ML20070L115
| ML20070L115 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/28/1991 |
| From: | Richard Anderson, Munro W BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-33, NUDOCS 9103190294 | |
| Download: ML20070L115 (7) | |
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A3 nosronumson Pilgnm Nuclear Fower Staten Rocky Hdi Road Piymouth, Massachusetts o236o R. A. And.ereen ve. pinio ni n ECr o7,'elon March 12,1991 BECo Ltr. #91-33 l
U.S. Nuclear.Reediatory Commission
. Attention: ! Doc W nt Control Desk-Hashington, DC 20555 License No. DPR Docket No. 50-293.
Subject:
February 1991 Monthly Report r
Dear Sir:
In accordance Eith 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...Should you.have.any questions concerning this report please contact me directly.
L
~r R.A. AnderAon
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o Attachment-cc: Regional Administrator. Region 1--
U.S. Nuclear Regulatory Commission i
475 Allendale Rd.
L King of Prussia, PA 19406-o Senior Resident Inspector l
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PDR ADOCK 05000203 R
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I AVERAGE DAILY MMIT POWER LEVE_
DOCKET NO.
50-293-UNIT Pilarim 1 DATE March 12. 1991 LOMPLETED BY H. Hunro TELEPHONE (508) 747-8474 H3 NTH February 1991 DAY AVERAGE DAILY PDHER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)
(MHe-Net) 1 665 17 532
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2 663 18 553 3
665 19 556 4
665 20 552 5
664 21 654 6
625 22 665 7
435 23 664 8
494 24 665 9
551 25 665 10 552 25
_666 11 552 27 664 12 552 28 665 13 553 29 N/A 14 557 30 N/A 15 559 31 N/A-16 422 This format lists the average daily unit power level in MHe-Net for each day in the reporting month, computed to the nearest whole megawatt, i
OPERATING DATA REPORT
)
DOCKET NO.
50-293
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DATE March 12. 1991 COMPLETED BY H. Hunro TELEPHONE
_1508) 747-8474 OPERATING STATUS Notes I
1.
Unit Name Pilorim 1 2.
Reporting Period February 1991 3..
Licensed Thermal Power (MHt) 1991l 4..
Nameplate Rating (Gross HHe) 678 5.
Design Electrical-Rating (Net MHe) 655-6.
Maximum Dependable Capacity (Gross MHe) 696 7.
Maximum Dependable Capacity (Net MHe) 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 MHe)
None-
)
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- 10. Reasons For Restrictions, If Any N/A 4 ummeeune This Month Yr-to-Date Cumulative-
- 11. Hours In Reporting Period 672.0 1416.0 159744.0
- 12. Number Of Hours Reactor Has Critical 672.0 1416.0 94016.7 13, Reactor Reserve Shutdown Hours 0.0 0.0-0.0-
- 14. Hours Generator On-Line.
672.0
%Q 90332 1
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- 15. Unit Reserve Shutdown Hours.
-16.- Gross TMrmal Energy Generated (MHH).
0.0
. A0 O_. 0 '
1210752.0.
2 6.,.a 68. 0 17977917.0-
- 17. Gross Electrical. Energy Generated (HHH) 415390.0
....909230.0.52556744.0
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- 18. Net Electrical Energy Generated (HHH) 400155.0 875582.0 50501990.0
- 19. Unit Service Factor..
100.0 100.0 56.5 20, Unit Availability Factor 100.0 100.0 56.5 21.-Unit Capacity Factor (Using HDC Net)'
88.9 92.3 47.2
- 22. Unit Capacity Factor (Using DER Net) 90.9 94.4 48.3 23.. Unit Forced Outage Rate 0.0 0.0 12.6
-24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):
Refuelino Outaae No~. 8.
May 1991. accroximatelv 70 days 25.llf Shut Down At End Of Report Period, Estimated Date of Startup N/A p.
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a BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Ooerational Summary for February 1991 The unit started ue reporting period at 100 percent power. On February 4, 1991 a metal shroud was removed from the "B" reactor feed pump,-to investigate the source of leaking water, and a pin hole leak was discovered in the casing. On Febrtary 6, 199i power was reduckd to 70 percent-and the "B" reactor feed pump was removed from service to further investigate the casing ieak.
Following removal of the pump from service, power was then returned to 80 percent using recirculation flow. On February 7, 1991 the "A" recirculation pump was removed from service and power was reduced to 52 percent when it was discovered that the "A" recirculation pump HG set exciter-t brushes were worn _and arcing. On February 8, 1991 following installation ~of a temporary modification which added an additional brush holder onto the MG set-
. exciter, the "A" cecirculation pump was restarted.
By February 9, 1991 power was increased to 64 percent and remained at that level, with the "B" reactor i
feed pump out of service due to the casing leak, until February 16, 1991. On
-February 16, 1991 power was-reduced to 50 percent to perform a backwash of-the main condenser. Upon completion of the backwasi, pnwer was increasec to 85 percent and rema Hed at that level until February 20, 1991 when power was reduced to 70% percent to re?. tore "B" reactor feed pump to service following
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repair to the pump casing. On February 20, 1991 a power increase was c
. initiated and power level reached 100 percent by 0805 hours0.00932 days <br />0.224 hours <br />0.00133 weeks <br />3.063025e-4 months <br /> on February 21, 1991 and remained there for the remainder of the reporting period. Control rod exercising was performed on February 2, 9, 16 and 23.
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Safety Relief Valve Challenges Month of February 1991 Requirement:
NUREG-0737 T.A.P. II.K;3.3 There were no safety relief valve challenges during this reporting period.
n An'SRV challenge is defined as anytimo an SRV has received a signal to operate I
via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo
-itr. #81-01 dated 01/05/81.
I
REFUELING INFORMATf0N The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo. dated January 18, 1978:
For your convenience, the information supplied has been enumerated so that, each number corresponds to equivalent notation utilized in the request, d
1.
The name of this facility is Pilgrim Nuclear Power Station, Docket INmber 50-293.
2.
Scheduled date for next Refueling Shutdown:
Second Quarter 1991 3.
Scheduled date for restart following refueling:
Third Quarter 1991 4.
Due to their similarity, requests 4 F, & 6 are responded to collectively under #6.
5.
See #6.
6.
The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.
7.
(a) There are 580 fuel assemblies in the core.
(b) There are 1320 fuel assemblies in the spent vel 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 accommodate an additional 1000 fuel assemblies.
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Month February 1991_
PILGRIM NUCLEAR POWER STATION.
MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACT'ON TO ASSOCIATED PREVENT RECURRENCE LER Fe?d-
"B" Reactor Feed-Crack in uoper Root cause.
Temporary Modifica-N/A N/A water water Pump (RFP) half of l,'
under investi-tion TM 91-14 System P-103B' F-1038 cuss.ng. gation.
Implemented to (F&MR 91-47) restore casing integrity using mechanical metal stitch repair l
process by Metalock l
Corp.
i Recirc-
"A" Recirculation Exciter b.ushes Root cavea Incorporated Temp-Collector rings N/A ulation Motor Generator worn and to be orary Modification scheduled for repair System Set.*
arcing due to determined.
TM 91-12 to add a or replacement during worn and second set of RFO-8.
pitted col-brushes or the out-1ector ring.
board collector ring.
(F&MR 91-48) l
- WOTE Items are not safety related, however caused major reduction in power.
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y UNIT SHUTD0HNS AND POWER REDUCTIONS DOCKET NO. 50-293 NAME Pilarin 1 DATE March 12, 1991 COMPLETED BY H. Munro TELEPHONE (5081 747-8474 REPORT HONTH February 1991 HETH00 0F LICENSE CAUSE & 00RRECTIVE DURATION SHUTTING EVENT SYSTEg COMPONENT ACTION TO PREVENT I
(HOURS)
REASON 2 DOHN REACTOR 3 REPORT #
CODE CODE 3 PECURRENCE NO.
DATE TYPE l
2 J2/07/91 F
0.0 N/A 5
N/A N/A N/A Power reduced to haestigate "B" RFP
- acing leak, and add
- J61tional brush on "L" Recirc. MG set.
l (TM91-12) l 3 02/16/91 S
0.0 N/A 5
N/A N/A N/A Power reduced to per-form main condenser i
backwash.
1 2
2 3
4&5 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Haint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation 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-!O22)
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