ML20071F085
| ML20071F085 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/11/1983 |
| From: | Gibson J NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20071F078 | List: |
| References | |
| NUDOCS 8303150433 | |
| Download: ML20071F085 (5) | |
Text
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OPERATING DATA REPORT DOCKET NO. 50-336 DATE 2/11/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 OPERATING STATUS 1.
Unit Name:
Millstone 2 Notes Items 21 and 22 2.
Reporting Period: January 1983 cumulative are weighted 3.
Licensed Thermal Power (MWt):
2700 ave. unit operated at 4.
Nameplate Rating (Gross MWe):
909 2560 MW thermal prior to 5.
Design Electrical Rating (Net MWe):
870 its uprating to its 6.
Maximum Dependable Capacity (Gross MWe):
895 current 2700 MW thermal 7.
Maximum Dependable Capacity (Net MWe): 864 power level.
8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
N/A 9.
Power Level To Which Restricted, If Any (Net MWe):
N/A 10.
Reasons For Restrictions, If Any:
N/A This Month Yr.-to-Date Cumulative 11.
Hours In Reporting Period 744 744 62256 12.
Number Of Hours Reactor Was Critical 744 744 45978.8 13.
Reactor Reserve Shutdown Hours 0
0 2205.5 14.
Hours Generator On-Line 683.9 683.9 43871.2 15.
Unit Reserve Shutdown Hours 0
-0 468.2 16.
Gross Thermal Energy Generated (MWH) 1801321 1801321 110235526 17.
Gross Elec. Energy Generated (MWH) 585680 585680 35816528 18.
Net Electrical Energy Generated (MWH) 562751 562751 34324564 19.
Unit Service Factor 91.9 91.9 70.5 20.
Unit Availability Factor 91.9 91.9 71.2 21.
Unit Capacity Factor (Using MDC Net) 87.5 87.5 66.2 l
22.
Unit Capacity Factor (Using DER Net) 86.9 86.9 65.3 23.
Unit Forced Outage Rate 8.1 8.1 19.3 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling Outage, MAY 28, 1983, 16 weeks.
25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
N/A 26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A B303150433 830215 PDR ADOCK 05000336 R
=
i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 2/11/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 MONTH JANUARY 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0 (-27) 17 846 2
0 (-29) 18 837 3
97 19 849 4
595 20 850 5
820 21 832 6
846 22 811 7
848 23 846 8
849 24 850 9
848 25 850 10 848 26 850 11 847 27 850 12 848 28 849 13 849 29 849 14 849 30 849 15 848 31 848 16 848 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day l
in the reporting month.
Compute to the nearest whole megawatt.
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Docket No. 50-336 Date 2/11/83 Unit Name Millstone 2 Completed By J. Gibson Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH January 83' DATE SYSTEM COMPONENT MAINTENANCE ACTION 1/24/83 CVCS 2-CH-512 Replace defective contact block on control switch HS-2512 in control circuit of 2-CH-512.
1/24/83 CVCS
'A' Charging Pump Remove pump relief valve and tighten valve
)
body - reinstall 1/28/83 CVCS
'C' Charging Pump Uncouple pump from gear box.
And replace bad bearing.
1/31/83 CVCS
'A' Charging Pump Repack crankcase plunger.
1/24/83 Safety Injection Safety Injection Piping Remove snubber and replace with new snubber.
1/24/83 Main Steam S/G Blowdown Quench Tk Weld repair 2-MS-148 & 2-MS-219 pipe 1/26/83 Reactor Protection RPS Channel 'C' Replace Hi power Bi-stable and re-calibrate.
System
Docket No. 50-336 Date: 2/11/83 Completed By: J. Gibson Telephone: (203) 447-1791 Ext. 4431 REFUELING INFORMATION REQUEST 1.
Name of facility: Millstone 2 2.
Scheduled date for next refueling shutdown:
May 28, 1983 3.
Schedule date for restart following refueling: September 17, 1983 (16 wks outage) 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
It is anticipated that Cycle 6 operations will require Technical Specification changes or other License amendments.
5.
Scheduled date(s) for submitting licensing action and supporting information:
Safety Analyses:
February 15, 1983 Steam Generator Licensing Action:
April 15, 1983 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 procedures: Additional plugged steam generator tubes will result in potential reactor coolant flow reduction.
Currently planning to install sleeves in steam generator tubes.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
217 (b) 288 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:
667 9.
The projected date of the last refueling that can be discharged to j
the spent fuel pool assuming the present licensed capacity:
l l
1985, Spent Fuel Pool, full core off load capability is reached.
1987, Core Full, Spent Fuel Pool contains 648 bundles.
l l
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