B16248, Monthly Operating Rept for Jan 1997 for Millstone Nuclear Power Station Unit 1

Monthly Operating Rept for Jan 1997 for Millstone Nuclear Power Station Unit 1

ML20138L836
Person / Time
Site:	Millstone
Issue date:	01/31/1997
From:	Hinnenkamp P, Newburgh G NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16248, NUDOCS 9702250121
Download: ML20138L836 (6)

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Northeast Hope Ferry thi. (Houte 156), Waterford, cr 06385 L

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, Northeast Nuclear EnerFy Cornpany P.O. Ik,x 128 i Waterford, Cr 06385-0128 i (860) 447-1791 Faz (860) 444-4277 The Northeast l'ailities System February 14,1997 Docket Nos. 50-245 B16248 1

Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. DPR-21 Monthly Operating 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 January,1997.

t Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Paul Hinnenkamp V '

Director- Unit Operations Millstone Unit No.1  !

Attachments (1) cc: Dr. W. D. Travers, Director, Special Projects i H. J. Miller, Region i Administrator i S. Dembek, NRC Project Manager, Millstone Unit No.1 T. A. Easlick, Senior Resident inspector, Millstone Unit No.1 9702250121 970131 I PDR ADOCK 05000245 PDR ys Q.

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i Docket No. 50-245 j B16150 i'

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I' Millstone Unit No.1 Facility Operating License No. DPR-21 Monthly Operating Report-January 4

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, OPERATING DATA REPORT

• I UNIT NAME Millstone Unit 1 DATE 2/7/97

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i COMPLETED BY G Fiewburgh ,

TELEPHONE (860)444 5730  !

OPERATING STATUS

1. Docket Number 50-245

2. Reporting Period January 1997 Notes:

3. Utility Contact G. Newburgh

4. Licensed Thermal Power (MWt):

l 2011 l

5. Nameplate Ratmg (Gross MWe): 662 l

6. Design Electrical Rating (Net MWe): 660  !

7. Maximum Dependable Capacity (Gross MWe): 670 l

8. Maximum Dependable Capacity (Net MWe): 641

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: Regulatory Restriction (10CFR50.54f)

This Month Yr. To-Date Cumulative

12. Hours in Reporting Period 744.0 744.0 228744.0

13. Number Of Hours Reactor Was Critical O.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 1

17. Gross Thermal Energy Generated (MWH) 0.0 0.0 314372827.0 l

18. Gross Electrical Energy Generated (MWH) 0.0 0.0 105938737.0

19. Net Electrical Energy Generated (MWH) -2376.0 -2376.0 101041173.0

20. Unit Service Factor 0.0 0.0 72.8

21. Unit Availability Factor 0.0 0.0 72.9 ]

22. Unit Capacity Factor (Using MDC Net) -0.5 -0.5 67.5

23. Unit Capacity Factor (Using DER Net) -0.5 -0.5 66.9  ;

24. Unit Forced Outage Rate 100.0 100.0 16.1  ;

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 Startup: 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 -

DATE 2/7//97 COMPLETED BY G. Newburah TELEPHONE (8601-444-5730 REPORT MONTH: January 1997 No. Date Type' Duration Reason

• Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code 5 Action to Down Reactor' Report # Prevent Recurrence 95-10M 9512.13 F 744 D 4 N/A 10CFR50.54f

' F: Forced

• Reason

• Method

• IEEE Standard 805-1984, S: Scheduled A- Equipment Failure (Explain) 1 - Manual " Recommended Practices B - Mainteneance or Test 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) 5 F - Administrative 0 - Other (Explain) IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers"

. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245 UNIT: Millstone Unit 1 DATE: 2/7//97 COMPLETED BY: G. Newburah TELEPHONE: (860)444-5730 MONTH: January 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 9 0 25 'O 10 0 26 0 11 0 27 0 l 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 1

l lNSTRUCTIONS l

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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'. 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 following refueling: To be determined

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes. however the entire scope is to be determined.

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

None at this time

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: ,

184 GE-11 fuel assemblies j

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

In Core: (a) 0 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 Capacity: Maximum 3229 fuel assembiv locations

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

1998/1999. spent fuel pool full. core offload capacity is reached  !

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