ML19220B029

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Forwards First Round Requests for Addl Info Re Potential Addl Energy Release from Steam Generators After Core Reflood & ECCS Evaluation
ML19220B029
Person / Time
Site: Crane Constellation icon.png
Issue date: 08/21/1974
From: Washburn B
US Atomic Energy Commission (AEC)
To: Kniel K
US Atomic Energy Commission (AEC)
References
NUDOCS 7904250212
Download: ML19220B029 (3)


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August 21, 1974 Wm ?

p-Docket No. 50-320

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N Karl Kniel, Chief, Light k' ster R2 actors Group 2, dranch 2 s

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..v Attached is a letter to Metrcpolitan Edison Cc=panv with first-round type questions for addi:icnal i: for.stica subnit:cd by the 2:s 3 ranch. Acciden:

Electrical Instrumentatica and Centrol Sys:

M r:ctural ingi-Analysis Branch, ".aterials Engineering 3ra-ch, neering 3r.nch, Machanical Eng neering Branch, Core Performance Sys tens Branch, Au : ilia y and Po ter Branch, Effluent Treatmen:

Conversica Systens Branca, Ccataine.in: Sycters 3 ranch, Site Analysis 3 ranch, Reactor Systems 3 ranch, Industrial Security and and Radio-Energency Planning Branch, Quali:j Assurance 3 ranch, logical Assess:ent Branch.

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respctses clarificacion and sorc detail rela:ing to tne applican:s' of the to the questions sub=1tted f elicwing the accep tance revies FSAR.

The folicwing significant revicw iters have been identified:

The applicant has not addresced po:ential additional 1.

the staa: generators after re-energy releasa frc flooding of the core in his analysis cf a pcstul2ted reactor ecolant syste ccid leg pipe b reak.

.*e are requiring the appliennt Oc include the pcs
-refloed generator energy release in his containceat stea:

analysis.

2.

The applicant has not ec pletely describ=d his ce:heds of analysis to determine the sub compartment pressure response.

3.

The auxiliary feedwater sys te say require design changes unless safe shutdcun can be achieved by acceptable netheds follcuing a feedwa:er line break which is acccapanied by a single failure.

Conf or:ance to applicable s tandards and. Regulator /

4 Gcices.

Seis=ic and environ: ental qualifica:icn of safety 5.

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Karl Kniel abstrec:s.

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Freeperational test 7

ECCS evaluatiCn.

Less of feedwater analyses and evaluarien.

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Additional itens noted in the subnitted questicas are:

The muniliary feeducter s/ sten has been de:ernined and must be capable of satis-1.

essential to plant saf etj af ter sus taining a fyin; its functional requirenent pipe break inside centainnent and a single electrical fsilure.

(22.15)

We are requiring qualification testing of the standby 2.

diesel generatior.

(22.20)

We are applying single f ailure criterien to nanuali -

f 3.

(22.15) controtled electrically-eperated valves.

isola-We are recuasting anal / sis of the control ro a 4.

(31. 1 tien capability for chlorine releases.

sing 1 f ailure The Residual Heat 2encval Systen is not 5.

the intent of AEC prcof and therefore aces not neetWe are asking f or nodi-General Design Criterica 34.

to echie"e a cold fi c a ti nn of *hh avsrem en enable it rest. ictite single shutdown conditica assucing the cost failure.

(21.33)

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' 'B. W. Wdshburn, Proj ect Manager Light Water Reactors 3 ranch 2-2 Directorate of Licensing Encics ure:

As stated Dis tribution:

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s 3-Karl F.niel Distri'cution:

Decket File Ilda 2-2 Reading M. Service W. Haass

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