ML20155E405

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Summary of 730223 Meeting W/Util in Bethesda,Md Re Fission Product Transport Modeling for Containment,Following Design Basis Loca.Meeting Attendees Encl
ML20155E405
Person / Time
Site: Grand Gulf, 05000000
Issue date: 03/13/1973
From: Owsley G
US ATOMIC ENERGY COMMISSION (AEC)
To:
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20155E140 List:
References
FOIA-88-91 NUDOCS 8806160095
Download: ML20155E405 (5)


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RP Reading I WAR 131973 BWR-1 File RSBoyd VA'toore Docket Nos. 50-416/417 }0!a igre t BWR BC's.

G0wsley WHaass DSkovholt  !!Ros en DKnuth R0 (3)

APPLICANT: !!ississippi Power and Light Company RMaccary RTedeseqc" FACILITY: Grand Gulf Nuclear Station, Units 1 and 2 HDenton

SUMMARY

OF MEETING RECARDING FISSION PRODUCT TRA%' SPORT MODELING FOR THE GRAND GULF CONTAIMIENT ,

At the applicant's request, a nceting was held on February 23, 1973, .

in Bethesda uith a representative of the Grand Gulf A-C (Bochtel) regarding fission product transport modeling for_the containment, follouing a design basis LOCA. The purpose of the meeting was to aid the applicant in designing the air circulation and discharge system

, for the upper enclosure building, and the penetration rooms. The applicant is to provide a description of the enclosure building and the air circulation system in an amend =cnt to be filed in March 1973.

The dir.cussion included consideration of potential bypass leak paths and cxfiltration. The staff stated that adequate support vill have to be provided by the applicant to establish that a negative pressure vill be naintained in penetration rooms and in ether small volu=es.

In addition, sensitivit'y studies of pressure diff erential (betucen the volume and the outside acciosphere) vs. flow rates fron the containment into these areas will be required. Willoughby (Bechtel) expressed her concern that flow from these small volunes misht be treated by the staff ao bypassing the building mixing systen and thus would have to be assumed to be exhausted directly (without holdup) -

through the filters; the staff stated that it will not be able to resolve this concern until the system description is filed. Duration of positive pressure periods in the secondary containnent was discussed as a potential problen that would require resolution.

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cueld O'v'tW Gerald F. Owsley, Project ?!anar.cr j Loiling Uater Reactors Branch 1 )

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  • nclosuro: j Meeting Attendance 8806160095 080605 PDR FOIA CONNOR 80-91 PDR j CUIC, >

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!!1ETI';G ATTENDANCE

!!ISSISSIPPI PO'.ii' R A.;l) LIGHT CO:tPA'iY CPA;D CULF :L'CLCAR STATIO: , UllITS 1 AND 2

- Fr.BRUARY 23, 1973 AtoQc Qcyev Co :nission i . Ad o ns a: .

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DDtECTORATE OF LICENSDOG n ,. Vh ~

I REQUEST FOR SCHEDULE CHANGE C/ //

DA'!E: 3/23/73 PE OF CHANGE REQUDT.

Information Item Technical Review Action  !

Applicat.t Action x Reactor Projects Action Lab Action CGC Action

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, TIATOR OF CHANGE REQUEST: _ cerald r ovslev ACTION CP OL: cp j ANT NAME: c.. ,cm., . . . , , , , 1 , DOCKrF NO. : So i.tueu

.ESTONE NUM3ER & DESCRIPTION: ,, .y e, %, . , . . r.o ,,,,s,, ......  !

24 04 SE Input to L PM from Containment Sys'tems )

24 21 SE Input to L PM from Reactor Systens 24- 9 1.PM Coepletes Draf: of Safety Evaluation 25 Safetv Evaluation issued.

ASON FOR CHANGE: Mem f rom R. Fralev (ACRS) indicated need for the staff's Safety Evaluation at least e veems prior to Ene, ACRS meeting because the meetings are now to be held as "open" meetings. This is in contrast to the 17-days previously required.

mil.ES M E TOCET DATE FSTIMATED DATE VAR I ANCE 24 02 12/12/73 12/10/73 2 24 04 12/14/73 12/10/73 4 24 21 12/14/73 12/10/73 4 24- 1 12/28/73 12/19/73 6 25 t/19/h. 1/ s/74 9 1GET DATE: ESTIMATED DATE: VARIANCE:

iCURRENCE: -

)1ect Organization) L PM: ,, BC: 4/3 AD:lfM@f'DD: h.

Date: nu4 Date: ,, . 4 , t D:.te: yyDate: p7 '

E PE: BQ s- AD: x-Date: Dcto a Date: - x JCURRENCE:

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BC AD: OI@ DD: l4 i Date: D:.te: v,n Date: me e i ,.

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'ACT DATA:

be Prepared by OPS) There should be no problea with such a NR N *1DM schedule acceleration if the present TR schedule is set. Any delay in the

  • Target New Estiented Total review schedule by Containment Safety, i Frospective Prospoetive farianceee Effluent Treatment, Core Performance. l Decision Decision and/or Reactor Systems branches will Sea nata probably delay the completion of these milestones.
  • Fuel Load Date does not apply for G variance Analysis
    • Difference Between Poal it,cd Date & Eso Estimtad Frospective Decisies Date PONSIBLE PARTIES:

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OMMENDED FOR APPROVAL: ' "- X - V -' _ DATE: l OMMENDED FOR APPROVALbr og/ucer;mg DATE: //!v!73

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