ML20210L052

Monthly Operating Rept for July 1997 for HNP

ML20210L052
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/31/1997
From:	Emmons K, Mellor R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9708200200
Download: ML20210L052 (6)

Text

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ONNECTICUT YANKEE ATOMIC POWER COMPANY l

HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e CAST HAMPTON, CT 06124-3039 l

August 15.1997 Re: Technical Specification 6.9.18 Docket No. 50 213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In cecordance with reporting requirements of Technical Specification 6.9.1.8, the Connecticut Yankee lladdr.m Neck Plant Monthly Operating P.eport 97 07 covering operations for the period hily 1,1997 to July 31,1997 is hereby forwardcd.

Very truly wars, Russell A. Mellor Director of Site Operations and Decommissioning Iladdam Neck Station lb\M/bom

@j ec: (1) Regional Administrator, Region 1 2 U. S. Nuclear Regulatory Commission 475 Alkndale Road

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King of Prussia, PA 19406 i

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m (2) William J. Raymond Sr. Resident inspector Connecticut Yankee 9708200200 V'/0701

. PDR ADOCK 05000213 R PDR f! fl ,

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-4 Connecticut Yankee Atomic Power Company lladdam Neck Plant fladdam, Connecticut

. Monthly Operating Report No. 97 07 For The Month of July.199,

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nnunty The Haddam Neck Plant has been shutdown since July 22,1996 and on December 4, 1990, 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.

t 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 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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e-NkC 0FERATIN3 STAMIS REPORT

, Haddam Neck

1. Ikicketi $0 313

2. Reporting Period 0*/97 Outage + On line Hours 144.0

• 0.0 e 144.0

3. Utility contact s E.W. Emons (203) 267 3654 4 1.icensed thermal Power (MWtl 1825 j l. Nameplate Rating -(Oross MWe) s 64? a 0.9 e 600.3

6. Design Electrir.a1 Rating (Net MWe)t $02

7. Maalmum Depen Aable capacity (Oross MWe): $$4.9

8. Maximum Dependable capacity (Not MWe): $60.1 l 9. !! changes occur above since last report, reasons are: NONE

10. Power lovesi to which restricted, if any (Not MWe) n N/A

11. Reasona for restriction, if any: N/A prJNTH YEAR.TO-DATE CUMULATIVE

-12. Report period houret 144.0 8,087.0 259,319.0

13. Hours reactor critical 0.0 0.0 199,493.6

14. Reactor reserve shutdown hours: 0.0 0.0 1,205.0

15. Hours generator on.line 0.0 0.0 193,539.3

15. Unit geserve shutdown houret 144.0 6,087.0 6,133.0

17. Cross thornal energy generated (MWtHi s 0.0 0.0 335,$51.124.0 *

14. Orces electrical energy generated (MWeHi s 0.0 0.0 110,009,804.0 *

19. Net electrical en* gy generated (MWeH): 1,250.8 10,062.2 104,504,461.4 *

20. Unit service factor 0.0 0.0 14.6

21. Unit availability factor 100.0 100.0 77.0

22. Unit capacity factor using MDC not 0,0 0.0 73.0

23. Unit capacity f actor using DER noti 0.0 0.0 69.2

24. Unit forced outas. rate:

~

0.0 J.0 6.3 254 Forced outage houre t 0,0 0.0 12.970.0 26,' Shutdowns scheduled over next 6 months (type,date, duration): NONE

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27.' If currently shutdown, estimated 6.artup dates N/A

-* Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of

_;comercial operation, '01'01/64) .-

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O REFUELING INFORMATION REQUEST Julv 1997

1. Name of tho facility: Haddam Neck

! 2. Scheduled dato for next refueling outage: n/a (decommissioniugl

3. Scheduled date for restart following refueling: n/a fdecommissioninal

4. (a) Will refueling or resumption of oporation thoroafter requito a technical specification change or other licenso amendment 7 da (b) If answer is yes, what, in general, will those ba?

I Nu (c) If answer is no, has the reload fuel design r.nd coro configuration boon reviewed by your Plant Safety Review Cor.imittoo to datormine if any unroviewed safety questions are associatad with the core reload?

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

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5. Scheduled date(s) for submitting liconsing r,ction and supporting information:

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6. Important licensing ennsiderations associated with refueling, e.g., now or difforent fuel design or supplier, unrevirwod design or performance analysis methods, significant changes in fuel d4 sign, now operating proceduros:

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The numbar of fuel assemblies (a) ira the core and (b) in the spent fuel storago l pool:

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In Core: (a) Q in Spont Fuel Pool: (b) 1019

8. The present licensed spent fuel racol storago espacity and the size of any 3

increase in licensed storage caracity that has been requested or is planned, in_

number of fuel assemblies:

Present storage caoacitv: 14FQ

9. The projected dato of the la'st refueling that can be discharged to the spent fuel pool assuming present license capacity:

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UNIT SHUTDOWNS AND POVER REDUCTIONS o DOCKET NO. 50-213 UNIT NAME Haddam Neck -

DATE 08/01/97 COMPLETED BY K.W_ Onniens TELEPHONE (8601447-1791 X6572 REPORT MONTH: Juiv 1997 ,

2 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 07/22/96- S 744 F 4 N/A N/A N/A Decommissioning plan continued

'F: Forced ' Reason ' Method 'IEEE 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 - Ref ueling 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 (Explain) " Recommended Practices H - Other (Explain) for Unique identification in J

Power Plants and Related Facilities - Component Function identifiers-

AVERAGE DAILY POWER LEVEL Docket No: 50-213 i

Unit: Haddam Neck I

Date: 8/11/97 4 Completed by: K.W. Emmons Month: Jul-97 Telephone: (060)4471791 X6572

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i AVERAGE POWER LEVEL AVERAGE POWER LEVEL l

DM (MWe-Net) DM (MWe Net) _

i f 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 0 16 0 i.