ML20138K572

Monthly Operating Rept for Jan 1997 for Haddam Neck Plant.W/

ML20138K572
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/31/1997
From:	Emmons K, Laplatney J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9702190038
Download: ML20138K572 (7)

Text

' '

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 February 15,1997 Re: Technical 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 11addam Neck Plant Monthly Operating Report 97-01 covering operations for the period ,

j January 1,1997 to January 31,1997 is hereby forwarded.

1 J

Very truly yours, p ,k J Jere J. aPlatney Nuclear, Unit Director liaddam Neck Station JJ11bom cc: (1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2) William J. Raymond Sr. Resident Inspector ,

Connecticut Yankee ,y' l 9702190038 970131 PDR ADOCK 05000213 R rm 1028-3 NEV 2--91

Connecticut Yankee Atomic Power Company lladdam Neck Plant 11addam, Connecticut 1

W i

1 i

4 d

Monthly Operating Report No. 97-01 For The Month of January 1997

.*. l 1

i l

Plant Operatine Summarv i

The following is the Summary of Plant Operations for January,1997: )

On Jonuary 1,1997, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was defueled, starting day 47 of decomissioning. This plant remained in this situtation for the month of December.  ;

1 I

- -u- . - . . - _ . .

b .

?

i NRC OPERATING STATUS REPORT i Haddam Neck t

l 1 Docket: 50-213

2. Reporting Period 01/97 Outage + On-line Hours: 744.0 + 0.0 = 744.0

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

4. Licensed Thermal power 04Wt): 1825

5. Nameplate Rating (Gross MWe) : 667 x 0.9 = 600.3 ,

6. Design Electrical Rating (Net MWe) : 592 7 Maximum Dependable Capacity (Gross MWe) : 586.9

8. Maximum Dependable Capacity (Net MWe): 560.1 l

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

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

12. Report period hours: 744.0 744.0 254,976.0 6

13. Hours reactor critical: 0.0 0.0 199,493.6 -

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

i

15. Hours generator on-line: 0.0 0.0 193,539.4 i

16. Unit reserve shutdown hours: 744.0 744.0 1,790.0 5

17. Gross thermal energy generated DMdtH): 0.0 0.0 335,551,124.0

• 1

18. Gross electrical energy generated 04WeH) : 0.0 0.0 110,009,804.0

• 1

19. Net electrical ene gy generated OfWeH) : -1,733.1 -1,733.1 104,512,790.4 *

20. Unit service factor 0.0 0.0 75.9 e

21. Unit availability factor: 100.0 100.0 76.6

22. Unit capacity factor using MDC net 0.0 0.0 74.3 l-i

23. Unit capacity factor using DER net: t' O 0.0 70.4

24. Unit forced outage rate: 0.0 0.0 6.4  ;

k

25. Forced outage hours: 0.0 0.0 13,330.0

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

27. If currently shutdown, estimated startup date 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 i

- ~,

s AVERAGE DAILY POWER LEVEL

, Docket No: 50-213-Unit: Haddam Neck i

Date: 2/3/97 Completed by: K.W. Emmons l Month: Jan-97 Telephone: (203) 267-3654 l

4 AVERAGE POWER LEVEL AVERAGE POVER LEVEL

} DM (MWe-Net) DM (MWe-Net) i i 1 0 17 0 t

2 0 18 0 1 3 0 19 0 i.

9

) 4 0 20 0 5 0 21 0 b 6 0 22 0 5' 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

UNIT SHUTOOWNS AND POWER REDUCTIONS j

DOCKET NO. 50-213 UNIT NAME Haddam Necli DATE O2/01/97 COMPLETED BY K.W. Emmons TELEPHONE (860) 447-1791 X6572 REPORT MONTH: January 1997 2

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

• Action to Down Reactor Report # Prevent Recurrence 96-05 01/01/97 S 744 F 4 N/A N/A N/A Decommissioning plan continued 2

'F: Forced Reason Method *lEEE 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 Power Plants and Related Facilities - Component Function identifiers"

:a -

REFUELING INFORMATION REQUEST Januarv 1997

-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 (decommissbning)

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

nLa (b) If answer is yes, what, in general, will these be?

DLa (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 unreviewed safety questions are associated with the core reload?

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

DLa

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

nLa

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:

DLa

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 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 storage caoacitv: 1480 1

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

nLa