BECO-89-067, Monthly Operating Rept for Apr 1989 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Apr 1989 for Pilgrim Nuclear Power Station

ML20247A040
Person / Time
Site:	Pilgrim
Issue date:	04/30/1989
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-89-067, BECO-89-67, NUDOCS 8905230015
Download: ML20247A040 (7)

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. Pilgrim Nuclear Power Station j- Rocky Hill Road Plymouth, Massachusetts 02360 K. L. Highfill Station Diiector May 12, 1989

! BECo Ltr, #89-067 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293

Subject:

April ~1989 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. Should you have any questions concerning this report please contact me directly.

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K.L. High il'1 WJM:bjh Attachment cc: Regional Administrator, Region 1 )

U.S. Nuclear Regulatory Commission j 475 Allendale Rd.

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King of Prussia, PA 19406 Senior Resident Inspector I

0905230015 PDR R

090430 ADOCK 05000293 PDC g! I 8

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,' . AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __ 50-293 UNIT Pilarim 1-DATE May 12. 1989 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 HONTH ADril 1989 '

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MHe-Net) l 1 126 17 0 2 121 18 0 l 3 127 19 __

0 4 126 20 0 5 126 21 0 6 128- 22 0 l-7 134 23 0 8 132 24 0 _

l 9 131 25 0 10 132 26 0 11 134 27 0 12 133 28 0 13 134 29 0 14 134 30 61 15 134 31 N/A 16 82 This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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. OPERATING DATA REPORT lj

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• DOCKET NO. 5D-293 DATE -May 12. 1989 l COMPLETED BY W. Munro TELEPHONE (508) 747-8474 )

l OPERATING STATUS-Notes

1. Unit Name Pilarim 1 ,

2. Reporting Period Acril 1989

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 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) 2.51. 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 719.0 2879.0 143687.0

12. Number Of Hours Reactor Was Critical 447.8 1416J 81208.0

13. Reactor Reserve Shutdown Hours 0.0 _

0.0 0.0

14. Hours Generator On-Line 391.3 842.1 78071.4

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 191328.0 421992.0 135421872.0

17. Gross Electrical Energy Generated (MWH) 54720.0 112930.0 45557534.0

18. Net Electrical Energy Generated (MWH) 50344.0 103723.0.33_779152.0

19. Unit Service Factor 54.4 29.2 54.3

20. Unit Availability Factor 54.4 29.2 54.3

21. Unit Capacity Factor (Using MDC Net) 10.5 5.4 45.5

22. Unit Capacity Factor (Using DER Net) 10.7 5.5 46.5

23. Unit Forced Outage Rate 45.6 38.0 12.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Maintenance outaae. October 1.1989 for a duration of 30 - 42 days (scoce under review).

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

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

Forecast Achieved L INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) f I

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l . . BOSTON EDIS0N COMPANY PILGRIM NUCLEAR POWER STATION

,- DOCKET NO. 50-293 Operational Summary for Aoril 1989 1 The unit remained on line operating at approximately 25 percent rated thermal power, in accordance with the approved Power Ascension Program, until April 16, 1989 when the unit was removed from the grid and the reactor was manually shutdown at 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br /> for a maintenance outage. The outage resulted from an inadvertent over-pressurization of the Reactor Core Isolation Cooling (RCIC) system, which occurred on April 12, 1989. At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on April 12, 1989, the RCIC system was declared inoperable. On April 16, 1989 at 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, a conservative management decision was made to declare an Unusual Event and to initiate a controlled shutdown. The Unusual Event was terminated at 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br />. Following repairs to the RCIC system, the unit was made critical at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> on April 28, 1989, and the generator was synchronized to the grid on April 30, 1989 at 0727 hours0.00841 days <br />0.202 hours <br />0.0012 weeks <br />2.766235e-4 months <br />. The unit remained on line for the remainder of the reporting period.

Safety Relief Valve Challenges Month of Aoril 1989 Requirement: NUREG-0737 T.A.P. II.K.3.3 Date: April 29,1989 Valve #203-3c Reason: Post maintenance testing.

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

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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: First Quarter 1991

3. Scheduled date for restart following refueling: Second Quarter 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 fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.

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