ML20058P244
| ML20058P244 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 09/30/1993 |
| From: | Feigenbaum T, Nardone P NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-93138, NUDOCS 9310220178 | |
| Download: ML20058P244 (5) | |
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eab o N H 03874 Telephone (603)474-9521
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Facsimile (603)474-2987 Energy Service Corporation Ted C. Feigenbaum Senior Vice President and Chief Nuclear Officer NYN-93138 October 14,1993 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Document Control Desk
Reference:
Facility Operating License No. NPF-86, Docket No. 50-443
Subject:
Monthly Operating Report Gentlemen:
Enclosed please find Monthly Operating Report 93-09. This report addresses the operating and shutdown experience relating to Seabrook Station Unit I for the month of September,1993 and is
.i submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.
Veiy truly yours, i
C Ted C. Feigenbaum TCF:ALL/act cc:
Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate 1-4 j
Division of Reactor Projects j
U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 Seabrook, Nil 03874 Q Q()(i t ',
i a member of the Northeast Utilities system p;s 9310220170 930930 e
'PDR ADOCK 050004 3
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j OPERATING DATA REPORT i
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DOCKET NO. 50-443 UNIT Seabrook 1-DATE 10/14/93 COMPLETED BY P. E. Nardone-I TELEPHONE (603) 474-9521
- Ext. 4074 e
OPERATING STATUS
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- I 1.
Unit Name:
Seabrook Station Unit 1 2.
Reporting Period:
. SEPTEMBER 1993 3.
Licensed Thennal Power (MWt):
3411 i
4.
Nameplate Rating (Gross MWe):
1197 i
5.
Design Electrical Rating (Net MWe):
~1148 6.
Maximu:n Dependable Capacity (Gross MWe):
1200 7.
Maximum Dependable Capacity (Net MWe):
1150 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7)
]
Since Last Report. Give Reasons:
Not ADDlicable 9.
Power Level To Which Restricted if Any:
None
- 10. Reasons For Restrictions. If Any:
Not ADDlicable j
This Month Yr.-to-Date-Cumulative l
- 11. Hours In Reporting Period 720.0 6551.0 60984.0
- 12. Number Of Hours Reactor Was Critical 532.7 6116.0 25619.4' i
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 953.3
- 14. Hours Generator On-Line 509.3 6036.8 23617 7
- 15. Unit Reserve Shutdown Hours 0.0 0.0
-0.0 i
- 16. Gross Thermal Energy Generated (MWH) 1737708-20414986~
76937543 17, Gross Elec. Energy Generated-(MWH) 608881 7159034-26720671 j
- 18. Net Electrical Energy Generated (MWH) 586020
-6886375-25663188
- 19. Unit Service Factor 70.7 92.2-81.4-
- 20. Unit Availability Factor 70.7' 92.2 81.4
- 21. Unit Capacity Factor (Using MDC Net) 70.8 91.4 78.4 i
- 22.' Unit Capacity Factor (Using DER Net) 70.9 91.6 78.5-l
- 23. Unit Forced Outage Rate 29.3 7.8 6.2
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
None Scheduled 4
- 25. If Shut Down At End Of Report Period. Estimated Date Of Startup: -10/07/93
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- NOTE: " Cumulative" values based on total hours starting 08/19/90.- date Regular Full Power Operation began.
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i AVERAGE DAILY UNIT POWER LEVEL f
DOCKET NO. 501443 UNIT Seabrook 1~
DATE 10/14/93 l
' COMPLETED BY P. E. Nardone' TELEPHONE-(603) 474-9521 i
Ext. 4074 MONTH SEPTEMBER. 1993 DAY AVERAGE DAILY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL (MWe; Net)
'(MWe-Net) 1 1151 17 1150 2
1150 18 1152 i
. i 3
1151 19 1151 r
4 1151 20 1150 5
1151 21 1150 I
6 1151 22 255 7
1150 23 0
8 1149 24 0
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1148 25 0
i 10 1150 26 0
11 1151 27 0
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12 1151 28 0-l 13 1151 29 0
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14 1152 30 0
15 1152 16 1152
- I i
1 INSTRUCTIONS month-. Compute to the nearest whole megawatt.
-l On this format, list the average daily unit power level in MWe-Net for each day in the reporting
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO, 50-443
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UNIT Seabrook 1 DATE 10/14/93 REPORT MONTH SEPTEMBER. 1993 COMPLETED BY P. Ec Nardone TELEPHONE (603) 474-9521-
_ Ext. 4074 No.
Date Type Duration Reason
- Method of Licensee Cause & Corrective l
(Hours)
Shutting Event Action to 3
Down Reactor Report #
Prevent Recurrence Page 1 of.1 93-05 09/22/93 F 210.7 A
3 93-018 Automatic reactor trip as a result of a RCP undervoltage trip si;nal. This was caused by arcing of the exciter field brushes which resulted in a degrading field condition on the main. generator. See. LER 93-018 for-information on root cause and corrective action.
The reactor was restarted on 09/29/93 and subsequently shutdown on 09/30/93 when attempts to stop a steam leak on a main steam drain' valve were unsuccessful.
i 1
2 3
F: Forced Reason:
Method:
S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 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-Operatio_nal Error (Explain):
(Duration - 0)
H-Other (Explain) 9-Other (Explain) 3 of 4-
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w DOCKET N0.'50-443 UNIT Seabrook 1 I
DATE 10/14/93 COMPLETED BY P. E. Nardone-TELEPHONE.(603) 474-9521 Ext. 4074 3
REFUEllNG INFORMATION REQUEST I
- 1. Name of facility: Seabrook Unit 1
- 2. Scheduled date for next refueling shutdown:
Refueling Outage 3. 03/26/94 3.
Scheduled date for restart following refueling:
Refueling Outage 3. 05/20/94
.j 4.
Will refueling or resumption of operation thereafter require a technical specification change or othar license amendment?
i No
- 5. Scheduled date(s) for submitting licensing action and supporting information:
^I N/A
.i 6.
Important licensing considerations associated with refueling, e.g., new or different fuel j
design or supplier, unreviewed design or performance 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 spent fuel storage pool:
(a) In Core:
193 (b) 136 i
8.
The present licensed spent fuel pool storage capacity and the size of any increase. in
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licensed storage capacity that has been requested or is. planned, in number of. fuel assemblies:
Present licensed capacity: 1236 No increase in storage capacity requested or planned.
- 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 two annual and twelve eighteen-l month refuelings with full core offload capability.
.j The current licensed capacity is adequate until at least the year 2010.
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