reset could not be determined during extensive investigation. The unit remained in cold shutdown until March 11, when at 2308 hours0.0267 days <br />0.641 hours <br />0.00382 weeks <br />8.78194e-4 months <br /> the reactor was made critical, and at 2351 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.945555e-4 months <br /> on March 12 the generator was synchronized to the grid. At 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br /> the i

turbine was tripped in an attempt to re-create the event of March 4, 1989.

Since the event did not re-occur, the turbine was reset and the generator was synchronized to the grid at 1811 hours0.021 days <br />0.503 hours <br />0.00299 weeks <br />6.890855e-4 months <br />. On March 13, a shutdown transformer lockout occurred apparently due to a solar magnetic storm. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on March 14, turbine MPR/EPR testing commenced. At 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br />, the generator was removed from the grid in preparation for the mode switch test. Due to bypass valve oscillations, the turbine was tripped at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br /> and the bypass valves steadied out. Testing of the mode switch per TP 88-76 commenced at 0118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> on March 15 and was successfully completed at 0354 hours0.0041 days <br />0.0983 hours <br />5.853175e-4 weeks <br />1.34697e-4 months <br />. The generator was synchronized to the grid at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> and remained on line until 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br /> on March 16 when the generator was removed from the grid to perform turbine overspeed testing. Following a successful test the generator was synchronized to the grid at 2012 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.65566e-4 months <br /> on March 16 and remained on line for the remainder of the month.

Safety Relief Valve Challenges Month of March 1989 l

l Requirement: NUREG-0737 T.A.P. II.K.3.3 i

There were no safety relief challenges during the 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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.. _- 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: January 1991

3. Scheduled date for restart following refueling: March 1991

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

5. See #6.

6. The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.

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

(b) There are 1320 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 fuei pool now has the capacity to accommodate an additional 1000 fuel assemblies.

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• BOSTorVEntSOM Pilgrim Nuclear Power Station l

[ Rocky Hill Road i- c Plymouth, Massachusetts 02360 '

j F-K. L. Highfill 5tation Director

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1 4 April 13,1989 BECo.Ltr. #89-055 U.S. Nuclear Regulatory Commission Attention:- Document Control Desk Hashington,'DC 20555.~

License No. DPR-35 Docket No. 50-293

Subject:

' March 1989HodhlyReport-  !

Dear Sir:

-In accordance with PNPS Technical Specification 6.9.A.2, a copy of the

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. 3 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.

K.L. Highf 1 HJH:bjh Attachment cc: Regional Administrator, Region 1 {

U.S. Nuclear Regulatory Commission  !

475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector

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