ML20129F829
| ML20129F829 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/31/1985 |
| From: | Mroczka E, Newburgh G NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-6789, NUDOCS 8506070051 | |
| Download: ML20129F829 (5) | |
Text
i.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-245 UNIT Millstone 1 DATE 840404 COMPLETED BY G. Newburgh TELEPHONE (203) 447-1791 Ext. 4400 MONTH March DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 653 17 654 2
654 18 654 3
653 19 654 4
653 20 652 5
653 21 654 6
651 22 653 7
653 23 654 8
653 24 654 9
654 25 654 10 654 26 654 11 653 27 653 12 653 28 654 13 644 29 654 14 655 30 654 15 654 31 654 16 654 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.
DR
's.
OPERATING DATA REPORT DOCKET NO.
50-245 DATE 850404 COMPLETED BY G. Newburgh TELEPHONE (203) 447-1791 Ext. 4400 OPERATING STATUS 1.
Unit Name:
Millstone Unit 1 Notes 2.
Reporting Period:
March 1985 3.
Licensed Thermal Power (MWt):
2011 4.
Nameplate Rating (Gross MWe):
662 5.
Design Electrical Rating (Net MWe):
660 6.
Maximum Dependable Capacity (Gross MWe):
684 7.
Maximum Dependable Capacity (Net MWe):
654 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 125688 12.
Number Of Hours Reactor Was Critical 744 2160 95914.4 13.
Reactor Reserve Shutdown Hours 0
0 2775.8 14.
Hours Generator On-Line 744 2160 93096.5 15.
Unit Reserve Shutdown Hours 0
0 26.5 16.
Gross Thermal Energy Generated (MWH) 1490365 4304258 170712527
- 17. Gross Elec. Energy Generated (MWH) 508000 1466400 57363096 18.
Net Electrical Energy Generated (MWH) 486117 1402943 54707103 19.
Unit Service Factor 100 100 74.0
- 20. Unit Availability Factor 100 100 74.0 21.
Unit Capacity Factor (Using MDC Net) 99.9 99.3 66.6 22.
Unit Capacity Factor (Using DER Net) 98.9 98.4 65.9 23.
Unit Forced Outage Rate 0
0 12.9 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 INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION J
1 DOCKET NO.
50-245 UNIT SHUTDOWNS ANL POWER REDUCTIONS UNIT.NAME Millstone 1 DATE 850404 COMPLETED BY G. Newburgh REPORT MONTH March TELEPHONE (203) 447-1791-Ext. 4400 1
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
- t N/A 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 LicenseG 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).
6-Other (Explain) s9 e
~
REFUELING INFORMATION REQUEST 1.
Name of facility:
Millstone 1 2.
Scheduled date for next refueling shutdown:
October 1985 3.
Schedule date for restart following refueling: December 1985 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes, Technical Specification Changes Regarding:
-(l) Maximum Average Planar Linear Heat Generating Rate (2) Maximum Critical Power Ratio 5.
Scheduled date(s) for submitting licensing action and supporting information:
Fall 1985-6.
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:
200 GE78 Fuel Assemblies 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core: (a) 580 (b) 1346 8.
The present licensed spent fuel pool storage capacity and the siie of any increase in licensed storage capacity that has been requestea or is planned, in number of fuel assemblies:
2184 Assemblies 9.
The projected date of the last refueling that can be disch Ned to the spent fuel pool assuming the present licensed capacity:
1986, Spent Fuel Pool Full Core Off Load Capability is Reached.
1991, Core Full, Spent Fuel Pool Contains 2146 Bundles.
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ggg General Offices
- Selden Street, Berlin, Connecticut v e ca.ecte.4 to.i e noma w."
P.O. BOX 270
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HARTFORD. CONNECTICUT 06141-0270
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g teORf4ast easCLE t EMmGYCOt#assy April ll, 1985 MP-6789 Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washint, ton, D. C. 20555 Reference-Provisional License DPR-21 Docket No. 50-245
Dear Sir:
In accordance with Millstone Unit 1 Technical Specification 6.9.1.6, the following monthly operating data report for Millstone Unit 1 is enclosed.
One additional copy of the report is enclosed.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY k
W
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E. J. Mroczka Station Superintendent Millstone Nuclear Power Station E24/GSN:jic
Enclosures:
(4) 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 s
t-