ML20077H784
| ML20077H784 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/12/1983 |
| From: | Gibson J, Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-5222, NUDOCS 8308110303 | |
| Download: ML20077H784 (7) | |
Text
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ga OPERATING DATA REPORT DOCKET NO.
50-336 DATE 7/12/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 OPERATING STATUS 1.
Unit Name:
Millstone 2 Notes:
Items 21 and 22 cumulative 2.
Reporting Period: June 1983 are weighted ave. unit 3.
Licensed Thermal Power (MWt):
2700 operated at 2560 MW 4.
Nameplate Rating (Gross MWe):
909 thermal prior to its 5.
Design Electrical Rating (Net MWe):
870 uprating to its current 6.
Maximum Dependable Capacity (Gross MWe):
891 2700 MW thermal power 7.
Maximum Dependable Capacity (Net MWe): 860.25 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 720 4343 65855 12.
Number Of Hours Reactor Was Critical 0
3130.5 48365.3 13.
Reactor Reserve Shutdown Hours 0
0 2205.5 14.
Hours Generator On-Line 0
2994.9 46182.2 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) (-2910.1) 2471459.2 36233271.9 19.
Unit Service Factor 0
69.0 70.1 20.
Unit Availability Factor 0
69.0 70.8 21.
Unit Capacity Factor (Using MDC Net) 0 70.1 66.2 22.
Unit Capacity Factor (Using DER Net) 0 65.4 65.3 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 l
25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
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
- Item 21 yr-to-date is weighted ave due to change in MDC effective May 1, 1983.
p lN 8308110303 830712 R
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PDR ADOCK 05000336
-6
- i,
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-336 UNIT Millstone 2 DATE 7/12/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 MONTH June 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL er (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
11 0
27 0
12 0
28 0
- 13 0
29 0
14 0
30 0
-15 0
31 16 0
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 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 7/12/83 COMPLETED BY J. Gibson REPORT MONTH JUNE 83 TELEPHONE (203) 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
720 C
1 N/A N/A N/A Continuation of Refuel and Maint-enance Outage-from previous Month.
1 2
3 4
F:
Forced Reason:
Method:
Exhibit G - Instructions 5:
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)
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Docket No.
50-336 Date 7/12/83 Unit Name Millstone 2 Completed By J. Gibson Telephone (203) 447-1792 Ext. 4431 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH JUNE 83 DATE SYSTEM COMFONENT MAINTENANCE ACTION 6/5/83 DIESEL GENERATOR "B" D/G INSTALL AIR DRYER 6/11/83 DIESEL GENERATOR "B" D/G PRE-LUBE MOTOR HANDSWITCH 6/14/83 CVCS 2-CH-210X REPAIR AIR LEAK ON OPERATOR AND CHANGE PACKING 6/17/83 SAFETY INJECTION 2-SI-638 DISASSEMBLE AND REPAIR 2-SI-648 VALVE SEATS 6/21/83 MAIN STEAM 2-MS-284 DISASSEMBLE VALVE, REPLACE STEM AND VALVE PLUG - REPACK VALVE 6/27/83 REACTOR PROTECTION CONTROL ELEMENT REPLACED POWER SUPPLY SYSTEM DRIVE POWER SUPPLY i
(<
s e Docket No.
50-336 Date:
7/12/83 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:
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) 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.
Some supporting documentation has already been submitted as follows:
Safety Analyses:
April 13, 1983 Steam Generator Licensing Action:
June 3, 1983 5.
Scheduled date(s) for submitting licensing action and supporting information:
Not Available 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 may 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) 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
0-(b) 505 5.
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8.
The present licensed spent fuel pool storage capacity and the size of.any increase in licensed storage capacity that has been requested I
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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L A lL';;::'?.':l;2";:lll"':l July 14, 1983 MP-5222 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 83-6 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
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E. J. Mroczka Station Superintendent Millstone Nuclear Power Station EJM/JG: pit cc:
Director, Office of Inspection and Enforcement, Region I i
Director, Office of Inspection and Enforcement, Washington, D. C. (10)
U. S. Nuclear Regulatory Commission, c/o Document Management Branch, Washington, D.C. 20555 Z G 3.sf l//
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