ML20140H524

Monthly Operating Rept for May 1997 for Haddam Neck Plant

ML20140H524
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/31/1997
From:	Emmons K, Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9706180300
Download: ML20140H524 (7)

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. CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 l

June 15,1997 Re: Technical Specification 6.9.1-8 .

Docket No. 50-213 1

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U. S. Nuclear Regulatory Commission  !

Document Control Desk  !

Washington, D. C. 20555 In accordance with reporting requirements of Technical Specif'ication 6.9.1.8, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 97-05 covering operations for the period  !

May 1,1997 to May 31,1997 is hereby forwarded.

Very truly yours, Russell A. Mellor Director of Site Operations and Decommissioning fladdam Neck Station RAM /bom v cc: (1) Regional Administrator, Region 1 -

U. S. Nuclear Regulatory Commission @V t 475 Allendale Road /

King of Prussia, PA 19406 (2) William J. Raymond

( Sr. Resident Inspector g k Connecticut Yankee 9706180300 970531 PDR ADOCK 05000213 R PDR l ms-a nev e--et  ; e Qft '

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l Connecticut Yankee Atomic Power Company i

lladdam Neck Plant lladdam, Connecticut 1 i

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Monthly Operating Report No. 97-05 I

For The Month of May 1997 i I

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s Plant Operatine Summag The following is the summary of Plant Operations fcr May,1997:

On May 1,1997, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was defueled, starting day 168 of decommissioning.

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

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, NRC OPERATING STATUS REPORT

( . Haddam Neck I .

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1. Docket: 50-213 l 2. Reporting Periods 05/97 Outage + On-line Hours 744.0 + 0.0 = 744.0

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

4. Licensed Thermal Power (MWC): 1825 f 6. Nameplate Rating (Gross MWe): 667 x 0.9 = 600.3

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

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

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8. Maximum Dependable Capacity (Net MWe): 560.1

p. If changes occur above since last report, reasons are NONE -

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

11. Reasons for restriction, if any: N/A F

MONTH YEAR-TO-DATE CUMULATIVE i

12. Report period hours: 744.0 3,621.0 257,855.0 i

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

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

15. Hours generator on-line 0.0 0.0 193,539.3

16. Unit reserve shutdown ho 744,0 3,623.0 4,669.0 i

17. Gross thermal energy generated (MWtH): 0.0 0.0 335,551,124.0 *

18. Gross electrical energy generated (fedeH) : C.0 0.0 110,009,804.0 *

19. Het electrical energy generated (MWeH)2 -1,306.5 -7,573.3 104.506,950.3 *

20. Unit service factor 0.0 0.0 75.1 1 I

21. Unit availability factor: 100.0 100.0 76.!

22. Unit capacity factor using MDC net 0.0 0.0 73,4

23. Unit capacity factor using DER net 0.0 0.0 69.6

24. Unit forced outage rate: 0.0 0.0 6.3

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

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

27. If currently shutdown, estimated startup dates N/A 8

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

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AVERAGE DAILY POWER LEVEL  !

l Docket No: 50-213  !

t Unit:- Haddam Neck l

r Date: 6/2/97 l Completed by: K.W. Emmons Month: May-97 Telephone: (860)447-1791 X6572 1

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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 f i

3 0 19 0 f 1

4 0 20 0 ,

5 0 21 0 1

6 0 22 0  !

1 7 0 23 0 l

8 0 24 0 9 0 25 0 10 0 26 0 ,

I 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 _

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REFUELING INFORMATION REQUEST '

I Mav1997 t

1. Name of the facility: Haddam Neck l l

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

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

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4. (a) Will refueling or resumption of operation thereafter require a technical  :

l specification change or other license amendment?  !

(b) If answer is yes, what, in general, will these be? l DID f i

(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?  ;

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

n/a l 5. Scheduled date(s) for submitting licensing action and supporting information: l l n/a ,

i 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: l DLE I

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

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: l Present storage caoacity: 1480

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

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 - * -

UNIT NAME Haddam Neck DATE 06/04/97 ,

COMPLETED BY K.W. Emmons TELEPHONE (860) 447-1791 X6572 REPORT MONTH: May 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 i

5 96-05 05/01/97 S 744 F 4 N/A N/A N/A Decommissioning plan ,

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'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) "IEEE Standard 803A-1983, I 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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