ML20058K258

Monthly Operating Rept for Nov 1993 for Millstone Unit 2.W/

ML20058K258
Person / Time
Site:	Millstone
Issue date:	11/30/1993
From:	Doboe S, Miller D NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-93-972, NUDOCS 9312150020
Download: ML20058K258 (5)

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[ NORTHEAST UTILITIES cenerai onices . semen street. Benin. connecticut

~ P.O. BOX 270 HARTFORD. CONNECTICUT 06141-0270 k k J 2.<=Y((,,7U w .n n r.

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. (203) 665-5000 December 10,'1993 MP-93-972 i Re: 10CFR50.71(a) 4 U.S. Nuclear Regulatory Commission Document Control Desk 4 Washington, D. C. 20555 i

Reference:

Facility Operating License No. DPR-65 .

Docket No. 50-336  ;

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Dear Sir:

This letter is forwarded to provide the report of operating and shutdown experience  !

relating to Millstone Unit 2 for the month of November 1993, in accordance with Appendix A Technical Specifications, Section 6.9.1.6. One additional copy of the report is enclosed.

Very truly yours, t

NORTHEAST NUCLEAR ENERGY COMP NY .

D. B. Miller, Jr. l Senior Vice President - Millstone Station  ;

SES/sid  ;

cc: T. T. Martin, Region i Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 $

P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1, 2 & 3 l (hl 15000"'

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• OPERATING DATA REPORT l UNIT NAME Millstone Unit 2 DATE 12/03/93  !

I COMPLETED BY S. Doboe TELEPHONE (203)447-1791 i EXT 4678 OPERATING S7ATUS g i

1. Docket Number 50-336 L Reporting Period November 1993 Notes: ltems 22 and 23

3. Utility Contact S.Doboe cumulative are weighted

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

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

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

7. Maximum Dependable Capacity (Gross MWe): _

903.10 2700 MWTH power level. ,

8. Maximum Dependable Capacity (Net MWe): 873.10 i

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): N/A

11. Reasons For Restrictions, if Any: N/A This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 720.0 8016 157200.0 $

13 Number Of Hours Reactor Was Critical 720.0 6945.9 112203.5

14. Reactor Reserve Shutdown Hours 0.0 0.0 -2205.5

15. Hours Generator On-Line 704.0 6713.3 107070.7

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2- !

17. Gross Thermal Energy Generated (MWH) 1848160.0 17626688.0 275608392.4 l

18. Gross Electrical Energy Generated (MWH) 616672.5 5880025.5 90284333.0

19. Net Electrical Energy Generated (MWH) 594556.5 5651266.5 86602142.8. '

20. Unit Service Factor 97.8 83.7 68.1'

21. Unit Availability Factor 97.8 83 1 68.4 l

22. Unit Capacity Factor (Using MDC Net) 94.6 80.7 64.5

23. Unit Capacity Factor (Using DER Net) 94.9 81.0 63.5

24. Unit Forced Outage Rate 0.0 12.7 15.3

25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): None

26. If Unit ShWtown At End Of Report Period, Estimated Date of Startup: N/A

27. Units in Test Status (Prior to Commercial Operation):

Forecast Acheived j INITIAL CRITICALITY N/A N/A  ;

INITIAL ELECTRICITY N/A N/A l COMMERCIAL OPERATION N/A N/A  !

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'. AVERAGE DAILY UNIT POWER LEVEL i DOCKET NO. 50-336 UNIT Millstone Unit 2 I DATE 12/03/93 1 COMPLETED BY S. Doboe TELEPHONE (2031447-1791 EXT 4678 MONTH: NOVEMBER 1993 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 856 17 877 2 814 18 873 3 826 19 874 4 832 20 100 5 836 21 480 6 842 22 869 7 874 23 875 8 875 24 876 9 875 25 875 10 876 26 874 11 875 27 876 12 876 28 876 13 876 29 850 14 877 30 846 15 872 31 16 877 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each i day in the reporting month. Compute to the nearest whole megawatt.

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t l- UNIT SHUTDOWNS AND POWER REDUCTIONS . .

l DOCKET NO. 50-336 l' UNIT NAME Mdtstone Unit 2 .

l DATE 12/03/93

! COMPLETED BY S.Doboe TELEPHONE (203)447-1791 REPORT MONTH November 1993 EXT 4678 .

t No. Date Type i Duration Reason 2 Method of License System Component Cause & Corrective (Hours) Shutting Event Code

• Code s Action to Down Reactor a Report # Prevent Recurrence 9 931120 F 0 B 5 N/A TG CAB On 11/20/93 at 0100 the unit 4 downpowered to 10% for Electro-Hydraulic Control system maintenance and repair. The unit was returned to 100%

power on 11/22/93.

1 F: Forced 2 Reason 3 Method 4 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 Related Facilities" E -Operator Training & License Examination Previous Month F -Administrative 5 -Power R 3 duction 5 IEEE Standard 803A-1983, G -Operational Error (Explain) (Duration - 0) " Recommended Practices H -Other (Explain) 6 -Other (Explain) for Unique Identification in Power Plants and Related Facilities Component Function Identifiers

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REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2  ;

2. Scheduled date for next refueling shutdown: Juiv 1994

3. Scheduled date for restart following refueling: N/A i

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

change or other license amendment?

None at this time  !

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:

None j i

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

f in Core: (a) 217 in Spent Fuel Pool: (b) 784 NOTE: These numbers represent the total Fuel Assemblies and Consolidated Fuel i Storaae Boxes (3 total - containina the fuel rods from 6 fuel assemblies) in these two f 12Litem Control Areas. ,

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:

Cungntiv 1237. A license amendment has been submitted to the NRC to increase l the soent fuel o001 storaae caoacity to 1306 storace locations.  ;

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

-1994, Soent Fuel Pool Full, Core Off Load caoacity is reached.

1998. Core Full, Soent Fuel Pool Full.

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