ML20067B122
| ML20067B122 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 01/31/1994 |
| From: | Feigenbaum T, Nardone P NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-94014, NUDOCS 9402230245 | |
| Download: ML20067B122 (5) | |
Text
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f P.O. Box 300 Odi seabroox. "" 03874 j
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-94014 February 15,1994 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
References:
Facility Operating License NPF-86, Docket No. 50-443
Subject:
Monthly Operating Report Gentlemen:
Enclosed please find Monthly Operating Report 94-01. This report addresses the operating and shutdown experience relating to Seabrook Station Unit I for the month of January,1994 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.
i Very tr j yours, W/ pg
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i Ted C. Fe
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TCF:ALL/sm Enclosure cc:
Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road
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King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 l
Mr. Antone C. Cerne NRC Senior Resident inspector P.O. Box 1149 Seabrook, Nil 03874 i
y 'tember of the Northeast Utilities system 3 g_yi 9402230245 940131 3
Y PDR ADOCK 05000443 s
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o OPERATING DATA REPORT DOCKET NO. 50-443 UNIT Seabrook 1 DATE 02/15/94 COMPLETED BY P. F. Nardone i
TELEPHONE (603) 474-9521 Ext. 40/4 OPERATING STATUS
- 1. Unit Name:
Seabrook Station Unit 1
- 2. Reporting Period:
JANUARY 1994
- 3. Licensed Thermal Power (MWt):
3411
- 4. Nameplate Rating (Gross MWe):
1197
- 5. Design Electrical Rating (Net MWe):
1148
- 6. Maximum Dependable Capacity (Gross MWe):
1200.
- 7. Maximum Dependable Capacity (Net MWe):
1150
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) i Since Last Report. Give Reasons:
Not Acolicable
- 9. Power Level Tu Which Restricted, If Any:
None
- 10. Reasons For Restrictions. If Any:
Not Acolicable i
This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 744,0 744.0 63937.0
- 12. Number Of Hours Reactor Was Critical 585 6 585.6 28292.7
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 953 T
- 14. Hours Generator On-Line 585.6 585.6 26262.8
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1997765 1997765 85430211
- 17. Gross Elec. Energy Generated (MWH) 69/064 697064 29670807'
- 18. Net Electrical Energy Generated (MWH) 670087 670087 28493705
- 19. Unit Service Factor 78.7 78.7 82.2
- 20. Unit Availability Factor 78.7 78./
82 2
- 21. Unit Capacity Factor (Using MDC Net) 78.3 78.3 78 9
- 22. Unit Capacity Factor (Using DER Net) 78.5 78.5 79.0
- 23. Unit Forced Outage Rate 21.3 21.3 6.7
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Each):
REFUELING. 03/26/94. 57 DAYS
- 25. If Shut Down At End Of Report Period. Estimated Date Of Startup: Feb. 12. 1994
- NOTE: " Cumulative" values based on total hours starting 08/19/90. date Regular 4
Full Power Operation began.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-443 UNIT Seabrook 1 DATE 02/15/94
. COMPLETED BY P. F. Nardone TELEPHONE (603) 474-9521 r
Ext. 40/4 MONTH 1ANUARY. 1994 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)-
1 1131 17 1145 2
1144 18 1145 3
1145 19 1144 4
1146 20 1145 5
1146 21 1145 6
1145 22 1144
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7 1145 23 1144 8
1143 24 1145-9 1145 25 456 l
10 1145 26 0
11 1145 27 0
12 1146 28 0
13 1146 29 0
14 1146 30 0
15 1145 31 0
16 1144 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-443 UNIT Seabrook 1 DATE 02/15/94 -
REPORT MONTH JANUARY. 1994 COMPLETED BY P.E. Nardone i
TELEPHONE (603) 474-9521 Ext. 40/4 i
No.
Date Type' Duration Reason' Method of Licensee Cause & Corrective (Hours)
Shutting Event Action to 3
Down Reactor Report-#
Prevent Recurrence Page 1 of 1 i
94-01 01/25/94 F
158.4 B/A 3
94-001 Automatic trip as a result of decreasing level in SG A This was caused by the slow full closure of MSIV A during the performance of the quarterly 10% partial stroke test.
See LER 94-001 for information on root cause and corrective action.
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i F: Forced Reason:
Method:
S: Scheduled A-Equipment Failure (Explain) 1-Manual 3
B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram i
D-Regulatory Restriction 4-Continued from
[
E-Operator Training & License Examination previous month F-Administrative 5-Power Reduction l
G-Operational Error (Explain)
(Duration - 0) 1 H-Other (Explain) 9-Other-(Explain) a i
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j DOCKET NO. 50 d43 i
UNIT Seabrook i DATE 02/15/94 l
COMPLETED BY P. -t.
Nardone TELEPHONE (603) 4/4-95?1 Ext 4074 l
REFUELING INFORMATION RE0 VEST l
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- 1. Name of facility: Seabrook Unit 1
- 2. Scheduled date for next refueling shutdown:
l Refueling Outage 3. 03/26/94
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- 3. Scheduled date for restart following refueling:
Refueling Outage 3. 05/21/94 I
- 4. Will refueling or resumption of operation thereafter require a technical spec 1fication change or other license amendment'?
No a
- 5. Scheduled date(s) for submitting licensing action and supporting information:
)
N/A 4
- 6. Important licensing considerations associated with refueling, e.g.,
i new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design.
new operating procedures:
None
- 7. The number of fuel assemb'ies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
193 (b) 136
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- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
i i
Present licensed capacity: 1236 No increase in storage capacity requested or planned.
- 9. The projected date of the last refueling that can be discharged tu the spent fuel pool assuming the present licensed capacity:
Licensed capacity of 1236 fuel assemblies based on two annual and twelve eighteen-month refuelings with full core of fload capability.
t The current licensed capacity is adequate until at least the year 2010.
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