ML20210U930

Monthly Operating Rept for Aug 1997 for Haddam Neck Plant

ML20210U930
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/31/1997
From:	Emmons K, Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9709220169
Download: ML20210U930 (7)

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• CONNECTICUT YA N K EE AT O MIC POWER COMPANY HADDAM NECK PLANT k:'. INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 September 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 97-08 covering operations for the period August 1,1997 to August 31,1997 is hereby forwarded Very truly w .s,

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

%Q  ;' f 475 Allendale Road f ii King of Prussia, PA 19406 (2) Wil:iam J. Raymond Sr. Resident inspector Connecticut Yankee 9709220169 970831 PDR ADOCK 05000213 R ..

PDR

Connecticut Yankee Atomic Power Company 11addam Neck Plant lladdam, Connecticut Monthly Operating Report No. 97-08 For The Month of August 1997

Plant Operatine Summary The Haddam Neck Plant has been shut down 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 decided to permanently cease operations at the Haddam Neck Plant and that fuel has been permanently removed from the reactor.

CYAPCO submited the Post Shutdown Decommissioning Activities Report (PSDAR) and the site-specific decommissioning cost estimate in accordance with 10CFR50.82 on August 22,1997.

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NRC CFERATING STATUS REPORT Haddam Nsck

1. Docket: 50+213

2. Reporting Period: 08/97 Outage + On-line Houres 144.0 + 0.0

• 744.0

3. Utility contact s K.W. Emmons (203) 261 3654 4, Licensed Thermal Power G4Wt): 1825

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

6. Design Electrical Rating (Not MWe): 542

7. Maximum Dependable Capacity (Gross MWe): 586.9

8. Maximum Dependable Capacity (Net MWel t 560.1

9. If changed occur above since last report, reasons are: 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 CLNULATIVE

12. Report period hours: 144.0 5,831.0 26 063.0

13. Hours reactor critical 0.0 0.0 9,493.6

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 hoursi 144.0 %5.831.0 6.877.0

17. Gross thermal energy generated (MWtH) : 0.0 0.0 335,$51,124.0 *

14. Gross electrical energy generated (MWeH): 0.0 0.0 110,009,804.0 *

19. Net electrical energy generated (MWeH)* -1,254.6 11.316.8 104,503.206.7 *

20. Unit serytce factort 0.0 0.0 74.4

21. Unit availability factori 100.0 100.0 77.1

22. Unit capacity factor using MDC net: 0.0 0.0 72.8 234 Unit capacity f actor using DER not i 0.0 0.0 69.0

24. Unit forced outage rate: 0.0 0.0 6.3

25. Forced outage hours: 0.0 0.0 12.970.0

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

27. If currently shutdown, estimated startup date N/A t.cymulative values from the.first criticality (07/24/67), (The remaining cumulative values are from the first date of commercial operation. 01/01/68).

AVERAGE DAILY POWER LEVEL L'ocket No: 50-213 Unit: Haddam Neck Date: 9/6/97 Completed by: - K.W Emmons Month: Aug-97 Telephone: (860)4471791 X6572

' 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 9 0 25 0-10 0 26 0 11 0 27 0 12 0 28 0

'.3 0 29 0 14' O 30 0 15 0 31 0 16 0

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REFUELING INFORMATION REQUEST August 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)

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

DLa (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?

Dia

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

Dia

6. Important licensing considerations associated with refueling, e.g., new or different fuel dengn or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

Dia

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 capacitv: 1480

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

DLa f

' UNIT SHUTDOWN $ AND POWER REDUCTIONS ....

DOCKET NO. 50-213 UNIT NAME Haddam Neck ', ,

DATE '09/01/97 COMPLETED BY K.W. Emmons ~,

TELEPHONE - (860) 447-1791 X6572 REPORT MONTH: Auaust 1997 Date Type' Duration Reason' Method of License System Component Cause & Corrective No.

(Hou s) . Shutting Event c ade' Code Action te Down Reactor' Report # Prevent Recurrence 744 F 4 N/A N/A N/A Decommissioning plan 96-05 07/22/96 .S continued I

1. ' Method *lEEE Standard 805-1984,- I

'F: Forced Reason A - Equipment Failure (Explain) 1 - Manual " Recommended Practices S: Scheduled B - Maintenance or Test 2 - Manual Scram for System Identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Reguistory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0) s lEEE 6 - Other (Explain) Standard 803A-1983, .

F - Administrative 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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