ML20005H107

Submits plant-specific Conceptual Design for Diverse Emergency Feedwater Actuation Sys Per 10CFR50.62.Requests NRC Approval of Design in Form of SER by End of Jul 1990 to Support Implementation During Eighth Refueling Outage

ML20005H107
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/15/1990
From:	James Fisicaro ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN019003, 2CAN19003, NUDOCS 9001240149
Download: ML20005H107 (2)

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"# January 15, 1990

'2CAN019003-t U. S. Nuclear Regulatory Commission

Document Control Desk 2

c Mail Station P1-137 1 Washington,-~DC's 20555-Subjecti Arkansas Nuclear 0ne'-' Unit 2

-Docket No. 50-368 License. No NPF-6 ANO-2 Plant Specific Diverse e' Emergency Feedwater Auctuation System (DEFAS) Conceptual Design Gentlemen:-

In response to your. correspondence of August 15, 1989, (2CNA098901) the .

> Arkansas Power and Light Company'(AP&L) is submitting our plant-specific, . >

conceptualtdesign for_the Diverse Emergency _Feedwater Actuation System 3 4

(DEFAS) to be installed on Arkansas. Nuclear 0ne, Unit 2 (ANO-2) to complete  !

the requirements of 10CFR50.62. This design-is in conformtace with the "

generic 1 design concept discussed with.the NRC staff and the Combustion Engineering _0wners Group-(CE0G) on July'12,1989, and which was also the c isubject of your previously referenced correspondence.

In performing the "eview required by 10CFR50.59, AP&L determined that the probability of an event previously evaluated in the Licensing Basis  ;

Documents (i.e. , Excess Heat Removal from a Secondary System Malfunction) ,

.would beiincreased, ~thus making DEFAS implementation an unreviewed safety

, question. The discussion of the generic design in the NRC's August 15, 1989 letter stated that because of the Diverse Scram System (DSS), Main Steam Isolation Signal (MSIS), and Emergency Feedwater Actuation System (EFAS) interlocks and the single failure design to avoid erroneous actuation, the

, ' probability of:the occurrence of a spurious Emergency Feedwater (EFW) actuation during non-Anticipated Transient Without Scram (ATWS) events had been adequately miaimized. AP&L agrees with the staff that the design does not unacceptably increase the probability of a previously evaluated accident.

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Page 2 January 15, 1990-F y 1 Since-the ANO-2 plant specific design for DEFAS is consistent both with the generic design prese~nted to the staff by the CE0G and the. design previously {

-approved on Louisiana Power and Light Company's (LP&L) Waterford-3 facility t T AP&L-will proceed with final design and hardware procurement to support l L implementation during the AN0-2 eighth refueling outage (2R8) as previously committed. However, considering the result of the 10CFR50.59 evaluation previously discussed, AP&L requests that the staff- provide a Safety Evaluation-Report (SER) prior to the implementation of the design. To

support our-schedule for 2R8, staff approval in the form of an SER will need j to be received prior to the.end of July.1990. The above information has j been discussed-with the'ANO-2 NRR Project Manager. l Should you have

any questions regarding this submittal, do not hesitate to j contact my office, j

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Very truly yours,-

dasi j es J.- isicaro-i Manager, Licensing  !

JJF/MWT/lw' cc: Mr. Robert Martin U. S. Nuclear Regulatory Commission i Region-IV 611 Ryan Plaza Drive, Suite 1000 )

Arlington, TX 76011 ,

NRC Senior Resident Inspector i Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road i Russellville, AR 72801 Mr. C. Craig Harbuck  !

NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike d Rockville, Maryland 20852 Mr. Chester Poslusny NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852

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