B16527, Monthly Operating Rept for May 1997 for Millstone Nuclear Power Station Unit 1

Monthly Operating Rept for May 1997 for Millstone Nuclear Power Station Unit 1

ML20148K671
Person / Time
Site:	Millstone
Issue date:	05/31/1997
From:	Hinnenkamp P, Newburgh G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16527, NUDOCS 9706180295
Download: ML20148K671 (5)

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llope Ferry 11d. (Itoute 156), Waterford, Cr 06385 Nuclear Energy staiuoo, Nocicar power stat- l 7 , Northeast Nuclear Energy Company P.O. Ibx 128 l Taterford, Cr 06385-0128 l (860) 447-1791 Fax (860) 444-4277 The Northemat l:tilities System I

JUN I O 1997 Docket No. 50-245 B16527 i

l 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 Monthly Operating Report in accordance with the reporting requirements of Technical Specification Section 6.9.1.6 for Millstone Unit No.1, enclosed is the monthly operating report for the month of May 1997.

l Very truly yours,

! NORTHEAST NUCLEAR ENERGY COMPANY l m id Paul HinnenR5m'p.Q q Director- Unit Operations v Millstone Unit No.1 V i Attachments (1) .

cc: Dr. W. D. Travers, Director, Special Projects l H. J. Miller, Region i Administrator I S. Dembek. NRC Project Manager, Millstone Unit No.1 l

T. A. Easlick Senior Resident inspector, Millstone Unit No.1 I

f 9706180295 970531 e

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! Docket No. 50-245 l B16527 <

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l Attachment 1 I I

Millstone Unit No.1  !

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Facility Operating License No. DPR-21  !

Monthly Operating Report - May  ;

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June 1997 1

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. OPERATING DATA REPORT UNIT NAME Millstone _U_ _ nit._1__

COMPLETED BY G. Newburgh TELEPHONE (860)444-5730 OPERATING STATU.S .

1. Docket Number 50-245

2. Reporting Period lVla[1997 ' Notes: 3

3. Utility Contact G. Newburgh l

4. Licensed Thermal Power (MWt): [ ~2011 l }

5. Nameplate Rating (Gross MWe): 662 i *

6. Design Electrical Rating (Net MWe): 660 -

7. Maximum Dependable Capacity (Gross MWe): ~~676  ;

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8. Maximum Dependable Capacity (Net MWe): ~

641

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9. If Changes Occur in Capacity Ratings (items Number 4 ThrougE85 Sinc'eilst'R'brt, e Give Reasons:

-.WA - _ . - - - - - - - - - . - -.-- - - . - _ . _ j

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10'. PowerEe6iTiWhicEResiricied,~ifiny (Neislihe): ~ ~

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11. Reasons For Restrictions,if Any: _ Regulatory Restrictioy1'OCFR50.5if)))~~ ___ [{~ ,

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This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period ~

744.0 3623.0 231623.0 l l 13. Number Of Hours Reactor Was Critical 0.0 ~~00 T"/6525~6 I

14. Reactor Reserve Shutdown Hours

15. Hours Generator On-Line

~~[ _ _ ((0[0_ 0_0 0.0 0.0

~]328' Y.3[

166560.7

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16. Unit Reserve Shutdown Hours ~0.0 93.Y i

17. Gross Thermal Energy Generated (MWH) - - ~0.0~ ~~60 ~3 Af758ff6 ~

18. Gross Electrical Energy Generated (MWH) ~0 10~ --~~ TO 0 ~T6f938V5f6 :

19. Net Electrical Energy Generated (MWH) -2022.0 -10919.0 101032630.0, l

20. Unit Service Factor ~

0.0 -

0.0 71.9

! 21. Unit Availability Factor 66 04 7f6 i i 22. Unit Capacity Factor (Using MDC Net) -0.4 -0.5 66.7 ,

l 23. Unit Capacity Factor (Using DER Net) -0.4 -0.5 66.1 l

24. Unit Forced Outage Rate 100.0 _ , _ _

100.0 _ 17.3_  ;

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

l Shutdown at time of this report ._ _ _ _ _ _ _ _ _ __ .,_

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26. If Unit Shutdown At End Of Report . . _ Period,

. . . _ Estimated

_ _ _ _ Date

_ _ -of_Startup:

__. _ _ _ _ . _ _ . _ . . _ . _ _ _ - . . _ . _ _ .To be de;

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

Forecast Acnhved INITIAL CRITICALITY N/A N/A l

lNITIAL ELECTRICITY COMMERCIAL OPERATION

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N/A

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UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 50-245 '.

UNIT NAME Millstone Unit 1 .

COMPLETED BY G. Newburah TELEPHONE (8601-444-5730 REPORT MONTH: May,1997 No. Date Type' Duration Reason' Method of License System Compnent Cause & Corrective (Hours) Shutting Event Code' Code Action to Down Reactor' Report # Prevent Recurrence 95-100 951213 F 744 D 4 N/A 10CFR50.54f 2 *

' F: Forced Reason

• Method IEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices B - Mainteneance 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) 5 F - Administrative 6 - Other (Explain) IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in i Power Plants and Related Facilities - Component Function identifiers"

AVERAGE DAILY UNIT POWER LEVEL l DOCKET NO: 50-245 l UNIT: Millstone Unit 1 DATE: 6/4/97 COMPLETED BY: G. Newburah j TELEPHONE: (860)444-5730 i

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MONTH: Mav.1997 l

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 1

4 0 20 0 l l 5 0 21 0 6 0 22 0 i 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 0 29 0 14 0 30 0 15 0 31 0 16 0 INSTRUCTIONS l 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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. REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit 1

2. Scheduled date for next refueling outage: Current refuelina outaae started November 1995. Next refuelina outaae date to be determined.

3. Scheduled date for restart following refueling. To be determined

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

Yes. however the ent5 scope is to be determined.

5. Scheduled date(t, ' submitting licensing action and supporting information:

Nona at this time

6. Important liceasing 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:

184 GE-11 fuel assemblies

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

In Core: (a) 0 in Spent Fuel Pool: (b) 3068 Unconsolidated

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 Capacity: 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:

1998/1999. spent fue; poo! full. core offload capacity is reached l