ML20079P458
| ML20079P458 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 10/31/1991 |
| From: | Gibson J, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-91-945, NUDOCS 9111120432 | |
| Download: ML20079P458 (5) | |
Text
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NORTHEAST UYlLITIES o.n 'ai Of t>ces + semen st'**t. B+'on. connect' cut
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P O. Box 270 w m.cs..w ;c#m H ARTFORD. CONNECTICUT 06141-0270
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A (203)665 5000 sc.,<.c u v.a.> :~..
November 8, 1991 MP-91-945 Re:
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Reference:
Facility Operating License No. DPR-65 Docket No. 50-336
Dear Sir:
This letter is forwarded to provide the rape.:t of operating and shutdown experience relating to Millstone Unit 2 for the month of October 1991, in accordance with Appendix A Technical Specifications, Seerion 6.9.1.6.
One additional copy of the report is enclosed.
Very truly yours, NORTHEAST NUC1. EAR ENERGY COM'/ANY f}ppy,,
incl-Stephh E. Scace Station Director Millstone Nuclear Power Station SES/JG cc: T. T. Martin, Region 1 Administrator G. S. Vissing, NRC Project Manager, Millstor.e 'Jnit No. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1,2 63 1 mr>
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l OPERATING DATA REPORT DOCKET NO.
_iQ 336 DATE 11/06/91 COMPLETED BY J. Gibson TELEPHONE __L203) 447-1791
- EXT, 4431
' OPERATING STATUS Notes: Items 21 and 22
'1.
Unit Name:
Millstone Unit 2 cumulative are weighted
- 2. ~ Reporting Period:
October 1991 averages. Unit operated 3.
Licensed Thermal Power (MWt):
2700 at 2560 MWTH prior to its 4.
Nameplate Rating (Gross MWe):
909 uprating to the current 5.
Design Electrical Rating (Net MWe):
870 2700 NanM power level.
6.
Maximum Dependable Capacity (Cross MWe):
893.88 7.
Maximus Dependable Capacity (Net MWe):
802 S3 8.
If Changes Occur-in Capacity Ratings (Items dumber 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 745.0 7296.0 138936.0
- 12. Number Of Hours Reactor Was Critical 745.0 4905.5 101818.1
- 3. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5
- 14. Hours Generator On-Line 641.8 4615.5 949}9 ]
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Cross Thermal Energy Generated-(MWH) 1708110.0 0.0 468.2 11963098.0 267019162.4
- 17. Gross Electrical Energy Generated (MWH) 567787.5 3970476.0 81410175.5
- 18. Net Electrical Energy Generated (MWH) 545310.5_
3797072.0 78098121.5 19, Unit Service Factor
-86.1 63.3 69.8
- 20. Unit Availability Factor 86.1 63.3 70.1
.21. Unit Capacity Factor (Using MDC Net) 84.8 60.3 66.0
- 22. Unit Capacity Factor (Using DER Net) 84.1 59.8 64.8
- 23. Unit Forced Outage Rate 13.9 36.4 14.7
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
N/A
- 25. If Unit Shutdown 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 COMMERCIAL OPERATION N/A N/A
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AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50 336 UNIT:
Millstone Unit 2 DATE:
11/06/91 COMPLETED BY:
J. Gibson TELEPHONE:
(203)447-1791 EIT:
4431 MONTH: OCTOBER 1991 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 870 17 873 2
869 18 564 3
869 19 0
4 869 20 0
5 869 21 0
6 870 22 0
7 873 23 446 8
873 24 866 9
873 25 870 10 872 26 872 11 872 27.
873 12 873 28 871 13 873 29 873 14 873 30 873 15 873 31 874 16 873 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.
I
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l UNIT SHUTDOWNS AND POWER REDUCTIONS
' DOCKET NO.
50-336 UNIT NAME-Millstone 2 i
DATE 11/06/91 COMPLETED BY J_ Gibson TELEPHONE (203) 447-1791
.l REPORT MONTH OCTOBER 1991 EXT.
4431 L
l 2
[
No.
Date
. Type Duration Reason Method of License Systgm Compgnent Cause & Corrective (Hours)
Shutting Event Code Code Action to 6
3 Down Reactor Report #
Prevent Recurrence 09 911018 F
103.2 F
6 91-010 N/A N/A On October 18, 1991, at 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br />, with the l
plant at 100 percent power, a reportability determination was made concerning a re-anal-ysis of the main steam line-break event. The evaluation determined this condition to be outside the design basis for the plant. The unit immediately commenced an orderly down-
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l-power to Mode 2.
A Justification for Con-r tinued Operation (JCO) plan was developed i
that allowed the unit to return to power operation on October 22. 1991. See LER.
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t I
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i 1: Forced Reason:
Method
' Exhibit G - Instructions f
2 3
j F
S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l
B-Maintenance or Test 2-Manual Scram Entry Sheets for License j
C-Refueling 3-Automatic Scram Event Report (LER) File
[
D-Regulatory Restriction 4-Continued from (NUREG-0161) v E-Operator Training & License. Examination Previous month I
5 l
F-Administrative 5-Power Reduction Exhibit 1 - Same Source G-Operational Error (Explain)
(Duration -0)
H-Other (Explain) 6-Other (Explain) t
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REFUELING INFORMATION REOUEST 1.
Name of facility:
H111 stone 2 2.
Scheduled date for next refueling shutdown:
Anril 1992 3.
Scheduled date for restart following refueling:
N/A 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
None at this time 5.
Scheduled date(s) for submitting licensing action and supporting information:
Fone 6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis methods, sign.ficant changes in fuel design, new operating proccoures:
Mil:. stone 2 will be replacina the Steam Generator sub-assenblies dur:.no the uncomina End of Cycle 11 refuelina outace.
It is ant:;cipated this-will be accomplished under 10CFR 50.59.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
In Core:
(a) 112 In Spent Fuel Pool:
(b) 712 NOTE:
These numbers represent the total fuel assemblies and consolidated fuel storace boxes in these two (2) Item Control Areas 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed starage capacity that has been requested or is planned, in ; 4mber of fuel assemblies:
Currently 1277 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1994. Spent Fue:
Pool Full, core off load capacity is reached (with
-out consolidat:.on).
1998. Cere Full.-Spent Fuel Pool Full 2009. Spent Fuel Poo] Full, core off load capacity is reached-continuent upon full scale storace of consolidated fuel in the Spent Fuel Pool.
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