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
rwn f$ Mw Hampshire Tod C. F '.
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Senior Vice Presi 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:
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Enclosed please find Monthly Operating Report 90-01. 'This report
~
addresses the operating.and shutdown experience relating to Seabrook Station-
. 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.
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=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
/
h2270151900131
'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
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OPERATING DATA REPORT
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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 i
'20. Unit Availability Factor 0.0 0.0 0.0 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
- 23. Unit Forced Outage Rate 0.0 0.0
-0.0 i.
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
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INITIAL CRITICALITY 1989 06/13/89 L
INITIAL ELECTRICITY 1990 Not Applicable COMMERCIAL OPERATION 1990 Not Applicable l
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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~
21-
'O 0-
' 7.
0 22 0
i 8
-0 23 0
9 0
24 0
1 4
i 10 0
25 0
i
'11 0
26 0'
.j 12 0
.27 0
13
-0 28 0
l 1
14 0
29 0
.j 15 0
30 0
-(
31 0
.(
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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-,- : w UNIT SHUTDOWNS AND POWER REDUCTIONS
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.. 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 Duration ' Reason 2-
- Method of-Licensee Cause & Corrective-l (Hours)
Shutting Event Action to 3
Down Reactor 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 4-Continued from 3-Automatic Scram D-Regulatory Restriction 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 TELEPHONE (603) 474-9521 REPORT MONTH JANUARY. 1990 (Ext. 4074)
Page 1 of 2 MAINTENANCE ACTION DATE SYSTDi COMPONENT 01/06/90 Primary 1-CC-V-121 Air operated valve failed to apen.
Component Train A Repaired broken wire at solenoid coil Cooling Water Inside Containment termination.
Isolation Valve Both reactor trip breakers failed to 01/06/90 Rod Control 1-CP-CP-111 Train A and B close during surveillance testing.
Reactor Trip Cleaned dirty contacts on charging Switchgear motor cutoff limit switches. Replaced faulty spring release coil on Breaker B.
01/06/90 Reactor 1-RC-LCV-459 Air operated valve failed to close during Coolant Train A letdown isolation test. Replaced defective 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
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o D00KET NO.
50-443 UNIT Seabrook 1
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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.
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- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Licensed capacity of 1236 fuel assemblies based on sixteen l
refuelings and full core offload capability.
The current licensed capacity is adequate until at least the l
year 2010.
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6 of 6 l
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