BECO-LTR-96-083, Monthly Operating Rept for Pilgrim Nuclear Power Station for Aug 1996 Ltr

Monthly Operating Rept for Pilgrim Nuclear Power Station for Aug 1996 Ltr

ML20129A696
Person / Time
Site:	Pilgrim
Issue date:	08/31/1996
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-96-083, BECO-LTR-96-83, NUDOCS 9609190021
Download: ML20129A696 (7)

Text

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Tech. Spec. 6.9.A.2 G

Boston Edison Pilgrirn Nuclear Power Station Rocky Hill Road Plymouth, Manachusetts 02360 L J. Olivier Vice President Nuclear operations September 12, 1996 and station oirector BECo Ltr. #96-083 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 AUGUST 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.

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. 7 ivier RLC/dmc/9458 l Attachment cc: Mr. Hubert Miller Regional Administrator, Region I i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident inspector c,0 a nh j b e

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9609190021 960831 PDR g

ADOCK 05000293 PDR TQ({ i i

OPERATING DATA REPORT DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH Auaust 1996 OPERATING STATUS NOTES

1. Unit Name Pilgrim i

2. Reporting Period August 1996

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 744.0 5855.0 208007J

12. Hours Reactor Critical 744.0 5740.5 132006.6

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 5721.9 127545.8 1

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1411264.0 11115746.0 227417916.0

17. Gross Electrical Energy Generated (MWH) 478260.0 3801720.0 77079044.0

18. Net Electrical Energy Generated (MWH) 459908.0 3662268.0 74105890.0

19. Unit Service Factor 100.0 97.7 61.3

20. Unit Availability Factor 10rLO 97.7 61.3

21. Unit Capacity Factor (Using MDC Net) 92.3 93.4 53.2

22. Unit Capacity Factor (Using DER Net) 94.4 95.5 54.4

23. Unit Forced Outage Rate 0.0 0.0 11.5

, 24. Shutdowns Scheduled Over Next 6 Months j (Type, Date, and Duration of Each)- Refueling outage scheduled for i February 1,1997. Expected duration is 42 days. 1 1 25. If Shutdown at End of Report Period, l

Estimated Date of Startup- UNIT OPERATING 1'

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AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-293 NAME: Pilarim

! COMPLETED BY: R.L. Cannon i TELEPHONE: (508)830-8321 j REPORT MONTH Auaust 1996 l

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i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) - (MWe-Net) 1 659 17 643 2 656 18 654 )

3 658 19 652 ,

l 4 657 20 651 l 5 656 21 656 6 652 22 654 7 651 23 628 8 652 24 384 ,

9 653 25 413 10 653 26 415 11 650 27 465 12 648 28 626 13 649 29 651 14 649 30 650 i 15 649 31 579 16 650 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.

OPERATIONAL

SUMMARY

DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH Auaust 1996 The plant entered August operating at 100% core thermal power (CTP) where it was essentially maintained until 9/23. On 8/23, at 2046 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.78503e-4 months <br />, the plant commenced reducing power to approximately 60% CTP to l facilitate scheduled power suppression testing of the nuclear fuel and perform selective maintenance in the I condenser bay. On 8/28, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, the plant attained 100% CTP where it was maintained until 8/31.

On 8/31, at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, the plant reduced power to approximately 90% CTP to perform control rod exercising. At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, power was further reduced to approximately 70% CTP to perform maintenance on I control rod 02-27. The plant attained 100% CTP at 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br /> ending August at full power.

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SAFETY RELIEF VALVE CHALLENGES MONTH OF AUGUST 1996 Requirement: NUREG-0737 T.A.P. II.K.3.3 There 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: Pilarim i COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH Auaust 1996 The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, datsd January 18,1978: ,

1 For your convenience, the information supplied has been enumerated so that each number corresponds to l equivalent notation utilized in the request. I

1. The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293. l

2. Scheduled date for next refueling shutdown: February 1,1997. l

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 fuel loaded 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.

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.

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9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an i 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 Auaust 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 [

DOCKET NO. 50-293 .

NAME: Pilorim COMPLETED BY: R.L. Cannon -

TELEPHONE: (508) 830-8321'

• REPORT MONTH Auaust 1996 METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURAT!ON REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO. DATE 1 (HOURS) 2 REACTOR REPORT 4 5 RECURRENCE 18 08/23/96 S 0.0 B N/A N/A N/A N/A Planned down power to conduct scheduled power suppression testing of the nuclear fuel and perform selective maintenance.

19 08/31/96 S 0.0 B N/A N/A N/A N/A Planned powered reduction to perform maintenance on control rod 02-27.

1 2 3 4&5 F-Forced A-Equip Failure 1-Manual Exhibit F & H S-Sched B-Main or Test 2-Manual Scram Instructions for C-Refueling 3-Auto Scram Preparations of 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)

F-Admin G-Operator Error

H-Other

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