ML20198J881

Monthly Operating Rept for Sept 1997 for Haddam Neck Plant

ML20198J881
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/30/1997
From:	Emmons K, Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9710220176
Download: ML20198J881 (7)

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I CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3009 O c4 L,,...J a 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 U, S. Nuc! car 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 97-09 covering operations for the period September 1,1997 to September 30,1997 is hereby forwarded.

Very truly yours.

Russell A. Mellor Director of Site Operations and Decommissioning lladdam Neck Station RAM /bom .

cc: (1) Regional Administrator, Region 1 -

U. S. Nuclear Regulatory Commission il }-

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475 Allendale Road King of Prussia, PA 14406 \

(2) William J. Raymond Sr. Resident inspector Connecticut Yankee

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lladdam Neck Plant lladdam, Connecticut Monthly Operating Report No. 97-09 For The Month of September 1997

Plant.9peratine 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), j CYAPCO provided docketed certification to the NRC that it has decided to pormanently .

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 ths site-specific decommissioning cost estimate in accordance with 10CFR50.82 on 4

August 22,1997.

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HR" JPEkAT!!O STATUS WEPORT Raddam Neck

1. Docketi 50-213 2, Peporting f eriod; 09/97 Outage e b line Hours: 720.0 + 0.0 720.0 3,- Ut ilit y Contact i 'm . W . Emmons (201) 26b 3654 4, Licensed Thermal Power IMWt,) i 1923

5. Nameplate Rating (Gross MWe): 6s? x 0.9 = 600.3

6. Design Elect raral Pating (Net MWe): $42 7, %xin,um Deg endable capacity (Gross MWe) : 586.5 8, Maximm Degendable Capacity (Net MWels 560.1 9, If changes occur above since last report, reasona are: NONE 10, Power level to which restricted, if any (Net MWel: N/A

11. Seasons f or g est r ict ion, if any3 N/A MCNTH YEAR TO-DATE CUMULATIVE 13 Report period hours; 720.0 6,551.0 260,743.0 13 th'ars rea t or crit ical t 0.0 0.0 199,493.6

14. koactcr reserve shutdown hours; 0.0 0.0 1,285,0

15. Hsurs genesator on-linai 0.0 00.

19),519.1 16e Unit reserve shutdown hours m .0 6,551,0 7,597 0

1. 7. G ro s .e t hern al eriergy generated (MWcH) 00 0.0 315.551.124.0 *

18. Gross ele..t rical energy generated (MWeHl: 00 0,0 110,009,804.0 *

19. Net. electrical energy generated LMWeH): -1,201,1 12,517,9 104,502.005.6

• 20, Unit serv!.ne factor: 0 0 00 74.2 21 Unit availatility f act or: 103.0 100.0 77,1 22 l'n tr capacit y f actor using MPC net -. 0.0 0,0 72.6

23. Unit capacity tactor usin<1 DER net: 0.0 0.0 68 9

24. Unit forced outage tate: 0.0 0.0 6.3 0.0 12,970.0

25. Forced outrJe hours: 9,0

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

27. It cbrient ly shutdown. estimat ed startup date ? N/A

• Cbmulat ive valugs f rom the first criticality (07/24/67) , (The remaining cumulative val.ias are frcm the first date of coewrcial operat torn 01/01/68).

AVERAGE DAILY POWER LEVEL Docket No: 50-213 Unit: Haddam Neck Date: 10/6/97 Completed by: K.W. Emmons Month: Sep-97 Telephone: (860)4471791 X6572 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DM (MWe-Net) DAY (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 13 0 29 0 14 0 30 0 15 0 31 16 0

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

UNIT NAME Haddam Neck ',

DATE 1091/97 COMPLETED BY K.W Emmons .

TELEPHONE (8601447-1791 X6572 REPORT MONTH: Sectember 1997 Method of License System Component Cause & Corrective No. Date Type' Duration Reason

• Shutting Event Code' Code' Action to (Hours)

Down Reactor' Report # Prevent Recurrence 4 N/A N/A N/A Decommissioning plan 96-05 07/22/96 S 720 F continued

1. ' Method *iEEE Standard 805-1984,

'F: Forced Reason 1 - Manual " Recommended Practices S: Scheduled A Equipment Failure (Exp!ain) 2 - Manual Scram for System identification in B - Maintenance or Test C - Ref ueling 3 - Automatic Scram Nuclear Power Ptsnts and i

D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reouction (Duration = 0) 5 6 - Other (Explain) 3EEE 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"

REFUELING INFORMATION REQUEST Scotember 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: Dia_(decommissioning)

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?

Dia (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?

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

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

Dla

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

DLa

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

In Core: (a) D 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:

DLa l

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