ML20246M148
| ML20246M148 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/30/1989 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8907190073 | |
| Download: ML20246M148 (7) | |
Text
,i N
New iampshire.
Ted C. Feigenbaum Vice President r.
NYN-89089 July 13, 1989 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
-References a) facility Operating License NPF-67, Docket No. 50-443
Subject:
Monthly Operating Report Gentlemen:
In accordance with Technical Specification Section 6.8.1.5,. enclosed please find Monthly Operating Report 89-06 covering the operation and shutdown-experience relating to Seabrook Station Unit 1.
Very truly yours, gjf&
,cv61 W
Ted C. Feige:1baum Enclosure
\\
cc:
Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 NRC Senior Resident Inspector P.O. Box 1149 Seabrook Station, NH 03874 G907190073 890630 PDR ADOCK 05000443 R
PDC New Hampshire Yonkee Division of Public Service Company of New Hampshire
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OPERATIIG DATA REPORT DOCKET 10.
50-443 UNIT Seabrook 1 DATE 07/11/89 CCMPIEfED BY P. Nardone TELEPHONE 1603) 474-9521 (Ext. 4074)
OPERATUG STATUS 1.
Unit Nane:
Seabrook Station Unit 1 2.
Reporting Period:
JUNE 1989 3.
Licensed 'IM-1 Power (1st):
3411 4.
Nameplate Rating (Gross ISe):
1197 5.
Design Electrical Rating (Net MWe):
1148 6.
Maximum Dependable Capacity (Gross MNe):
1197 (Initial design value) 7.
Maximum Dependable Capacity (Net MNe):
1148 (Initial design value) 8.
If Changes Occur in Capacity Ratings (Itans Number 3 nrough 7)
Since Last Report, Give Reasons:
Not Applicable 9.
Power Invel 'Ib Which Restricted, If Any 170 MNt
- 10. Reasons For Restrictions, If Any:
License issued on 05/26/89 is a low oower license authorizing operation at reactor core power levels not in excess of 170 mecawatts thermal.
% is Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Pericd 720.0 4343.0 23712.0
- 12. Number Of Hours Reactor Was Critical 194.4 194.4 194.4
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 0.0 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross hennal Energy Generated (MWH) 1090 1090 1090
- 17. Gross Elec. Energy Generated (MNH) 0 0
0
- 18. Net Electrical Energy Generated (MNH) 0 0
0
- 19. Unit Service Factor 0.0 0.0 0.0
- 20. Unit Availability Factor 0.0 0.0 0.0
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 0.0
- 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 0.0
- 23. Unit Forced Outage Rate 0.0 0.0 0.0
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Durr. tion of Each):
Reactor shutdown as of 06/22/89 for indefinite duration.
- 25. If Shut Down At End Of Report Period, Estimated Date Of Startup:
Indefinite
- 26. Units In Test Status (Prior to Cu m u. vial Operation): Forecast Achieved INITIAL CRITICALITY 1989 06/13/89 INITIAL ELECTRICITY 1989 Not Applicable CCHMERCIAL OPERATION 1989 Not Joplicable f
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.' AVERAGE DhILY INIT PONER IJME n: - -.,
Y DOC 10!,T NO.
50-443 y*
INIT Seabrook 1 DATE 07/11/89 OCEPLETED BY P. Nardone TELEPH3E (603) 474-9521~
-(Ext. 4074)'
K NIH
'JtME, '1989 -
a i DRYi ' AVERAGE DhILY PGIER IJM!L DAY
- AVERAGE DhILY PONIR IJMEL (160e-Net).
(Ble-Net) o 1
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INS'IRUCTIONS -
On this fornet, list the average daily unit power level in NNe-Net for each day in the
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DOCKET NO.
50-443-UNIT Seabrook 1 DATE 07/11/89 j
CCMPLETED BY P. Nardone j
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TELEPHONE (603) 474-9521
)
(Ext. 4074)
REFUELDG INFORMATION Rwumr j
- 1. Name of facility: Seah d Unit 1
- j u
- 2. Scheduled date for next refueling shutdown: Not Scheduled
- 3. Scheduled date for restart following refueling: Not Scheduled
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license airealiuut?
Unknown at this time.
- 5. Scheduled date(s) for submitting licensing action and supporting information:
Not Applicable
- 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 pu m bres:
None
- 7. The number of fuel ass ablies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
193 (b) 0
- 8. The present licensed spent fuel pool storage capacity and ths 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 capc: city requested or planned.
I i
- 9. W e 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 assablies based on sixteen refuelings and full core offload capability.
1 h e current licensed capacity is adequate until at least the year 2007.
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