ML20084M280
| ML20084M280 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/13/1983 |
| From: | Gibson J, Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-4958, NUDOCS 8306020077 | |
| Download: ML20084M280 (7) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 4/13/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 MONTH MARCH 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 687 17 0 (-26) 2 0 (-22) 18 0 (-28) 3 0 (-6) 19 38 4
0 (-5) 20 501 5
0 (-5) 21 839 6
0 (-5) 22 859 7
0 (-5) 23 859 8
0 (-5) 24 857 9
0 (-5) 25 858 10 0 (-5) 26 847 11 0 (-5) 27 823 12 0 (-5) 28 858 13 0 (-5) 29 858 14 0 (-5) 30 858 15 0 (-5) 31 858 16 0 (-12)
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.
8306020077 830413 PDR ADOCK 05000336 R
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I DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 4/11/93 COMPLETED BY J. Gibson REPORT MONTH March 1983 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 J
3 830301 F
424.8 A
1 83-5 CJ VALVEX Shutdown from 100%
power due to RCS leakage in excess of 1.0 GPM. While in cold shutdown, leaks from 2 valves were fixed and 2 steam i
generator tubes were plugged. The sanit returned to service on 3/19/83.
See LER 83-5.
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-Refuling 3-Automatic Scram Event Report (LER) File i
D-Regulatory Restriction 4-Other (Explain) (NUREG-0161) i E-Operator Training & License Examination-F-Administrative 5
G-Operational Error (Explain)
Exihibit 1 - Same Source 1
H-Other (Explain) l l
I Docket No. 50-336 Date 4/13/83 Unit Name Millstone 2 Completed By J. Gibson Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH March DATE SYSTEM COMPONENT MAINTENANCE ACTION 3/9/83 Reactor Coolant 2-RC-405 Install new seal ring.
System i
3/8/83 Reactor Coolant 2-RC-001, 2-RC-002, Repacked vlvs and relube solenoids on System 2-RC-003 valves.
3/13/83 Reactor Coolant
'A' RCP Change out seal.
System 3/15/83 Reactor Coolant
'D' RCP Change out seal.
System i
3/13/83 Reactor Coolant
- 1 S/G Plugged tubes (2)
System 3/2/83 CVCS
'B' Charging Pump Filled oil reservoir to proper level.
3/31/83 CVCS 2-CH-326 Install new valve body.
3/7/83 Fire Protection.
RCP Heat Detectors Replaced Detector.
and Deluge o
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i Docket No. 50-336 i
Date 4/13/83 Unit Name Millstone 2 Completed By J. Gibson Telephone _(203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH March (Cont'd)
DATE SYSTEM COMPONENT MAINTENANCE ACTION 3/10/83 Safety Injection Safety Injection Tank Re-calibrate level Transmitter #311 and #321.
3/1/83 Main Steam 2-MS-16D Inject furmanite into packing area.
1 3/3/83 Main Steam 2-MS-280 Replace valve stem.
l 3/9/83 Main Steam 2-MS-118, 2-MS-16B, Repair valves / Repack valves / Replace bonnet.
l 2-MS-297 3/16/83 Main Steam
'A'
& 'B' Moisture Repair leaks / Replace gaskets.
j separator.
l j
3/1/83 Reactor Protection Channel 'C' RPS Replace Bi-stable Trip Unit.
3/24/83 Reactor Protection Pressurizer level Repair transmitter amplifier.
Transmitter Ch 'X' l
LT-110X 4
n o
p 4
OPERATING DATA REPORT DOCKET NO. 50-336 DATE 4/13/83 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: March 1983 cumulative are weighted 3.
Licensed Thermal Power (MWt):
2700 ave unit operated at 4.
Nameplate Rating (Gross MWe):
909 2560 MW thermal prior to 5.
Design Electrical Rating (Net MWe):
870 its 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 744 2160 63672 12.
Number Of Hours Reactor Was Critical 360.3 1759.4 46994.2 13.
Reactor Reserve Shutdown Hours 0
0 2205.5 14.
Hours Generator On-Line 319.2 1623.8 44811.1 15.
Unit Reserve Shutdown Hours 0
0 468.2 16.
Gross Thermal Energy Generated (MWH) 806911 4243141 112677346 17.
Gross Elec. Energy Generated (MWH) 265500
_ 1379930 36610778 18.
Net Electrical Energy Generated (MWH) 251431 1322201.3 35084014 19.
Unit Service Factor 42.9 75.2 70.4 l
20.
Unit Availability Factor 42.9 75.2 71.1 21.
Unit Capacity Factor (Using MDC Net) 39.1 70.8 66.1 22.
Unit Capacity Factor (Using DER Net) 38.8 70.4 65.2 23.
Unit Forced Outage Rate 57.1 22.7 19.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
l 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 i
COMMERCIAL OPERATION N/A N/A l
l
Docket No. 50-336 Date:
4/13/83 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:
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:
April 13, 1983 Steam Generator Licensing Action:
May 13, 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 off load capability is reached.
1987, Core Full, Spent Fuel Pool contains 648 bundles.
NORTHI!AST IFFII.frII!S
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L TJ 3?55'35b))hb?T April 15,1983 MP-4958 Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 205S5
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 83-3 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
///4 A</
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J. Mroczka Station Superintendent Millstone Nuclear Power Station 1
EJM/JG:bjo cc:
Director, Office of Inspection and Enforcement, Region 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 l
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