ML20133M612

Monthly Operating Rept for Dec 1996 for Yankee Haddam Neck Plant

ML20133M612
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1996
From:	Emmons K, Laplatney J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9701220455
Download: ML20133M612 (7)

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 January 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 U. S. Nuclear Regulatory Commission I)ocument 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 96-12 covering operations for the period December 1,1996 to December 31,1996 is hereby forwarded.

l Very truly yours,

,e z, b'r ere J. LaPlatney )

Nuclear, Unit Director lladdam Neck Station JJilbom cc: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission 475 Allendale Road j King of Prussia. PA 19406 1

(2) William J. Raymond Sr. Resident inspector Connecticut Yankee

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9701220455 961231 5 PDR ADOCK 05000213 '

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Connecticut Yankee Atomic Power Company

( Iladdam Neck Plant Iladdam, Connecticut l

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Monthly Operating Report No. 96-12 For The Month of' i

December 1996 I

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l 11 tnt Operatine Summary The fbliowing is the Summary of Plant Operations for December,1996:

On December 1,1996, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was defueled, starting day 16 of decomissioning. ;

This plant remained in this situtation for the month of December.

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NRC OPERATING STATUS REPORT Haddam Neck l

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1. Docket 50 213

2. Reporting Period: 12/96 Outage + On-line Hours: 744.0 + 0.0 = 744.0

3. Utility Contacts K.W. Emmons (203) 267 3654

4. Licensed Thermal Power (MWt): 1825

5. Name' plate Rating (Gross MWels 667 x 0.9 600.3 )

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6. Design Electrical Rating (Net MWe): 582

7. Maximum Dependable Capacity (Gross MWe): 586.9

8. Maximum Dependable capacity (Net MWe): 560.1

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

10. Power level to which restricted, if any (Net MWe): N/A

11. Reasons for restriction, if any N/A MONTH YEAR-TO-DATE CUMULATIVE

. 1 944,o 8,784.0 254,232.0  ;

'32. Report period hours: l f

0.0 4,895.3 199,493.6

13. Hours reactor critical: l i

0.0 0.0 g 1,285.0

14. Reactor reserve shutdown hours:

0.0 4,893.5 193,539.4

15. Hours generator on-line

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0.0 0.0 398.0

16. Unit reserve shutdown hours:

0.0 8.754,617.0 335,551,124.0 *

17. Cross thermal energy generated (MWtH):

0.0 2,906,956.0 110,009,804.0 *

18. Gross electrical energy generated (MWeH):

2,763,062.0 104,514,523.5 *

19. Net electrical energy generated (MWeH): -1,678.5 0.0 55.7 76.1

20. Unit service fae: ors ]

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71. Unit availability factor 0.0 55.7 76.3 l I

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22. Unit capacity f actor using MDC net: 0.0 56.2 74.5 23.' Unit capacity factor using DER net: 0.0 54.0 10.6 0.0 16.4 6.4

24. Unit forced outage rate:

l 0.0 961.5 13,330.0

25. Forced outage hours:

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

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

• Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of commercial operation. 01/01/68).

I AVERAGE DAILY POWER LEVEL Docket No: 50-213 Unit: Haddam Neck Date: 1/2/97 Completed by: K.W. Emmons ,

Month: Dec-96 Telephone: (203)267-3654  !

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AVERAGE POWER LEVEL AVERAGE POWER LEVEL  ;

DAf (MWe-Net) DAY (MWe-Net) 1 0 17 0 1

2 0 18 0 3 0 19 0 4 i

I 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 1

13 0 29 0 1 14 0 30 0 15 0 31 0 i

16 0

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.t LINIT SHUTDOWNS AND POWER REDUCTIONS * .

DOCKET NO. 50-213 .

UNIT NAME Haddam Neck - l  !

i DATE 01/01/97 COMPLETED BY K.W. Emmons - -

TELEPHONE 1860) 267-3654 REPORT MONTH: December.1996 j 2

No. Date Type' Duration Reason Method of License System Component Cause & Corrective f (Hours) Shutting Event Code' Code' Actiori to  !

Down Reactor

• Report # Prevent Recurrence f I

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96-05 10/01/96 S 744 F 4 N/A N/A N/A Decommissioning plan continued ,

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'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) 'lEEE Standard 803A-1983,  :

G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in l Power Plants and Related Facilities - Component Function Identifiers" l 1

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BEFUELING INFORMATION REQUEST December 1996

1. Name of the facility: Haddam Neck

2. Scheduled date for next refueling outage: No date

3. Scheduled date for restart following refueling: No date

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

n/a (b) If answer is yes, what, in general, will these be?

DLa l (c) If answer is no, has the reload fuel design and core configuration been l aviewed by your Plant Safety Review Committee to determine if any unreviewed safety questions are associated with the core reload?

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

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

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6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis l 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 pool:

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

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 i number of fuel assemblies: l Present storage caoacity: 1480 i

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

! fuel pool assuming present license capacity:

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