ML20065R635
| ML20065R635 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/30/1990 |
| From: | Richard Anderson, Basilesco G BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-155, NUDOCS 9012190118 | |
| Download: ML20065R635 (7) | |
Text
. _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
{m) sosTONtotscw
.s svgnm Nvuear,9*ei stanon lL'K k ) H!h ID0d I1pmosth, f/at%8C hus0ti $ 02 %D December 12, 1990 BECo Ltr. #90-155 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293
Subject:
November 1990 Honthly 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. Should you have any questions concerning this report please contact me directly.
,l
//
Is; y/(WUL/n--
K s
R,A. Anderson Station Director and Vice President, Nuclear Operations GJB/bal Attachment cc: Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Rd.
King of Prussia, PA 19406 Senior Resident Inspector kb$dk$$$$$$93
[
PDR lI
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-293 UNIT Pilarim 1 DATE necember 12. 1990 COMPLETED BY G. Basilesco TELEPHONE (508) 747-8534 HONTH November 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0HER LEVEL (HHe-Net)
(HHe-Net) 1 663 17 662 2
586 18 C64 3
428 19 662 4
546 20 663 5
656 21 663 6
663 22 662 7
664 23 663 8
663 24 662 I
9 663 25 663 10 661 26 663 11 664 27 663 12 664 28 663 13 664 29 663 14 664 30 661 15 663 31 N/A 16 663 This format lists the average daily unit power level in HHe-Net for each day in the reporting month, computed to the nearest whole megawatt.
.-------.-u
OPERATING DATA REPORT DOCKET NO.
50-293 DATE December 12. 199n COMPLETED BY G. Basilesto TELEPHONE (508) 747-8534 OPERATING STATUS Notes 1.
Unit Name Pilarim 1 g
2.
Reporting Period November 1990 3.
Licensed Thermal Power (MHt) 1998 4.
Nameplate Rating (Gross MHe) 613 5.
Design Electrical Rating (Net MWe) 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 Hhich Restricted, If Any (Net HHe)
None
- 10. Reasons for Restrictions, If Any N/A This Month Yr-to-Date Cumulative i
- 11. Hours In Reporting Period 720.0 8016.0 157584.0
- 12. Number Of Hours Reactor Has Critical 720.0 6451.0 91856.7
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 720.0 6042.8 88172.1
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MHH) 1408056.0 11435568.0 151920480.0
- 17. Gross Electrical Energy Generated (MHH) 484810.0 3921470,0 51158294.0
- 18. Net Electrical Energy Generated (MHH) 4667804 3772292.0 _49155476.0
- 19. Unit Service factor 100.0 75.4 56.0
- 20. Unit Availability Factor 100J 75.4 56.0
- 21. Unit Capacity Factor (Using HDC Net) 96.8 70.2 46.6
- 22. Unit Capacity Factor (Using DER Net) 99_.0 71.8 47.6
- 23. Unit forced Outage Rate 0.0 12 &
12.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):
Refuelino Outagg No. 8. Hav 1991. aDoroximatelv 70 days
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup -
N/A
- 26. Units In Test Status (Prior to Commerc k! Operation):
N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
..--.--...........--..--._...-.--.....-....-....a-.d
BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION QQCK[T NO. 5(L-L93 Operational Summary for November 1990 The unit started and ended the reporting period at approximately 100 percent power. On November 1, 1990, the High Pressure Coolant Injection (HPCI) System was voluntarily taken out of service and maintenance was performed on the HPCI turbine.
The system was returned to service on November 5, 1990. On November 3, 1990, power was reduced to approximately 50 percent to perform a thermal backwash of the main condenser and returned to 100 percent power on November 5, 1990.
In addition, minor power reductions for control rod exercises were performed on November 10, 17 and 24.
Safety Relief Valve Challenge; Honth of November 1990 Requirement:
NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during this reporting period.
An SRV challenge 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.
REFUELING INFORMATION 4
I 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, j
each number corresponds to equivalent notation utilized in the request.
.1.
The name of this facility is Pilgrim Nuclear Power Station Docket Number i
50-293.
2.
Scheduled date for next Refueling Shutdown: Second Quarter 1991
)
3.
Scheduled date for restart following refueling:
Third Quarter 1991 1'
4.
Due to their similarity, requests 4, 5, & 6 are responded to collectively j
under #6.
5.
See N6.
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 fuel pool.
2 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.
L 9.
With present spent 'uel in storage, the spent fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.
1
.u._..,_..-._.._._._,_.._.__..__.,_,,._.
_ _,.. _. _..., _.... _... _ _ _ _... _ _. ~. _ _. _ _ _. _, _
Month November 1990 PILGRIM DJCLEAR POWER STATf C t
MAJOR SAFETY RELATED MAINTENANCE i
SYSTEM COMPONENT MALFUNCTION cal)SE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER i
High HPCI Turbine Overspeed trip Mechanical /
Changed pliot Reference LER LER 90-017-00 Pressure (F&MR 90-352) hydraulic mal-valve spring:
90-017-00 Coolant function of aligned bushing Injection speed control ports; replaced (HPCI) system.
EG-M.
System I
I i
4
- LCIT SHUTDOMMS AND PONER REDUCTIONS DOCKET NO. 50-293 NAME P11crin 1 i -'
DATE December 12. 1990 COMPLETED BY G. Basilesco TELEPHONE (508) 747-8534 REPORT MONTH November 1990 METHOD OF LICENSE CAUSE & CORRECTIVE.
I DURATION SHUTTING EVENT SYSTE ENT ACTION TO PREVENT CgODE j.
NO. -
DATE TYPEI (HOURS)
REASON 2 00MN REACTOR 3 REPORT #
C00 RECURRENCE i
14' 11/3/90-S..
0.0 N/A 5
N/A N/A N/A Power redur.tlon to perform main condenser backwash.
1 1
2 2
3 4&S F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H l
S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for j
C-Refueling H-Other 3-Auto Scram Preparation of
~
0-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5--Reduced Load
_ Licensee Event Report
& License Examination 9-Other (LER) File (NUREG-1022) 4 i
I-l l
1 i
.