ML20198N668

Monthly Operating Rept for Dec 1997 for Haddam Neck Plant

ML20198N668
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1997
From:	Emmons K, Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CY-980-007, CY-980-7, NUDOCS 9801210165
Download: ML20198N668 (9)

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN Hollow ROAD e EAST HAMPTON, CT 06424-3009 January 15,1998 Re: Technical Specification 6.9.1-8 Docket No. 50-213 CY-980-007 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In accordance with reporting icquirements of Technical Specification 6.9.1.8, the Connecticut Yankee IInddam Neck Plant Monthly Operating Report 97-12 covering operations for the period December 1,1997 to December 31,1998 is hereby forwarded.

Very truly yours, C

a Russell A. Mellor Vice President Operations and Decommissioning Haddam Neck Station RAM /bom cc: (1) Regional Administrator, Region i U. S. Nuclear Regulatcry Commission 475 Allendale Road King of Prussia, PA 19406 ig t -

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(2) William J. Raymond h Sr. Resident inspector Connecticut Ynnkee

((h 9001210165 971231 PDR ADOCK 05000213 R PDR.

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Connecticut Yankee Atomic Power Company lladdam Neck Plant lladdam, Connecticut Monthly Operating Report No. 97-12 For The Month of December 1997 l

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I'lagi 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 c 'ase oparations 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 docommissioning cost estimate in accordance with 10CFR50.82 on l August 22,1997.

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- . -n. n MRC OPERATING STATUS REPORT i 1

~ ltaddam Neck ,

• ., Docket: $0 21' 2, Reporting Periode 12/97 'Ntsgo + On line Hours: 744.0 + 0.0 e 744.0 3, iltility Contatt4 K.W. _ Emmons (203) 267 3654

4. Licensed Thormal Power (MWt): 1825 ,

S. Nameplate Rating (GrooJ MWel t 667 x 0.9 = 600.3

6. Design Electrical Rating (Net MWel 582

7. Maximum. Dependable capacity (Gross MWe) 566.9

8. Maximum Dependable Capacity (Not MWels 560.1 i

9. If changes occur above since last report, reasons ares NONE

10. Power level to which restricted, if any (Net MWel r N/A

11. . Reasons for restriction, if any: N/A MONTH.. YEAR-TO-DATE CUMULATIVE 12, Beport period houtsi 744.0 - 8,750.0 262,992.0

13. Hours reacto- critica1r C.0 0.0 199,493.6 ,

14 Reactor reserve shutdown hourst 0.0 0.0 1.283.0

15. Hours generator on linei 0.0 0.0 1';3,5 * ) . 3

14. Unit reserve shutdown hoursi 744.0 8,759.0 9,80%.0

17. Ornss thermal energy generated {MWtH) 0,0 0.0 335,551,124.0 *

18. Crosa electrical energy generated (MWeH1: 0.0 0.0 110,009,804.0 *

19. Not elect rical energy generated - (MWeHi s -1,599.0 -16,859.4 104,497,664.1 *

20. Unit service factor: 0.0 0.0 13.6

21. Unit availability f actori 100.0 100.0 77.3

22. Unit capacity factor using MDC net 0.0 0.0 71.9

23. Unit capacity factor using DER nett 0.0 0.0 68.3 24, Unit forced outage rate: 0.0 . 0.0 6.3 25.. Forced outage hours: 0.0 h.0 12.970.0

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

27. !! currently shutdown, estimated startup date N/A

• cumulative values the the first criticality (07/24/67), (The remaining cumulative values are from the first date of commercial operation, 01/C1/68),

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CL EKf1VE REPORT

12/97:

• p CUMULATIVE le Report period hours: - 266,856.0 h

t Hours generator on-ljnet 195,D83.9 ,

) 3. Hours reactor critical: 301,702.3 ,

t 4, . on-line net' niectrical energy generated (MWeH) : 104.749,354.2 -

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4. Off line station service electrical energy utilfred (MWeH)r- 272,769.6

6. Transf ormer losses -(MWeH) : 276,153.1:

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-J_-Effective full power days: 7.734.1' y R.- Ef fective full power hoursi 185,637.3

9. Core burn up - (MWtD/>TJ) : 218,701.8

10. Number of reactor shutdownsi 307 +

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Note s all values are cumulative f rom the first criticality (0104 hrs 07/24/67). 'i i

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, AVERACE DAILY POWER LEVEL - .f Docket No: 50-213 Unit Haddam Neck 1 . t Date: 1/5/98 i Completed by; _ K.W. Emmons l Month: Dec-97 ' Telephone: (860)4471791 X6572 _

j AVERAGE POWER LEVEL AVERAGE POWER LEVEL '

- _ DAY (MWe-Net) D6Y - (MWe-Net) -  ;

i 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 i 8 0 24. 0 9 0 25' O

.10 0 26 0-11 0 27 0 12- 0 28 0-

{ 13- 0' 29 0 1 14 - 0 30 0

i15 ~ 'O 31 0

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UNIT 3HUTDOWNS AND POWER REDUCTIONS -

- DOCKET NO. 50-213 UNIT NAME Haddam Neck DATE 01/01/98 COMPLETED BY K.W. Emmons TELEPHONE 18fi.01447-1791 x6572 REPORT MONTH: December 1997

_ No. Date Typel Duration Reason 2 Method of License . System Component Cause & Corrective (Hours) Shutting Event Code 4 Codes Action to Down Redctor3 Report #

Prevent Recurrence s

96-05 07/22/96 S 744 F 4 N/A N/A

- 1F: Forced 2 Reason 3 Method 4lEEE 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 a Continued from

' Previous Month Related Facilities" -

E Operator Training & License Examination 5 - Power Reduction (Duration = 0)

F Administrative 6 - Other (Explain)

SIEEE Standard 803A-1983, G - Operational Error (Explain)

" Recommended Practices i

il H - Other (Explain) for Unique' identification in-Power Plants and Fielated ,

Facilities - Component Function identifiers"

REFUELING INFORMATION REQUEST December 1997

1. Name of the f acility: Haddam !{eri,

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

3. Scheduled date for restart following refueling: n/a (decommissioning 1

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

nLa (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:

Dia S. 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:

n/a

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 cool assuming present license capacity:

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