B17461, Monthly Operating Rept for Dec 1998 for Millstone Nuclear Plant,Unit 3.With

Monthly Operating Rept for Dec 1998 for Millstone Nuclear Plant,Unit 3.With

ML20199K842
Person / Time
Site:	Millstone
Issue date:	12/31/1998
From:	Brothers M, Emmons K NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17461, NUDOCS 9901270050
Download: ML20199K842 (5)

Text

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• # [Y Northeast - Rage Feny Rd. (Rate 156), Toedord, CT 06385

$ NuclearEnergy  % Noaear Po stat;oo l Northeast Nudear Energy company P.O. Box 128 Tatedord, CT 06385-0128 (860) 447 1791 Faz (860) 444-4277 l

The Nrthout Utilities sy. tem f

JAN I 51999 Docket No. 50-423  ;

517461 i

U.S. Nuclear Regulatory Commission i Attention: Document Control Desk  :

Washington, D.C. 20555 l

Millstone Nuclear Power Station Unit No. 3 i Facility Operating License Number NPF-49 Monthly Operatina Report for December 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 i month of December 1998.  !

I There are no regulatory commitments contained within this letter, j Should you have any questions regarding this submittal, please contact Mr. David Smith at (860) 437-5840.

i Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

/1IN

• M. H. Brothers "

Vice President - Operations cc: H. J. Miller, Region 1 Administrator A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 l

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, 9901270050 981231 PDR ADOCK 05000423 R PDR O"['d U .1 v OM422-5 RTL t2 05 i

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i Docket No. 50-423 B17461 I

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

Facility Operating License No. NPF-49 i December 1998 Monthly Operating Report 3 I

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January 1999 i

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. . '. U.S. Nuclear Regulatory Commission  !

. B17461%ttachment ihge 1 :  !

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REFUELING INFORMATION REQUEST f December 1998 l i

. 1. Name of the facility: Millstone Unit 3  !

2. Scheduled date for next refueling outage: May 1.1999  !

3. Scheduled date for restart following refueling: June 15.1999 f

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

Fui Core ff ad. Cvele 7 Reload

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

Full Core Offload - 01/99. Cycle 7 Reload - 3/99. )

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6. Important licensing considerations associated with refueling, e.g., new or i different fuel design or supplier, unreviewed design or performance analysis  !

methods, significant changes in fuel design, new operating procedures: l None. l 1

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage l pool: l in Core: (a) .193 in Spent Fuel Pool: (b) dlfi i

8. . The present I; censed 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: l Present storaae caoacitv: 756.  !

increase in licensed storaae caoacity olanned for total of 1860 locations.

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

End of Cvcle 7.

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. U.S. Nuclear Reguletory Commission  :

. 817461%ttachment 1Pege 2  ;

i AVERAGE DAILY UNIT POWER LEVEL  !

DOCKET NO.: 50-423 i UNIT: Millstone Unit 3  !

DATE: 1/1/99  !

COMPLETED BY: K.W. Emmons i TELEPHONE: (860) 447-1791 {

Ext. 6572  !

MONTH: Doc-98  !

DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (

(MWe-Net) (MWe-Net) 1  !!56 17 0 I 2 1151 18 0 3- 1155 19 0 i 4 1154 20 0

)

5 1153 21 0 )

6 1154 22 0 7 1153 23 0 8 1154 24 0

9. I157 25 0 10 1152 26 0 11 386 27 0 l 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 i 16 0 1

l INSTRUCTIONS 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.

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• U.$. Nuclear Regulatory Comm' sion B17461%ttachment 1Page 3

'1 OPERATING DATA REPORT UNIT NAME: Millstone Unit 3 DATE: 1/01/99

< COMPLETED BY: K. W. Emmons '

TELEPHONE: (860)447-1791 Ext 6572 I

OPERATING STATUS l

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- 1. Docket Number : 50-423

2. Reporting Period Dec-98 Notes:

3. Utility Contact K. W. Emmons

4. Ucensed Thermal Power (MWt): 3411

5. Nameplate Rating IGross MWe): 1253MW

6. Design Electrical Rating (Net MWe): 1153.6

7. Maximum Dependable Capacity (Gross MWe): 1184.2

8. Maximum Dependable Capacity (Net MWe): 1137.0

9. If Changes Occur in Capacity Ratings (ltems 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 744.0 8760.0 111264.0 13 Number Of Hours Reactor Was Critical 283.3 3665.2 70745.3

14. Reactor Reserve Shutdown Hours .0 39.2 6565.0

15. Hours Generator On-Line 253.6 3403.7 69316.1  ;

16. Unit Reserve Shutdown Hours 0.0 0.0 0.0

17. Gross Thermal Energy Generated (MWH) 857010.0 10475068.0 227412796.1

18. Gross Electrical Energy Generated (MWH) 299535.0 3586671.0 78491774.1 j

19. Not Electrical Energy Generated (MWH) 273154.1 3305900.8 74544210.1

20. Unit Service Factor 34.1 38.9 62.3

21. Unit Availability Factor 34.1 38.9 62.3

22. Unit Capacity Factor (Using MDC Net) 32.3 33.2 58.9

23. Unit Capacity Factor (Using DER Net) 31.8 32.7 58.1 j

. 24. Unit Forced Outage Rate 65.9 61.0 30.9 l

25. Unit Forced Outage Hours 490.4 5329.6 31055.7 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Refueling RFO 6 5/01/99 45 days

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

28. Units in Test Status (Prior to Commercial Operation): j Forecast Achieved INITIAL CRITICALITY N/A ,

N/A INITIAL ELECTRICITY N/.A N/A COMMERCIAL OPERATION N/A N/A

U.S. Nuclear Regulatory Commission s '*

B17461%ttachment 1 Pope 4 UNIT SHUTDOWNS AND POWER REDUCTIONS  ;

DOCKET NO.: 50-423 t UNIT NAME: Mdistone Unit 3 DATE: 01-01-99 COMPLETED BY: K. W. Emmons

• TELEPHONE: (860) 447-1791 X6572  !

REPORT MONTH: December 1998 No. Date Type' Duration Reason

• Method of License System Component Cause & Corrective '

(Hours) Shutting Event Code

• Code' Action to  :

Down Reactor

• Report # Prevent Recurrence  ;

98-10 12-11-98 F 490.4 A 3 9845 SB SV/PSV Automatic reactor trip due to "A" MSIV closing during routine i performance of part stroke testing.

Valve closed due to a crack in the solenoid valve disc. Replaced solenoid. *

'F: Forced

• Reason ' Method 'IEEE Standard 805-1984, ,

S: Scheduled A - Eouipment Failure (Explain) 1 - Manual " Recommended Practices B - Maintenance or Test 2 - Manual Scram for System Identification in  !

C - Ref ueling 3 - Automatic Scram Nuclear Power Plants and  !

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

F - Administrative 6 - Other (Explain) *lEEE Standard 803A-1983, G - Operational Error (Explain)

• Recommended Practices H - Other (Explain) for Unique identification in  ;

Power Plants and Related Facilities - Component Function Identifiers" f

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