ML20034G642
| ML20034G642 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1993 |
| From: | Newburgh G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-93-200, NUDOCS 9303100302 | |
| Download: ML20034G642 (5) | |
Text
_.
. g.
NORTHEAST tlTILITIES senerei On ce.. seiden street, seriin. connecticut w cm ou ton.wmma a==
l
.tstm x smaa-ccw-P.O BOX 270 2 '*t ", e"...v"*s u*m"*i c""
HARTFORD. CONNECTICUT 06141-0270 w4.r.
n, w w m, en~
(203) 665-5000 March 3, 1993 MP-93-200 Re:
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Reference:
Facility Operating License No. 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 COMPA!W Of Cace -
Step ed E. Scace i
Vice President - Millstone Station l
l l
SES/GSN cc: T. T. Martin, Region I Administrator J. W. Andersen, NRC Project Manager, Millstone Unit No. 1 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1,2&3 i
i
/
l' l
i t
i 1'
9303100302 930228 PDR ADOCK 05000245 R
pon
l i
OPERATING DATA REPORT l
UNIT NAME Millstone Unit 1 l
DATE 930303 COMPLETED BY G. Neuburgh TELEPHONE (203) 447-1791 EXT 4400 OPERATING STATUS i
1.
Docket Number:
50-245 Notes:
2.
Reporting Period:
February 1993 1
3.
Utility
Contact:
G. Newburch 4.
Licensed Thermal Power (MWt):
2011 5.
Nameplate Rating (Gross MWe):
662 6.
Design Electrical Rating (Net MWe):
660 7.
Maximum Dependable Capacity (Gross MWe):
684 8.
Maximum Dependable Capacity (Net MWe):
654 9.
If Changes occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Cive Reasons N/A
- 10. Power Level To Which Restricted, If any (Net MWe):
N/A
- 11. Reasons For Restrictions, If Any:
N/A This Month Yr.-To-Date Cumulative
- 12. Hours In Reporting Period 672.0 1416.0 195072.0
- 13. Number Of Hours Reactor Was Critical 672.0 1416.0 150885.4
- 14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3 l
- 15. Hours Generator On-Line 672.0 1416.0 147191.8 l
l
- 16. Unit Reserve Shutdown Hours 0.0 0.0 93.7
- 17. Gross Thermal Energy Generated (MWH) 1330618.0 2805583.0 276672456.0
- 18. Gross Electrical Energy Generated (MWH) 443912.0 935698.0 93346694.0
- 19. Net Electrical Energy Generated (MWH) 424764.0 895377.0 89048288.0
- 20. Unit Service Factor 100.0 100.0 75.5
- 21. Unit Availability Factor 100.0 100.0 75.5
- 22. Unit Capacity Factor (bsing MDC Net) 96.6 96.7 69.8
- 23. Unit Capacity Factor (Using DER Net) 95.8 95.8 69.2
- 24. Unit Forced Outage Rate 0.0 0.0 12.4
- 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): N/A 1
I
- 26. If Unit Shutdown At End Of Report Period, Estimated Date of Startup:
N/A 27.
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 1
l
l 1
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-245 UNIT:
Millstone Unit 1 DATE:
930303 COMPLETED BY:
G. Newburth TELEPHONE:
(203) 447-1791 EIT:
4400 MONTH:
FEBRUARY 1993 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 642 17 639 l
l 2
642 18 642 3
638 19 642 4
643 20 642 5
642 21 642 6
642 22 642 7
630 23 643 1
8 642 24 454 9
643 25 560 10 638 26 641 11 642 27 642 12 642 28 643 13 642 14 643 15 642 16 642 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.
DOCKET No.
50-245 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 1 DATE 930303 COMPLETED BY G. Newburch TELEPl{0NE (203) 447-1791 REPORT MONTil FEBRUARY 1993 EXT.
4400 l
2 No.
Date Type Duration Reason Method of License Systgm Compgnent Cause & Corrective (Hours)
Shutting Event Code Code Action to 3
Down Reactor Report #
Preverit Recurrence 93-01 930224 F
0 B
5 N/A N/A N/A Power reduction to find and repair condenser tube leaks I: Forced 2
3 F
Reason:
Method 0Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for License 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 5Exhibit 1 - Same Source G-Operational Error (Explain)
(Duration -0)
H-Other (Explain) 6-Other (Explain)
Eh A
l l
REFUELING INFORMATION REOUEST 1.
Name of facility:
Millstone 1 2.
Scheduled date for next refueling shutdown:
February 1994 3.
Scheduled date for restart following refueling:
April 1994 f
i 4.
Will refueling or resumption of operation thereafter require a l
technical specification change or other license amendment?
s l
Yes. Technical Specification Chances Recardina:
I l
(1) Maximum Averaae Planar Linear Heat Generatina Rate and 12L Maximum Critical-Power Ratio i
i 5.
Scheduled date(s) for submitting licensing action and supporting l
l information:
l a
]
Summer 1993 i
1 I
1 l
l 6.
Important licensing considerations associated with refueling, e.g.,
j j
new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, j
new operating procedures:
}
I 188 GE10 Fuel Assemblies I
4 i
7.
The number of fuel assemblies (a) in the core and (b) in the spent j
j fuel storage pool:
j i
i In Core:
(a) 580 (b) 2116 (Unconsolidated) i 8.
The present licensed spent fuel pool storage capacity and the size l
of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present capacity: Maximum 3229 fuel assemolv iocations.
l t
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1997. Soent Fuel Pool Full. Core Off Load capacity is reached.
- _.