ML20203K427

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Monthly Operating Rept for Nov 1997 for Haddam Neck Plant
ML20203K427
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 11/30/1997
From: Emmons K, Mellor R
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CY-970-123, NUDOCS 9712220369
Download: ML20203K427 (10)
v • d • e


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CtONNECTICUT YANKEE ATOMIC POWER COMPANY  !

HADDAM NECK PLANT ,

302 INNN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 December 15,1997 Re: Technical Specification 6.9.18 Docket No. 50-213 CY-970-123 U. S. Nuclear llegulatory 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 hionthly Operating fleport 9711 covering operations for the period November 1,1997 to November 30,1997 is hereby forwarded.

Very truly yours, e'~) a -

Ilussell A. hiellor Vice President Operations and Decommissioning lladdam Neck Station IRAht/bom cc: (1) llegional Administrator,llegion i U. S. Nuclear llegulatory Commission ,

475 Allendale lload King of Prussia, PA 19406 g@L 4 (2) William J. Ray mond Sr. Ilesident inspector Connecticut Yankee ll Ill.ll!Illl

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9712220369 971130 PDR ADOCK 05000213 R PDR

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. 1 Connecticut Yankee Atomic Power Company ,

Iladdam Neck Plant  ;

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lladdam, Connecticut

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Monthly Operating Report No. 9711 For The Month of November 1997

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Plant opermaine summan-i 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, i i

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 i placed in the spent fuel pool for temporary storage. j 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 permanently i cease operations at the Haddam Neck Plant and that fuel has been permanently removed j from the reactor.

l CYAPCO submited the Post Shu'down Decommissioning Activities Report (PSDAR) and  ;

the site specific decommissioning cost estimate in accordance with 10CFR50.82 on j August 22,1997.  ;

- On October 27,1997 the NRC held an infomational meeting at the Haddam Killingworth High School in Higganum, CT to solicit public comments on the "0DAR.

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4 NRC OPtkATING STATUS REPORT 14addam Neck i l

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1. Docket # $0 313 }
3. Reporting Periode 11/97 Outege e On line Houret 730.0 o 0.0 e 130,0 f

3, Littlity Contact : R.N. Esemone (303) 347 8654 .

4. 1.lcensed Thermal Power (MWtis' 1936 6 Nameplete Rating to:ose psels 667 a 0.9's 600.3 f
6. Design klect rical kating (Net Mwel t $43
1. Manteue Dependable Capacity (Gross MWel t 196.9 0, Manimum Dependable capacity (Net Muel a $40.1 l 9, !! chatges occur above since last report, reasons ares NONE l I

10 Power level to which restricted, !! any INet MWela N/A- t 11, Reasons for restriction, if anys N/A MONTH YEAR 70 Daft CUMUIATIVE  !

li. Report period houres 130.0 6,018.0 363,340.0

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13. Hours reactor criticals 0.0 0.0 199,493.6 i
14. Reettor reserve shutdown hours 0.0 0.0 1,306.0

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16. Hours generatr r on* lines 4.0' O.0 193.639.3 1
16. Ifnit reserve shutdown houre t 720.0- 48,016.0 9,061.0

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l 17 Gross thermal energy generated (MutH): 0.0 0.0 335,651,134.0 e

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it, Croce electrical energy generated (MWeHit 0.0 0.0 110,009.004.0 *

19. Net electrical energy generated (MWeH) 2 1.439.3 15.260.4 104,499,363.1 e e

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20. thsit service f actore 0.0 0.0 73.8 f

31.- Unit availability f actori 100.0 100.0 77.3 l

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33. Unit capacity factor using HDC noti 0.0 0.. 73.1 $

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23. Unit capacity f actor using Dra reti 0.0 0.0 6e 5 34' tinit forced catege inte

. 0.0 0.0 6,3 St. Forced outage hours 0.0 0.0 13,970.0-1 i

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- 34, Shutdowns ocheddled over next 6 months (type,date, duratinnii NONE l 31,If currently shutdown, estimated startup dates N/A-s

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  • Cumulative values from the first criticality (07/34/671. (The remaining cumulative values are from the first date of -

' comenercial operation, 01/01/65).

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i. Pegert (+tind herus e s 266,112.0
2. House ponesato.t on lines- 196,04).9
3. Itouts teactair crataral: 201.102.5 i

4, Oreline teet elect rical eriergy generated (MeeH), 304,149,354.3 {

- 6. Of f *!!ne et etion service electrical ene:gy utilf red (MWeH): 273,160.6 I 14.' transtornet losses (MWein e 276.153.1' -- .

Ti tf f tetIve iull gewer days s 7,1)4.1 j

- Di Ef f ective f ull gewer house: 106.617.3  ;

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9. Cot e baa n-up (MWt D/>frU) i 216,701.0 ,

10.18uthr of teactor shutdowns: 301 i

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. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 213 UNIT NAME Haddam Neck i DATE 12/01/97 COMPLETED BY K.W. Emmons .

TELEPHONE 18801447-1791 X6572 REPORT MONTH: thember 1997 ,

No. Date Type 1 Duration Reason 2 Method of Licentre System Component Cause & Corrective (Hours) Shutting Event Code 4 Code 5 Action to Down Reactor 3 Report #

Prevent Recurrence 90 05 07/22/90 S 720 F 4 N/A N/A i

1F: Forced 2 Reason 3 Method 4lEEE Standard 805 1984 S: Scheduled A Equipment Failure (Explain) 1 Manual

" Recommended Practices l B - Maintenance or Test 2 Manual Scram for System identification in C - Refueling 3 Automatic Scram Nucleai Power Plants and D Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E Operator Training & License Examination 5 Power Reduction l

F Administrative 0 Other (Explain) 61EEE Standard 803A 1983, G Operational Error (Explain)

" Recommended Practices i

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i H . Other (Explaini foi Unique identificatior. In Power Plants and Related .

Facilities Component [

Function identifiers'  ;

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.-  : REFUELING INFORMATION REQUEST November 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 (decommissioninal .-
4. (a) Will refueling or resumption of operation thereafter require a technical
  • specification change or other license amendment?

nLa (b) if answer is yes, what, in general, will these be? -

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

(d) ,

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

n/a

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:

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 iri licensud storage ccoacity that has been requested or is planned, in g . number of fuel assemblies:

Present storage canacitv: 1480

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

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