B16241, Monthly Operating Rept for Jan 1997 for Millstone Nuclear Power Station Unit 2

Monthly Operating Rept for Jan 1997 for Millstone Nuclear Power Station Unit 2

ML20138L831
Person / Time
Site:	Millstone
Issue date:	01/31/1997
From:	Doboe S, Price J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16241, NUDOCS 9702250116
Download: ML20138L831 (6)

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U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No DPR-65 Monthly 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 January 1997.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY J. A. Pri

/c l Directo illstone Unit No. 2 cc: H. J. Miller, Region 1 Administrator D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. Beaulieu, Acting Senior Resident inspector, Millstone Unit No. 2 Dr. W. D. Travers, Director, Special Projects Office 1

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1 Attachme.it 1  :

Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No. DPR-65 )

Monthly Operating Report l

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January 1997

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone Unit 2 DATE 2/5/97 COMPLETED BY S. Doboe TELEPHONE (860)447-1791 EXT 4678 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 0 )

10 _

O 26 0 t 11 0 27 O-12 0 28 0 13 ____0____ _

29 0 14 O__ 30 0 i _ _ , _ . _. _ _ _ _ _ _ _ _

i 15 0 31 0 16 _ . _ _

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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.

OPERATING DATA REPORT UNIT NAME Millstone Unit 2 DATE 02/05/97 COMPLETED BY S. Doboe TELEPHONE (860) 447-1791 EXT 4678 i

OPERATING STATUS I 1. Docket Number 50-336

2. Reporting Period January 1997 Notes: Items 22 and 23

3. Utility Contact S.Doboe culmulative are weighted J

4. Licensed Thermal Power (MWt): 2700 averages. Unit operated at

5. Nameplate Rating (Gross MWe): 909 2560 MWTH prior to its I

6. Design Electrical Rating (Net MWe): 870 uprating to its current i l

7. Maximum Dependable Capacity (Gross MWe): 901.63 2700 MWTH power level. l 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 _

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

11. Reasons For Restrictions, if Any; NRC Category ill Facility; NRC Confirmatory Order requiring implementation of an independent corrective action verification program; NRC order requiring a third-party review of the employee concerns program at Millstone 2; design basis verification response pursuant to 10CFR50.54(f).

l This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 744,0 744.0 184992.0  :

13. Number Of Hours Reactor Was Critical 0.0 0.0 121911.7

14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

15. Hours Generator On-Line 0.0 0.0 116611.9

16. Unit Reserve Shutdown Hours 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 .

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19. Net Electrical Energy Generated (MWH) -2283.0 -2283.0 94638900.4 l 20. Unit Service Factor 0.0 0.0 63.0 l L1. Unit Availability Factor ~

0.0 0.0 63.3 l l lt2. Unit Capacity Factor (Using MDC Net) ~

0.0 0.0 59.7 I l 23. Unit Capacity Factor (Using DER Net) 0.0 0.0 58.9

! 24. Unit Forced Outage Rate 100.0 100.0 19.7 l

25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):  !

Shutdown at_the ti,me of this_ report __

26. If Unit Shutdown At EnJ 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 l

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UNIT SHUTDOWNS AND POWER REDUCTIONS ,

DOCKET NO. 50-336 .

1. T NAME - Millstone Unit 2 DATE 02/05/97 COMPLETED BY S. Doboe -

TELEPHONE (860) 447-1791 EXT 4678 REPORT MONTH: January 1997 No. Date Type' Duration Reason' Method of License System Component Cause & Corrective (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 mid cycle surveillance testing from previous year.

Forced: Continued from previous year. NRC Category lli facility; NRC Confirmatory Order requiring independent corrective action verification: NRC order requiring third party review of Millstone Station employee concems program; design basis verification for reoonse to NRC pursuant to 10CRF50.54(f).

'F: Forced Reason Method "IEEE Standard 805-1984, 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

, D - Regulatory Restriction 4 - Contint.ed from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)

F - Administrative 6 - Other (ExpMin) 'IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique ider.tification in Power Plants and Related Facilities - Component Function Identifiers"

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REFUELING INFORMATION REQUESTfPRIVATE 1

1. Name of the facility: Millstone Unit 2

2. Scheduled date for next refueling outage: To Be Determined I Scheduled date for restart following refueling: To Be Determined 3.

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

To Be Determined

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

To Be Determined

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, ur. reviewed design or performance analysis a methods, significant changes in fuel design, new operating procedures:

To Be Determined

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

In Core: (a) JJ__ in Spent Fuel Pool: (b) 990 NOTE: These numbers represent the total Fuel Assemblies and Consolidated FueLSlorace Boxes (3 total corttainina the fuel rods from 6 fuel assemblies) in these two (2) Item Control Areas.

The core was beina offloaded from 1/28/97 to 2/2/97. The above numbers renresent the fuel assembly locations at 2359 on 1/31/97.

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

.P_wsent storaae capacity: 1306 storaae locations

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

i 2000, Soent Fuel Pool Full. Core offload capacity is reached.

2004, Core Full, Soent Fuel Pool Full. l j