ML20078K706
| ML20078K706 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/14/1983 |
| From: | Gibson J, Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-5382, NUDOCS 8310190207 | |
| Download: ML20078K706 (7) | |
Text
.
OPERATING DATA REPORT DOCKET NO.
50-336 DATE 9/14/83 COMPLETED BY J. Cibson TELEPHONE (203) 447-1791 Ext. 4431 OPERATING STATUS 1.
Unit Name:
Millstone 2 Notes: Items 21 and 22 2.
Reporting Period:
August 1983 cumulative are weighted l
3.
Licensed Thermal Power (MWt):
2700 ave. unit operated at 4.
Nameplate Rating (Gross MWe):
909 2560 mw thermal prior to L
5.
Design Electrical Rating (Net MWe):
870 its uprating to the current 6.
Maximum Dependable Capacity (Gross MWe):
895 2700 mw thermal power level.
7.
Maximum Dependable Capacity (Net MWe):
864 l
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 L
11.
Hours In Reporting Period 744 5831 67343
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12.
Number Of Hours Reactor Was Critical 0
3130.5 48365.3 l
13.
Reactor Reserve Shutdown Hours 0
0 2205.5
~
14.
Hours Generator On-Line 0
2994.9 46182.2 l
15.
Unit Reserve Shutdown Hours 0
0 468.2 16.
Gross Thermal Energy Generated (MWH) 0 7877464 13171669
- 17. ' Gross Elec. Energy Generated (MWH) 0 2575530 37806378 18.
Net Electrical Energy Generated (MWH)_(-3007) 2465436.4 36227249 19.
Unit Service Factor 0
51.4 68.6 20.
Unit Availability Factor 0
51.4 69.3 21.
Unit Capacity Factor (Using MDC Net) 0 48.9 64.2 22.
Unit Capacity Factor (Using DER Net) 0 48.6 63.3 23.
Unit Forced Outage Rate 0
13.7 19.1 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Continuation of Refuel / Maintenance Outage 25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
l 26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY N/A_
N/A INITIAL ELECTRICITY N/A N/A CCMMERCIAL OPERATION N/A N/A g
8310190207 830914 PDR ADOCK 05000336 R
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i
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-336 UNIT Millstone 2 DATE 9/14/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431
' MONTH August 1983 DAY AVERAGE DAILY POWER LEVEL DAY
. AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1-0 17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0'
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
l 0
l 11 0
27 12 0
28 0
I 13 0
29 0
14 0
30 0
15 0
31 0
16 0
' 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.
l L
DOCKET NO.
50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 9/14/83 COMPLETED BY J. Gibson REPORT MONTH August TELEPHONE J203) 447-1791 Ext. 4431 l
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 5
830528 S
744 C
1 N/A N/A N/A Continuation of Refuel and Maintenance Outage from previous month 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 9/14/83 Unit Name Millstone 2 Completed By J. Gioson Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH August 4
DATE SYSTEM COMPONENT MAINTENANCE ACTION 8/4/83 Safety Injection 2-SI-726 Replaced valve plug 8/4/83 Safety Injection SI Recirc. Header Install isolation valve and pressure tap 8/4/83 Reactor Coolant System Press. Trans. PT 103 and Replaced pressurizer press.
i PT 103-1 transmitters 8/11/83 Reactor Coolant System RCP Seal Rebuilt 'D' Rx Coolant Pump Seal 8/16/83 Main Steam Steam Flow & Feed Flow Replace with new Transmitters 8/17/83 Loose Parts Monitoring Loose Parts Monitor Installed new accelerometers and cabling 8/22/83 Main Steam 2-MS-201 Rebuild valve operator 8/22/83 Reactor Protection RPS Cabinet Modify all channel Bi-stables System 8/24/83 Safety Injection 2-SI-460 Grind off burr in valve guide 8/25/83 Nuclear Instrumentation 4-Wide Range Channels Replace 4 wide range neutron detectors
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Docket No.
50-336 Date:
9/14/83 Completed By:
.1. Gibson Telephone: (203) 447-1791 Ext. 4431 REFUELING INFORMATION REQUEST 1.
Name of facility:
Millstone 2 2.
Scheduled date for next refueling shutdown:
Currently in Refuel / Maintenance Outage which commenced May 28, 1983.
3.
Schedule date for restart following refueling:
Estimated date for restart is unavailable.
NNECo is currently developing a schedule consistent with the repair of the reactor vessel thermal shield.
(See LER 83-24) i 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.
Supporting information has already been submitted.
5.
Scheduled date(s) for submitting licensing action and supporting information:
A schedule has not been determined for further submittals.
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 S.G. tubes will result in reactor coolant flow reduction.
Currently planning to install sleeves in S.G. tubes.
Reactor Vessel thermal shield removal will be necessary prior to startup. As previously identified to the NRC, NNECo has identified failed fuel at Millstone Unit 2.
The need to replace defective fuel assemblies will impact the core loading pattern and core physics parameters used as input to the safety analyses.
The effect of a new loading pattern on the ongoing review of docketed material is not fully apparent at this time; however additional transient analysis may be required if significant loading pattern changes are needed.
(See LER 83-19/3L-1).
In addition, recent problems identified with the top nozzles of a number of fuel assemblies (See LERS 83-25 & 83-26) have left uncertainty as to the core loading plan.
These problems are currently under review.
J
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
0 (b) 505 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 off load capability is reached.
1987, Core Full, Spent Fuel Pool contains 648 bundles.
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P.O. BOX 270 3NSI((O[* 1 sYr$<I[em HARTFORD, CONNECTICUT 06101
.<w.r.4 rw e= crerw (203) 666-6911 L
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September 15, 1983 MP-5382 Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Reference:
facility Operating License No. DPR-65 Docket No. 50-336
Dear Sir:
This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 Monthly Operating Report 83-8 in accordance with Appendix A Technical Specifications, Section 6.9.1.3.
One additional copy of the report is enclosed.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
' ((h
'M E.
. Mroczka Station Superintendent Millstone Nuclear Power Station EJM/JG:jlc cc:
Director, Office of Inspection and Enforcement, Region I Director, Office of Inspection anJ Enforcement, Washington, D. C. (10)
U. S. Nuclear Regulatory Commission, c/o Document Management Branch, Washington, D.C. 20555 If'