ML20132B986

Monthly Operating Rept for Nov 1996 for Connecticut Yankee Haddam Neck Plant

ML20132B986
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/30/1996
From:	Emmons K, Laplatney J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9612180058
Download: ML20132B986 (7)

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s a CONNECTICUT YANKEE ATOMIC POWER COMPANY l

HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMFrON. CT 06424-3099 December 15,1996 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 lladdam Neck Plant Monthly Operating Report 96-11 covering operations for the period November 1,1996 to November 30,1996 is hereby forwarded.

Very truly yours, 7-

/0 N7 ere J. LaPla y Nuclear, Unit Director Haddam Neck Station JJL/bom 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 9612180058 961130 PDR ADOCK 05000213

'fh' R PDR 1028-3 REV 2-01

Connecticut Yankee Atomic Power Company lladdam Neck Plant Iladdam, Connecticut t

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Monthly Operating Report No. 96-11 For The Month of November 1996

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Plant Operatine Surnmary TFe following.is the Summary of Plant Operations for November,1996:

On November 1,1996, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was in Mode 6, Cold Shutdown, starting day 77 of I the Refueling and Maintenance Outage 19. l i

On November 13,1996 at 0033 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, the reactor core defueling commenced. 1 On November 15,1996 at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br /> defueling the reactor core was completed and the plant has remained defueled for the month of November.

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l NRC OPERATING STAWS REPORT l Haddam Neck

1. Docket 50-213

2. Reporting Period 11/96 Outage + On-line Hours: 720.0 + 0,0 = 720.0

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

4. Licensed Thermal Power (MWt): 1825

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

6. Design Electrical Rating (Net HWel s 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 ares 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 CUMUIATIVE l l

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12. Report period hours: 720.0 8,040.0 253,488.0 1

13. Hours reactor critical: 0.0 4,895.3 199,493.6 ,

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

15. Hours generator on-line 0.0 4.893.5 193,539.4 i

16. Unit reserve shutdown hours: 0.0 0.0 398.0

17. Gross thermal energy generated (MWtH): 0.0 8,754,617.0 335,551,124.0 *

18. Gross electrical energy generated (MWeH): 0.0 2,906,956.0 110,009,804.0

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19. Net electrical energy generated (MWeH): -1,866.3 2,764,740.4 104,516,202.0

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20. Unit service factor 0.0 60.9 76.4

21. Unit availability factor 0.0 60.9 76.5

22. Unit capacity factor using MDC net 0.0 61.4 74.7

23. Unit capacity factor using DER net 0.0 59.1 70.9

24. Unit forced outage rate: 0.0 16.4 6.4

25. Forced outage hours: 0.0 961.5 13,330.0 l

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

27. If currently shutdown, estimated startup dater 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).

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AVERAGE DAILY POWER LEVEL l I

i Docket No: 50-213

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Unit Haddam Neck l Date: 12/1/96 i Completed by: K.W. Emmons Month: Nov-96 Telephone: (203)267-3654 I

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4 AVERAGE POWER LEVEL AVERAGE POWER LEVEL I DM (MWe-Net) DM (MWe-Net) .;

1 0 17 0  ;

2 0 18 0 3 0 19 0 4 0 20. 0- .

5 0 21 0 1 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 l 15 0 31 l 16 0 4

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

UNIT NAME Haddam Neck -

DATE 12/01/96 COMPLETED BY K.W. Emmons ,

TELEPHONE (8601 267-3654 -

REPORT MONTH: November.1996 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 10/01/96 S 720 C 4 N/A AC RCT Core XIX Refueling and Maintenance Outage 2

'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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• i REFUELING INFORMATION REQUEST l November 1998

1. Name of the facility: Haddam Neck

2. Scheduled date for next refueling outage: No scheduled date

3. Scheduled date for restart following refueling: No scheduled date

4. (a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? l' Yes (b) If answer is yes, what, in general, will these be?

Amendments to sunoort soecif'c design changes  !

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

unreviewed safety questions are associated with the core reload? j n/a j i

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

DLB '

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

Per schedule established with cro.iect manager

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:

None

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 number of fuel assemblies:

Present storage caoacitv: 1480

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

2007