ML20112B268
| ML20112B268 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/31/1985 |
| From: | Gibson J NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20112B246 | List: |
| References | |
| NUDOCS 8503190101 | |
| Download: ML20112B268 (6) | |
Text
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OPERATING DATA REPORT s
DOCKET NO. 50-336 DATE 2/14/85 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 OPERATING STATUS 1.
Unit Name: Millstone Unit 2 Notes Items 21 and 22 cumulative 2.
Reporting Period: January 1985 are weighted ave. unit 3.
Licensed Thermal Power (Wt): 2700 operated at 2560 W thermal j
4.
Nameplate Rating (Gross MWe): 909 prior to its uprating to the j
5.
Design Electrical Rating (Net W e): 870 current 2700 MW thermal 6.
Maximum Dependable Capacity (Gross We):
866.25 power level.
7.
Maximum Dependable Capacity (Net MWe):
833.25 l
8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
N/A l
9.
Power Level To Which Restricted, If Any (Net We):
N/A 10.
Reasons For Restrictions, If Any:
N/A a
This Month Yr. -to-Date cumulative
- 11. Hours In Reporting Period 744 744 79800
- 12. Number Of Hours Reactor Was Critical 744 744 57706.1 13.
Reactor Reserve Shutdown Hours 0
0 2205.5
- 14. Hours GeneratorL0n-Line 744 744 55137
- 15. Unit Reserve Shutdown Hours 0
0 468.2
- 16. Gross Thermal Energy Generated (MWH) 1994395 1994395 13 % 78852 f
- 17. Gross Elec. Energy Generated (MWH) 652900 652900 45334579 18.
Net Electrical Energy Generated (MWH)-
629972 629972 43453495 19.
Unit Service Factor 100-100 69.1 20.
Unit Availability Factor 100 100 69.7
- 21. Unit Capacity Factor (Using M)C Net) 101.6 101.6 65.1 22.
Unit Capacity Factor (Using DER Net) 97.3 97.3 64.1 23, Unit Forced Outage Rate 0-0 16.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
j-N/A 25.
If Shut Down At End Of Report Period, Estimated Date of Startup: N/A
- 26. Units In Test Status (Prior to Commercial Operation):
Torecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A H7K COWERCIAL OPERATION N/A N/A 36 a
...., ~ -. -. -. - - - -..
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 2/14/85 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 MONTH January DAY AVERAGE DAILY POWER LEVEL.
DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 855 17 853 2
854-18 853 3
855 19 829 4
855 20 852 5
855 21 852 6
855 22 852 7
854 23 850 8
854 24 847 9
853 25 842 10 854 26 839 11 854 27 833 12 850 28 827 13 854 29 822 14 854 30 818 15 855 31 813 16-852 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.
P c
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---m.
DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 2/14/85 COMPLETED BY J. Gibson REPORT MONTH January TELEPHONE (203) 447-1791 Ext. 4431 l
2 No.
Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours)
Shutting Event Code Code Action to 3
Down Reactor Report #
Prevent Recurrence N/A t
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-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)
E-Operator Training & License Examination previous month
'F-Administrative 5-Power Reduction 5 G-Operational Error (Explain)
(Duration = 0)
Exihibit 1 - Same Source H-Other (Explain) 9-Other (Explain)
Docket No. 50-336 Date 2/14/85 Unit Name Millstone 2 Completed By J. Gibson
. Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE S'Jle4ARY FOR SAFETY RELATED EQUIPMENT REPORT MONTH January 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION 1/2/85 Fire Protection And 2-FIRE-628 Replaced valve assembly.
Deluge Systesa 1/10/85 CVCS Charging Pump 'C' Repacked pump.
1/24/85 Reactor Protection RPS Channel 'C' Replace power supply.
System 1/25/85 Reactor Protection RPS Channel 'B' Replace channel 'B' rod System drop card.
4
Docket No. 50-336 Date: 2/14/85 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:
Next refueling is scheduled to begin on February 16, 1985.
3.
Schedule date for restart following refueling: June 1985 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
The discharge of failed fuel'may require additional technical specification changes and a new reload safety evaluation for the revised core loading pattern and is expected by May 15, 1985.
5.
Scheduled date(s) for submitting licensing action and supporting information:
a.
A technical specification change request has been submitted for the outage equipment hatch.
b.
A technical specification change request for the total planar peaking factor was submitted on February 4, 1985.
Along with a preliminary reload analysis.
1 c.
A proposed license amendment for reracking the spent fuel-pool will be submitted in March 1985.
d.
A Technical Specification Change Request for excluding up to 10 steam generator tubes from 100% eddy current testing requirements (and of cycle 6) was submitted on February 8, 1985.
J l
e.
The NRC will be advised of plans to inspect the core barrel.
Results from the core barrel inspection will be submitted prior to re-start.
l f.
A Technical Specification Change Request will be submitted concerning NU-REG-0737 Item III.d.3.4 - Control Room Habitability Modifications.
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, i
new operating procedures:
The discharge of failed fuel may require additional technical
. specification changes and will impact the reload safety evaluation.
i
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core: 217 (b) 376 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:
Currently 667 Plans are being formulated to rerack the spent fuel pool beginning in July 1985, to increase the storage capacity to 1106 fuel assemblies.
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 off load capacity is reached.
1987, Core fall, Spent Fuel Pool contains 648 bundles.
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