ML20210Q706
| ML20210Q706 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1986 |
| From: | Neron G, Romberg W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-8815, NUDOCS 8605140224 | |
| Download: ML20210Q706 (8) | |
Text
i AVERAGE DAILY UNIT POWER LEVEL
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DOCKET NO. 50-336 UNIT Millstone 2 DATE 3/11/86 COMPLETED BY G.'Neron TELEPHONE (203) 447-1791 Extension 4417 MONTH February 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 847 17 845 2
847 18 844 3
845 19 844 4
846 20 844 5
845 21 844 6
845 22 845 7
845 23 845 8
845 24 844 9
844 25 844 10 844 26 844 11 845 27 844 12 845 28 844 13 844 29 14 845 30 15 845 31 16 845 INSTRUCTIONS On this format, list the average daily unit power' level in MWe-Net for each day i
in the reporting month.
Compute to the nearest whole megawatt.
. M. 6 q\\
M 8605140224 86
OPERATING DATA REPORT DOCKET NO. 50-336 DATE 3/11/86 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Extension 4417 OPERATING STATUS 1.
Unit Name: Millstone Unit 2 Notes Items 21 and 22 cumulative 2.
Reporting Period:
February 1986 are weighted averages.
Unit 3.
Licensed Thermal Power (MWt):
2700 operated at 2560 MW Thermal 4.
Nameplate Rating (Gross MWe):
909 prior to its up rating to 5.
Design Electrical Rating (Net MWe):
870 the current 2700 MW Thermal 6.
Maximum Dependable Capacity (Gross MWe):
888.75 power level.
7.
Maximum Dependable Capacity (Net MWe):
857.25 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 89232
- 12. Number Of Hours Reactor Was Critical 672 1416 63953.7 13.
Reactor Reserve Shutdown Hours 0
0 2205.5 14.
Hours Generator On-Line 672 1416 60133.7 15.
Unit Reserve Shutdown Hours 0
0 468.2 16.
Gross Thermal Energy Generated (MWH) 1813645 3797744 151901546 17.
Gross Elec. Energy Generated (MWH) 587600 1231200 49572679 18.
Net Electrical Energy Generated (MWH) 566888 1187490 47508709 19.
Unit Service Factor 100 100 67.4 20.
Unit Availability Factor 100 100 67.9 21.
Unit Capacity Factor (Using MDC Net) 98.4 57.8 63.2 -
22.
Unit Capacity Factor (Using DER Net) 97.0 96.4 62.2 23.
Unit Forced Outage Rate 0
0 17.0 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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):
Forecast Achieved N/A INITIAL CRITICALITY N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A e
DOCKET NO. 50-336 UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 3/11/86 COMPLETED BY G. Neron REPORT MONTH February 1986 TELEPHONE (203) 447-1791 Extension 4417 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 4
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)
Exhibit 1 - Sama Source
.H-Other (Explain) 9-Other (Explain) 9
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Docket No. 50-336 Date 3/11/86 Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791 Extension 4417 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT l
REPORT MONTH February 1986 DATE SYSTEM COMPONENT MAINTENANCE ACTION f
2/8/86 Boric Acid Boric Acid Emergency Supply Machined seat and disc, renewed gasket.
Header Relief Valve (2-CH-157) l 2/12/86 Boric Acid Boric Acid Pump Discharge Installed new stem and disc, machined Relief Valve (2-CH-160) seat and lapped.
l 2/10/86 HPSI "C" HPSI Pump Washed away boric acid and tightened pipe caps on casing vent.
2/10/86 Shutdown Cooling S.C Line from Loop "2B" Realigned hanger and tightened nuts.
Pipe (14-GCB-1) l l
2/12/86 M5in Steam Hanger #4130828 and Snubber Adjusted snubber.
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- 11576 2/12/86 Main Steam Hanger #413080 Torqued Bolts.
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- 413082 l
- 413085
- 413076
- SAFR-2 l
2/12/86 Main Steam Hanger #SAFR-8 Adjusted clevis rod to reseat j
base plate on concrete wall.
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Docket No. 50-336 Date 3/11/86 Unit Name Millstone 2 Completed By G. Neren Telephone (203) 447-1791 Extension 4417 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REf0RT MONTH February 1986 DATE SYSTEM COMPONENT MAINTENANCE ACTION 2/12/86 Main Steam Hanger #413061 Welded new shoe on hanger and set spring set tension on spring can at hot setting.
2/4/86
' Reactor Coolant ICC System Panel Spliced lead and raychemed.
and Vessel Train "A" i
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2/20/86 Reactor Coolant ICC System Panel -
Replaced D0-1 relay with spare in j
- and Vessel Train "A" D0-3.
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2/3/86 Diesel Generator.
Diesel B Jacket Cooling Replaced TS-8776 Water Temperature 2/5/86.
Process and Area, CTMT Air Gaseous Radiation Replaced photo tube, crystal, mylar l
Rad. Monitoring Monitor Loop (RM-82628) window and 0-ring; applied crystal j
sealing compound.
2/14/86 React.or Protection Wide Range Drawer "A" Adjusted high voltage bistable.
System 2/1/86 Reactor Protection Wide Range Drawer "D" Replaced high voltage potentiometer System by soldering in new Bourns potentiometer and installed new terminal lugs.
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Docket No. 50-336 Date 3/11/86 Unit Name Millstone 2- _
Completed By G. Neron Telephone (203) 447-1791 1
Extension 4412 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT
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REPORT MONTH February 1986 l
j DATE SYSTEM COMPONENT MAINTENANCE ACTION
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'2/14/86 Annunciator Logic Annunciator Power Supply Replaced blown fuse and capacitor C3; j
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Panel Cabinet (RC22A) replaced CRIS and 16 also; installed i
and adjusted power supply.
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l Docket No. 50-336 Date: 3/11/86 Completed By: G. Neron Telephone: (203) 447-1791 Extension 4417 REFUELING INFORMATION REQUEST 1.
Name of facility:
Millstone 2 2.
Scheduled date for next refueling shutdown:
September 1986 3.
Schedule date for restart following refueling: December 1986 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
i Unknown at this time.
5.
Scheduled Cate(s) for submitting licensing action and supporting information:
The license amendment request for the spent fuel pool re-rack was l
approved on January 15, 1986 1
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:
None 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
217 (b) 449 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:
4
..,g..
Currently 667 Reracking of-the Spent Fuel Pool to incre'ase the storage capacity to 1106 fuel assemblies is in progress.
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The projected date of the last refueling that can be discharged to
'o the~ spent fuel pool assuming the present licensed capacity:
- 1986, Spent Fuel Pool, Full Core off load capacity is reached.
1987, Core Full, Spent Fuel Pool contains 648 bgndles.
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March 13, 1986 MP-8815 Director, Office of Resource Management 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 86-02 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 b d A $~
,. D. Rom rg W
Station Superintendent Millstone Nuclear Power Station WDR/GN:ck Director, Office of I'nspection and Enforcement, Region I cc:
Director, Office of Inspection and Enforcement, Washington, D. C. (10)
U. S. Nuclear Regulatory Commission, c/o Document Management Branch, Washington, D.C. 20555 9