ML20155F176

Summary of ACRS 740307 Meeting to Review Util Application Re Listed Items.Transcript of Proceedings Available

ML20155F176
Person / Time
Site:	Grand Gulf, 05000000
Issue date:	04/02/1974
From:	Owsley G US ATOMIC ENERGY COMMISSION (AEC)
To:	US ATOMIC ENERGY COMMISSION (AEC)
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References
FOIA-88-91 NUDOCS 8806160306
Download: ML20155F176 (2)

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"'t, UNITED STATL3 ,, [ c j N/- ATOMIC ENERGY COMB.ilSSION F p )

WASHINGTON. O.C. 20545 In s ,

APR 2 S 74 DOCKET NOS: 50-416/417 APPLICANT: Mississippi Power and Light Company FACILITY: Grand Gulf Nuclear Station, Units 1 & 2

SUMMARY

OF ACRS MEETING HELD ON MARCH 7, 1974 The ACRS reviewed the Grand Gulf application (second meeting) at its meeting on March 7, 1974. The Committee considered the following four subjects at its March meeting. A transcript of the proceedings is available. ,

1. Guard Pipe Design The Committee members asked a number of q n stions regarding the proposed guard pipe design vb' s described by the applicant.

No ccnclusions were reached. cemittee Chairman indicated that the Grand Gulf Subcommitu aould consider the proposed design at its next meeting and that the Full Comittee would wish to review this matter further. The staff stated that it would reopen its review of the guard pipe matter.

2. Combustible Gas Control The Co=ittee members asked a number of questions in regard to control of combustit,le gas in the containment. Subjects discussed included effects of hydrogen explosion on components in the drywell, rates of hydrogen buildup for radiolysis, effects of water overflow from the suppression pool into the drywell (assuming no vacuum breakers) and a listing of safety related equipment in the drywell which could possibly be affected by either hydrogen combustion or flooding.

3. ECCS General Electric Company representatives presented probability estimates of exceeding various peak clad temperatures, based on progressive failures of the ECCS beyond that specified in the IAC. The Committee inquired about the effect of the new GETAB correlation on calculated peak clad temperatures. Also, the applicant and staf f were asked to explain the f actors which resulted in the lower peak clad temperatures calculated for the BWR/6 design; in particular, the relative effects of core design and ECCS design. At the next Subcommittee meeting, questions will be asked in regard to drying and film boiling near the cop of the core.

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PDR FOIA CONNOR 80 -91 PDR

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4. Industrial Security The Committee asked a number of questions in regard to the potential for sabotage; in particular, the possibility of sabotage involving the guard pipes and possible consequences. Discussion on this subject will be continued at a future meeting. The applicant and staff were requested to consider various design alternatives which

- would improve protection against sabotage.

The Chairman indicated that all the subjects which had been brought up at '

this meeting would be considered at a future meeting of the Committee.

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./bn s 'l0 E "G. Owsley, Proj ect Ma ger Light Water Reactors roject Branch 1-2 Directorate of Licensing I

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