ML20127G621

Safety Evaluation Accepting 740123 Proposed Changes During Refueling Outage

ML20127G621
Person / Time
Site:	Monticello
Issue date:	03/14/1974
From:	James Shea, Ziemann D US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20127G595	List: ML20127G591 ML20127G609 ML20127G621
References
NUDOCS 9211170394
Download: ML20127G621 (5)

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ratdadu e return to g..c cparal,lon in RTy.t97/i.

Laerefore @ proval-j of the 09Pating chrQ2 's :lescrit.06 by BP in 1:

M auy % 1974 i:

submit ta.1, cannot be Errited at thic tims.

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To allow the meJor mullfications described by NP to procesd au

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chedulaa, in the Sprhg of 1974, before the Ulrectorate of Licenaina i

e/rlustica of the PRT syste.?. an:1 G2 :malytical rMhuja are ca;rplew, various alternativea 4: era e:.:plored. At a r.teeting C uJ WP and /EC 4

npresentatives.on Febrtw 20 an,1 al, -1974, it was ntat::ct by Directorm.e of Licensi:0 representatives thit e::1stin, overpresatuu relief spacity must be renained and the propoced dependence on : riff I

I calavaa at Jeast entil our ovaluation is cucccanfull:/ cocpleted,

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estimated to take abcuc cin months.

CE ana li3P rt pre.wntatives in:2.cand bhat. these Directorate ?f i_icensin;q conditions thd La satisfia! and y

j-nt a st:pp10 mental a=iyala- -tauld Le provided -T.

W avaludica prio;

.0 plu.3 startup in iay 197J.

du GF. analytical resulta for the trorat abncma.! teenalent, turbina

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trip withuut bypass tua na P3T,.nba;/cu a 12] pui Frayiu, or ;

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transient pressure of 1252 psig corpated with the deuip tuuulent j~

int of 3 375; howev9r il thanal daalgn -limits :ca a wid (UZ R(1).

'..ith the. oroposed PET operar.1ve the peak prescura nuld qe 74 pai lore, nacordhr to the GZ arclysis, and tha overpresonrt ianirn tr.argli ?nul'

. ecrrespondingly largar, 1.c.,197 psi carpaced M Lh Mi pl.

Tb-correspondina; MCliFR would tb 135 with 5 or 6 relim.valv:n ncstloains.

The 1:rportance of the FRT sys?.am a reducina th vturere Leansiant ana p

preventing fuel clad te7 rr.res in excesa of. dssi,g ilmita it evident In this Dr.alyals.

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Safety / relief valve etpaalty based ca closure o s

r n11 ain 'ateara icolation valves with fail "e of the valve closure reacton surm algnlc, w in previous an dycis g) En. era cala.lced reactor ucra::t, 'cux,.:. tea ra-utroa l-j flux raachaa.its trip at paintilc auff$cient, act ru % uo D calycale-crith a total'or o uafs c/rc ief valves operatl e W. <canni d cretw ra assumin;; that the # cafvty/ relief valves open ubin tv uro n acSa tha j

1080 pa;.g mainal set point u calculated La bi 60-: m below the trancient

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DATE F ROM (Name and unrtl REMARKS DLZiemann Ltr to Northern States approving plant modifications for (JJShea) fuel cycle 3.

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