ML20063G180

Monthly Operating Rept for Jan 1994 for Millstone Unit 2.W/

ML20063G180
Person / Time
Site:	Millstone
Issue date:	01/31/1994
From:	Doboe S, Miller D NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-94-111, NUDOCS 9402150353
Download: ML20063G180 (5)

Text

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l General Offices

• Selden Street. Berkn. Connecticut I P.O. Box 270 72$U,$[U7E.,,, H ARTFORD. CONNECTICUT 06141-0270 k k U w.w wu ,% um . (203) 665-5000 '

February 10, 1994 DON ALD B, MILLER, Jr. MP-94-111.

SENIOR VICE PRESIDENT. MILLSTONE Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk 1 Washington, D. C. 20555 c

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336

Dear Sir:

sc "

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

relating to Millstone Unit 2 for the month of January 1994, in accordance.with!

Appendix A Technical Specifications, Section 6.9.1.6. One additional copy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY u

m D.

lMiller, Jr.

0 Senior Vice President - Millstone Station DBM/sid ,

cc: T. T. Martin, Region 1 Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 .

P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1; 2 & 3 aonn m 9402150353 940131 I" .

PDR ADOCK 05000336 -

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone Unit 2 DATE 2/02/94-l COMPLETED BY S. Doboe .

TELEPHONE (203) 447-1791  ;

EXT 4678  ;

MONTH: JANUARY 1994 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL '

(MWe-Net) (MWe-Net) 1 877 17 830 2 876 18 830 3 876 19 832 4 876 20 873 5 876 21 875 ;l 6 875 22 876 I 7 875 23 876 8 876 24 877 9 875 25 877 10 875 26 875' 11 847 27 875 1 i

12 844 28 -876 13 845 29 876 14 843 30 ~ 875 15 842 31 875 16 837 INSTRUCTIONS -l l

1 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.

I

V OPERATifdG DATA REPORT

. UNIT NAME Millstone Unit 2 DATE 2/02/94 _

COMPLETED BY S. Doboe __,

T ELEPHONE (203)447-1791 EXT 4678 OPE _ RATING STATUS _

1. Docket Number 50-336

2. Reporting Period January 1994 Notes: ftems 22 and 23

3. Utility Contact S.Doboo cumulative are weighted

4. Licensed Thermal Power (MWt): _, 2700 _

cverages. Unit operated

5. Nameplate Rating (Gross MWe): 909 __

< t 2560 MWTH prior to its

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

7. Maximum Dependable Capacity (Gross MW #: 903.10 2700 MWTH power level.

B. Maximum Dependable Capacity (Net MWe): 873.10

9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons:

.. . ..N / A _ _ _ _ _ _ _ _ _ _ , _ _ _ _ . _ , _ _ _ _ _ _

~ ~ ~ ' ~

10. PoweIL'evel ToijhicIIFI~esIUctid[If a3INet fAUc)I _ _ /A_

11. Reasons For Restrictions, if Any: _ _N/A _ _ _ _ , _ _ _ _ _ _ _ _ _

This Month Yr.-To Date Cumulative

12. Hours in Reporting Period 744.0 _

744.0, 158688.0 13 Number Of Hours Reactor Was Critical 744.0 744.0, 113691.5

14. Reactor Reserve Shutdown Hours _,0 0 0.0 2205.5

15. Hours Generator On-Line 744.0, _ 744.0_ 1')8558.7

16. Unit Reserve Shutdown Hours 0.0_ O.0 468.2

17. Gross Thermal Energy Generated (MWH) 1987044.0 1987044.0 279587197.4

18. Gross Electrical Enetgy Generated (MWH) 666477.0 666477.0 91618466.0

19. Net Electrical Energy Generated (MWH) 643434.0 643434.0 87890221.8

20. Unit Service Factor _.__ 100.0 100.0 68.4

21. Unit Availability Factor 100.0 100.0, 68.7

22. Unit Capacity Factor (Using MDC Net) 99.1 99.1 64.8 23 Unit Capacity Factor (Using DER Net) _

99.4 99.4 63.8

24. Unit Forced Outage Rate 0.0 0.0 15.1

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

None

' ~~

26'."~lfinit StIu~tio3riAtinTOTR3 ort Period, Estimated Date of Startup: N/A

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

Forecast Ache!ved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPER ATION N/A N/A _

l

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-336 UNIT NAME Millstone Unit DATE 2/02/94 COMPLETED BY S. Doboe TELEPHONE L203)-447-1791 EXT 4678 REPORT MONTH: January 1994 No. Date Type' Duration Reason 2 Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code' Action to Down Reactor' Report # Prevent Recurrence N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 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 j C - Refueling 3 - Automatic Scram Nuclear Power Plants and l D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0) i F - Administrative 6 - Other (Explain)

• IEEE Standard 803A-1983,

! G - Operational Error (Explain) " Recommended Practices i H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component h Function Identifiers" a

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, REFUELING INFORMATION REQUEST

1. Name of the facility: M.illstone Unit 2

2. Scheduled date for next refueling outage: July 1994

3. Scheduled date for restart following refueling: October 1994 i

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

specification change or other license amendment?

Yes. Modifications clanned to be imolemented durina the uncomina refuelina j nutaae will reauire license amendment chanaes orior to startuo. ,

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

Aoril 1994.

6. Important licensing considerations associated withrefueling, e.g., new or  ;

different fuel design or supplier, unreviewed design or performance analysis  :

methods, significant changes in fuel design, new operating procedures:

Same fuel sucolier. imnroved new fuel assembiv_desian oursuant to 10CFR50.59. .

.i

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

In Core: (a) in Spent Fuel Pool: 4 212 (b) 2f_4 NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storaae Boxes (3 total containina the fuel rods from 6 fuel assemblies) in these two (2) Item 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:

• Currentiv 1072 storace locations (without fuel consolidation). Licensed ,

caoacity is 1237 storane locations with fuel consolidation. A license amendment has been submitted to the NRC to increase the soent fuel cool y storace caoLcity to 1306 storaae locations.

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

1994. Scent Fuel Pool Full. Core offload caoacity is reached.

1998. Core Full. Soent Fuel Pool Full. .

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