ML20006F084
| ML20006F084 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/31/1990 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-90039, NUDOCS 9002270151 | |
| Download: ML20006F084 (7) | |
Text
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f$ Mw Hampshire -
..'+ Tod C.Presi Senior Vice F '.
- 5nt and -
Chief Operating Oflicer
.p lin NYN- 90039
$ February 15, 1990 i
i United States Nuclear Regulatory Comission Washington, DC 20555
.;
' Attention: Document Control Desk
References:
Facility Operating License NPF-67. Docket No. 50-443
Subject:
Monthly Operating Report Gentlemen: j
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Enclosed please find Monthly Operating Report 90-01. 'This report addresses the operating.and shutdown experience relating to Seabrook Station-
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. Unit 1 for the month of January 1990 and is-submitted in.accordance with the-roquirements of Seabrook. Station Technical Specification 6.8~.1.5.
- l. =Very truly yours, l
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Ted C. Fe genbaum- !
Enclosure.
ces- Mr. William T. Russell-Regional' Administrator
, United States Nuclear Regulatory Comission .
Region I 475 Allendale Road
-King of Prussia, PA 19406 1
~Mr.' Noel Dudley- 1 NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874
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'R ADoCK 0500o443:
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.New Hampshire Yonkee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521 h U't I
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~'" OPERATING DATA REPORT t
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DOCKET NO. 50-443 UNIT Seabrook 1 DATE '02/15/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)-
OPERATING STATUS ,
1.- Unit Name ~ Seabrook Station Unit 1
- 2. Reporting Period: JANUARY 1990
- 3. Licensed Thermal Power'(ISit): 3411
- 4. Nameplate Rating (Gross-MWe): 1197
- 5. . Design Electrical Rating (Net MWe): 1148
- 6. ' Maximum Dependable Capacity (Gross MWe): 1197 (Initial design value) 7 . -- Maximum Dependable Capacity (Net'MWe): 1148 (Initial design value)
- 8. If. Changes Occur in Capacity Ratings (Items Number 3 Through 7)
-Since Last Report, Give Reasons:
Not Applicable
- 9. Power Level To Which Restricted, If Any: 170 MWt ]
- 10. Reasons For Restrictions, If Any: License issued on.05/26/89 is a low power !
license authorizinn operation at reactor core power levels not in excess of 170 megawatts thernel.
This Month Yr.-to-Date Cumulative 11.-Hours In Reporting Period' 744.0 744.0 28873.0- j
- 12. Number Of Hours Reactor Was Critical 0.0 0.0 194.4 i 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 L 14. Hours Generator.On-Line 0.0 0.0 0.0
- 15. Unit Re' serve. Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 0 0 1090
- 17. Gross Elec. Energy Generated (MWH) 0 0 0 L 18. Net Electrical Energy Generated (MWH) 0 0 0 ,
l- 19. Unit Service Factor 0.0 0.0 0.0
'20. Unit Availability Factor 0.0 0.0 0.0 i
l 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 0.0 22.JUnit Capacity Factor (Using DER Net) 0.0 0.0 0.0 ,
i.
- 23. Unit Forced Outage Rate 0.0 0.0 -0.0
! J24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Reactor shutdown as of 06/22/89 for indefinite duration.
- 25. If Shut Down At End Of Report Period, Estimated Date Of Startup: Indefinite
- 26. Prior to Commercial Operation: Forecast Achieved
) INITIAL CRITICALITY 1989 06/13/89 L INITIAL ELECTRICITY 1990 Not Applicable COMMERCIAL OPERATION 1990 Not Applicable l
1 of 6 Y-
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[ AVERAGE DAILY UNIT POWER LEVEL
- DOCKET NO. - 50-443 UNIT Seabrook 1 DATE 02/15/90 COMPLETED BY- P. Nardone
, TELEPHONE (603) 474-9521:
(Ext. 4074) l
- l. 'HONTH JANUARY. 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
,1 - 0 __
16 'O g
21 0 17 0 j
- !3- 0 18 0 4 0 19 0
.5 0 20 0
,e: '6~ 0- 21- 'O
' 7. 0 22 0 ,
i 8 -0 23 0 ,
9 0 24 0 1 4
i 10 0 _
25 0 ;
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'11 0 _
26 0' .j 12 0 .27 0 13 -0 28 0 l 1
14 0 29 0 .j 15 0 30 0 ;
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31 0
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INSTRUCTIONS-
-On this format, list the average daily unit power level in MWe-Net for each day in the raporting month.- Compute to the nearest whole megawatt.
2 of 6 c = '
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UNIT SHUTDOWNS AND POWER REDUCTIONS .. DOCKET NO6 7 50-443 J- i UNIT Seabrook'l~ .
DATE 02/15/90 REPORT MONTH JANUARY.'1990 ~ -COMPLETED BY P. Nardone TELEPHONE'(603) 474-9521~-
, (Ext.-4074)
No. Date Type l Duration ' Reason 2- : Method of- Licensee Cause & Corrective-(Hours) Shutting Event Action to Down Reactor 3 Report i Prevent' Recurrence i
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NO ENTRIES FOR THIS 210 NTH 1 2 3-F: Forced Reason:- Method:-
S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling .
3-Automatic Scram D-Regulatory Restriction 4-Continued from E-Operator Training & License Examination previous month F-Administrative 5-Power Reduction G-Operational Error (Explain). (Duration = 0)
H-Other (Explain)- 9-Other~(Explain) l l
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DOCKET NO. 50-443 ,
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UNIT Seabrook 1 DATE 02115/90 COMPLETED BY P. Nardone CORRECTIVE MAINTENANCE SUt99LRY FOR SAFETY RELATED EQUIPMENT JANUARY. 1990 TELEPHONE (603) 474-9521 REPORT MONTH (Ext. 4074)
Page 1 of 2 COMPONENT MAINTENANCE ACTION DATE SYSTDi Primary 1-CC-V-121 Air operated valve failed to apen.
01/06/90 Repaired broken wire at solenoid coil Component Train A Cooling Water Inside Containment termination.
Isolation Valve Rod Control 1-CP-CP-111 Both reactor trip breakers failed to 01/06/90 close during surveillance testing.
Train A and B Reactor Trip Cleaned dirty contacts on charging Switchgear motor cutoff limit switches. Replaced faulty spring release coil on Breaker B.
Reactor 1-RC-LCV-459 Air operated valve failed to close during 01/06/90 letdown isolation test. Replaced defective Coolant Train A Letdown Isolation solenoid valve.
Valve 4 of 6
. w-DOCKET NO. Sti-443 UNIT Seabrook 1 DATE 02115190 CORRECTIVE MAINTENANCE SUt9%RY FOR SAFETY REIATED EQUIPMENT COMPLETED BT P. Nardone REPORT MONTH JANUARY. 1990 TELEPHONE (603) 474-9521 (Ext. 4074)
Page 2 of 2 DATE SYSTEM COMPONENT MAINTENANCE ACTION 01/08/90 Residual Heat 1-RB-P-9B Installed redesigned impellar to reduce Removal Train B thrust loads during operation.
RER Pump 01/17/90 Primary 1-CC-E-17B Heat exchanger leaking. Plugged tubes Component Train B identified during eddy current testing.
Cooling Water Primary Component Resleeved all remaining tubes.
Cooling Water Heat Exchanger 01/22/90 Reactor Coolant 1-RC-TB-412D/G Bistable failed to operate during Protection Set 1 surveillance test. Replaced fuse.
LO TAVG, LO-LO TAVG Temperature Bistable 5 of 6
_- m . . . . . . -~ ____. ._________.-___J
o ' - D00KET NO. 50-443
+ UNIT Seabrook 1
- DATE 02/15/90 __
. COMPLETED BY P. Hardone TELEPHONE (603) 474-9521 (Ext. 4074)
REFUELING INFORMATION REOUEST
- 1. Name of facility: Seabrook Unit 1
- 2. Scheduled date for next refueling shutdown: Not Scheduled
- 3. Scheduled date for restart following refueling: Not Scheduled
- 4. Vill refueling or resumption of operation thereafter require a technical specification change or other license amendmentt Unknown at this time.
- 5. Scheduled date(s) for submitting licensing action and supporting infonmation l
Not Applicable 1
- 6. Important licensing considerations associated with refueling, e.Bae new or different fuel design or supplier, unreviewed design or parformance analysis methods, significant changes in fuel design, new operating procedures:
None
- 7. The number of fuel assemblies (a) in the core and (b) in the opert fuel storage pools (a) In Core 193 (b) 0
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requestod or is planned in number of fuel assemblies:
Present licensed capacity: 1236 No increase in storage capacity requested or planned.
l I 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
l Licensed capacity of 1236 fuel assemblies based on sixteen refuelings and full core offload capability.
The current licensed capacity is adequate until at least the l year 2010.
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