ML20073E901
| ML20073E901 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/11/1983 |
| From: | Gibson J NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20073E899 | List: |
| References | |
| NUDOCS 8304150387 | |
| Download: ML20073E901 (5) | |
Text
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t OPERATING DATA REPORT DOCKET NO.
50-336 DATE 3/11/83 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:
February 1983 cumulative are weighted 3.
Licensed Thermal Power (MWt):
2700 ave. unit operated at 4.
Nameplate Rating (Gross MWe):
909 2560 MW thermal prior 5.
Design Electrical Rating (Net MWe):
870 to 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 672 1416 62928 12.
Number Of Hours Reactor Was Critical 655.1 1399.1 46633.9 13.
Reactor Reserve Shutdown Hours 0
0 2205.5 14.
Hours Generator On-Line 620.7 1304.6 44491.9 15.
Unit Reserve Shutdown Hours 0
0 468.2
- 16. Gross Thermal Energy Generated (MWH) 1634909 3436230 111870435 17.
Gross Elec. Energy Generated (MWH) 528750 1114430 36345278 18.
Net Electrical Energy Generated (MWH) 508019.3 1070770.3 34832583 19.
Unit Service Factor 92.4 92.1 70.7
- 20. Unit Availability Factor 92.4 92.1 71.4
- 21. Unit Capacity Factor (Using MDC Net) 87.5 87.5 66.5
- 22. Unit Capacity Factor (Using DER Net) 86.9 86.9 65.6 23.
Unit Forced Outage Rate 7.6 3.8 ^
19.1 l
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 INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A
- Corrects minor math error in January 1983 report.
8304150387 830315 PDR ADDCK 05000336 R
PM L
J
6 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-336 UNIT Millstone 2 DATE 3/11/83 i
COMPLETED 8Y J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 MONTH FEBRUARY 83 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 848 17 847 2
849 18 749 l
l 3
848 19 116 4
843 20 0 (-28) 5 835 21 203 l
6 848 22 678 7
847 23 843 l
8 848 24 845 9
850 25 845 10 849 26 845 l
11 849 27 845 12 848 28 844 13 848 29 14 847 30 15 847 31 16 847 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.
DOCKET NO.
50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 3/11/83 COMPLETED BY J. Gibson REPORT MONTH FEBRUARY TELEPHONE (203) 447-1701 Ext. 4431 l
2 Wo.
Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours)
Shutting Event Code Code Action to 3
Down Reactor Report #
Prevent Recurrence 1
830218 F
0 A
1 83-23 RB CONROD While performing CEA partial move-ment surveillance, CEA number 16 (regulating group 6) slipped to 150 steps.
Power was reduced inom 100% tn 68%
power per Tech.
Spec. action state-ment.
See LER 82-83.
2 830219 F
51.3 A
3 N/A ED INSTRU Tripped from 100%
power, electrical fault caused no. 1 control rod drive mechanism mg set to trip.
At that time, no. 2 mg set was off-line causing total loss of power to control rods.
1 2
3 4
F:
Forced Reason:
Method:
Exhibit G - Instructions S:
Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refuling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREG-0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exihibit 1 - Same Source H-Other (Explain)
Docket No.
50-336 Date 3/11/83 Unit Name Millstone 2 Completed By J. Gibson Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH FEBRUARY DATE SYSTEM COMPONENT MAINTENANCE ACTION 2/3/83 CVCS
'A' Charging Pump Tighten bodynut on pump releif valve &
repack crankcase plunger packing.
2/4/83 CVCS
'C' Charging Pump Weld repair leaking joint on flush line 2/9/83 CVCS
'C' Charging Pump Remove flush line nipple from casing-remove flange and replace with pipe cap 4
2/24/83 Reactor Protection Channel
'D' RPS Replace +15V and +5V power supply in System drawer DW1 2/28/83 Main Steam S/G Blowdown Piping Replace elbow between 2-MS-147C and 2-MS-148C 2/28/83 Main Steam 2-MS-117A Change flange gasket on valve 2/28/83 Reactor Protection Channel 'B' RPS TM/LP Replace defective bistable System Trip Limit i
2/28/83 CVCS
'B' Charging Pump Change out valve and plunger packing i
i
.=
Docket No.
50-336 Date:
3/11/83 Coneleted By: J. Gibson Telephone: (203) 447-1791 ht. 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: March 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 the spent fuel pool assuming the present licensed capacity:
1985, Spent Fuel Pool, full core of load capability is reached.
1987, Core Full, Spent Fuel Pool contains 648 bundles.