B16893, Monthly Operating Rept for Nov 1997 for Mnps,Unit 2
| ML20203E160 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/30/1997 |
| From: | Price J, Stark S NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B16893, NUDOCS 9712160400 | |
| Download: ML20203E160 (7) | |
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- gg Rope Terry Rd. (Route 156), Wttericrd. Cr Oto85 NtK' N h fgy M& tone Nudear Poser Station Nordnut Nudear Enesgy Cumieny P.O. Iba 128 Tetwford, CT 06385-0128 (860) 447 1791 i'an (860) 444 4277 ne Nortlwt Utahtace System DEC l 01997 Docket No. 50-336 B16893 Re: 10CFR50.71(a)
U.S. Nuclear Regulatory Com aission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Pcwer Station, Unit No. 2 Facility Operating License No DPR-65 LAonthlv Operatina Report 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 November,1997.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY J.A. fide y
Directsf, Millstone Unit No. 2
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cc: H. J. Miller, Region i Administrator
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D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 W. D. Travers, Ph.D, Director, Special Projects Office 3
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Millstone Nuclear Power Station, Unit No. 2
- Facility Operating License No. DPR-65 Monthly Operating Report f
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- U S. Nuclear Regulato y Commission B16893%ttachment 1\\Page1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50 336 UNIT:
Millstone Unit 2 DATE:
12/1/37 COMPLETED BY:
S. Stark TELEPHONE:
(860)447 1791 EXT:
4419 MONTH: NOVEMBER 1997 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 C
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 levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
U S* Nuclear RegulatoryCommission B16893\\ Attachment 1\\Page 2 OPERATING DATA REPORT UNIT NAME: Millstone Unit 2 DATE: 12/01/97 COMPLETED BY:
S. Stark TELEPHONE: (8601447 1791 EXT: 4419 OPERATING STATUS 1.
Docket Number 50-336
'2.
Reporting Period November 1997 Notes: Items 22 and 23 3.
Utihty Conta;t 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 cur.ent 7.
Maximum Dependable 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 til Facility; NRC Confirmatory Order requiring implementation of an independent corrective action venfication 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 Cumulativ a
- 13. Hours in R porting Period 720.0 8016.0 192264.0
- 13. Number or Hours Reactor Was Critical 0.0 0.0 1211111.7
- 14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5 1r.. Hours Generator On Une 0.0 0.0 116611.9
- 16. Unit Reserve Shutdown Mours 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 1911.0 21735.6 94621176.8
- 19. Net Electrical Energy Generated (MWH)
- 20. Unit Service Factor 0.0 0.0 60.7
- 31. Unit Availabihty Factor 0.0 0.0 60.9
- 22. Unit Capacity Factor (Using MDC Net) 0.0 0.0 57.4
- 23. Unit Cipacity Factor (Using DER Net) 0.0 0.0 56.7
- 24. Unit Forced Outage Rate 100.0 100.0 23.5
- 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Shutdown at the time of this report
- 26. If Unit Sh"tdown At End Of Report Period, Estimated Date of Startup:
To be determined
- 27. Units in Test Status LPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICAllTY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A
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U.S. Nudear Regulatory Commission i
B96893%ttachrnent1Page 3 UNIT SHUTDOWNS AND POWER REDUCTIONS I
DOCKET NO:
50-336 I
UNIT NAME:
Mdistonebrut 2
+
I DATE:
12/01/97 l
COMe't.ETED BY:
S. Starit TELEPHONE:
(860)447:1791 EXT:
4419 REPORT MONTH: November 1997 No.
Date Type' Duration Reason
- Method of License System Component Cause & Correctrve (Hours)
Shutting Event Code
- Code' Action to Down Reactor' Report #
Prevent Recurrence 97-01 03/07/96 S/F 720 B/D 4
N/A N/A N/A Scheduled: Continued cycle survedlance testing from previou* month.
Forced: Continued from i
previous month. NRC Category til facility: NRC Confirmatory Order requiring independent corrective action venfication:
NRC order requiring third party i
review of Mi!! stone Station employee concems program; design basis venfication for
[
response to NRC pursuant to10CFR50.54(f).
f f
'F: Forced Reason
' Method "lEEE Standard 805-1984, i
S: Scheduled A - Equipment Failure (Explain) 1 - Manual
" Recommended Practices B - Maintenance or Test 2 - Manual Scram for System identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and 0 - Regu'atory Restriction 4 - Continued from Previous Month Related Facsisties*
E - Operator Training & License Examination 5 - Pow r Reduction (Duration = 0) l F - Administrative 6 - Other (Explain)
'IEEE Standard 803A-1983, l
G - Operational Error (Explain)
- Recommended Practices H - Other Explain) for Unique identification in i
Power Plants and Related Facilities - Component Function Identifiers" l
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U.& Nuclear Regulatory Commission
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B16893%ttachrnent1\\Page 4 REFUELING INFORMATION REQUEST l
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1.
Name of the facility:
Millstone Unit 2 2.
Scheduled date for next refueling outage: Second_ Quarter of 1999 3.
Scheduled date for restart following refueling: First Quarter of 1998 (Note -
l The current shutdown is not a refualina outaae. 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 13 Technical Soecification Chance Reauests or license amendments which are reouired to be sooroved bv the NRC orior to startuo.
As of December 2. 1997. 10 reauests have been sent to the NRC. 5 have l
been aooroved, and 3 have been imolemented. The 3 remainina chanaes to be submitted are:- 1) Technical Specification comollance issues (e.a. mode aoolicability for CEA droo time soecification) 2) 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, and
- 3) Condensate Storaae Tank minimum level and TSP volume inside pontainment, i
5.
Scheduled date(s) for submitting licensing action and supporting information:
Januarv 30,1998 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 chanaes and Larae Break LOCA analvsis chanaes.
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 NOTE:- These numbers represent the total Fuel Assemblies and Consolidated Fuel Storaae Boxos (3 total containina the fuel rods from 6 fuel assemblies) in these two (2) Item Control Areas.
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U.S NuclearRegulatoryCommistion B16893%ttachment1\\Page 5 8.
.The present licensed spent fuel pool storage capaci y and the size of any t
increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present storaae caoacity: 1306 storaae 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 capacity is reached.
2005, Core Full, Soent Fuel Pool Full.
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