B16384, Monthly Operating Rept for March 1997 for Mnps

Monthly Operating Rept for March 1997 for Mnps

ML20137W623
Person / Time
Site:	Millstone
Issue date:	03/31/1997
From:	Hinnenkamp P, Newburgh G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16384, NUDOCS 9704180160
Download: ML20137W623 (6)

Text

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jff NuclearEnergy sui +ne nuaear Po.n stadon Northem Nuricar Energy Cornpany P.O. Ibn 128 Weierford, CF 06E-0128 (860) 447-1791 Fax (860) 444 4277 ,

'Ihe Northcaat Utilities System APR I 21997 ,

Docket No. 50-245 I B16364 2

s U.S. Nuclear Regulatory Cornmission .

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 Spccification Section  !

6.9.1.6 for Millstone Unit No.1, enclosed is the monthly operating report for the month of March 1997 .

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY k - U A 1r

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Paul Riririenkdm'p" V Director- Unit Operations Millstone Unit No.1 1

i Attachments (1) g cc: . Dr. W. D. Travers, Director, Special Projects H. J. Miller, Region i Administrator

[@Yp S. Dembok, NRC Project Manager, Millstone Unit No.1 T. A. Easlick, Senior Resident inspector, Millstone Unit No.1

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! Attachment 1 i.

Millstone Unit No.1 l

Facility Operating License No. DPR-21 Monthly Operating Repcrt - March A

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April 1997 W I

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• - OPERATING DATA REPORT

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UNIT NAME Millstone Unit 1 DATE 4/2/97 COMPLETED BY d.~Newburgh TELEPHONE (866)~444 ~ ~ J 5730 OPERATING STATUS

1. Docket Number 50-245.,_ _ _ _._

2. Reporting Period March 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): 67,0 ,

6. 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, _ ___ _ _ , . _ , _ _ _

~~

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16'Poweilevel TEW'hicii R'eitricteci~lf aily (NetliWe): 0 ~

11. Reasons For Restrictions, if Any: _ Regulatory RestrictioniT6CFR565If)~ _

~ _ . - _ _ . _ _ ~ . _ . . _ . _ _ _

This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 744.0 2160.0 230160.0

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 Og _,_,_._ 932

17. Gross Thermal Energy Generated (MWH) _0.0_ 0.0 31_4_'372827.0_

18. Grose Electrical Energy Generated (MWH) .. 0.0, _ _0.0_ 105938737.0

19. Net Electrical Energy Generated (MWH) -2340.0 -6842.0 _101036707.0,

20. Unit Service Factor 0.0 0.0 72.4

21. Unit Availability Factor 0.0 0.0 72.4

22. Unit Capacity Factor (Using MDC Net) -0.5 -0.5 67.1

23. Unit Capacity Factor (Using DER Net) -0.5 -0.5 66.5

24. Unit Forced Outage Rate 100.0 100.0 16.7

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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b UNIT SHUTDOWNS AND POWER REDUCTIONS' '

DOCKET NO. 50-245 "

UNIT NAME Millstone Unit 1 -

DATE: 4/2/97 ,

COMPLETED BY G. Newburah -

TELEPHONE (8601-444-5730 REPORT MONTH: March 1997 No. Date Type' Duration Reason

• Method of License System Cause & Corrective Compnent (Hours) Shutting Event Code' Code- Action to 3

Down Reactor Report # Prevent Recurrence

[95-100 951213 .F 744 D 4 N/A 10CFR50.54f 2 3

' 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 - Regulatery Restriction 4 -Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0) 5 F - Administrative 6 - 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" i

,=- .

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245' UNIT: Millstone Unit 1 DATE: 4/2/97 COMPLETED BY: G. Newburah TELEPHONE: (860)444-5730 MONTH: Mars h.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 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 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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L REFUELING INFORMATION REQUEST I

w Name of the facility: Millstone Unit 1 1.

2. Scheduled date for next refueling outage: Current refuelina outaae started i ' November 1995. Next refuelina outaae date to be determined.~

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3. Scheduled date for restart following refueling: To be determined i .

l 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.

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

i 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

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 nurnber of fuel assemblies:

Present Capacity: Maximum 3229 fuel assembly locations

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

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

,