B17460, Monthly Operating Rept for Nov 1998 for Millstone Nuclear Power Station,Unit 3.With

Monthly Operating Rept for Nov 1998 for Millstone Nuclear Power Station,Unit 3.With

ML20198D235
Person / Time
Site:	Millstone
Issue date:	11/30/1998
From:	Emmons K, Mccracken D NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17460, NUDOCS 9812230042
Download: ML20198D235 (6)

Text

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N::rthe st R pe Ferry Rd. (Route 156), Tcterford, CT 06385 Nuclear Energy Mmstone Nuclear Power Station

• Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385 0128 (860) 447-1791 Fax (860) 444-4277

'ne Northeast Utihties System DEC l 51998 Docket No. 50-423 B17460 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Millstone Nuclear Power Station Unit No. 3 Facility Operating License Number NPF-49 Monthly Operatina Reoort for November 1998

.In accordance with the reporting requirements of Technical Specification 6.9.1.5 for Millstone Unit No. 3, enclosed in Attachment 1 is the Monthly Operating Report for the month of November 1998.

There are no regulatory commitments contained within this letter.

Should you have any questions regarding this submittal, please contact Mr. David Smith at (860) 437-5840.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: C. J. Schwarz Unit Director - Millstone Unit No. 3 BY:

Douglas S. McCracken

!M V I8 Assistant Unit Director - Millstone Unit No. 3 Attachments (2)

\ I cc: H. J. Miller, Region 1 Administrator E. V. Imbro, Director, Millstone ICAVP Inspections '

A. C. Corne, Senior Resident inspector, Millstone Unit No. 3 h['y J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 9812230042 981130 PDR T

R ADOCK 05000423:

PDR w o

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Docket No. 50-423 B17460 )

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l i Attachment 1 Millstone Nuclear Power Station, Unit No. 3 1 1

Facility Operating License No. NPF-49 November 1998 Monthly Operating Report l

I December 1998

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U.S. Nuclear Regulatory Commission B17460\ Attachment 1\P;g'21 REFUELING INFORMATION REQUEST November 1998

1. Name of the facility: Millstone Unit 3

2. Scheduled date for next refueling outage: May 15,1999

3. Scheduled date for restart following refueling: June 30,1999

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes - Full Core Offload Cycle 7 Reload.

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

Full Core Offload - 12/98. Cvele 7 Reload - 3/99.

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) 193 in Spent Fuel Pool: (b) .416

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:

EIesent storaoe caoacitv: 756.

Increase in licensed storaoe caoacity olanned for total of 1860 locations.

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

End of Cvcle 7.

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U.S. Nuclear Regulatory Commission B17460%ttachment 14' age 2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50423 UNIT: Millstone Unit 3 DATE: 12/2/98 COMPLETED BY: K.W. Emmons TELEPHONE: (860) 447-1791 Ext. 6572 MONTH: Nov-98 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 235 17 1154 2 408 18 1150 3 446 19 1152 4 487 20 1158 5 44 21 1152 6- 185 22 1154 7 656 23 1153 l l

8 795 24 1151 l

9 1045 25 1155 10 1153 26 1153 11 321 27 1153 12 0 28 1154 13 46 29 1156 14 352 30 1156 15 696 4

16 1138 i 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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' U.S. Nuclear Regulatory Commission B17460\ Attachment 1\Page 3 OPERATING DATA REPORT UNIT NAME: Millstone Unit 3 DATE: 12/02/98 COMPLETED BY: K. W. Emmons TELEPHONE: (860)447-1791 Ext 6572 OPERATING STATUS

1. Docket Number 50 423

2. Reporting Period Nov-98 Notes: 1

3. Utility Contact K. W. Emmons

4. Licensed Thermal Power (MWt): 3411

5. Nameplate Rating (Gross MWe): 1253MW

6. Design Electrical Rating (Net MWe): 1153.6

7. . Maximum Dependable Capacity (Gross MWe): 1184.2

8. Maximum DependatAe Capacity (Net MWe): 1137.0

9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons: l 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 8016.0 110520.0 13 Number Of Hours Reactor Was Critical 680.8 3381.9 70462.0

14. Reactor Reserve Shutdown Hours 39.2 39.2 6565.0

15. Hours Generator On-Line - 645.0 3150.1 69062.5

16. Unit Reserve Shutdown Hours 0.0 0.0 0.0

17. Gross Thermal Energy Generated (MWH) 1791172.0 9618058.0 226555786.1

18. Gross Electrical Energy Generated (MWH) 612129.0 3287136.0 78192239.1

19. Net Electrical Energy Generated (MWH) 578728.6 3032746.7 74271056.0

20. Unit Service Factor 89.6 39.3 62.5

21. Unit Availability Factor 89.6 39.3 62.5 l 22. Unit Capacity Factor (Using MDC Net) 70.7 33.3 59.0

23. Unit Capacity Factor (Using DER Net) 69.7 32.8 58.3

24. Unit Forced Outage Rate 10.4 60.6 30.7

25. Unit Forced Outage Hours 75.0 4839.2 30565.3 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Refueling RFO 6 5/15/99 45 days

27. If Currently Shutdown, Estimsted Date of Startup: N/A

28. Units in Tc.st Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICAUTY N/A N/A INITIAL ELECTRICITY N/A N/A

COMMERCIAL OPERATION N/A N/A t

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U.S. Nuclear Regulatory Commission gg B17460%ttachment 1Page 4 ,.'

~ UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.: 50-423 UNIT NAME: Mestone Unit 3 '

DATE: 12-02 COMPLETED BY: K. W. Emmons ,

TELEPHONE. IS60) 447-1791 X6572 REPORT MONTH: November 1998 No. Date Type' Duration Reason' Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code' Acton to

• i Down Reactor

• Report # - Prevent Recurrence 98-08 11-05-98 F 21 B 6 SJ HX Took plant off line to realign the feedwater system due to problems with feedwater.

heater level instabslites.

(Reactor remained critical) 98-09 11-11-98 F 54 H 2 SH COND Manual plant trip due to high differential between "A" and  ;

e ~B" waterboxes caused by storm condstens.

'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 Screm Nuclear Power Plants and '

D - Regulatory Restriction 4 - Continued from Previous Month Related Faceleties" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)

F - Administrative Other (Explain) 'IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in

• Power Plants and Related Facilities - Component Function Identifiers" 1

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