ML20012D289
| ML20012D289 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/28/1990 |
| From: | Highfill K, Munro W BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-037, 90-37, NUDOCS 9003270151 | |
| Download: ML20012D289 (7) | |
Text
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. ),4g;f t BOSTON EDeSON Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts o236o En D r&
%ce Presdent, Nuclear Operstons March 14 1990 BECo Ltr. #90- 037 U.S. Nuclear Regulatory Commission-Attention: Document Control Desk
-Hashington, DC 20555 License No. DPR-35 Docket No. 50-293
Subject:
February 1990 Monthly Report Dear Siri-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.
Should you have any questions concerning this report please contact me directly.
s. f. hg K.L. Highfin HJH:bal:
Attachment cc: Regional Administrator, Region 1
-U.S. Nuclear. Regulatory-Commission 47S Allendale Rd.
King of Prussia, PA 19406 Senior Resident Inspector 9003270151-900228 yg$N PDR. ADOCK 0500o293 fp/4 91 1
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57 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.-
50-293 6'
UNIT Pilorim 1 1
DATE March 14. 1990 COMPLETED.BY H. Munro TELEPHONE (508) 747-8474 MONTH February 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
(MHe-Net)
(MHe-Net).
I 665 17 662 2
665 18 662 3
663 19 663
-4 666 20 663 5
664 21 663 6
664 22 663 7
665 23 663 8
665 24 661 9
622 25 663
.i 10 423 26 664 11 647 27 664 12 663 28 664 13 663 29 N/A 14 663 30 N/A i.
15 663 31 N/A l
1 16 660 l
l This format lists the average daily unit power level in MHe-Net for each day u
in the reporting month, computed to the nearest whole megawatt.
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OPERATING DATA REPORT 4,
- c..,.
DOCKET NO.
50-293 DATE March 14. 1990 (b8 74 -8474 OPERATING STATUS 1
L Notes
]
1.
Unit Name Pilarim 1 2.
Reporting Period February 1990 j
3.
Licensed Thermal Power (MHt) 1998 i
-4.
Nameplate Rating (Gross MHe) 678 5.
Design Electrical Rating (Net MHe) 655-6.
Maximum Dependable Capacity (Gross HHe) 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 p
L 9.-
Power Level To Hhich Restricted, If Any (Net MHe)
None I
- 10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 672.0 1416.0 150984.0
- 12. Number Of Hours Reactor Has Critical 672.0 1416.0 86821.2
-13. Reactor Reserve Shutdown Hours 672.0 1416.0 83545.3 0.0 0.0 0.0
- 14. Hours Generator On-Line 15.. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MHH) 1321392.0 2806056.0 143290968.0
- 17. Gross-Electrical Energy Generated (MHH).
455670.0 970270.0 48207094.0 18 Net' Electrical Energy Generated-(MHH) 438641.0 934090.0. 46317274.0
- 19. Unit Service Factor 100.0-100.0 55.3
- 20. Unit Availability Factor 100.0 100.0 55.3
- 21. Unit Capacity Factor (Using MDC Net) 97.4
-98.5 45.8
~
22.. Unit Capacity Factor (Using DER Net) 99.7 100.7 4 6 ~. 8
- 23. Unit Forced Outage Rate 0.0 0.0 12.7
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Maintenance Outaae March 9. 1990 for a duration of 39 days.
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup - N/A
- 26. Units In Test Status (Prior to Commercial Operation):
N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
BOSTON EDISON COMPANY-9' PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
- l d
' Operational Summarv~ for February 1990 -
~
The unit remained on line at approximately-100 percent thermal power "D
throughout the reporting period. Power was. reduced to approximately 46 percent thermal. power on 2-10-90 to perform a backwash of the' main condenser due to macrofouling.
The "A" Recirculation Motor Generator Set remained ~in manual control throughout the reporting period.
Safety Relief Valve Challenges Month of February 1990 Requirement: NUREG-0737 T. A.P. II.K 3.3 U
There were-no safety relief valve challenges during the reporting period.-
An SRV'cha11enge is defined as anytime an SRV has received a signal to operate
.via reactor pressure, auto signal (ADS) or control switch (manual).
Ref. BECo Ltr. #81-01 dated 01/05/81.
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L
N" REFUELING INFORMATION The following refu4 ling information is included inLthe Monthly Report as-q 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.
1.
The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.-
2.
Scheduled date for next Refueling Shutdown:
Second Quarter 1991
.3.
Scheduled-date for restart following refueling:
Second Quarter 1991 4.
Due to their similarity, requests 4, 5, & 6'are: responded to collectively
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under #6.
5.
See #6.
6.
The-new fuel loaded during the 1986/87 refueling outage was of the same
- deeign 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 fuel pool.
8.
(a) The station is-presently licensed to store 2320 spent fuel 4
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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man 990
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PILGRIM NUCLEAR PONER-STATION g
MAJOR SAFETY.RELATED MAINTENANCE' SYSTEM COMPONENT MALFUNCTION ~
CAUSE
' MAINTENANCE CORRECTIVE' ACTION ~TO.
-ASSOCIATED PREVENT RECURRENCE LER Feedwater Feedwater Reg.
FCV-642A'
. Faulty Manual Replaced M/A station;
-N/A' 1N/A System Valve oscillating
/ Automatic re-calibrated (FH)
FCV-642A in automatic Station-
.I/P.642A converter, mode..
M/A-640-19A and replaced airlock at' Panel relay (AL642A).
C905.
Residual RHR Outboard Stem key sheared
' Root cause Replaced: damaged stem N/AL
-N/A Heat Injection off, set. screw under-
-key, set screw and Removal Valve damaged and set.
investigation set screw locking nut.
(RHR)
M01001-28A screw locking (FRN 90-03-04) '
nut missing.
(F&MR 90-19) r D
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'UN T SHOTDONNS AND..PO NC REDUCTIONS DOCKET NO. 50-293
^
NAME Pilaris 1 DATE March 14, 1990 COMPLETED BY M. Munro TELEPHONE (508) 747-8474 REPORT (DiTH _.Egbruary 1990 F4THCD OF LICENSE CAUSE & CORRECTIVE-DURATION Stt0TTIN'i EVENT SYSTEg g ENT ACTION TO PREVENTIVE NO.
DATE TYPEI (HOURS)
REASON 2 DOMN REACTOR 3' REPORT #
CODE RECURRENCE 17 02/10/90 S
0.0 N/A
~ 5 N/A N/A N/A Power reduction due to backwash of main condenser.
4 1
2 2
3 45 i
F-Forced A-Equip r llure F-Admin 1-Manual Exhibit F & H a
i S-Sched B-Maint or Test G-Oper Error 2-Manori Siram Instructions for i
C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continaea Data Entry Sheet E-Operator Training 5-Feduced Load Licensee Event Report
& License Examination W0ther (LER) File (NUREG-1022) l
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