ML19354D891
| ML19354D891 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/31/1989 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-90014, NUDOCS 9001230173 | |
| Download: ML19354D891 (7) | |
Text
. y
, New Hampshire--
Tod C. F?"e President and
- :m Senior Vic Chief Operating Officer NYN 90014 January 12, 1990 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:
Enclosed please find Monthly Operating Report 89-12..This report.
addresses the operating and shutdown experience' relating to Seabrook Station
~
Unit'l for the month of December 1989 and is submitted in-accordance with the.
requirements of Seabrook Station' Technical Specification 6.8.1.5s.
--i Very truly yours,
/*
Ted C. Fei enbaum Enclosure cc Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road 1
King of-Prussia,.PA 19406 i
Mr. Antone C. Cerne NRC Senior-Resident Inspector P.O.-Box 1149' Seabrook,-NH 03874
- 1 9001230173 891231 PDR ADOCK 05000443 R
- l(
New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521.
New Hampshire Yankee January. 12, 1990 ENCLOSURE 1 TO NYN-90014; l-I 1
1 i
- i
I
}
OPERATING DATA REPORT DOCKET NO.
50-443-UNIT Seabrook 1 DATE 01/12/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9511 (Ext. 4074)
OPERATING STATUS 1.
Unit Name:
Seabrook Station Unit 1
- 2.. Reporting Period DECEMBER 1989 3.
Licensed Thermal Power (MWt):
3411 4.
Nameplate Rating (Gross MWe):
1197 5.
Design Electrical Rating (Net HWe):
1148-6 '. Maximum Dependable Capacity (Gross MWe):
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 Reasons:
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 oower license authoriaina operation at reactor core power levels not in excess of 170 menawatts thermal.
This Month Yr.-to-Date
' Cumulative l
1
- 11. Hours In Reporting Period 744.0 8760.0 28129.0
- 12. Number Of Hours 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 Hours 0.0 0.0-0.0
- 16. Gross Thermal Energy Generated (MWH)
-O' 1090 1090
- 17. Gross Elec. Energy Generated (MWH) 0 0
0-18.- Net Electrical Energy Generated (FMH) 0 0
0
- 19. Unit Service Factor-0.0 0.0 0.0
- 20. Unit Availability. Factor 0.0 0.0 0.0 j
- 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 ofLEach):
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. Prior to Commercial' Operation:
Forecast Achieved-j i
INITIAL CRITICALITY 1989 06/13/89 j
INITIAL ELECTRICITY 1990 Not-Aeolicable COMMERCIAL OPERATION 1990 Not Aeolicable i
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-443 UNIT Seabrook 1-DATE-01/12/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521-(Ext. 4074)
MONTH DECEMBER. 1989 DAY-AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER-LEVELI (MWe-Net)
(MWe-Net) 1 0
'16 0
1 2
0 17 0
3 0
18.
0 4
0 19 0-5 0
20 0
6 0
21 0
7 0
22 0
-l 8
0 23-0 9
0 24 0
1 10 0
25 0
11 0
26 0-12 0
27-
-0 13 0
28 0
l
.14 0
'29 O'
15 0
30 0
1 31 0
INSTRUCTIONS
-i 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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UNIT' SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-443 UNIT Seabrook l' DATE 01/12/90 REPORT MONTH DECl!MB2R. 1989 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521-(Ext. 4074)
-No. Date
- Type Duration Reason Method of'
' Licensee.
Cause & Corrective l
2 (Hours)
Shutting Event
' Action to 3'
Down Reactor Report #
Prevent Recurrence NO ENTRIES FOR THIS MONTH
?
1 2.
.3 F: Forced Reason:
Method:
G: 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-5-Power Reduction F-Administrative G-Operational Error.(Explain)
(Duration =.0)
H-Other (Explain) 9-Other.(Explain)
.3 of.-5
_-____.___.-,.-.-me--
..--e.+r-Es-A-
-O-+
- - = ' - - -
- - - * " - - - - - ~ - - -
" ' + - - - " - - - --
- ~ ' * '
~ s
.T.
DOCKET NO.
50-443 UNIT Seabrook 1 DATE 01/12/90 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 REPORT MONTH DECEMBER. 1989 (Ext. 4074)
Page 1 of 1 DATE SYSTEM COMPONENT MAINTENANCE ACTION 12/05/89 Service 1-SW-P-110B Surveillance data showed high pump vibra-Water Train B tion. Replaced worn stuffing box bearing.
~ Cooling Tower Pump 12/27/89
' Primary 1-CC-E-17A Heat exchanger leaking. Plugged tubes Component Train A identified during eddy current testing.
Cooling Water Primary Component
'Resleeved all remaining tubes.
Cooling Water Heat Exchanger 12/30/89 Containment 1-CAP-V-2 and 3 Valves would not open. Replaced defective Air Purge
. Train B quick exhauster on valves.
Inside Containment Isolation Valves 1
i t
- =
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' ~'
DOCKET NO.
50-443 UNIT _Seabrook 1 DATE 01/12/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)
REFUELING INFORMATION REQUEST
- 1. Name of facility:
Seabrook Unit 1
- 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 amendment?
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 3
performance analysis methods, significant changes in fuel design, new operating procedures:
None I
i l
- 7. The number of fuel assemblies (a) in the core and.(b) in the spent-fuel-storage pools (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 is planned, in number of fuel assemblies:
F Present licensed capacity: 1236 i
No increase in storage capacity requested or planned.
- 9. The projected date of the last refueling that can be discharged to the spent tuel pool assuming the present licensed capacity:.
Licenced capacity of 1236 fuel assemblies based on sixteen refuelings and full core offload capability.
The current licensed capacity is adequate until at least the j
year 2007.
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