B17579, Monthly Operating Rept for Nov 1998 for Millstone Nuclear Power Station,Unit 1.With

Monthly Operating Rept for Nov 1998 for Millstone Nuclear Power Station,Unit 1.With

ML20197K162
Person / Time
Site:	Millstone
Issue date:	11/30/1998
From:	Harkness E, Newburgh G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17579, NUDOCS 9812160105
Download: ML20197K162 (6)

Text

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Northeast -. Roge Fury Rd. (Route W), Warfwd, Cr 06385

, Nucl:ar Energy Millstone Nuclear Power station Northeast Nuclear Energy Company P.O. Box 128 Waterford, Cr 06385-0128 (860) 447-1791 Fax (860) 444-4277

'Ibe Northeast Utilitice System DEC 8 1998 Docket Noc50-245 B17579 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. DPR-21 Monthlv Doeratina Reoort in accordance with the report requirements of Technical Specification Section 6.9.1.6 for Millstone Unit No.1, enclosed is the Monthly Operating Report for the month of November 1998.

Should you have any questions regarding this submittal, please contact Mr. Paul Willoughby at (860) 447-1791, Ext. 3655.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

<k E. Haru14ss, Director - Unit Operations ,

Attachments (1) cc: H. J. Miller, Region l Administrator L. L. Wheeler, NRC Project Manager, Millstone Unit No.1 ,

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. . . . J 9912160105 991130

• PDR ADOCK 05000245 R PH u 063422 5 REY.12-95

Docket No. 50-245 B17579 Attachment 1 Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. DPR-21 Monthly Operating Report - November 1998 L

December 1998

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l-U.S. Nucle:r Regulttory Commission B17579%ttachment 1\ Pag) 1 -

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, REFUELING INFORMATION REQUEST

1. Name'of the facility: Millstone Unit 1 l

2. Scheduled date for next refueling outage: Permanentiv ceased ooeration and certifications submitted to the NRC in accordance with 10CFR50.82.m ,

3. Scheduled date for restart following refueling: N/A

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

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

N/A l

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

In Core: (a) Q in Spent Fuel Pool: (b) 3068 Unconsolidated

8. The present licensed spent fuel pool storage capacity and the size of any increase in L licensed storage capacity that has been requested or is planned, in number of fuel f assemblies: I i' Present Canacity: Maximum 3229 fuel assembiv locations

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

d' B. D. Kenyon letter to U.S. Nuclear Regulatory Commission, " Millstone Nuclear Power

( Station, Unit No.1, Certification of Permanent Cessation of Power Operations and that Fuel has been Permanently Removed from the Reactor," dated July 21,1998.

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U.S. Nuclear Regulatory Commission B17579%ttachment 1\ Pag 3 2 i

I AVERAGE DAILY UNIT POWER LEVEL l .

DOCKET NO: 50-245

. UNIT: Millstone Unit 1 DATE: 12/03/98 COMPLETED BY: G. Newburah TELEPHONE: 1860)444-5730 l

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MONTH: November 1998 i I

DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL I (MWe-Net) (MWe-Net) i 1 0 17 0 )

2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0

, 6 0 22 0 7 0 23 _

O 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 N/A 16 0 INSTRUCTIONS On this format, list the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt, i

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• U.'S. Nucle r Reguiltory Commission L . B17579%ttachment 1\Page 3 I

, DOCKET NO: 50-245 UNIT NAME: Millstone Unit 1 DATE: 12/3/98 COMPLETED BY: G. Newburgh TELEPHONE: (8601444-5730 r

OPERAT!NG STATUS

1. Docket Number 50-245

2. Reporting Period November 1998

3. Utility Contact G. Newburgh

4. Licensed Thermal Power (MWt): 2011

5. Nameplate Rating (Gross MWe): 662

6. Design Electrical Rating (Not MWe): 660

7. Maximum Dependable Capacity (Gross MWe): 670

8. Maximum Dependable Capacity (Net MWe): 641

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

N/A

10. Power Level T9 Which Restricted, If any (Net M'Ne): 0

11. Reasons For hestrictions, if Any: Permanently ceased operations and certifications submitted to the NRC in accordance with 10CFR50.82 This Month Yr.-To-Date Cumulative

12. Hours In Reporting Period 720.0 8016.0 244776.0

13. Number Of Hours Reactor Was Critical 0.0 0.0 170529.9

14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3

15. Hours Generator On-Line 0.0 0.0 166560.7

10. Unit Reserve Shutdown Hours 0.0 0.0 93.7

17. Gross Thermal Energy Generated (MWH) 0.0 0.0 314372827.0

18. Gross Electrical Energy Generated (MWH) 0.0 0.0 105938737.0

19. Net Electrical Energy Generated (MWH) -1758.0 -21848.0 100i)95878.0

20. Unit Service Factor 0.0 0.0 68.0

21. Unit Availability Factor 0.0 0.0 68.1

22. Unit Capacity Factor (Using MDC Net) -0.4 -0.4 63.2

23. Unit Capacity Factor (Using DER Net) -0.4 -0.4 62.5

24. Unit Forced Outage Rate 100.0 100.0 22.3

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

Shutdown at time of this report

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

operations

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

! Forecast Achieved

! 'liJITIAL CRITICALITY N/A N/A l

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

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. U.S. Nuclear Regulatory Commission , . .

B17579%ttachment 1\Page 4 . ...

-l UNIT SHUTDOWNS AND POWER REDUCTIONS ,

DOCKET NO.: 50-245 UNIT NAME: Millstone Unit 1 ,

COMPLETED BY: G. Newburab TELEPHONE: (860) 444-5730 i

REPORT MONTH: November 1998 r

2 No. Date Type' Duration Reason Method of License System Component Cause & Co*rective *

(Hours) Shutting Event Code' Code' ' Action to Down Reactor 3 Report # Prevent Recurrence e

+

95-1011951213 S 720 F 4 N/A 10CFR50.82(a)(1)(i) 10CFR50.82(a)(1)(ii) i e

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3 3

• IEEE Standard 805-1984,

' F: Forced Reason Method S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices -

B - Maintenance or Test 2 - Manual Scram for Systera identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)  !

F - Administrative 6 - Other (Explain) ' IFimancard 803A-1983, G - Operational Error (Explain) ' Recommended Practices H - Other (Explain) for Unique identification in

• Power Mants and Related i Facilities - Component ,

Function identifiers" i

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