ML20077Q259
| ML20077Q259 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/31/1991 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-91124, NUDOCS 9108210146 | |
| Download: ML20077Q259 (7) | |
Text
,
Ted C. Feigenbovm President and e'
Chief Executive Of ficer NYN-91124 August 14, 1991 United States Nuclear Regulatory Commis.sion Washington, DC 20555 Attention:
Document Control r)esk
Reference:
Facility Operating License NPF-86, Docket No. 50-443
Subject:
Monthly Operating Report Gentlemen:
Enclosed please find Monthly Operating Report 91-07.
This report addresses the operating and shutdown experience relating to Seabrook Station Unit 1 for the month of J uly, 1991 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.
Very truly yours, f f # J' Ted C. Fei, nbaum Enclosure (s)
TCF:WJT/ tad cc:
Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commissioe Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senio Resident Inspector P.O. Box 1149 Seabrook, NH 03874 9108210146 >10731 PDR ADOCK O'3000441 R
PDR Q
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New Hampshire Yankee Division of Public Service Company of New Hampshire J-
- 1g P.O. Box 300 = Seabrook, NH 03874 = Telephone (603) 474-9521 iI
New llampshire Yankee August 14, 1991 j
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OPERATING DATA REPORT DOCKET NO.
50-443 UNIT Seabrook 1 DATE 08/34/91 COMPLETED BY P. Hy done TELEPHONE (603) 474 9521 (Ext. 4074)
OPERATING STATUS 1.
Unit Name:
Seabrook Station Unit 1 2.
keporting Period:
JULY 1991 3.
Licensed Thermal Power (MWt):
3411 4.
Nameplate Rating (Gross HWe):
1197 5.
Design Electrical Rating (Net MWe):
1148 6.
Maximum Dependable Capacity-(Cross MWe):
1200 7.
Maximum Dependable Capscity (Net MWe)..
1150 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 Anys:
None
- 10. Reasons For Restrictions. If Any:
Not Ano11 cable This Month Yr. to-Date Cumulative
- 11. Hours In Reporting Period 744,0 5087.0__
41976 0 t
- 12. Number Of !!ours Reactor Was Critical 530.1 4650.1 10369.4 13.-Reactor Reserve Shutdown !!ours o q__
0.0
_ _ _ 8703.0 953.3
- 14. Hours Generator On-Line 513.9 4575.6
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (HWH) 1642082 14687730
_27288055
- 17. Gross Elec. Energy Generated (MWH) 56974P 5107161 9379078 18 Het Electrical Energy Generated (HWH) 548318 4904131 8998129
- 19. Unit Service Factor 69.1 89.9 88.2 L
- 20.' Unit AvaA1 ability Factor 69.1 89.9' 88.2-
- 21. Unit Capacity Factor (Using MDC Net) 64.1 83.8 83.3
- 22. Unit Capacity Factor (Using DER Net).
64.2 84.0 83.4 L
- 23. Unit Forced Outage Rate 17.6 7.9 10.5 24; Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
REFUELING. 07/27/91. 67 DAYS
- 25. If Shut Down At End Of Report Period. Eitimated Date of Startup:
09/30/91
- NOTE' ' Values based on accumulated hours starting 08/19/90, date Regular Full Power Operation began.
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AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO.
50-441 UNIT Seabreok 1 DATE 08/14/01 COMPLETED BY P. Nnrdone TELEPHONE (603) 474-9521 (Ext. 4074)
MONTH,_ JULY. 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(1Ne - Ne t )
1 9M 16 1145 2
1145 17 1144 3
1145 18 1146 4
401 19 1149 5
0 20 1150 6
0 21 1150 7
89 22 1150 8
282 23 1149 9
915 24 1149 10 1149 25 662 11 1150 26 0
12 1150 27 0
13 1149 28 0
14 1149 29 0
13 1348 30 0
31 0
INSTRUCTIONS On this f ormat, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whcle negawatt.
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1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-443 UNIT Seabrock I i
DATE OS/14/91' REPORT MONTH
' JULY. 1991 COMPLETED BY P. Nardone TELEPHONE 1603) 474-9521 (Ext. 4074)
No.
Date Type Duration
. Reason' Method of Licensee Cause & Corrective i
(Hours)
Shutting Event Action to 3
i Down Reactor Report f Prevent Recurrence Page 1 of 2 l
91-06 07/04/91 F
77.7 A.
3 91-009 Low flow in reactor coolant system loop 3 caused an auto-matic reactor / turbine trip. See LER 91-009 for information on root cause and corrective action.
l 91-07 07/25/91 F
32.4 A
91-010 Reactor coolant system unidenti-j.
fled leakage exceeded 1.0 g;m l.
which required a manual plant i
shutdown.
.iee LER 91-010 for l.
information on root cause and corrective action.
a e
i 1
2 3
F:
Forced Reason:
Method:
S: Scheduled A-Equipment Failure (Explain) 1-Manesi B-Maintenance or Test 2-Manual Scram l
C-Refueling 3-Automatic Scram l
D-Regulatory Restriction 4-Continued from j
E-Operator Training & License Examination previous month l
F-Administrative 5-Fower Reduction G-Operational Error (Explain)
(Duration - O}
l H-Other (Explain) 9-Other (Explain) l' 3 of 5 i
1 i
_.. - _.,,, _,. _,_.~...-_ _ _ _.._ _ _
o UNIT SHUTDOWNS AND POWER EEDUCTIONS DOCKET NO.
50-403 UNIT Seabrock 1 l
DATE 08/14/91' REFCRT MONTH JULY. 1991 COMPLETED BY F. Nardene TELEPHONE (603) 474-9521 (Ext. 4074) 4 No.
Date Type!
Duration Reason.
Method of Licensee.
Cause & Corrective 2
(Hours)
Shutting Event Action to 3
l Down Reactor Report i
. Prevent Recurrence Page 2 of 2 i
i 91-08 07/27/91-S' 120 C.
9 N/A Start of scheduled refueling j
outage following manual shut-down on 07/25/91.
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DOCKET NO.-
50-443 i
UNIT Seabrook 3 1
DATE,_ 08/14/91 t
COMPLETED BY P. Hardone TELEPHONE (603) 474-9521 (Ext. 4074) l REFUELING _INFORMATION REQUEST l
- 1. Name of facility:
Seabrook Unit 1
- 2. Scheduled date for next refueling shutdown:
07/27/91 actual 07/25/91
- 3. Scheduled date for restart following refueling:
09/30/91
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other Itcense amendment?
I Hone 5
- 5. Scheduled date(s) for submitting licensing action and supporting informations 1
None
+
- 6. Important licensing considerations associated with refueling, e.g..-
new or different fuel design ur supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures t
None
-7.
The number of fuel assemblies-(a) in the core and (b) in the spent fuel storage pools (a) 'In Core:
193 (b) 60 (new) l I
- 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, i.
~
- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
L Licensed capacity of 1236 fuel assemblies based on sixteen l
annual refuell.1gs and full core offload capability.
1
[
The current licensed capacity is adequate until ct least the year 2007.
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