ML20149E445

Monthly Operating Rept for June 1997 for Haddam Neck Plant

ML20149E445
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1997
From:	Emmons K, Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9707180196
Download: ML20149E445 (7)

Text

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q CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT l 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 I

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July 15,1997 l Re: Technical Specification 6.9.1-8 Docket No. 50-213 U. S. Nuclear Regulatory Commission i

Document Control Desk

. Washington, D. C. 20555 In accordance with reporting iequirements of Technical Specification 6.9.1.8, the Connecticut Yankee lladdam Neck Plant Monthly Operating Report 97-06 covering operations for the period June 1,1997 to June 30,1997 is hereby forwarded.

1 Very truly yours, 4

Russell A.Mellor I Director of Site Operations and Decommissioning Y, D i IIaddam Neck Station b RAM /bom cc: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission }

475 Allendale Road I

King of Prussia, PA 19406  :

(2) William J. Raymond Sr. Resident Inspector .

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Connecticut Yankee Atomic Power Company IIaddam Neck Plant Haddam, Connecticut i

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Monthly Operating Report No. 97-06 For The Month of June 1997

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l Plant Operatine Summarv The Haddam Neck Plant has been shutdown since July 22,1996 and on December 4, 1996,' the Connecticut Yankee Atomic Power Company (CYAPCO) Board of Directors voted to permanently and immediately cease operations prior to expiration of its license.

The removal of fuel from the reactor vessel started on November 13, 1996. As of

November 15,1996, all fuel assemblies were permanently removed from the reactor and placed in the spent fuel pool for temporary storage.

On December 5,1996, pursuant to 10CFR50.82(a)(1)(i) and 10CFR50.82(a)(1)(ii),

CYAPCO provided docketed certification to the NRC that it has determined to permanently cease operations at the H8ddam Neck Plant and that fuel has been '

permanently removed from the reactor.

CYAPCO will submit at a later time the Post-Shutdown Decommissioning Activities Report (PSDAR) and the site-specific decommissioning cost estimate in accordance with 10CFR50.82.

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NRC OPERATING STATUS REPORT

, Haddam Neck I

1. Docket 50-213 2, Reporting Period: 06/97 Outage + On-line Hours 720.0 + 0.0 e 720.0

3. Utility Contacts K.N. Fasnons (203) 267-3654

4. Licensed Thermal Power (MWt): 1825

5. Nameplate Rating (Cross MWe) 667 x 0.9 600.3

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 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 CUMULATIVE

12. Report period hours: 720.0 4,343.0 258,575.0 13 ~ Hours reactor critical: 0.0 0.0 199,493.6

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

15. Hours generator on-linei 0.0 0.0 193.539.3

16. Unit reserve shutdown hours: 720.0 4,343.0 5,389.0

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

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18. Gross electrical energy generated (MWeH's 0.0 0.0 110,009,804.0

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19. Net electrical energy generated (MWeH): -1,238.1 -8,811.4 104,505,712.2 *

20. Unit service factor 0.0 0.0 74.8

21. Unit availability factori 100.0 100,0 76.9 22, Unit capacity factor using MDC neti 0.0 0.0 73.2 j

23. Unit capacity factor using DER net 0.0 0.0 69.4 l

24. Unit forced outage rate: 0.0 0.0 6.3 .

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

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

21. If currently shutdown, estimated startup dates N/A i

'* Cumulatire values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of comercial operation. 01/01/68).

.o REFUELING INFORMATION REQUEST ,

June 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 (decommissioning) f

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

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.. i (b) If answer is yes, what, in general, will these be? '

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. (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?  :

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

l 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 1

- different fuel design or supplier, unreviewed design or performance analysis  :

7 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:-

IriCore: (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

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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.6 AVERAGE DAILY POWER LEVEL  ;

F h-Docket No: 50-213 l Unit: Haddam Neck '

Date: 7/1/97 Completed by: K.W. Emmons Month: Jun-97 Telephone: (860)447-1791 X6572 i

AVERAGE POWER LEVEL AVERAGE POWER LEVEL DM (MWe-Net) DM (MWe-Net)

'I i 0

'1 0 17 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 1

9 0 25 0 10 0 26 0 l

11 0 27 0  !

12 0 28 0 13 0 29 -0 1 14 0 30 0 15 0 31 16 0 l I

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e UNIT SHUTDOWNS AN'D POWER REDUCTIONS. .-

DOCKET NO. 50-213 ~ -

UNIT NAME Haddam Neck DATE . _' 07/01/97 2 COMPLETED BY K.W. Emmons TELEPHONE ' (8601447-1791 X6572 REPORT MONTH: June 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 96-05 06/01/97 .Sl 720 F 4 N/A N/A N/A . Decommissioning plan continued -

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'F: Forced

• Reason ' Method 'lEEE Standard 805-1984, 4

S: Scheduled A - Equipment Failure (Explain) 1 - Manua! " 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 ('sxplain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function identifiers"

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