BECO-LTR-96-097, Monthly Operating Rept for Oct 1996 for Pilgrim Nuclear Power Station

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Monthly Operating Rept for Oct 1996 for Pilgrim Nuclear Power Station
ML20134J892
Person / Time
Site: Pilgrim
Issue date: 10/31/1996
From: Cannon R, Olivier L
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-96-097, BECO-LTR-96-97, NUDOCS 9611180125
Download: ML20134J892 (7)
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. l Tech. Spec. 6.9.A.2 G

Boston Edison Pilgnm Nuclear Power Staten Rocky Hdi Road Plymouth, Massachusetts 02360 '

L J. OlMer Vice President Nuclear operations November 14, 1996 and siaton otrector BECo Lir. #96 097 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 i

OCTOBER 1996 MONTHLY REPORT  ;

In accordance with Pilgrim Nuclear Power Station 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.

L.[Olivier RLC/dmc/9458 Attachment cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident inspector i

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9611180125 961031 PDR ADOCK 05000293 R PDR

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OPERATING DATA REPORT DOCKET NO. 50-293

NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508)830-8321 <

REPORT MONTH October 1996 )

OPERATING STATUS NOTES

1. Unit Name Pilgrim 1
2. Reporting Period October 1996 l
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) 696
7. Maximum Dependable Capacity (Net MWe) 670
8. If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give Reasons:

No Chanaes

9. Power Level To Which Restricted, If Any (Net MWe): None
10. Reasons For Restrictions, if Any: N/A This Month Yr-to-Date Cumulative
11. Hours in Reporting Period 745.0 7320.0 209472.0 l Hours Reactor Critical 745.0 6916.8 133182.9 12.
13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0 l
14. Hours Generator On-Line 745.0 6882.1 128706.0 l
15. Hours Unit Reserve Shutdown 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1434280.0 13315341.0 229617511.0 -
17. Gross Electrical Energy Generated (MWH) 488100.0 4547940.0 77825264.0
18. Net Electrical Energy Generated (MWH) 469092.0 4379524.0 74823146.0
19. Unit Service Factor 100.0 94.0 61.4
20. Unit Availability Factor 100.0 94.0 61.4
21. Unit Capacity Factor (Using MDC Nei) 94.0 89.3 53.3 ,
22. Unit Capacity Factor (Using DER Net) 99.1 91.3 54.5 l
23. Unit Forced Outage Rate 0.0 4.2 11.4
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)- RFO-11, February 1,1997,42 days
25. If Shutdown at End of Report Period, Estimated Date of Startup - UNIT OPERATING i

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508)830-8321 REPORT MONTH October 1996 j l

l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 251 17 638 2 555 18 648 3 655 19 515 4 629 20 660 5 649 21 658 6 655 22 658 7 654 23 656 8 655 24 658 9 644 25 657 10 650 26 615 11 647 27 657 12 643 28 658 13 647 29 658 14 646 30 659 15 643 31 658 16 642 This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to tha nearest whole megawatt.

OPERATIONAL

SUMMARY

DOCKET NO. _ 50-293 l NAME: Pilanm COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH October 1996 ,

1 Tha unit started the period in power ascension at approximately 40 percent core thermal power (CTP). At 0139 hours0.00161 days <br />0.0386 hours <br />2.29828e-4 weeks <br />5.28895e-5 months <br /> on October 3,1996,100 percent CTP was achieved. At 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> on October 4,1996 power w::s reduced to approximately 80 percent CTP to perform a control rod pattern change. The plant was returned to 100 percent CTP at 0512 hours0.00593 days <br />0.142 hours <br />8.465608e-4 weeks <br />1.94816e-4 months <br /> on October 5,1996. One hundred percent CTP was maintained until 0201 hours0.00233 days <br />0.0558 hours <br />3.323413e-4 weeks <br />7.64805e-5 months <br /> on October 19, 1996, when power was reduced to approximately 50 percent CTP to accommodate a backwash of the Inain condenser. Following the backwash power was returned to 100%

CTP at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on October 19,1996, where it maintained until 1646 hours0.0191 days <br />0.457 hours <br />0.00272 weeks <br />6.26303e-4 months <br /> on October 21,1996. Power was reduced approximately 10 percent first by control rods and then by recirculation flow for operator training.

On October 26,1996, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> reactor power was reduced to approximately 90 percent CTP to perform control rod exercising Reactor power was returned to 100 percent CTP at 1859 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.073495e-4 months <br /> on October 26,1996, whsre it remained for the duration of the operating period.

! SAFETY RELIEF VALVE CHALLENGES MONTH OF OCTOBER 1996 l Requirement: NUREG-0737 T.A.P. II.K.3.3 Th:re were no safety relief valve challenges during the reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure signal (ADS) or control switch (manual). Reference BECo Ltr. #81-01 dated January 5,1981.

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REFUELING INFORMATION DOCKET NO. 50-293

~ NAME: Pilorim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH October 1996 Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, ditrd 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: February 1,1997.
3. Scheduled date for restart following next refueling: March 14,1997.
4. Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6.
5. See #6.
6. The new fuelloaded during the 1995 refueling outage (RFO-10)is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies.
7. (a) There are 580 fuel assemblies in the core.

(b) There are 1765 fuel assemblies in the spent fuel pool.

(c) There are 148 fuel assemblies on-site awaiting receipt inspection for RFO-11.

8. (a) The station is presently licensed to store 3859 spent fuel assemblies. The spent fuel storage capacity is 2891 fuel assemblies. However,23 spent fuellocations cannot be used due to refuel bridge limitations.

(b) The planned spent fuel storage capacity is 3859 fuel assemblies.

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1103 fuel assemblies.

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PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE .

DOCKET NO. 50-293 .

NAME- Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH October 1996 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT RECURRENCE No major safety related corrective maintenance was completed during this reporting period.

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UNIT SHUTDOWNS AND POWER REDUCTIONS -. .

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DOCKET NO. 50-293 1 NAME- Pdonm .

COMPLETED BY: R.L. Cannon-  ;

4 TELEPHONE: (508) 83M321

REPORT MONTH October 1996 ,

4 METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO. DATE 1 (HOURS) 2 REACTOR REPORT- 4 5 RECURRENCE ,

.25 10/04/96 _S 0.0 B N/A N/A N/A N/A Power reduchon to 80% CTP  !

perform rod pattern change. ,

. 26 10/19/96 S 0.0 B N/A N/A N/A N/A Power reduchon to 50% CTP. i to perform a backwash of main condenser.  !

1 2 3 4&S  !

i F-Forced A-Equip Failure 1-Manual Exhibit F & H  !

S-Sched B-Main or Test 2-Manual Scram Instructions for -l C-Refueling 3-Auto Scram Preparations of i D-Regulatory Restriction 4-Continued Data Entry Sheet ,

E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-1022) 'I F-Admin I G-Operator Error H-Other  :

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