ML20127D215
| ML20127D215 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/31/1992 |
| From: | Doboe S, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-92-972, NUDOCS 9209110282 | |
| Download: ML20127D215 (5) | |
Text
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NORTHEAST UTILITIES cenerai Off.ces. seiden street. Bernn. connecircut
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P O BOX 270
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HARTFORD. CONNECllCUT 06141-0270 L
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(203) 665-5000 September 8, 1992 MP-92-972 Re:
16C FR50. 71( r. )
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Reference:
Facility Operating Lice se 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 August, 1992, in accordance with Appendix A Technical Specifications, Section 6.9.1.6.
One additional copy of the report ir enclosed.
Very truly yours, NORTHEAST NGCLEAR ENERGY COMPANY
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Scace Vice President - Millstone Station SES/GN cc: T. T. Martin, Region I Adminir'.rator G. S. Vissing, NRC Project Mat. -ger, Millstone Unit No. 2 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 9209110282 920831 PDR ADOCK 05000336
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OPERATING DATA REPORT 1
DOCKET NO.
50-336 l-DATE 09/02/92 COMPLETED BY S. Doboe TELEPHONE (203) 447-1791 EXT.
4678 OPERATING ST E Notes: Items 21 and 22 1.
Unit Name:
Millstone Unit 2 cumulative are weighted 2.
Reporting Period:
August 1992 averages. Unit operated j;
3.
Licensed Thermal Power (MWt):
2700 at 2560 MWTH prior to its i
4 Nameplate R4 ting (Gross MWe):
909 uprating to the aurrent 5.
Design Electrical Rating (Net MWe):
870 2700 MWTi. power le/e1.,
j 6.
Maximem Depc Mable Cnpacity (Gross MWe):
903.1Q 7.
Maximam Deper.dable Cr -city (Net MWe):
873.10 j
8.
If cbanges 'ccur in sspacity Ratings (Items Number 3 Through 7, Sines Last Report, Cive Reasons:
b/A i
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 i
- 11. Hours in Reporting Period 744.0 5855.0_
146255.0
- 12. Numbet Of Hours Reactor Was Critical 0.0 3204.0 105,117.5.
- 13. Reactor Reserve Shutdown Hours 0.0 0_. 0 220LJ
- 14. Hours Generator On-Line-0.0
-3188.6 100357.4
- 15. Unit "aserve Shutdown Hours 0.0 0.0 468.2
'16.' Gross Thermal Energy Generated (MWH) 0.0 8506218.0 276028682.4
- 17. Gross Electrical Energy Generated (MWH) 0.0 28276}5.1 84404307.5
- 18. Net Electrical _ Energy Generated (MWH)
(-2870.0) 2715893.3.
80961671.3 t
- 19. Unit Service Factor 0.0 54.5 fld
- 20. Unit Availability Factor 0.0.
54.5 68.9
- 21. Unit Capacity-Factor (Usirg MDC Net)
-0.4 53.1 64.9
- 22. Unit Capacity Factor (Using DER Net)
-0.4 53.3 63.8
- 23. Unit Forced Outage Rate 0.0 11.4 15.4
- 24. Shutdowns Scheduled Over Next 6 Months (Typa, Date, and Duration of Each):
The Unit is cresentiv shutdown for refuelinz. replacement of the steam cererators and main-j
=tenance.
Duration - 185 days.
- 25. If Unit Shutdown At End Cf Report. Period, Esrf mated Date of Startup: November. 1992
- 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 2,_,.
A AVERAGE DAILY UNIT POWER LEVEL DOCKET E0.
50-336 UNIT:
Millstone Unit 2 DATE:
09/02/92 COMPLETED BY:
S.
Doboe TELEPHONE:
(203) 447-1791 EXT:
4678 MONTH:
AUGUST 1992 i
DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MVe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
?
5 0
21 0
6 0
22 6
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
'O' 15 0
31 0
.16 0
4 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.
d
. _ _. _ _ _ _.. - _. ~ _.
DOCKET NO.
50-336 UNIT SHUTDOWJS AND PGWER REDUCTIONS UNIT NAME Millstone 2 DATE 09/02/92 COMPLETED BY S. Doboe TELEPHONE (203) 447-1791 REPORT MONTH AUGUST 1992 EXT. __4678 l
2 No.
"Date
. Type Duration Reason
. Method of License System Compgnent Cause & Corrective (Hours)
Shutting Event Code" Code Action to 3
Down Reactor Report #
Prevent Recurrence
'I 03 920529 S-744 C
1 N/A N/A N/A Continuation of the re-fueling, steam generator replaccment and mainten-t ance outage from the 1
pr vious month.
J r
l I
i a
I : Forced' 2
3 Method Exhibit G - Instructions 4
F Reason:
i i
Si Scheduled A-Equipment Failure'(Explain) 1-Manual-for Preparation of Data l
B-Maintenance or Test 2-Manual Scram Entry Sheets for License 3-Automatic Scram Event Report (LER) File-C-Refueling 4-Continued from (NUREG-01't)-
D-Regulatory Restriction E-Operator Training 6 License Examination Previous morfh 5
F-Administrative 5-Power Reduction Exhibit 1 - Same Source G-Operational Error (Explain)
(Duration -0)
'H-Other (Explain) 6-Other (Explain) l. --
i E
J REFUELING INFORMATION REOUEST
-1.
Name of facility:
Millstone _2 2.
Scheduled date for next refueling shutdowr:
..pyrrently in the EOC 11 Refuelina. Maintenance _and Steam Gragr.ator Reolacement Outace.
3.
Scheduled date for restart following refueling:
December, 1992 4.
Will refueling or resumption of operatioi.'hereafter require a c
technical specification change or other license amendment?
YES 5.
Scheduled date(s) for submitting licensing action and supporting information:
October, 1992 w
6.
Important licensing considerations associated-with refueling, e.g.,
new or different fuel design or supglier, unreviewed design or performance anal / sis methods, significant changes in fuel design, new ooerating procedures:
-Mil:. stone 2 will be reolacina the Stg.am Generator sub-assemblies dur:.no the_uresent End of Cycle.1 ref';elina Autage.
It is ant:.cinated this will be accgf pl:.shed under 10CFR 50.59.
7.
The nrmber of fuel assemblies (a) in the core and (b) in the spent j
fuel ctorage pool:
In Core:
(a) 0 In Spent Fuel Pool:-
(b) 229 NOTE: "hese numbers reoresent the total Fr'1 Assemblies and Consol-
- . dated Fuel-Storace Boxes (3 total - containina the-fuel rods from 6 fuel asserkJies) in these two (2) Item-Control Arnas.
l 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:
Current 1v 1237 l
9.
The projected date of the last refueling that can be discharged to l
the spent fuel pool assuming the present licensed eipacity:
-1994,' Spent Fuel Pool Full, Core Off Load tocacit' is reached.
1998. Core Full. Soent Fuel Pool Full.
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