ML20141D414

Monthly Operating Rept for Apr 1997 for Connecticut Yankee Haddam Neck

ML20141D414
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/30/1997
From:	Emmons K, Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9705200099
Download: ML20141D414 (7)

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CONNECTICUT YANKEE ATOMIC POWER COMPANY l

HADDAM NECX PLANT 1 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 May 15,1997 Re: Technica: Specification 6.9.1-8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 97-04 covering operations for the period April 1,1997 to Apirl 30,1997 is hereby forwarded.

Very truly yours, r

Russdl A. Mellor

• Director of Site Operations

l. and Decommissioning IIaddam Neck Station RAM /bom cc: (1) Regional Administrator, Region 1 l U. S. Nuclear Regulatory Commission ,4 l 475 Allendale Road King of Prussia, PA 19406 j

! William J. Raymond (2)

Sr. Resident Inspector l Connecticut Yankee g 9705200099 970430 PDR ADOCK 05000213 R PDR VUUUuu

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r Connecticut Yankee Atomic Power Company lladdam Neck Plant Haddam, Connecticut i

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Monthly Operating Report No. 97-04 For The Month of April 1997

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l Plant Operatine Summary The following is the summary of Plant Operations for April,1997:

On April 1,1997, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was defueled, starting day 137 of decommissioning.

The plant remained in this condition for the remainder of the month.

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• NRC OPERATING STAWS REPORT j

Haddam Neck I i

- 1. Docket t 50-213.

2. Reporting Period 04/97 Outage + On-line Hours: 719.0 +

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0.0 = 719.0 j

{ '3. Utility Contacts K.W. Emmons (203) 267-3654 l

[ 4. Licensed Thermal Power (MWt): 1825 l

'5, Nameplate Rating (Cross MWe): 667 x 0.9 600.3 3

6. Design Electrical Rating (Net MWe): 582 l

-7. Maximum Dependable Capacity (Gross MWe): 586.9 i

8. Maximum Dependable Capacity (Not MWe): 560.1

9. If changes occur above since last report, reasons a 9: NONE '

l. 10. Power level to which restrictedi if any (Net MWelt N/ -  !

j, 11. Reasor.4 for restriction, if any: N/A i i I i McKrH YEAR-TO-DATE CUMULATIVE i

l- -12. Repos; period hours: 719.0 2,879.0 257,111.0

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13. Hours reactor critical

• 0.0 0.0 199,493.6

14. Reactor reserve shutdown hours: 0.0 0.0 1,285.0

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15. nours generator on-line

l. 0.0 0.0 193,539.3 4

16. Unit reserve shutdown houra s 719.0 2,879.0 3,925.0 l 17. Cross thermal energy generated (MWtW): 0.0 0.0 335,551,124.0

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18. Cross electrical energy generated (MWeH): 0.0 0.0 110,009,804.0

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'19. Net electrical energy generated (MWeHli 1,433.9 -6,266.8 104.508.256.7 *

20. Unit service f actors ' O.0 0.0 75.3 l

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21. Unit availabilaty factor 100.0 100.0 76.8

22. Unit capacity factor using MDC net 0.0 0.0 13.6 l

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[ 23. Unit capacity factor using DER nett 0.0 0.0 69.8 l

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24. Unit forced outage rate: 0.0 0.0 6.3 l

25. Forced outage hours: 0.0 0.0 12,970.0 i

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26. Shutdowns scheduled over next 6 months (type,date, duration): NONE 4

i. 27. If currently shutdown, estimated startup date N/A i

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J Cumalative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of

commercial operation, 01/01/68).

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, AVERAGE DAILY POWER LEVEL i 1

i Docket No: 50-213 Unit: Haddam Neck Date: 5/1/97 .

Completed by: K.W. Emmons - I Month:- Apr-97 Telephone: (860)447-1791 X6572 l

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' AVERAGE POWER LEVEL AVERAGE POWER LEVEL  :

DM (MWe-Net) DM (MWe-Net) I 1 0 17 0 2 0 18 0 1 3 0 19 0 4 0 20 0  !

.5 0 21 0 ,

6 0 22 0 7' 0 23 0 8 0 24 0

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l 9 0 25 0

i. 10 0 26 0 l 11 0 27 0 l 12 0 28 0 13 0 29 0  :

14 0 30 0 i

15 0 31 i

[ 16- 0 i:

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UNIT SHUTDOWNS AND POWER REDUCTICNS '

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DOCKET NO. 50-213 ..

UNIT NAME Haddam Neck DATE 05/04/97 COMPLETED BY K.W. Emmons TELEPHONE (860) 447-1791 X6572 REPORT MONTH: Anril 1997

• 2 No. Date Type' Duration Reason Method of License System Component Cause & Corrective -

5 (Hours) Shutting Event Code' Code Action to Down Reactor Report # Prevent Recurrence 96-05 04/01/97 S 719 F 4 N/A N/A N/A Decommissioning plan continued

'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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. .. . u l REFUELING INF RMATION REQUEST '

l Aoril 1997 i f  ;

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1. Name of the facility: Haddam Neck

2. Scheduled date for next refueling outage: n/a (decommissioning)

3. Scheduled date for restart following refueling: n/a (decommissioning) ,

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

8 I l (b) If answer is yes, what, in general, will these be?

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(c) If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine if any ,

L unreviewed safety questions are associated with the core reload? l nLa 4

-(d) If no such review has taken place, when is it scheduled?

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 fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

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

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in Core: (a) Q In Spent Fuel Pool: (b) 1019 i

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 storage canacitv 1480

9. The projected date of the last refueling that can be discharged to the spent ,

i fuel pool assuming present license capacity: '

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