ML19220C554

Discusses 790407 Briefing by Westinghouse Re Preliminary Conceptual Design of Mods to Heat Removal Sys

ML19220C554
Person / Time
Site:	Crane
Issue date:	04/08/1979
From:	Mattson R Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7905110219
Download: ML19220C554 (3)

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Task M3nagement/ Scheduling s

IMI ?.2cevery Creanization T.e hF.R Technical ?2 view Team was brie fed by esting'.ouse (Cle, Eicheldinger, et al.) on 4/7/79 on the prelis-icary conceptual design of nodifications of the THI-2 decay beat rc,aval system.

The nodi fications are intended to increase the larg tcra relichility of the JM3 a td to reduce its radiological fr pact on the av. ilia ry building and the envi rce. cent in the ev-:nt it is eventually needed to cool the El-2 core, k*e undarstand that the JHR system is intended for use onty in the cant other pre (crred c. odes of long terra co.oling are not accen?!!sbad.

T e existing WF systers is a redundcnt, two train system with a pep sad heat exc5anser in each t rain capable of delivering req.:i red ficw and heat re.sval under non_st core coalability i

cend i t i ons.

The conceptcal desige being devet ; ed by

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.,es t.e rs,.:ur e inr,ard has inree pr.incipal s.catwes, as foll ows:

I I) Provide pipi,g andIsolct ~ca vaiv: 5

.~ro-, e xi s t i.7 OHR intet pi ? n; to a 1 0 ation eurside r:e a nitiary 'ciidir.g

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n, le-k:'gst, 3:'? a c.t

• l ru ning and c:: ling t?e e s:e (,r s. nr 1 yg.:s. train e

M R syste.7 7.3 '.:.0 s t a f f full y e-ds eg :s i t e-s 1) ced 3) c.,d t.rges t ha t they be eccm plished as soon es e3 sihte.

In addi t i on,wi th ce r ta i n revisicns that we Se!ieve can reas ed:1y te ac:rpt ished i n :t,e i

r ela tively shart tire avai!aai e (: to three m.ts is es tred et tnis jrocture), the S taf f also er.d.,rses t' e se::

ite Car sugges tions far ite: 2, the third DMR trcin, are as fe! 35:

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.- s Fred Stern April 8, 1979 currently being offerred by IW be)are aiding in a ration-Find and ese better (cre I - 9.t i 8t pe ;s than those 3) wide search for better etegs at this wri ting).

I b) Callect pu.p and valve leakage for cenfine: ent in a volume separate Fro, the auxiliary tuilding waste cas and liquid s ys ter-s, but wi th re :ta control relief capability to those s y s t e-ns,

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Usa welded connections.

I d) Jtupent the ner. al DMR inst ru.menta tica to provide long te r.,

reactor coolant c. cat toring, sanpling, e;4 chwis t ry control,edt.,

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Shield or cbtain radiation hardened instre entation.

f)

Saild in pre:; erat! oral Teck detectic., cspebility.

g)

Frovide boron r:sure,-nt and control for the reactor conlant system.

h) Use A 5..I code regai rce.cn t s Oc re prac ti:a l.

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Fred) yec all N.uipncnt t o e r. t e r. t practical, i

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C3srecteriza piping and equis tnt seisr-ic cs: ability and provi3:

G3E seisr.ic capability to extent practical.

k) Frovida 06.inistrative or de sign n.atures to prevent TiA isciation by spurious high pressure or contain.. cat isolatian signals.

1) Fr: vide for trete apitoring af pu p seals.

C ar su;_: es tic s f or' i ter. 3, in;rc,

nt of t'.e two e>:i s t ir g Jhs t rai-5, a re as ~olin<s:

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col *tct 7, _. 3 1snd valve it.&i'jy tCr t07 fir-cent i n e y ig,3 e

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1. e ek t M.: and weld lecks.

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Aq. ent ins trumntatica if n-t I:.x T r ::re third train, f) Same as ite1 k) far third tr21 %

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Lu LL-ks 1 5elieve it is in;erative that GF)1, Wo&6use 4..d the N?.C staf f

-. set early tror rcw aitorn:ca t ms/f d ue 5t.~"s.sti:ns and to nutually agree.:cen and freeze the.~y c

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