ML20058P714

Monthly Operating Rept for Sept 1993 for Millstone,Unit 2.W/

ML20058P714
Person / Time
Site:	Millstone
Issue date:	09/30/1993
From:	Doboe S, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-93-813, NUDOCS 9310250179
Download: ML20058P714 (5)

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October 15, 1993 MP-93-813 Re:

10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk i

LTashington, D. C. 20555

Reference:

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

Dear Sir:

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

experience relating to Millstone Unit 2 for the month of September 1993, 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 FOR: Stephen E. Scace Vice President - Millstone Station 1

L BY: Harry F'.

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Director - $Qp one Un t SES/sid cc: T. T. Martin, Region I Administrator G. S. Vissing, NRC 1roj ect Manager, Millstone Unit No. 2 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1,263 990:93 9310250179 930930 f?

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REFUELING INFORMATION REOUEST-g 1.

fame of facility: ' Millstone 2 2.

' Scheduled date for next refueling shutdown:

June 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 i

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 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) 784 NOTE: These numbers represent the total Fuel Asse nblies and Consol-i idated Fuel Storace Boxes (3 total - contailina 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:

Current 1v 1237.

A license amendment has been submitted to the NRC to increase the spent fuel cool storace capacity to 1306 storace locations.

9.

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

1994. Spent Fuel Pool Full, Core Off Load capacity is reachsd.

1998, Core Full, Spent Fuel Pool Full.

r OPERATING DATA REPORT UNIT NAME Millstone Unit 2 DATE 10/06/93-COMPLETED BY S.Doboe TELEPHONE (203) 447-1791

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EXT' 4678 OPERATING STATUS

1. Docket Number 50-336

2. Reporting Period September 1993_

Notes: Items 22 and 23

3. Utility Contact -

S. Doboe cumulative are weighted

4. Licensed Thermal Power (MWt):

2700 avemges. Unit operated

5. Nameplate Rating (Gross MWe):

909 at 2C63 MWTH prior to its

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

7. Maximum Dependable Capacity (Gms A We):

903.10 2700 MWTH power level.

8.

Maximum Dependable Capacity (Net ruve):

873.10

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 l

11. Reasons For Restrictions, if Any:

N/A i

i This Month Yr.-To-Date Cumulative t

12. Hours in Reporting Period 720.0 6551 155735.0 13 Number Of Hours Reactor Was Critical 337.2 5687.1 110944.7 j

14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

15. Hours Generator On-Line 336.8 5494.0 105851.4

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2 17, Gross Thermal Energy Generated (MWH) 902578.0 14422646.0 272404350.4

18. Gross Electrical Energy Generated (MWH) 300410.0 4810306.0 89214613.5

19. Net Electrical Energy Generated (MWH) 283537.0 4623385.0 85574261.3

20. Unit Service Factor 46.8 83.9 68.0

21. Unit Availability Factor 46.8 83.9 68.3

22. Unit Capacity Factor (Using MDC Net) 45.1 80.8 64.4

23. Unit Capacity Factor (Using DER Net) 45.3 81.1 63.3

24. Unit Forced Outage Rate 53.2 12.0 15.3

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

None

26. If Unit Shutdown At End Of Report Period, Estimated Date of Startup:

N/A

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

Forecast Acheived INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A i

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AVERAGE DAILY UNIT POWER LEVEL '

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1 DOCKET NO. 50-336

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UNIT Millstone Unit 2 DATE 10/06/93 j

COMPLETED BY S. Doboe TELEPHONE (203)447-1791 EXT 4678 1

MONTH: SEPTEMBER 1993 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 866 17 0

2 867 18 0

t 3

867 19 0

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4 868 20 0

5 868 21 0

6 868 22 0

7 868 23 0

8 865 24 0

9 868 25 0

10 869 26 0

11 870 27 0

12 870 28 0

13 869 29 0

14 000 30 0

15 0

31 16 0

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.

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UNIT SHtlTDOWNS AND POWER REDUCTIONS DOCIET NO.

50-336 UNIT NAME Millstone Unit 2 DATE 10/06/93 COMPLETED BY S.Doboe TELEPHONE (203) 447-1791 REPORT MONTH September 1993 EXT 4678 No.

Date Type $

Duration Reason 2 Method of License System Component Cause & Corrective (Hours)

Shutting Event Code d Code 5-Action to Down Reactor a Report #

Prevent Recurrence 8

930914 F

383.2 F

1 93-015 SJ V

On 9/14/93 at 1915, with the plant at 100% power, a reportability determination was made conceming 4 motor operated valves (MOVs) in the feedwater system. A review of industry experience of MOVs with motor brakes in a -

reduced voltage condition determined the valves to be inoperable. The unit immediately commenced an orderly reactor shutdown. See LER.

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 Reduction 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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