ML20125E315
| ML20125E315 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/30/1992 |
| From: | Doboe S, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-92-1293, NUDOCS 9212160297 | |
| Download: ML20125E315 (5) | |
Text
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NORTHEAST UTILITIES o,ne,.i on,ces. semen siro.t o nin Connecticut
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HARTFORD, CONNECTICUT 06141-0270 k
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(20M 665-5000 December 10, 1992 MP-92-1293 Re:
U.S. Nuclear Regulatory Conanission Docwnent 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 report of operating and shutdown experience relating to Millstone Unit 2 for the month of November,1992, in accordance with Appendix A Technical Specifications, Section 6.9.1.6.
One additional copy of the report is enclosed.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
/
//O v4 ace
/
Stephe i E.
Scace Vice President Millstone Station SES/SD cc: T. T. Martin, Region 1 Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1,263 hk
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PDR os34n nEv 4-88 i
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3 1
OPERATING DATA REPORT i
l l
DOCKET NO.
50 336 i
DATE 12/07/92 COMPLETED BY S.
Doboe TELEPHONE (203) 447-1791
- EXT, 4678 j
OPERATING STATUS i
Notes: Items 21 and 22 1.
Unit Name:
Millstone Unit 2 cumulative are weighted a
2.
Reporting Period:
November 1992 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 MWTI' power level.
6.
Maximum Dependable Capacity (Gross MWe):
903.10 1
7.
Maximum Dependable Capacity (Net MWe):
873.10 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A i
I 9.
Power Level To Which Restricted, If any (Net MWe):
N/A i
- 10. Reasons For Restrictions, If Any:
N/A l
l This Month Yr.-To Date Cumulative
- 11. Hours In Reporting Period 720.0 8040.0 148440.0
- 12. Number Of Hours Reactor Was Critical 0.0 3204.0 105257.6
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5
- 14. Hours Generator On-Line 0.0 3188.6 100357.4
- 15. Unit Reserve Shutdown Hours 0.0 0.0 468.2
- 16. Gross Thermal Energy Generated (MWH) 0.0 8506218.0 276028682.4
- 17. Cross Electrical Energy Generated (MWH) 0.0 2827636.5
-84404307.5
- 18. Net Electrical Energy Generated (MWH)
(-2488.0) 2713105.3 80958883.3 i
- 19. Unit Service Factor 0.0 39.7 67.6 4
- 20. Unit Availability Factor 0.0 39.7 67.9 i
- 21. Unit Capacity Factor (Using MDC Net)
-0.4 38.6 64.3 i
- 22. Unit Capacity Factor (Using DER Net) 0h 38.8 63.1 i
- 23. Unit Forced Outage Rate 0.0 11.4-15.4
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
The Unit i
is presentiv shutdown for refueling. replacement of the steam renerators and main.
tenance Duration - 210 days.
- 25. If Unit Shutdown At End Of Report Period, Estimated Date of Startup:
December. 1992 26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved M
INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY'
-N/A N/A COMMERCIAL OPERATION N/A N/A
a AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-336 UNIT:
Millstone Unit 2 DATE:
12/07/92 COMPLETED BY:
S. Doboe TELEP110NE:
(203) 447-1791 EXT:
.4678 MONTH:
NOVEMBER 1992 DAY AVG. DAILY POVER LEVEL DAY AVO. DAILY POWER LEVEL (MVe-Net)
(MVe Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 16 0
INSTRUCTIONS On this format, list the average daily unit power level in MVe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
-. _. - - - - - - ~... - - - -...... - -....... -
., ~,.. - ~ _. -
DOCKET NO.
50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 12/07/92-COMPLETED BY S. Doboe TELEPHONE (203) 447-1791 REPORT MONTH NOVEMBER 1992 EXT.
4678 1
i l
2 Cause & Corrective
[
No.
Date Type Duration Reason Method of License Systgm Compgnent
.(Hours)
Shutting Event Code Code Action to f
3 Down Reactor Report #
Prevent Recurrence f
03 920529 S
720 C
1 N/A N/A N/A Continuation of the re-l fueling, steam generator l
replacement and mainten-ance outage from the previous month.
t l
I i
I h
b 2
3 Method Exhibit C - Instructions 4
1: Forced Reason:
F 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)
LE-Operator Training & License Examination Previous month l
F-Administrative 5-Power Reduction 5 Exhibit 1 - Same Source G-Operational Error (Explain)
(Duration -0)
H-Other (Explain) 6-Other (Explain) l L
f L
.. =
e i
REFUELING INFORMATION REOUEST l
l 1.
Name of facility:
Millstone 2 2.
Scheduled date for next refueling shutdown:
Currently in the 4
l LOC 11 Refuelina. Maintenance and Steam Generator Reolacement outace.
]
3.
Scheduled date for restart following refueling:
December, 1992 4
4.
Will refueling or resumption of-operation thereafter require a j
technical specification change or other license amendment?
YES
)
5.
Scheduled date(s) for submitting licensing action and supporting 4
information:
Licensina action was submitted to U.S.
Nuclear Reculatory l
CommissiUn~in October 1992.
i i
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:
i Millstone 2 is replacina the Steam Generator sub-assemblies durina
^
the Dresent End of Cycle 11 refuelina outace.
This is beino accom-olished under 10CFR 50.59.
7.
The number of fuel assemblies (a) in the core and (b) in the spent j
fuel storage pool:
l In Core:
(a) 217 In Spent Fuel Pool:
(b) 1EA NOTE: "hese nqrbers represent the total Fuel Assemblies and Consol_
. dated Fuel Storace Boxes (3 total - containina the fuel rods from 6 fuel assemblies) in these two (2) Item Control Areas.
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been l
requested or is planned, in number of fuel assemblies:
Currently 1237 9.
The projected date of the last refueling that can be discharged to-the spent-fuel pool assuming the present licensed capacity:
1994. Spent Fuel Pool Full. Core Off Load canacity is reached.
1998. Core Full. SDent Fuel Pool Full.
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