ML20116L084
| ML20116L084 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/31/1996 |
| From: | Cannon R, Olivier L BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BECO-LTR#96-074, BECO-LTR#96-74, NUDOCS 9608160097 | |
| Download: ML20116L084 (7) | |
Text
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Tech. Sp:c. 6.9.A.2 Boston Edison Pilgrim Nuclear Power Station f
Rocky Hill Road Plymouth, Massachusetts 02360 L J. Olivier Vice President Nuclear Operations August 14, 1996 and station oirector BECo Ltr. #96-074 U.S. Nuclear Regulatory Commission Attention: Document Control Desk j
Washington, DC 20555 Docket No. 50-293 License No. DPR-35 l
JULY 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 l
planning. Should you have any questions conceming this report, please contact me directly.
'o s
[ Olivia' i
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 j
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'p 9608160097 960731 PDR ADOCK 05000293 R
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160021
OPERATING DATA REPORT DOCKET NO.
50-293 NAME:
Pilorim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508) 830-8321 REPORT MONTH July 1996 OPERA TING STATUS NOTES t
1.
Unit Name Pilgrim 1 2.
Reporting Period July 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 Chanoes 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 5111.0 207263.0 12.
Hours Reactor Critical 744.0 4996.5 131262.6 13.
Hours Reactor Reserve Shutdown 0.0 0.0 0.0 14.
Hours Generator On-Line 744.0 4977.9 126801.8 15.
Hours Unit Reserve Shutdown 0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH) 1455474.0 9704482.0 226006652.0 17.
Gross Electrical Energy Generated (MWH) 493700.0 3323460.0 76600784.0 18.
Net Electrical Energy Generated (MWH) 474818.0 3202360.0 73645982.0 l
- 19. -
Unit Service Factor 100.0 97.4 61.2 20.
Unit Availability Factor 100.0 97.4 61.2 21.
Unit Capacity Factor (Using MDC Net) 95.3 93.5 53.0 22.
Unit Capacity Factor (Using DER Net) 97.4 95.7 54.2 23.
Unit Forced Outage Rate 0.0 0.0 11.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-
NONE PLANNED 25.
If Shutdown at End of Report Period, Estimated Date of Startup-UNIT OPERATING l
l AVERAGE DAILY UNIT POWER LEVEL 1
l DOCKET NO.
50-293 i
NAME:
Pilarim COMPLETED BY:
R.L. Cannon
)
TELEPHONE:
(508) 830-8321 J
l REPORT MONTH July 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
(MWe-Net)
(MWe-Net) l l
1 650 17 662 l
2 652 18 661 3
649 19 661 l
4 649 20 661 5
648 21 660 l
6 649 22 660 l
l 7
646 23 660 i
8 647 24 658 9
647 25 659 10 645 26 657 11 645 27 658 12 597 28 657 l
I 13 231 29 658 14 626 30 656 15 662 31 657 16 657 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.
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OPERATIONAL
SUMMARY
DOCKET NO.
50-293 NAME:
Pilarim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508) 830-8321 REPORT MONTH July 1996 The unit started the reporting period at 100% core thermal power (CTP) where it was maintained until 2022 hours0.0234 days <br />0.562 hours <br />0.00334 weeks <br />7.69371e-4 months <br /> on July 12,1996. At that time, reactor power was reduced to approximately 50% CTP in supoort of a i
backwash of the main condenser. During the downpower it was identified that one of the reactor feed flow indicators was not tracking properly. The flow indicator was replaced and a reactor heat balance was j
satisfactorily performed. At 1924 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.32082e-4 months <br /> on July 13,1996, power ascension to 100% CTP commenced. At 0536 hours0.0062 days <br />0.149 hours <br />8.862434e-4 weeks <br />2.03948e-4 months <br /> on July 14, 1996, 100 % CTP was achieved and was maintained for the remainder of the
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reporting period.
J SAFETY RELIEF VALVE CHALLENGES i
MONTH OF JULY 1996 Requirement:
NUREG-0737 T.A.P. II.K.3.3 Thsre 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 L tr. #81-01 dated January 5,1981.
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REFUELING INFORMATION l
DOCKET NO.
50-293 NAME:
Pilorim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508) 830-8321 l
REPORT MONTH July 1996 Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, d;.t;d 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.
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 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.
1 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 July 1996 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT RECURRENCE 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:
Pilorim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508) 83 4 8321 REPORT MONTH July 1996 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 17 07/12/96 S
0.0 B
N/A N/A N/A N/A Planned down power to conduct main condenser back wash.
1 2
3 4&5 F-Forced A-Equip Failure 1-Manual
- Exhibit F & H i
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 i
& License Examination 9-Other (LER) File (NUREG-1022) r-Ad m h i
G Operator Error H-Other l
-