ML20210C736
| ML20210C736 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/31/1986 |
| From: | Hamilton P, Lydon J BOSTON EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 86-137, NUDOCS 8609180415 | |
| Download: ML20210C736 (7) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-293 UNIT Pilgrim 1 DATE Sept. 11, 1986 COMPLETED BY.o. Hamilton TELEPHONE (617)746-7900 MONTH August 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)-
1 0.
17 0'.
2 0.
18 0.
-3 0.
19 0.
4 0.
20 0.
'S 0.
21 0.
6 0.
22 0.
7 0.
23 0.
8 0.
24 0.
9 0.
25 0.
10 0.
26 0.
11 0.
27 0.
12 0.
28 0.
13 0.
29 0.
14 0.
30 0.
15 0
31 0.
16 0.
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.
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8609180415 860831
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OPERATING DATA REPORT DOCKET NO.
50-293 DATE Sept. 11. 1986 COMPLETED BY P. Hamilton TELEPHONE (617)?46-7900 OPERATING STATUS l.
Unit Name Pilgrim i Notes 2.
Reporting Period August 1986_.
3.
Licensed Thermal Power (*Ni) 1998 4.
Nameplate Rating (Gross *Ari 678 5.
Design Electrical Rating (Net MWe) 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)
None
- 10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 744.0 5831.0 120335.0
- 12. Number Of Hours Reactor Was Critical 0.0 1715.5 79791.1
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 0.0 1646.0 77229.3
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross. Thermal Energy Generated (MHH) 0.0 3094416.0 134999880.0
- 17. Gross Electrical Energy Generated (MWH) 0.0 1068000.0 45444604.0
- 18. Net Electrica) Energy Generated (MHH) 0.0 1027531.0 43675429.0
- 19. Unit Service Factor 0.0 28.2 64.2
- 20. Unit Availability Factor.
0.0 28.2 64.2
- 21. Unit Capacity Factor (Using MDC Net) 0.0 26.3 54.2
- 22. Unit Capacity Factor (Using DER Net) 00 26.9 55.4
- 23. Unit Forced Outage Rate 100.0
- 6).2 12.3
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Shutdown for Refueling Outage Number 7 - Outage commenced on July 25. 1986
- 25. If Shut Down At End Of Report Pe.iod, Estimated Date of Startup -
March. 1987
- 26. Units In Test Status (Prior to Coinniercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
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REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC !etter to BECo, dated January 18, 1978:
For your convenience, the information suppIled 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:
September 1988 3.
Scheduled date for restart following refueling: March 1987 4.
Due to their similarity, requests 4, 5, & 6 are responded to collectively-under #6:
5.
See #6.
6.
The new fuel, which was loaded during the 1983-84 refueling outage, is of the same P8x8R design as loaded the previous outage and consists of 160 P80R8282 assemblies.
In addition, 32 GE68-P8DRS282 assemblies were also loaded.
7.
(a)
There are 580 fuel assemblies in the core.
(b) There are 1,128 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 accommodato an additional 1192 fuel assemblies.
BOSTON EDISON COMPANY PILGRIH NUCLEAR FvHER STATION DOCKET NO. 50-293 Operational Summary for August 1986 The unit has been shutdown all month for Refueling Outage Number 7.
Safety Relief Valve Challenges Month of August 1986 Requirement:
NUREG-0737 T.A.P. II.K.3.3
'There were no safety relief valve challenges.during the month.
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M nth August 1986 PILGRIM NUCLEAR PONER STATION
. MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT
-ASSOCIATED RECURRENCE LER l
l Secondary Damper Cracked Drive Aging Replaced Drive Improved Damper.
N/A Containment A0/N90 Gear - Failed Gear and Pin /
Modification to be Isolation Closed Aligned Damper completed during Blades RF0 7 "A" Diesel Prelube
- Pump Ceased Loose wire on Wirc cleaned and N/A N/A Generator Pump Operating Breaker in
.Retorqued Panel C-103A Nitrogen FQ 5061 Inoperative Aging Replaced N/A N/A-HVAC Outside Air Actuator Aging
' Replaced two Installed two N/A Air Damper Mounting Bracket Mounting support brackets Broken Brackets 1
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-293 UNIT NAME Pilgrio 1-DATE Sept. 11,1985 COMPLETED BY P.-Hamilton-TELEPHONE (617)746-790 REPORT MONTH August 1986 METH00 0F LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO NO.
DATE TYPE' (HOURS) REASON' DOWN REACTOR' REPORT #
CODE' CODE PREVENT RECURRENCE.
5 08 8/1/86 S
744.0 C
4 N/A N/A N/A N/A - Shutdown for Refueling Outage Number 7 i
i 1
2 2
3 4&5 i
j F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H 4
S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for i
C-Refueling H-Other 3-Auto Scram Preparation of l
D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training S-Reduced Load Licensee Event Report 4
i
& License Examination 9-Other (LER) File (NUREG-1022) i 1
O Executive Offices 800 Boylston Street Boston. Massachusetts 02199 James M. Lydon.
September 11,1986 Chief Operating Officer BECo Ltr. #86-137 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn: Document Control Desk License No. OPR-35 Docket No. 50-293
Subject:
August 1986 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.
Respectfully submitted,
&na An Aen J. M. Lydon PJH:vep Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
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