B17545, Monthly Operating Rept for Oct 1998 for Mnps,Unit 1.With

Monthly Operating Rept for Oct 1998 for Mnps,Unit 1.With

ML20195F485
Person / Time
Site:	Millstone
Issue date:	10/31/1998
From:	Harkness E, Newburgh G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17545, NUDOCS 9811200008
Download: ML20195F485 (6)

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,. . .' Northeast nop. rerry aa. (nooi. is6), w.terrera, er 06383 uc ear EnN Miti ton. Nuclear Power station Northcaat Nudcar Energy Company P.O. Box 128 Waterrord, CT 06385-0128 (860) 447 1791 Fax (860) 444 4277 The Northeast Utilities System l kAf -7 W Docket No. 50-245 l B17545 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 Operatina Report 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 October 1998.

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

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY C A E. HarSsll, Director - Unit Operations

' Attachments (1) cc: H. J. Miller, Region I Administrator c S. Dembek, NRC Project Manager, Millstone Unit No.1 L T. A. Easlick, Senior Resident inspector, Millstone Unit No.1 i L. L. Wheeler, Senior Project Manager Q g l .  : J ;".13

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Docket No. 50-245 B17545 l

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Attachment 1

. Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. DPR-21 Monthly Operating Report - October 1998 i

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p November 1998

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U.S. Nuclear Regulatory Commission l B17545.%ttachment 1\Page 1 l

l REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit 1

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

3. Scheduled date for restart following refueling: N/A 4

! 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

6. Important licensing considerations associated with refueling, e.g., new or different l fuel design or supplier, unreviewed design or performance analysis methods, 1 significant changes in fuel design, new operating procedures: N/A i

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 l 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:

Present Caoacity: Maximum 3229 fuel assembly locations

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

l N B. D. Kenyon letter to U. S. Nuclear Regulatwy 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.

. , U.S. Nucle:r Regul:t:ry Commission B17545%ttachment 1\P:g3 2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245 '

UNIT: Millstone Unit l DATE: 11/05/98 COMPLETED BY: G. Newburah TELEPHONE: (860)444-5730 MONTH: October 1998 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 _ O 21 0 6 _ O 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 _ O 29 0 14 0 30 0 15 0 31 0 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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. U,'S. Nuclier R:gulltory Commission B17545%ttachmsnt 1\Prg3 3 DOCKET NO.: 50-245 UNIT NAME: Millstone Unit 1 DATE: 11/5/98 COMPLETED BY: G. Newburgh TELEPHONE: (8601444 5730 OPERATING STATUS l 1. . Docket Number 50 245 f 2. Reporting Period October 1998 Notes:

• Change to Eastem .

3. Utility Contact. G. Newburgh Standard Time  !

4. Licensed Thermal Power (MWt): 2011 l 5. Nameplate Rating (Gross MWe): 662

, .6. Design Electr! cal Rating (Net MWe): 660 l l 7. Maximum Dependable Capacity (Gross MWe): 670

8. Maximum Dependable Capacity (Net MWe): 641

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): 0

11. Reasons For Restrictions, if Any: Permanently ceased operations and certifications submitted to the NRC in accordance with 10CFR50.82 l I I

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! I This Month Yr.-To-Da'e Cumulative 1

12. Hours in Reporting Period . *745 72960 244056.0

13. Number Of Hours Reactor Was Critical 0.0 0.0 170529.9 i

14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3

15. Hours Generator On-Line 0.0 0.0 166560.7

16. Unit Reserve Shutdown Hours 0.0 0.0 93.7 l 17. Gross Thermal Energy Generated (MWH) 0.0 0.0 314372827.0 l 18. Gross Electrical Energy Generated (MWH) 0.0 0.0 105938737.0

19.- Net Electrical Energy Generated (MWH) 2069.0 20090.0 100997636.0

20. Unit Service Factor 0.0 0.0 68.2

21. Unit Availability Factor 0.0 0.0 68.2

. 22. Unit Capacity Factor (Using MDC Net) -0.4 0.4 63.4

23. Unit Capacity Factor (Using DER Net) -0.4 -0.4 62.7 l 24. Unit Forced Outage Rate 100.0 100.0 22.1 L 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 l o 27. Units in Test Status (Prior to Commercial Operatic n):

Forecast Achieved INITIAL CRITICALITY N/A N/A IN; TIA'. ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A 1

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4 U.S. Nuclear Regulatory Commission -

B17545%ttachment 1\Page 4 , ,

UNIT SHUTDOWNS AND POWER REDUCTIONS '

DOCKET NO.: 50-245 UNIT NAME: Millstone Unit 1 COMPLETED BY: G. Newburah TELEPHONE. (860)444-5730 REPORT MONTH: October 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 95-10HH 951213 S 745 F 4 N/A 10CFR50.82(a)(1)(il 10CFR50.82:a)(1)(ii) 2

' 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 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) ' 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

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