B16321, Monthly Operating Rept for Feb 1997 for Millstone Nuclear Power Station,Unit 1

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Monthly Operating Rept for Feb 1997 for Millstone Nuclear Power Station,Unit 1
ML20136J523
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/28/1997
From: Hinnenkamp P, Newburgh G
NORTHEAST NUCLEAR ENERGY CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16321, NUDOCS 9703200131
Download: ML20136J523 (6)


Text

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  • e b Northeast Roge fem Rd (House 156h Watnford Cm385

/)h NuclearEnergy suistone Nm tear ro er staiion Northeet Nuclear Energy Cornpany P.O. Ibn 123 Waterford LT 0o385 0128 <

(860) 447-1791 Fax (860) 444-4277 1he Northeast I tibties Systern MAR I i 1997 l

Docket No. 50-245 i B16321 I l

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

Millstone Nuclear Power Station, Unit No.1 l 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 February,1997.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Paul Hinnenkamp U Director - Unit Operations i Millstone Unit No.1 Attachments (1) f cc: Dr. W. D. Travers, Director, Special Projects g H. J. Miller, Region I Administrator ,

S. Dembek, NRC Project Manager, Millstone Unit No.1 17[Od T. A. Eastick, Senior Resident inspector, Millstone Unit No.1 ./

9703200131 970229 PDR ADOCK 05000245 R PDR m 200042

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Docket No. 50-245 l B16321 4

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j Attachment i 1

Millstone Unit No.1 i

j Facility Operating License No. DPR-21 4

Monthly Operating Report - February i ,

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i March 1997

l I, OPERATING DATA REPORT l 1

UNIT NAME Millstone Unit 1

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DATE 3i5'i97~

COMPLETED BY G. Newburgh TELEPHONE (860}ddd~573'd- )

I OPERATING STATUS 1 Docket Number 50-245 l

2. Reporting Period February 1997 Notes:
3. Utility Contact G. Newburgh _
4. Licensed Thermal Power (MWt): 2011
5. Nameplate RLting (Gross MWe): 662 j
6. Design Electrical Rating (Net MWe): 660  !
7. Maximum Dependable Capacity (Gross MWe): 670 'I
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 _

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1'd~ Power LeveiTo Which RestrictEi.'ifany (Net M9Ve): 0

11. Reasons For Restrictions,if Any: Regulatory Restriction (I6CFR5075df)

This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 672.0 1416.0 229416.0-
13. Number Of Hours Reactor Was Critical 0.0 0.0 170529.9
14. Reactor Reserve Shutdown Hours _ 0.0 0.0_ 3_283.3_
15. Hours Generator On-Line 0.0 0.0 166560.7
16. Unit Reserve Shutdown Hours 0.0 0.0 93.7

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17. Gross Thermal Energy Generated (MWH) 6[.0' [ - ~ ~ 0.0~ y4f7)527]O'
18. Gross Electrical Energy Genenit)d (MWH) _ _ 0_.0_ _ _ _ 0.0 10593873_7.0_
19. Net Electrical Energy Gene ated st@M4) _ -2126 O_ _ -4502_.0 101039047.0_
20. Unit Service Factor 0.0 0.0 72.6
21. Unit Availability Factor 0.0 0.0 72.6
22. Unit Capacity Fac'or (Using MDC Net) -0. 5_

__ -0.5_ 67.3_

23. Unit Capacity Facte (Using DER Net) _-0.5

. _ _-_ 0. 5 66.9

24. Unit Forced Outage Date 100.0 100.0 16.3
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

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-245 - t UNIT NAME Millstone Unit'1 DATE 3/5/97 l COMPLETED BY G. Newburoh TELEPHONE (860)-444-5730 j REPORT MONTH: February 1997 No. Date Type' Duration ' Reason

  • Method of License System Comp'onent Cause & Corrective (Hours) Shutting Event Code' Code Action to Down Reactor Report # Prevent Recurrence i

95-10N 951213 F 672 D 4 N/A 10CFR50.54f i

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' F: Forced Reason

  • Method
  • IEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices i 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" l E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)  ;

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 i Facilities - Component Function Identifiers"  ;

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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245 UNIT: Millstone Unit 1

DATE
3/5/97 1 4

COMPLETED BY: G. Newburah l TELEPHONE: (860)444-5730 MONTH: February 1997 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL

, (MWe-Net) (MWe-Net) l 1

. 1 0 17 0 '

i 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 N/A 14 0 30 N/A 15 0 31 N/A 16 0 INSTRUCTIONS i

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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r f REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit 1 i
2. Scheduled date for next refueling outage: Current refuelina outaae started November 1995. Next refuelino outaae date to be determined.

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3. Scheduled date for restart following refueling
To be determined i
4. Will refueling or resumption of operation thereafter require a technical specification i 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 f 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 l 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 l
in licensed storage capacity that has been requested or is planned, in number of i fuel assemblies

Present Capacity: Maximum 3229 fuel assembly locations i

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

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

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