ML20115B676
| ML20115B676 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/30/1992 |
| From: | Feigenbaum T, Nardone P NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-92138, NUDOCS 9210160193 | |
| Download: ML20115B676 (5) | |
Text
- -_ - _ ____ - __
M,m North te A & ~8r<
Telephone (603)474 9521 Facsimile (603)474 2987 Energy Service Corporation Ted C. Feigenbaum Senior Vice President and Chiel Nuclear Officer NYN. 92138 October 9,1992 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:
3 Enclosed please find Monthly Operating Report 92-09.
This report addresses the operating and shutdown experience relating to Seabrook Station Unit 1 for the month of September,1992 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.
Very tr. you rs,
- J*
A%4v /
Ted
. Fei' nbaum Enclosure cc:
Mr. Thomas T. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Preject ' Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regu!atory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior R.sident inspector P.O. Box 1149 Seabrook, NH 03874 hhR b
I DD 0
0 43 a member of the Northeast Utihties system
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OPERATING DATA REPORT F_ '
DOCKET NO.
50-443 UNIT Seabrook 1 DATE 10/09/92 I
COMPLETED BY P.-Nardone TELEPHONE (603) 474-9521 1
(Ext. 4074)
OPERATING STATljS 1.
Unit Names Seabrook Station Unit 1 2.
Reporting Period SEPTEMBER 1992 l
3.
Licensed Thermal Power (MWt):
3411 4.
Nameplate Rating (Gross MWe):
1197
.5.
Design Electrical Rating (Net MUe):
1148 6.
Maximum Dependable Capacity (Gross MWe):
1200 i
7.
Maximum Dependable Capacit/ (Net MWe):
1150 8.
If Changes occur in Capacity Ratings.(Items Numbar 3.Through 7)-
Since t-**
D-nort, Give-Reasons:
Not Aonlicable 9.
Powet' %.
'ch Restricted, If Any None
- 10. Re sans Fe v :tions. If Any:
Not Applicable i
This Month-Yr.-to-Date
. Cumulative
- 11. Hours In aeporting Period 720.0 6575.0 52224.0
- 12. Number Of Hours Reactor Was Critical 144.5~
,_,5999.5 18365.0 L
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 953.3 i
- 14. Hours-Generator On-Line 144,0
'5999.0 16523.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH)
__356668 20302552 53372412
- 17. Gross Elec. Energy Generated (MWH) 122754 7098902 18470152
!l
- 18. Net-Electrical 1 Energy Generated '(FNH) 116527-6824172 17732547 I
- 194 Unit Service Factor 20.0 91.2 81.6 1
I
- 20. Unit Availability Factor 20.0 91.2 81.6 l
- 21. Unit-Capacity: Factor-(Using MDC Net) 14.1 90.3
'78.2 l-
- 22. Unit Capecity Factor (Using DER Net) 14.1-90.4 78.4 l
- 23. Unit Fo.ced Outage Rate 0.0-0.0-5.4-
- 24. ShutdownsLScheduled10ver Next 6 Months (Type, Date, and Duration of Each):'
REFUELING. 09/07/9'.. 62 DAYS-t i[
- 25. If Shut Down At-End Of Report Period. Estimated Date:Of-Startup _
11/07/92 i
l
- NOTE: "Cumulati.e"-values based on total hours starting 08/19/90, date_ Regular Full i-Power'D eration began.
y 1 of s l
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..__._m.
b AVERAGE DAILY. UNIT POWER LEVEL 4
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DOCKET NO.-
50-443' f.
. UNIT Seabrook 1-2 DATE 10/09/92
' COMPLETED BY P. Nardone TELEPHONE (603) 474-9521-(Ext. 4074)-
t' MONTH SEPTEMBER, 1992 DAY AVERAGE DAILY POVER LEVEL DAY _
AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net).
4
}
1
-1083 16:
0 4
2 1073 17 0
)
1 3
1056 18 0-t 4
841 19
~0 j
5
- 548:
20-0-
t I
6 254 21 0
l 7
0 22 0
t
{
8 0-23-0 9
0 24_.
0 10 0
25 0
2 4
11 0
26-
-0 12 6
27:
0 13-0 28
'O l
14 0
29 0-15 0
30 0
+
i-
~ INSTRUCTION 3-t s
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.
1 l
1 1
2
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-443
. UNIT Seabrook 1 DATE 10/09/92 REPCRT MONTH SEPTEMBER. 1992 COMPLETED BY P. Nardone TELEt' HONE (603) 474-9521 (Ext. 40743-No.
Date Type-Duration ~
Reason'
. Method of
. Licensee Cause & Corrective l
(Hours)
Shutting Event Action to 3
Down Reactor Report f Prevent Recurrence..
Page l'of 1; t
P 92-01' 09/01/92-S OH4 N/AFuel Coastdown 1Z RTP/ Day 92-02 09/07/92 S
576 C,H 3
92-016 Scheduled refueling. outage.
Low Steam Generator level caused an automatic reactor tri p.
-Generator breaker was opened as scheduled prior to trip.. :;ee LER 92-016 for information on root cause and corrective action.
l' 2
3 F:
Forced Reason:
Method:
S
- Scheduled ~~
.A-Equipment Failure (Explain) 1-Manual..
B-Maintenance or Test' 2-Manual'. Scram 3-Automatic Scram..
C-Refueling.
~
4-Continued from 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).
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4.
DOCKET NO.~
50-443-5 UNIT-Seabrook 1 1
DATE 10/09/92 COMPLETED BY-P. Nardone TELEPHONE-(603) 474-9521 REFUELING INFORMATION REQUEST
- 1. Name of facility:
Seabrook Unit 1
- 2. Scheduled date for next refueling shutdown = 09/07/92
- 3. Scheduled date for restart following refueling:
11/07/92
- 4. Will refueling or resumption of operation thereafter require a technical 1
specification change or other license amendment?
Yes, Reactor Coolant System Narrow Range RTD Bypass Elimination
- 5. Scheduled date(s) for submitting licensing action and supporting information:
Submitted March 20, 1992, NRC Approved August '10,1992 (License Amendment 12).
- 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:
This refueling will be the initial start of-the eighteen-month fuel cycle schedule.
~
7 The number of fuel assemblies (a) in the core'and (b) in the spent fuel storage pools t
(a)
In Core:
0 (b) 329
- 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.
T
- 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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