BECO-LTR-96-066, Monthly Operating Rept for June 1996 for Pilgrim Nuclear Power Station

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Monthly Operating Rept for June 1996 for Pilgrim Nuclear Power Station
ML20115D686
Person / Time
Site: Pilgrim
Issue date: 06/30/1996
From: Cannon R, Olivier L
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-96-066, BECO-LTR-96-66, NUDOCS 9607150229
Download: ML20115D686 (7)


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Tech. Spic. 6.9.A.2 s

Boston Edison Pilgnm Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 L J. Olivier  !

Vice President Nuclear Operations July 11, 1996  ;

and Staton Director BECo Ltr. #96- 066 ,

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. U.S. Nuclear Regulatory Commission  ;

Attention: Document Control Desk '

Washington, DC 20555 i Docket No. 50-293 +

License No. DPR-35 i f

JUNE 1996 MONTHLY REPORT l

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.

Law l

. J. Olivier i

RLC/dmc/9458 )

Attachment cc: Mr. Thomas T. Martin 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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9607150229 960630 l PDR ADOCK 05000293

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OPERATING DATA REPORT DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH June 19%

OPERATING STATUS NOTES

1. Unit Name Pilgrim 1
2. Reporting Period June 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) 6_96,
7. Maximum Dependable Capacity (Net MWe) 670 G. 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 720.0 4367.0 206519.0
12. Hours Reactor Critical 720.0 4252.5 130518.6
13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 4233.9 126057.8
15. Hours Unit Reserve Shutdown 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1397769.0 8249008.0 224551178.0
17. Gross Electrical Energy Generated (MWH) 472680.0 2829760.0 76107084.0
18. Net Electrical Energy Generated (MWH) 454763.0 2727542.0 73171164.0
19. Unit Service Factor 100.0 97.0 61.0
20. Unit Availability Factor 100.0 97.0 61.0 ,
21. Unit Capacity Factor (Using MDC Net) 94.3 93.2 52.9
22. Unit Capacity Factor (Using DER Net) 96.4 95.4 54.1
23. Unit Forced Outage Rate 0.0 0.0 11.6 i
24. Shutdowns Scheduled Over Next 6 Months I (Type, Date, and Duration of Each)- NONE PLANNED J
25. If Shutdown at End of Report Period, l Estimated Date of Startup - UNIT OPERATING l l

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4e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH June 19%

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 654 17 652 2 654 18 650 3 654 19 651 4 655 20 651  ;

5 656 21 646 6 654 22 650 'i 7 6'- 23 651 1

8 655 24 650 9 655 25 652 10 654 26 648 11 653 27 650 12 655 28 643 13 655 29 612 14 624 30 564 15 298 16 550 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: Pilorim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH June 1996 Tha unit started the reporting period at 100% core thermal power (CTP) where it was maintained until 2002 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.61761e-4 months <br /> on June 14,1996. At thet time, reactor power was reduced to approximately 50% CTP in support of a backwash of the main condenser and rod scram testing. At 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> on June 16,1996, power ascension to 100% CTP commenced. At 1122 hours0.013 days <br />0.312 hours <br />0.00186 weeks <br />4.26921e-4 months <br /> on June 16, 1996, 100 % CTP was achieved. The unit was maintained at approximately 100% CTP until 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on June 29, 1996, when the unit power was reduced to approximately 50% CTP to support back washing of the main condenser. At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> on June 30, 1996, 50 % CTP was achieved. At 0227 hours0.00263 days <br />0.0631 hours <br />3.753307e-4 weeks <br />8.63735e-5 months <br /> on June 30,1996, the main condenser backwash was complete. At 0236 hours0.00273 days <br />0.0656 hours <br />3.902116e-4 weeks <br />8.9798e-5 months <br />, on June 30,1996, power ascension began. At 0831 hours0.00962 days <br />0.231 hours <br />0.00137 weeks <br />3.161955e-4 months <br /> on June 30,1996, 100% core thermal power was achieved.

SAFETY RELIEF VALVE CHALLENGES MONTH OF JUNE 1996 Requirement: NUREG-0737 T.A.P. II.K.3.3 Thnre 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 June 1996 i Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dit:d 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. i

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

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2. Scheduled date for next re'aeling 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.

t 5.' See #6.

l 6. The new fuel loaded during the 1995 refueling outage (RFO-10) is of a different design than that j loaded in the previous refueling outage and consists of 136 riew fuel assemblies. '

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

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(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 i i capacity is 2891 fuel assemblies. However,23 spent fuel locations cannot be used due to  !

refuel bridge limitations. ,

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

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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-  : y PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE  !

4 DOCKET NO. '50-293  :

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

REPORT MONTH June 1996 >

SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED '

ACTION TO LER ,

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PREVENT' RECURRENCE j No major safety related maintenance was completed during this reporting period.  ;

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UNIT SHUTDOWNS' AND POWER REDUCTIONS DOCKET NO. 50-293 NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508) 830-8321 REPORT MONTH June 1996 l 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 15 06/14/96 S 0.0 B N/A N/A N/A N/A Planned down power to conduct a main condenser back wash and surveillance testing.

16 06/29/96 F 0.0 B N/A N/A N/A N/A Unplanned down power to conduct main condenser back wash.

i 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 Ucensee Event Report

& License Examination 9-Other (LER) File (NUREG-1022)

F-Admin G-Operator Error H-Other

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