B16469, Monthly Operating Rept for Apr 1997 for Millstone Nuclear Power Station,Unit 1

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

ML20141E277
Person / Time
Site:	Millstone
Issue date:	04/30/1997
From:	Hinnenkamp P, Newburgh G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16469, NUDOCS 9705200389
Download: ML20141E277 (6)

Text

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Hope Ferry Rd. (Houte 156), Waterford, CT 06385 Nohad '

jh NuclearEnergy wai.., wear ro.,r siation Nortwant Nuricar Energy Company P.O. Ibx 128 Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444-4277 The Northeast l'tilities System MAY I 41997 Docket No. 50-245 B16469 U.S. Muclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. OPR-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 April 1997.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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Paul Hinnentaifip' Director, Unit Operations Attachments (1) ,

cc: Dr. W. D. Travers, Director, Special Projects I !

H. J. Miller, Region i Administrator S. Dembek, NRC Project Manager, Millstone Unit No.1 /

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T. A. Eastick, Senior Resident inspector, Millstone Unit No.1

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Docket No. 50-245 !

B16469 4'.

i Attachment 1 Millstone Unit No.1

- Facility Operating License No. DPR-21 Monthly Operating Report - April i

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1 May 1997 {

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• 8 OPERATING DATA REPORT - ,

UNIT NAME Millstone Unit 1 DATE 5/5757 4 . COMPLETED BY G.'Newburgh ~ ~

TELEPHONE i860A. i4 5730_ -

E OPERATING STATUS  ;

1,' Docket Number . 50-245 )

2/ Reporting Period ,Aprit 1997_ _

' Notes: 7

3. Udlity Contact G. Newburgh ,

4; UcensedTherrnalPower(MWt): ~ ~ ~ ~2011' ~~

5. Nameplate Rating (Gross MWe): 662

' 6, Design Electrical Rating (Net MWe): 660  :

< -7, Maximum Dependable Capacity (Gross MWe):

__670 t ,

8. Maximum Dependable Capacity (Nat MWe): 641  !

9. -if Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, l Give Reasons:.

i N/A .

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10. Power Level To Which Restricted, if any (Net MWe): 0

11. Reasons For Restrictions,if Any: __ Regulatory RestrictisidOCFR50'.[Sif)[~))))' _, _____ ,

- - - - . ~ . . - . - - . . . - - . - . - . . . - - - - ~ . . - . ~ . . . . - . - - . . - . - . - - - -  ;

_ _ - _ _ . - _ . . . - . . . . . _ _ - _ . - - _ _ ~ . . _ ~ _ _. - ..._ -..- - __... _ - -- - - -- -  !

This Month Yr.-To-Date Cumulative

13. Hours in Reporting Period .

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719.0 2879.0 230879.0 .

13. Number Of Hours Reactor Was Critical 0.0 0.0 ~~ -170529.9 I

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14. Reactor Reserve Shutdowti Hours ~~~~00 "'~~'.~0'

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0 328f.5' i

15. Hours Generator On-Line 00 ~ ~0.0 ~i 66560.7'

16. Unit Reserve Shutdown Hours ] ] ] ] 0l0' ~ ][05

, ((]l]531

17. Gross Thermal Energy Generated (MWH) _ __ _0 0_ __0 0, 31437_2827.0

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

105938737.0 ~

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19. Not Electrical Energy Generated (MWH) ~ 7 055

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2 0 ~ 788975 ~~~10'i634552 1 J

20. Unit Service Factor 00 DTd 72T

31. Unit Availability Fac'or. ~~~~ - ~~00 ~~ ~~ IO 0 ~ ~ ~~T2.Y I

22. Unit Capacity Factor (Using MDC Net) -0.5 0.5 66.9  !

23. Unit Capacity Factor (Using DER Net) [ ~ ~ ] 0[4l -(5l 100.0

] ] 63 17.0 I

24. Unit Forced Outage Rate . 100.0

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

Shutdown at time of this report

~~~~~ ibnetermined~~ ~

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26]f Ust SIutidn~5t Eiid"Of RepsiPeri6d,"EiiiinateliDimiioi Startup: T

27. Units in Test Status (Prior to Commercial Operation): l Forecast Achieved i INITIAL CRITICALITY N/A N/A  !

INITIAL ELECTRICITY N/A N/ ~~ !

t. COMMERCIAL OPERATION N/A._ _'

N/A I

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UNIT SHUTDOWNS AND POWER REDUCTIONS

• DOCKET NO.' 50-245 Date: 5/6/97 UNIT NAME Millstone Unit 1 ,

COMPLETED BY G. Newburah TELEPHONE (8601-444-5730 REPORT MONTH: April,1997 No. Date Type' Duration Reason' Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code' Action to Down Reactor' Report # Prevent Recurrence 95-10P 951213 F 719 D 4 N/A 10CFR50.54f 3

' 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)

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"

4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245 UNIT: Millstone Unit 1 DATE: 5/6/97 COMPLETED BY: G. Newburah TELEPHONE: (860)444-5730 MONTH: April.1997 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 0 21 0 6 0 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 0 29 0 14 0 30 0 15 0 31 N/A 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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REFUELING INFORMATION RECUEST l

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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 change or other license amendment?

Yes however the entire scope is to be determined.

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

None at this time

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:

184 GE-11 fuela_ssemblies

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 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 fuel pool full. core offload capacity is reached