ML20087F152
| ML20087F152 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/31/1995 |
| From: | Feigenbaum T, Nardone P NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-95062, NUDOCS 9508150158 | |
| Download: ML20087F152 (5) | |
Text
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4 Nortli-North Atlantic Energy Service Corporation L:
1 y.o. 3,,3oo dil8Dtic-Seab moA m 03874 r
(603)474-9521, Fax (603)474-2987 The Northeast Utilities System Ted C. Feigenbaum NYN-95062 Senior Vice President &'
Chief Nuclear Officer August 9,1995 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
Reference:
Facility Operating License NPF-86, Docket No. 50443
Subject:
Monthly Operating Report Gentlemen:
Enclosed please find Monthly Operating Report 95-07. This report addresses the operating and shutdown experience relating to Seabrook Station Unit I for the month of July,1995 and is submitted in accordance with the requirements of Seabrook Station Technical Specification Very t
- yours,
/
y g;;ilu Ted C. Feigenbaum Enclosure t
cc:
Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road i
King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission i
Washington, DC 20555 I
Mr. John B. Macdonald NRC Senior Resident Inspector PO Box 1149 Seabrook, NH 03874 i
9508150158 950731
/
F DR ADOCK 0500 3
/
OPERATING DATA REPORT DOCKET NO.
50-443
' UNIT Seabrook 1 DATE 08/09/95 COh"PLETED BY P.E. Nardone TELEPHONE 603/474-9521 Ext. 4074 OPERATING STA'IUS 1.
Unit Name:
Seabrook Station Unit 1 2.
Reporting Period:
JULY 1995 3.
Licensed Thermal Power (MWt):
3411 4.
Nameplate Rating (Gross MWe):
1197 i
Design Electrical Rating (Net MWe):
1148 6.
Maximum Dependable Capacity (Gross MWe):
1200 7.
MaAimum Dependable Capacity (Net MWe):
1150 8.
If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Not Applicable Report, Give Reasons:
9.
Power Ixvel To Which Restricted, If Any (Net MWe):
1090MWe 10.
Reasons For Restrictions, If Any:
Final Stage FW Heating capability lost for remainder of Cycle.
1his Month Yr-to-Date Cumulative 11.
Ilours in Reporting Period 744.0 5087.0 77040.0 12.
Number of Hours Reactor Was Critical 744.0 4836.6 38103.6 13.
Reactor Reserve Shutdown Hours 0.0 0.0 953.3 14.
Ilours Generator On-Line 644.4 4693.9 35838.1 15.
Unit Reserve Shutdown Hours 0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH) 2211297 16037941 117874749 l
17.
Gross Elec. Energy Generated (MWII) 719790 5597035 41021370 18.
Net Electrical Energy Generated (MWII) 690221 5383621 39410737
- 19.
Unit Service Factor 86.6 92.3 79.5
- 20.
Unit Availability Factor 86.6 92.3 79.5
- 21.
Unit Capacity Factor (Using MDC Ne0 80.7 92.0 76.9
- 22.
Unit Capacity Factor (Using DER Nc0 80.8 92.2 77.1
- 23, Unit Forced Octage Rate 13.4 7.7 6.9 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, Refueling, 11/04/95. 45 Days and Duranon of Each):
25.
If Shut Down At End Of Report Period, Estimated Date of Not Applicable Startup:
- NOTE: ' Cumulative
- values based on total hours starting R/19/90. date Regular tvil Power Operation began.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50 413
- g UNIT Seabrook DATE 08/09/95 COMPLETED BY P.E. Nardone TELEPilONE 603/474-9521 Ext. 4074 MONTH: JULY,1995
' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL -
)
(MWe-Net)
(MWe-Net) l l
0 17 1089 2
0 18 1086 3
0 19 1086 4
0 20 1085 5
471 21 1088 6
1074 22 1088 7
1090 23 1088 8
1090 24 1088 9
1091 25 1088 l
10 1090 26 1088 l
l 11 1090 27 1088 12 1090 28 1088 13 1090 29 1087 i
14 1090 30 1087 l
15 1090 31 1088 16 1089 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 l
DOCKET NO.
50-443 UNIT Seabrook 1 DATE 08/09/95 l
COMPLETED BY P.E. Nardone g TELEPIIONE 603/474-9521 Ext. 4074 REPORT MONT11 JULY 1995 NO.
DATE TYPE' DURATION l REASON
- METilOD OF SilUITING LICENSEE EVENT CAUSE & CORRECTIVE ACTION TO PREVENT (IIOURS)
DOWN REACTOR' REPORT #
RECURRENCE Page1of1 Manual trip as a result of the loss of both turbme E!cctro-9541 07/01/95 F
99.6 A
4 95 m Ilydraulic Control (EllC) pumps on 06/18/95.
EllC pumps lost electrical power when Unit Substation 14 feeder breaker tripped open while crosstied to Unit Substation 21.
See LER 9542 for information on root cause and corrective action.
Reactor critical on 06/29/95.
Restart was delayed on 06/30/95 when Main Generator Breaker failed to close.
Additional pioblems with Main Turbine bearing vibration further delayed restart until 07/05/95.
1 3
F: Forced Reason-Method:
S: Scheduled A - Equipment Failure (Explam) 1 - Manual B - Maintenance or Test 2 - Manual Scram C - Refueling 3 - Automat c Scram i
D - Regulatory Restriction 4 - Continued from previous month E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)
F - Administrative 9 - Other (Explain)
G - Operational Error (Explain)
II - Other (Explain) 3 Of 4
REFUELING INFORMATION REQUEST 4
DOCKET NO.
50-443
),
UNrr Seabrook1 DATE 08/09/95 COMPLETED BY P.E. Nardone TELEPIIONE 603/474-9521 Ext. 4074 1.
Name of Facility:
Seabrook Unit 1 2.
Scheduled date for next refueling shutdown:
Refueling Outage 4,11/04/95 3.
Scheduled date for restart following refueling: Refueling Outage 4,12/19/95 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes, revisions to Technical Specifications for Accumulator and Refueling Water Storage Tank boron concentration, Main Steam Safety Valve setpoints and of Pressure Isolation Valves will be required.
5, Schedule date(s) for submitting licensing action and supporting information:
Accumulator and Refueling Water Storage Tank boron concentration was submitted on June 16,1995.
Pressure Isolation Valves was submitted on July 27,1995. Main Steam Safety Valve setpoint revisions are scheduled for submittal by August 31,1995.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Implementation of Amendment #33, to Facility Operating License Wide Band Operation.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a)In Core:
193 (b) 208 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:
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-month refuelings with full core offload capability.
The current licensed capacity is adequate until at least the year 2010.
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