ML20247P267
| ML20247P267 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/31/1989 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-89113, NUDOCS 8909270083 | |
| Download: ML20247P267 (7) | |
Text
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gNew Hampshire-1 Yankee j
NYN-89113 September. 15,'1989 United' States Nuclear Regulatory Commission
-Washington, DC 20555 Attention: Document Control Desk
References:
Facility Operating License NPF-67, Docket No. 50-443
Subject:
- Monthly Operating Report Gentlemen:
.In accordance with Technical Specification Sect!.on 6.8.1.5, enclosed please find Monthly Operating Report 89-08 covering the operation and shutdown experience relating to Seabrook Station Unit 1.
Very truly yours, fxs/6 Ted C. Feigenbaum Senior Vice President end Chief Operating Officer Enclosure cc:
'Mr. William T. Ruscell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Antone C. Cerne NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 8909270083 890831 PDR ADOCK 05000443 R
PDC g
ii New Hampshire Yonkee Division of Public Service Company of New Hampshee
/
P.O. Box 300 = Seabrook, NH 03874
- Telephone (603) 474-9521
L DOCKET NO.
50-443 UNIT Seabrook 1
)
DATE 09/05/89 I
CCMPLETED BY P. Nardone TELE 210NE (603) 474-9521 (Ext. 4074)
OPEATING STATUS
- 1.
Unit Name:
Seabrook Station thit 1 2.
Reporting Period:
AUGUST 1989
- 3. ' Licensed haal Power (MRt):
3411 4.
Nameplate Rating (Gross MWe):
1197 5.
Eesign Electrical Rating (Net MWe):
1148 6.
Max 12ran D pendable Capacity (Gross MWe):
1197 (Initial design value) 7.
Maxinom Dependable Capacity (N3t MWe):
1118 (Initial design value) 8.
If Changas Occur in Capacity Ratings (Items Number 3 9hrough 7)
Since Iast Report, Give Reasons:
'Not 7Dolicable 9.
Power level To Which Restricted, If Any: _170 MWt
- 10. Reasons For Restrictions, If Ar.y:
Licente issued on 05/26/89 in a low power license authorizing operation at reactor core power levels not in excess of 170 meaawatts thermal.
'311s Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 744.0 58.31.0 25200'0
- 12. Number Of Houra Reactor Was Critical 0.0 194.4 194.4
- 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 Hoars 0.0 0.0 0.0
~
- 16. Gross 'Ibernel Energy Generated (MWH) 0 1090 1090 _
- 17. Gross ele.c. Energy Generated (MWH)
-0 0
0
- 18. Net Electrical. Energy Generated (MWH) 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 MOC Net) 0.0 0.0 0.0
- 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 0.0
- 23. Unit Forced Outage lhte 0.0 0.0 0.0
- 24. Shutdowns Scheduled Ovar Next 6 Months (Type, Date, and Duration 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 Cummulal Operation): Forecast Achieved INITIAL CRITICALITY 1989 06/13/89 INITIAL ELEC'IRICITY 1989 Not Applicable OCMMERCIAL OPERATIO 1989 Not Applicable 1 of 6
.. :. ;y-l' AVEIUGE DMLY UNIT POWER LEVE DOCKETT NO.-
50-443-UNIT Seabrook 1 DATE 09/05/89 CXMPIRfED BY P. Nardane TELEPH21E (603) 474-9521
- (Ert. 4074)-
M0tml AIEIUST, 1989 DU ' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PONER LEVEL (MWe-Net)
(NWe-Net) 1 0
16 0'
2 0
17 0
3 0
18 0
4-0 19 0
5 0
20 0
6' 0
21 0
7 0
22 0
8 0
23 0
9 0
24 0
10 0
25 0
11 0
26 0
12 0
27 0
13 0
28 0
14 0
29 0
15 0
30 0
31 0
l 1Nsmcrras On this format, list the average daily unit power level in NWe-Net for each day in the reporting Irnth. Ocznpute to the nearest whole megawatt.
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DOCKET 10.
50-443 UNIT Seabrook 1 DATE 09/05/89 COFLLTED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)
REFUELIfC IfMIRMATION REQUEST
- 1. !broe of facility: Seabrook Unit 1
- 2. Scheduled date for next refueling shutdown: Not Scheduled 1
- 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 amondment?
Unknown at this time.
l
- 5. Scheduled date(s) for subnitting licensing action and supporting i
infonnation:
Not Applicable
- 6. Important licensing considerations associated with refueling, e.g.,
l new or different fuel design or supplier, unreviewed design or l
performance analysis methods, significant changes in fuel design, new operating procedures:
Ibne l
l
- 7. %e number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a) In Core:
193 (b) 0
- 8. W e present licensed spent fuel pool storage capacity and the size cf any increase in license:1 storage capacity that has been requested or is planned, in number of fuel asscanblies:
Present licensed capacity: 1236 No increase in storage capacity requested or planned.
- 9. h 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 assemblies based on sixteen refuelings and full core offload capability.
We current licensed capacity is adcquate until at least the year 2007.
G of 6
. _ _ _