B16615, Monthly Operating Rept for June 1997 for Mnps

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Monthly Operating Rept for June 1997 for Mnps
ML20141H100
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/30/1997
From: Hinnenkamp P, Newburgh G
NORTHEAST NUCLEAR ENERGY CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16615, NUDOCS 9707220010
Download: ML20141H100 (6)


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Nodl e t Hope Ferry Rd. (Houte 156), Waterford, (70 0638*2 Nuclear Energy stai,ione suaear Po.er siauoo Northeast Nudear Energy Company P.O. Ibx 128 Waterfont, (Tr 0638.50128 l (860) 447 1791 )

Fax (860) 444 4277 )

The Northeast Utilities System JUL 1 1 1997 Docket No. 50-245 l B16615  !

1 U.S. Nuclear Regulatory Commission Attention: Document Control Desk i Washington, DC 20555 l i

Millstone Nuclear Power Station, Unit No.1 l Facility Operating License No. DPR-21 Monthly Operatina Report in accordance with the reporting requirements of Technical Specification Section 6.9.1.6 for Millstone Unit No.1, enclosed is the monthly operating report for the month of June 1997.

Very truly yours NORTHEAST NUCLEAR ENERGY COMPANY cOhks!3 O xC P. D. Hinnenk~ amp * >

Director - Unit Operations Millstone Unit No.1 j Attachments (1) cc: H. J. Miller, Region i Administrator W. D. Travers, PhD., Director, Special Projects Offica S. Dembek, NRC Project Manager, Millstone Unit No.1 T. A. Eastick, Senior Resident inspector, Millstone Unit No.1 9707220010 970630 "

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Docket No. 50-245 B16615 3

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Attachment 1 ,

1 Millstone Unit No.1 1

Facility Operating License No. DPR-21 Monthly Operating Report - June July 1997

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REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit 1
2. Scheduled date for next refueling outage: Current refuelina outaae started November 1995. Next refuelina outaae date to be determined.
3. Scheduled date for restart f >llowing refueling: To be determined l
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes. however the entire scoes is to be determined. I

5. Scheduled date(s) for submitting licensing action and supporting information:

None at this time G. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, sign

  • cant changes in fuel design, new operating procedures:

184 GE 11 fuel assemblies I

7. The number of fuel assemblies (a)in the core and (b) in the spent fuel storage pool: i in Core: (a) Q in Spent Fuel Pool: (b) 3068 Unconsolidated
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 Caoacity: Maximum 3229 fuel assembiv locations _

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:

1998/1999, soent fuel oool full, core offload caoacity is reached

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245 UNIT: Millstone Unit 1 DATE: 7/7/97 COMPLETED BY: G. Newburah TELEPHONE: (800)444-5730 MONTH: June.1997 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 0 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 N/A 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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UNIT NAME Millstone Unit 1 DATE 7/7/97 COMPLETED . G. Newburgh BY TELEPHONE (860)444-5730 OPERATING STATUS

1. Docket Number 50-245
2. Reporting Period June 1997 Notes:
3. Utility Contact- G. Newburgh 4 Licensed Thermal Power (MWt): 2011
5. Nameplate Rating (Gross MWe): 662
6. Design Electrical Rating (Net MWe): 660
7. Maximum Dependable Capacity (Gross MWe): 670
8. Maximum Dependable Capacity (Net MWe): 641
9. If Changes Occur in Capacity Ratings (items Number 4 Througi. 8) Since Last Report, Give Reasons:

N/A

10. Power Level To Which Restricted, if any (Net MWe): 0

- il Reasons For Restrictions, if Any: Regulatwy Restriction (10CFR50.54f) -

This Month Yr.-To Date Cumulative

12. Hc,urs in Reporting Period 720.0 4343.0 232343.0
13. Number Of Hours Reactor Was Critical 0.0 0.0 170529.9
14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3
15. Hours Generator On-Line 0.0 0.0 166560.7
16. Unit Reserve Shutdown Hours 0.0 0.0 93.7 17.. Gross Thermal Energy Generated (MWH) 0.0 0.0 314372827.0
18. Gross Electrical Energy Generated (MWH) 0.0 0.0 105938737.0
19. Net Electrical Energy Generated (MWH) -1976.0 -12895.0 101030654.0
20. Unit Service Factor 0.0 0.0 71.7 ,
21. Unit Availability Factor 0.0 0.0 71.7
22. Unit Capacity Factor (Using MDC Net) -0.4 -0.5 66.5
23. Unit Capacity Factor (Using DER Net) * -0.4 -0.4 65.9
24. Unit Forced Outage Rate 100.0 100.0 17.6
25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Shutdown at time of this report

26. _If Unit Shutdown At End Of Report Period, Estimated Date of Staitup: To be determined
27. 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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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO 50-245 UNIT NAME Millstone Unit 1 -

COMPLETED BY G. Newburuh -.

TELEPHONE (860)-444-5730 REPORT MONTH: June,1997 ^

2 No. Date Type' Duration Reason Method of License System Comp

  • orient Cause & Corredive (Hours) Shutting Event Code' Code Action to Down Reactor' Report # Prevent Recurrence 95-10R 951213 F 720 D 4 N/A 10CFR50.54f 2 3 -* IEEE Standard 805-1984,

' F: Forced Reason Method S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices B- Mainteneance orTest . 2 - Manual Scram for System identification in

- C - Refueling 3 - Automatic Scram Nuclear Power Plants and D- Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0) 8 F- Administrative 6 - Other (Explain) IEEE Standard 803A-1983, G - Operational ErTor(Explain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers"

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