ML20244E112

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Monthly Operating Rept for May 1989 for Pilgrim Nuclear Power Station
ML20244E112
Person / Time
Site: Pilgrim
Issue date: 05/31/1989
From: Highfill K, Munro W
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-076, 89-76, NUDOCS 8906200148
Download: ML20244E112 (7)
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Pilgrim Nuclear Power station 

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                                                                      ' Rocky Hill Road
                                                           . Plymouth. Massachusetts 02360 4                         K. L. HighfiH station Director _

June 12,1989 BECo Ltr. #89 076 U.S'. Nuclear Regu'latory Commissio'n Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293

Subject:

' May 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.

4 

                                                                                                                                 .                                  A.Q K.L. Highfil HJM:bjh Attachment L                      cc: Regional Administrator, Region i U.S'. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector l l g21 I 8906200148 890531 

                             'PDR..ADOCK 05000293 PDC                                                                                                                   ,,

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 l UNIT Pilorim 1 DATE June 12, 1989 COMPLETED BY W. Munro TELEPHONE (508) 747-8474 l ! MONTH May- 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL. (MWe-Net) (MWe-Net) 1 -114 17 0 2 116 18 0 3 16 19 0 4 0 20 0 5 0 21 0 . 6 0 22 0 7 0 23 0 8 0 24 0 l 9 0 25 0 10 0 _ 26 _11 11 0 27 125 12 0 28 125 13 0 29 126 14 0 30 127 15 0 31 128 16 Q This format lists the average daily unit power level in MWe-Net for each day in the reporting month, conputed to the nearest whole megawatt.

OPERATING DATA REPORT i. DOCKET NO. DATE 50-293 June 12, 19u9 i COMPLETED BY H. Munro TELEPHONE (508) 747-8474__ OPERATING STATUS Notes

1. Unit Name Pilarim 1
2. Reporting Period May 1989
3. Licensed Thermal Power (MHt) 1998
4. Nameplate Rating (Gross MHe) 678
5. Design Electrical Rating (Net MHe) 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 Regulatory Restriction. Confirmatory Action Letter 86-10. Power Ascension Phase.

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 3623.0 144431.0
12. Number Of Hours Reactor Has Critical 213.8 1630.4 81421.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 210.8 __ 1052.9 78282.2
15. Unit Reserve Shutdown Hours 0.0 0. 0 __ 0.0
16. Gross Thermal Energy Generated (MHH) 91752.0 513744.0 135513624.0
17. Gross Electrical Energy Generated (MWH). 2488Q2D 137810.0 45582414.0
18. Net Electrical Energy Generated (MWH) 22797.0 126520.0 __43801949.0
19. Unit Service Factor 28.3 29.1 5412
20. Unit Availability Factor 28.3 29.1 54.2
21. Unit Capacity Factor (Using MDC Net) 4.6 5.2 45.3
22. Unit Capacity Fcctor (Using DER Net) 4.7 5.3 46.3
23. Unit Forced Outage Rate 71.7 49.9 13.0
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 (scone 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION l (9/77) l

t BOSTON EDISON COMPANY . PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-393 Doerational Summarv for Mov 1989 

                       .The unit remained on line operating at approximately 25 percent rated thermal power, in accordance with the approved Power Ascension Program,.until 0325 hours on' Hay 3,1989.when a high reactor vessel water level occurred that resulted in an automatic turbine trip, generator trip, and Reactor Protection.

System load reject scram. The high reactor vessel . water level was primarily caused while troubleshooting the actuator controls of a feedwater regulating. valve. The unit remained in cold shutdown for maintenance until'May 25, 1989 when the reactor was made critical at 0525 hours, and the generator was synchronized to the grid 0834 hours. The unit remained on.line for the remainder of the reporting period. Safety Relief Valve Chr.llenges Month of May 1989 Requirement: NUREG-0737 T.A.P. II.K.3.3 l- There were no safety relief valve challenges during the month. An SRV challenge is defined as anytime ar. SRV has received a signal to operate 

                     .via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo L                          ltr. #81-01 dated 01/05/81.

I l i l l l 1 1 _ __ ___-_-_____-_-_-_ - a

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         .:     ...                             REFUELING INFORMATION j >>; ..
            -The following refueling information'is. included in the Monthly Report as u             requested in an NRC letter to BECo, dated' January 18, 1978:

l 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 1
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 previious 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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