B16145, Monthly Operating Rept for Dec 1996 for Millstone Nuclear Power Station,Unit 2

Monthly Operating Rept for Dec 1996 for Millstone Nuclear Power Station,Unit 2

ML20133M217
Person / Time
Site:	Millstone
Issue date:	12/31/1996
From:	Price J, Stark S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16145, NUDOCS 9701220306
Download: ML20133M217 (6)

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' Utilities System snhea.: Unude. Smice com;>any P.O. Box 270 Ilanford, CT 06141-0270 (860) 665-5000 DAN ild iB97 Docket No. 50-336 B16145 i

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

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! Millstone Nuclear Power Station, Unit No. 2 .

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Facility Operating License No DPR-65' Monthly Operatina Report  ;

. In accordance with the reporting requirements of Technical Specification Section ,

i '6.9.1.7 for Millstone Unit No. 2, enclosed, in Attachment 1, is the monthly operating report for the month of December 1996.

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Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 4

t QT /N J. A. Prp' e' j Director \JAillstone Unit No. 2 43  ;

cc: H. J. Miller, Region i Administrator j

D. G. Mcdonald, Jr., NRC Project Manager, Millstone Unit No. 2 D. Beaulieu, Acting Senior Resident inspector, Millstone Unit No. 2 ff .

Dr. W. D. Travers, Director, Special Projects -

9701220306 961231 f PDR ADOCK 05000336 '

R PDR L 230.037 w._

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Docket No. 50-336 B16145

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Attachment 1 Millstone Nuclear Power Station, Unit No. 2

' Facility Operating License No. DPR-65 Monthly Operating Report i

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January 1997

. OPERATING DATA REPORT UNIT NAME Millstone Unit 2 DATE 01/03/97 COMPLETED BY S. Stark TELEPHONE (860) 447-1791 EXT 4419 OPERATING STATUS

1. Docket Number 50-336

2. Reporting Period December 1996 Notes: ltems 22 and 23

3. Utility Contact S. Stark culmulative are weighted

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

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

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

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

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

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

11. Reasons For Restrictions, if Any: NRC Category lli 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).

This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 744.0 8784.0 184248.0

13. Number Of Hours Reactor Was Critical 0.0 1223.6 121911.7

14. Reector Reserve Shutdown Hours 0.0 0.0 2205.5

15. Hours Generator On-Line 0.0 1222.1 116611.9

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2

17. Gross Thermal Energy Generated (MWH) 0.0 3240377.0 300862506.4

18. Gross Electrical Energy Generated (MWH) 0.0 1085422.5 98709460.0

19. Net Electrical Energy Generated (MWH) -2166.0 1021737.3 94641183.4

20. Unit Service Factor 0.0 13.9 63.3

21. Unit Availability Factor 0.0 13.9 63.5

22. Unit Capacity Factor (Using MDC Net) 0.0 13.4 60.0

23. Unit Capacity Factor (Using DER Net) 0.0 13.4 59.2

24. Unit Forced Outage Rate 100.0 85.7 19.3

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

Shutdown at the 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

AVERAGE DAILY UNIT POWER LEVEL I

DOCKET NO. 50-336 UNIT Millstone Unit 2 DATE 1/3/97 i COMPLETED BY S. Stark TELEPHONE (860)447-1791 l EXT 4419 t i

MONTH: December 1996 ,

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 i 7 0 23 0 8 0 24 0  ;

9 0 25 0 .

10 0 26 0 f 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0

. 15 0 31 0 16 0 INSTRUC'!ONS i

On this formatilist the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-336 * -

, UNIT NAME Millstone Unit 2 .

DATE 01/03/97 '

COMPLETED BY S. Stark TELEPHONE (860) 447-1791 EXT 4419 REPORT MONTH: December 1996 No. Date Type' Duration Reason

• Method of License System Component Cause & Corrective (Hours) Shutting Event Code

• Code' Action to Down Reactor' Report # Prevent Recurrence 96-04 03/07/96 S/F 744 B/D 4 N/A N/A N/A Scheduled: Continued mid cycle surveillance testing from previous month.

Forced: Continued from previous month. NRC Category lll facility; NRC Confirmatory Order requiring independent corrective action verification; NRC order requiring third party review of Millstone Station employee concerns program; design basis verification for response to NRC ursuant to 10CRF50.54(f).

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'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 - Continued from Previous Month Related Facilities" E - Operator Training & Ucense Examination 5 - Power Reduction (Duration = 0)

F - Administrative 6 - Other (Explain) "lEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers"

REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit'2

2. Scheduled date for next refueling outage: To Be Determined __

3. Scheduled date 1or restart following refueling: To Be Determined

4. Will refueling or resumption of operation thereafter require a technical ,

specification change or other license amendment? l To Be Determined ,

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

To Be Determined ,

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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:

To Be Determined  ;

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

in Core: (a) 217 In Spent Fuel Pool: (b) afS_

NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storaae Boxes (3 total eqatainina the fuel rods from 6 fuel assemblies) in than two (2) Item Control Areas. <

8. The present licensed spent fuel peol 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 storaae caoacitv: 1306 storaae locations

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

2000, Soent Fuel Pool Full, Core offload capacity is reached. I 2004, Core Full, Soent Fuel Pool Full. j 1

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