ML20012B749
| ML20012B749 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1990 |
| From: | Newburgh G NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20012B740 | List: |
| References | |
| NUDOCS 9003160218 | |
| Download: ML20012B749 (4) | |
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OPEPATING DATA REPORT' l
e D00KET No.
50-245 l
DATE 900302
~j COMPLETED BY G. Newburgh TELEPHONE (203)447-1791 i
Extension 4400 F
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OPER) TING STATUS l
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NiitName: Millstone 1-Notes:
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- 2.
Reporting Perloc: February 1990 l
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- Licensed Thermal Power (MWt)
- 2011 O
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Nameplate Rating (Gross MWe):
662 l
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Design Electrical Rating (Net MWe): 660 6.
Maximum Dependable Capacity (Gross MWe): 664
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- 7. -
Maximum Dependable Capacity (Net.MWe):
654 l
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.8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7)
'Since Last Report, Give Reasons:
N/A j
9.
- Power Level to.Which Restricted,- If Any (Net MWe):
N/A
- j 10... Reasons For Restrictions,.11 Any:
N/A
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- 11. 'HoureLInReportingPeriod 672 1,416 168,768 j
12.
Number Of Hours Reactor Was Critical 672-1,416 133,780.9 13 Reactor Reserve Shutdown Hours 0
0-3,283.3--
.l 14.' Hours: Generator On-Line 672 1,416 130,492.8
- 15. Unit Reserve Shutdown Hours.
0 0
93.7
.q c16., Gross-Thermal Energy Generated (MWH) 1,333,794 2,817,367 244,214,904 l17.
Gross. Elec. Energy Generated (MWH) 457,800-967,700-82,389,796 l
'18.'
Net' Electrical Energy Generated (MWH) 438,356 926,805 78,619,065
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- 19. Unit Service Factor 100 100-77.3 i
20.- Unit; Availability ractor 100 100 77.4 r
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21.
Unit Capacity ractor (Using MDC Net) 99.7 100.1 71.2 1
- 22. Unit Capacity Factor (Using DER Net) 98.6 99.2 70.6
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- 23. -Unit Forced Outage Rate 0
0 10.2
- 24.. Shutdowns, Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
?j N/A' i
25.
If Shutdown at End of Report Period, Estimated Date of Startup: N/A
.26.- Units in Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY N/A N/A-t INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A__
N/A i
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AVERAGE DAILY UNIT POWER LEVEL DOCKET No.
50-245 UNIT Millstone 1 DATE 900302 COMPLETE BY G. Newburgh TELEPHONE (203)447-1791 Extension 4400 MDNTH Tebr 2ary 1990 '
DAY-AVEP. AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 657
' 17 660 2
661-18 661 3
661 19 661 4
661 20 661 5-661 21 661 6
-662 22 657 7
662 23 660' 8
659 24 661 g
9 662 25 661
. 10 662 26 661
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.11-662 27 660 12 661 28 565 13 661 29 N/A-14' 661 30 N/A 15 568 31 N/A
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16 621 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each
. day in the reporting month. Computer to the nearest whole megawatt.
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,i DOCKET NO. 50-245 UNIT SI N a AND FOWER FIDUCTIONS UNIT NAME Millstone 1 DATE 900302 COMPLETED BY G. Newburgh REPORT MONTH February, 1990
-TELEPHONE J203) 447-1791 Extension 4400 t
2 Method of Licensee System Coreponent Cause & Corrective No.
Date Type Duration Reason (Hours)
Shutting Event Code 8 Codes Action to 3
Report I Frevent Recurrence Down Reactor N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 8 Exhibit G - Instructions 3 Method:
2 Reason:
IF: Forced 1-Manual for Preparation of Data S: Scheduled A-Equipment Failure (Explain)
B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee 3-Automatic Scram Event Report (LER) File-C-Refueling 4-Continued from (NUFIG-0161)
D-Regulatory Restriction E-Operator Training & License Examination previous month 5 Exhibit 1 - Same Source 5-Fower Reduction F-Administrative G-Operational Error (Explain)
(Duration = 0)
H-Other (Explain) 6-Other (Explain)
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RETUELING INPORMATION REQUEST
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1.
Name of facility: Mi)lstone 1 i:
2.
Scheduled date for next refueling shutdown: March 1991 3.
Schedule date for restart following refueling: April 1991 4.
Will refueling or resumption of operation thereafter require a i
technical specification change or other license amendment?
Yes, Technicial Specification Changes Regarding:
Q) Maximum Average Planar Linear Heat Generating Rate I
(2) Maximum Critical Fower hatio l-L 5.
Scheduled date(s) for submitting licensing action and supporting information:
Winter 1990-91 6.
Important licensing considerations associated with refueling, e.g., new 1
or different fuel design or supplier, unreviewed design or performance-analysis methods, significant changes in fuel design, new operating procedures:
196 GEBB ruel 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) 1928 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:
Present capacity, 3229 assemblies 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1997, Spent Fuel Pool, Full Core Off Lead Capability is Reached lI l
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