ML20033F554
| ML20033F554 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/28/1990 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-90074, NUDOCS 9003220027 | |
| Download: ML20033F554 (6) | |
Text
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- 5 J
'New H.ampshire
' Ted C. Feigenboum Senior Vice President and -
Chief Operating Officer t
NYN-90074 March 15, 1990 1
United States Nuclear Regulatory Commission L
Washington, DC-20$55
' Attention:
Document Control Desk
References:
. Facility Operating License NPF-67. Docket No. 50-443
Subject:
Monthly Operating Report Gentlemen:
Enclosed please' find Monthly Operating Report 90-02.
This report addresses the. operating and shutdown experience relating to Seabrook Station r
Unit 1 for the month of February 1990 and is submitted in accordance with-i the requirements of Seabrook Station Technical Specification 6.8.1.5.
Very_truly yours,
{dwh Ted C. Feigenbaum Enclosure cc Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr.' Noel Dudley NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 9003220027 900229
{DR ADOCK 05000443 PDC
\\
New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrocsk, NH 03874
- Telephone (603) 474 9521
-1.
OPERATING DATA REPORT 4
DOCKET NO.
50-443 UNIT Seabrook 1 DATE 03/15/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 i
(Ext. 4074) i t
' OPERATING STATUS
- 1.. Unit Name:
Seabrook Station Unit 1 2.-
Reporting Period:
FEBRUARY 1990 3.
Licensed Thermal Power (HWt):
'3411 4.
Nameplate Rating (Gross MWe):
1197 5.
Design Electrical Rating (Net MWe):
1148 6.
Maximum Dependable Capacity (Gross HWe):
1197 (Initial design value) 7.
Maximum Dependable Capacity (Net MWe):
1148 (Initial design value) 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Raasons:
Not Aeolicable 9.
. Power Level To Which Restricted, If Any:
170 MWt
-10. Reasons For Restrictions, If Any:
License issued on 05/26/89 is a low power license authorizinn operation at reactor core power levels not in excess of 170 megawatts thermal.
This Month Yr..to-Date Cumulative
'11. Hours In Reporting Period 672.0 1416.0 29545.0 12.-Number'0f Hours Reactor Was Critical 0.0 0.0 194.4
- 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. Groso Thermal Energy Generated (HWH) 0 0
1090
- 17. Gross Elec. Energy Generated (HWH) 0 0
0
- 18. Net Electrical Energy Generated (HWH) 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 Duration of Each):
Reactor shutdown as of 06/22/89 for indefinite duration.
l
- 25. If Shut Down At End Of Report Period, Estimated Date Of Startup:
Indefinite j
- 26. Prior to Commercial Operation:
Forecast Achieved i
INITIAL CRITICALITY 1989 06/13/89 L
INITIAL ELECTRICITY 1990 Not Applicable L
COHHERCIAL OPERATION 1990 Not Aeolicable 1
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AVERAGE DAILY UNIT POWER LEVEL
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6:
DOCKET NO.
50-443 UNIT Seabrook 1 j
DATE 03/15/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074) i MONTH FEBRUARY. 1990 l
i DAY AVERAGE DAILY POWER LEVEL-DAY AVERAGE DAILY POWER LEVEL 1
(MWe-Net)
(MWe-Net) 1 1
0 16 0
.\\
l.
2-0 17 0
3 0
18 0
4 0
19 0
5 0
20 0
6-0 21 0
i
.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
15.
O 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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IJNIT SHlHDOWS Af0 POWER REDUCTIGES DOQQtt NO.~
50-443
-- ~!
INIT Sentrook 1
~
DPGE 03/15/90 REKRP MJNDI FEBRUARY, 1990 O[MPIMED BY P. Nartkme TE MPM]NE (603) 474-9521
._ Ext. 4074)~-
(
l 2
Method of Licensee Cause & Cuuec.i.ive No. Date Type Duratim h
(Hours)
Shutting Event Action to Down Reactor 3 Report #
Frevad. Recurrence 10 ENIRIES KR 'DIIS MNDI l
1 2
3 F: Forced Reason:
Method:
S: Scheduled A-Equipnent Failure (Explain) 1-Manual B-Maintenanm or Test 2-Manual Scram C-Refueling 3-Automatic Scrima D-Regulatory Restriction 4-Continued fran E-Operator Training & Li nse Examination previous nonth F-Administrative 5-Power Redtu: tim G-Operational Error (Explain)
'(Duratim = 0)
H-Other (Explain) 9-Other (Explain) f i
3 of-5
DOGWT MO3 50-443 L.
INIT M-uA1 DME 03/15/90 l
i QNIECTIVE MINIDRNCE
SUMMARY
KR SAETTY REumD BQUIPMENT COMPIEIED BY P. Nardone I
REPG E 20NIH EH EUARY, 1990
'IEEEPEDE (603) 474-9521 (Ext. 4074)
Page 1 of 1 l
IRTE SYSTEM (DfEGENE
)RIN1HENCE ACTIGE 02/03/90 Reactor 1-RC-P-1A Time delay relay fcr ptmp wavultage Coolant Reactor Coolant p.vbsctica ci=n==l operatrs erratically.
Ptap W W relay.
02/05/90 Various Limitorque Replaced thirteen IE liidtorque actuator Actuators notar pinion keys with new keys per IRC Information Notice 88-84.
02/15/90 Resichel Gold Iag Check valve leakage 0 c.uu.M during Heat Injection 5% testing. Rewacked each valve's disc Removal Check Valve and seat.
Icops 1,2,3,4 i
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,..s DOCKET 10.
50-443 t-I INIT h hrook 1 DATE 03/15/90 CCMPLETED BY P. Nardone i'
L TELEPHONE (603) 474-9521 (Ext. 4074) p
- 1. Name of facility: h hrook Unit 1
- 2. Scheduled date for next refueling shutdown: -Not Schedcled
- 3. Scheduled date for restart following refuelino:- Not Scheduled
- 4. Will refueling or resunption of open. tion thereafter require a technical specification change or other license amendment?
Unknown at this time..
- 5. Scheduled date(s) for sulmitting licensing acticn and supporting information:
L Not Applicable 1:
- 6. Inportant licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design,
.new operating s d ures:
None i
- 7. The number of fuel ass a blies (a) in the core and (b) in the spent L
fuel storage pool:
(a) In Core:
193 (b) 0
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or l
is planned, in number of fuel assemblies:
l Present licensed capacity:. 1236 l
No increase in storage capacity requested or planned.
1
- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
j Licensed capacity of 1236 fuel assa blies based on sixteen refuelings and full core offload capability.
The current licensed capacity is adequate until at least the year 2010.
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