B17104, Monthly Operating Rept for Feb 1998 for Mnps,Unit 2
| ML20248L152 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1998 |
| From: | Price J, Stark S NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B17104, NUDOCS 9803190004 | |
| Download: ML20248L152 (7) | |
Text
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g Rope Ferry Rd. (Route 156), Eterford, CT 06385 Nuclear Energy uiti,tooe Nocica, rower station Northeast Nuclear Energy Company P.o. Box 128 Waterford, CT 06385-0128 (860) 447-1791 i
Fax (860) 444-4277 l
The Northeast Utilities System j
MAR 5 1998 Docket No. 50-336 B17104 Re: 10CFR50.71(a) i i
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No DPR-65 Monthlv Ooeratina Reoort j
In accordance with the reporting requirements of Technical Specification Section 6.9.1.7 for Millstone Unit No. 2, enclosed, in Attachment 1, is the monthly operating report for the month of February 1998.
There are no regulatory commitments contained within this letter.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
,,, 1 M
_ v v v v
J. A. Prf, Millstone Unit No. 2 Directoi I
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'N 9803190004 900228 llllllllHilglNlllHEINilllill PDR ADOCK 05000336 ll1I11111111Imilu,IlllEluI EIIE g
R PDR H. J. Miller, Region I Adr$ninistrator cc:
D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 l
W. D. Travers, Ph.D., Director, Special Projects Office
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083422-5 REY.11-95 j
Docket No. 50-336 B17104 l
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1 i
i Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No. DPR-65 4
' Monthly Operating Report i
1 March 1998 i
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__________-_-__a
' U.S. Nucle:r Regulatory Commission B17104%ttachment 1\\Pags 1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-336 UNIT:
Millstone Unit 2 DATE:
03/02/98 COMPLETED BY:
S. Stark
-TELEPHONE:
(860) 447-1791 EXT:
4419 MONTH: FEBRUARY 1998 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-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 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
l 11 0
27 0
12 0
28 0
13 0
29 14 0
30 l
15 0
31 16 0
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.
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U.S. Nuclear Regulatory Commission B17104%ttachment 1\\ Pag 3 2 OPERATING DATA REPORT UNIT NAME: Millstone Unit 2 DATE: 03/02/98 COMPLETED BY:
S. Stark TELEPHONE: (860)447-1791 EXT: 4419 OPERATING STATUS 1.
Docket Number 50 336 2.
Reporting Period February 1998 Notes: Items 22 and 23 3.
Utility Contact S. Stark cumulative are weighted 4.
Licensed Thermal Power (MWt):
2700 averages. Unit operated at 5.
Nameplate Rating (Gross MWe):
909 2560 MWTH prior to its 6.
Design Electrical Rating (Net MWe):
870 uprating to its current 7.
Maximum Dependabie Capacity (Gross MWe):
901.63 2700 MWTH power level.
8.
Maximum Dependable Capacity (Net MWe):
870.63 9.
If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons:
N/A
- 10. Power Level To Which Restricted, if any (Net MWe):
0
- 11. Reasons For Restrictions, if Any:
NRC Category lli Facility; NRC Confirmatory Order requiring implementation of an independent corrective action verification program; NRC order requiring a third party review of the employee concerns program at Millstone 2; design basis verification response pursuant to 10CFR50.54(fl.
This Month Yr.-To-Date Cumulative
- 12. Hours in Reporting Period 672.0 1416.0 194424.0
- 13. Number Of Hours Reactor Was Critical 0.0 0.0 121911.7
- 14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5
- 15. Hours Generator On-Line 0.0 0.0 116611.9
- 16. Unit Reserve Shutdown Hours 0.0 0.0 468.2
- 17. Gross Thermal Energy Generated (MWH) 0.0 0.0 300862506.4
- 18. Gross Electrical Energy Generated (MWH) 0.0 0.0 98709460.0
- 19. Net Electrical Energy Generated (MWH)
-1702.7
-3751.7 94615338.5
- 20. Unit Service Factor 0.0 0.0 60.0
- 21. Unit Availabihty Factor 0.0 0.0 60.2
- 22. Unit Capacity Factor (Using MDC Net) 0.0 0.0 56.8
- 23. Unit Capacity Factor (Using DER Net) 0.0 0.0 56.0
- 24. Unit Forced Outage Rate 100.0 100.0 24.6
- 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Shutdown at the time of this report
- 26. If Unit Shutdown At End Of Report Period. Estimated Date of Startup:
To be determined
- 27. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY N/A N/A i
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INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A I
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U.S. Nucle r Regulatory Commission B17104\\ Attachment 1\\ Pag 34 REFUELING INFORMATION REQUEST I
1.
Name of the facility:
Millstone Unit 2 2.
Scheduled date for next refueling outage: Fourth Quarter of 1999
)
3.
Scheduled date for restart following refueling: Third Quarter of 1998 (Note -
The current shutdown is not a refueling outage. This date reoresents the expected startuo date from the current shutdown.)
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes.
There are 17 Technical Specification Change Reauests or license amendments which are reauired to be aooroved bv the NRC orior to startuo.
As of March 3.1998.11 reauests have been sent to the NRC. 7 have been aooroved, and 6 have been implemented.
The 6 remaining changes to be submitted are: 1) Certain RPS and ESAS trios did not consider the uncertainty associated with a Harsh Environment. Some RPS and ESAS setooints were based on 24 months instead of 18 months. 2) Condensate Storage Tank minimum level. 3) TSP volume inside containment. 4) Comoliance issue lli -
MSIV mode change and RCS vent. 5) USQ issue related to the low range oressure transmitters (diversity issue) and 6) Service Water Coating.
5.
Scheduled date(s) for submitting licensing action and supporting information:
March 31,1998 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: Small Break LOCA analvsis changes and Large Break LOCA analvsis changes.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
In Core: (a)
_Q_
in Spent Fuel Pool: (b) 1085 l
NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storage Boxes (3 total containing the fuel rods from 6 fuel I
assemblies) in these two (2) ltem Control Areas.
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_____________________o
U.S. Nuclear Regulatory Commission B17104%ttachment 1\\Pags 5 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 storage caoacitv: 1306 storage locations 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
2001. Soent Fuel Pool Full. Core offload caoacity is reached.
2005. Core Full. Soent Fuel Pool Full.
,