ML20128Q766

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

ML20128Q766
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/30/1996
From:	Emmons K, Laplatney J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9610210162
Download: ML20128Q766 (7)

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CONNECTICUT YANKEE AT O MIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3009 October 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 96-09 covering operations for the period September 1,1996 to September 30,1996 is hereby forwarded.

i Very truly yours,

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Jere J. LaPlatn Nuclear, Unit Director l IIaddam Neck Station l I

JJL/bom I cc: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission l 475 Allendale Road King of Prussia, PA 19406 (2) William J Raymond Sr. Resident inspector ,

Connecticut Yankee

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9610210162 960930 PDR ADOCK 05000213 R PDR 1020-3 REY t-01 210045  ;

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1 Plant Onerating Summarv ,

i The following is the Summary of Plant Operations for September,1996: l On September I,1996, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was in Mode 5, Cold Shutdown, starting the 16th  ;

day of the Refueling and Maintenance Outage 19. ,

The plant remained in Mode 5, Cold Shutdown for the month of September.

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Connecticut Yankee Atomic Power Company lladdam Neck Plant Haddam, Connecticut Monthly Operating Report No. 96-09 For The Month of September 1996

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NRC OPERATING STATUS REPORT Haddam Neck i

1. Dockets 50 213

< 2, Reporting Periods 09/96 Outage + On line Hours: 720.0 + 0.0 = 720,0 3, Utility Contact s K.W. Emmons (203) 267-3654 4, Licensed Thermal Power (MWt) 1825 ,

5. Nameplate Rating (Gross MWe) 667 x 0.9 e 600.3

. 6 Design Electrical Rating (Net MWe): 582

7. Maximum Dependable Capacity (Gross MWe): 586.9

8. Maximum Dependable Capacity (Not MWe): 560,1

9. It changes occur above since last report, reasons ares NONE 10, Power level to which restricted, if any (Not MWe) N/A

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

12. Report period hours: 720.0 6,575.0 252,023.0 a

13. Rours reactor critical 0.0 4,895.3 199,493.6 I

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

15. Hours generator on lines 0.0 4,893.5 193,539.4

16. Unit reserve shutdown hours: 0.0 0.0 398.0 17, Cross thermal energy generated (MWt3): 0.0 8,754,617.0 335,551,124.0

• 18, Oross electrical energy generated (MWeH) s 0.0 2,906,956.0 110,009,804.0

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19. Net electrical energy generated (MWeHis -2,138.6 2,768,722.6 104,520,184.2

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20. Unit service factor 0.0 74.4 76.8 ,

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21. Unit availability factors 0.0 74.4 77.0

22. Unit capacity factor using HDC not 0.0 75.2 75.1 e

23, Unit capacity factor using DER nets 0.0 72.4 71.3

24. Unit forced outage rate: 0.0 16.4 6.4

25. Forced outage hoursa 0.0 961.5 13,330.0

, 26. Shutdowns scheduled over next 6 months (type,date, duration): NONE 27, if currently shutdown, estimated startup dates No Start Date

• 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 ,

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l Docket No: 50-213 Unit: Haddam Neck Date: 10/1/96 Completed by: K.W. Emmons Month: Sep-96 Telephone: (203) 267-3654  !

AVERAGE POWER LEVEL AVERAGE POWER LEVEL 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 )

6 0 22 0 7 0 23 0 8 0 24 0 l

l 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 16 0

__ _. _ _ . . _. . . . _ ._ _ . . _ _ _ _ . ___ _.___m._ _. . . . . . . . . . . . _ _ _ . . _ . .

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

i UNIT NAME Haddam Neck DATE 10/01/96 ,

COMPLETED BY K.W. Emmons TELEPHONE (860) 267-3654 REPORT MONTH: Sentember.1996  !

No. Date Type' Duration Reason

• Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code' Action to Down Reactor 3 Report # Prevent Recurrence 96-05 09/01/96 S 720 C 4 N/A AC RCT Core XIX-XX Refueling and Maintenance Outage

'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 i H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers" i

HEF'UELING INFORMATION REQUEST j Seotember 1996 i

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 i

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

Y.as i 1

(b) If answer is yes, what, in general, will these be? i Amendments to suonort soecific 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?

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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:

Per schedule established with oroject 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) 152 In Spent Fuel Pool: (b) Bfi2

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.

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