ML20044C939

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

ML20044C939
Person / Time
Site:	Millstone
Issue date:	04/30/1993
From:	Doboe S, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-93-389, NUDOCS 9305140145
Download: ML20044C939 (5)

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(203) 665-5000 a e u..m waa w May 10, 1993 MP-93-389 Re:

10CFR50.71(a)

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

20555

Reference:

Facility Operating License No. DPR-55 Docket 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 April 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 COMPANX AS

1. L L.

Stephen E. Scace Vice ' resident - Millstone Station SES/rab 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

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9305140145 930430

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OPERATING DATA REPORT i

UNIT NAME Millstone Unit 2

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DATE 5/04/93 COMPLETED BY S. Doboe l

TELEPHONE (203) 447-1791 l

EXT 4678 i

OPERATING STATUS 1.

Docket Number:

50-336 Notes: Items 22 and 23 l

2.

Reporting Period:

April 1993 cumulative are weighted 3.

Utility

Contact:

S. Doboe averages. Unit operated 4.

Licensed Thermal Power (MWt):

2700 at 2560 MWTH prior to its l

S.

Nameplate Rating (Gross MWe):

909 uprating to the current 6.

Design Electrical Rating (Net MWe):

870 2700 MWTH power level, i

7.

Maximum Dependable Capacity (Gross MWe):

903.10 8.

Maximum Dependable Capacity (Net *fWe):

873.10 9.

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

N/A

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

N/A

11. Reasons For Restrictions, If Any:

N/A I

This Month Yr.-To-Date Cumulative

12. Hours In Reporting Period 719.0 2879.0 132063.0

[

13. Number Of Hours Reactor Was Critical 719.0 2613.8 107871.4

-14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

15. Hours Generator On-Line 719.0 2503.7 102861.1 y

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2 t

17. Gross Thermal Energy Generated (MWH) 1870993.0 6421532.0 264403236.4

18. Gross Electrical Energy Generated (MWH)

_.5?6044.5 2141920.5 86546228.0 l

19. Net Electrical Energy Generated (MWH) f43950.5 2058690.5 83009566.8

20. Unit Service Factor 100.0 87.0 67.6

21. Unit Availability Factor 100.0 87.0 68.0

22. Unit Capacity Factor (Using MDC Net) 96.2 81.9 64.0 l

23. Unit Capacity Factor (Using DER Net) 96.6 82.2 62.9

24. Unit Forced Outage Rate 0.0 2.5 15.2

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

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 Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l

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F y

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AVERAGE DAILY UNIT POWER LEVEL

~

DOCKET NO.

50-336 UNIT:

Millstone Unit 2 DATE:

5/04/93 l

COMPLETED BY:

S. Dodoe TELEPHONE:

(203) 447-1791 l

EXT:

4678 l

MONTH:

APRIL 1993 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)

(MWe-Net) l 1

676 17 876 2

876 18 876

[

3 876 19 876 4

876 20 876 i

5 873 21 877 6

446 22 877 i

7 381 23 877 8

730 24 877 i

i 9

874 25 877 10 876 26 876 r

11 877 27 876 i

f 12 877 28 860 13 87' 29 877 J

14 877 30 877 l

15 877 31 16 877 l

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each 1

day in the reporting month.

Compute to the nearest whole megawatt.

j i

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4

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DOCKET NO.

50-336 o

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 5/04/93

+

COMPLETED BY S. Doboe _

TELEPHONE (203) 447-1791 REPORT MONTil APRIL 1993 EXT.

4678 l

2 No.

Date Type Duration Reason Method of Licensee Systym Compgnent Cause & Corrective (Hours)

Shutting Event Code' Code Action to 3

Down Reactor Report #

Prevent Recurrence 1

930406 1

0 A

5 N/A N/A N/A On 4/5/93., a tube leak in the 4A feedwater heater was identified.

On 4/6/93, the unit was reduced to approximately 50% power to isolate the effected heater string. The unit was returned to 100% power on 4/8/93.

2 3

0 I: Forced Reason:

Method IEEE Standard 805-1983, F

5: Scheduled A-Equipment Failure (Explain) 1-Manual

" Recommended Practices for B-Maintenance or Test 2-Manual Scram System Identification in C-Refueling 3-Automatic Scram Nuclear Power Plants and i

D-Regulatory Restriction 4-Continued from Related Facilities" E-Operator Training & License Examination Previous month F-Administrative 5-Power Reduction S lEEE Standard 803A-1983, G-Operational Error (Explain)

(Duration -0)

" Recommended Practice for H-Other (Explain) 6-Other (Explain)

Unique Identification in Power Plants and Related Facilities - Component Function Identifiers" m..-

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l REFUELING INFORMATION REOUEST 1.

Name of facility:

Millstone 2 i

I 2.

Scheduled date for next refueling shutdown:

July 1994-1 3.

Scheduled date for restart following refueling:

N/A I

3 4.

Will refueling or resumption of operation thereafter require a j

4 technical specification change or other license amendment?

i I

None at this time i

r 5.

Scheduled date(s) for submitting licensing action and supporting l

information:

i None at this time j

i i

i i

6.

Important licensing considerations associated with refueling, e.g.,

I new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fual design, i

new operating procedures:

None J

7.

The number of fuel assemblies (a) in the core and (b) in the spent i

fuel storage pool:

In Core:

(a) 217 In Spent Fuel Pool:

(b) 784 l

NOTE: These numbers represent the total Fuel Assemblies and Consol-idated Fuel Storace Boxes (3 total - containina the fuel rods 2

i from 6 fuel assemblies) in these two (2) Item Control Areas.

1 8.

The present licensed spent fuel pool storage capacity and the size j

of any increase in licensed stcrage capacity that has been requested or is planned, in numLar of fuel assemblies.

Currently 1237 i

9.

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

j 1994. Soent Fuel Pool Full. Core Off Load capacity is reached.

l l

1998. Core Full. Spent Fuel Pool Full.

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4 a

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3 1

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