ML20126H521: Difference between revisions

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| document type = TEXT-SAFETY REPORT, TOPICAL REPORT EVALUATION
| document type = TEXT-SAFETY REPORT, TOPICAL REPORT EVALUATION
| page count = 12
| page count = 12
| project =
| stage = Other
}}
}}



Latest revision as of 11:24, 22 August 2022

Topical Rept Evaluation of Rev 0 to PS-53-0378, NUS Process Svcs Corp Topical Rept on Radwaste Solidification Sys. Rept Acceptable for Referencing in Future License Applications for LWRs
ML20126H521
Person / Time
Issue date: 05/30/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126H463 List:
References
NUDOCS 8506100352
Download: ML20126H521 (12)


Text

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'i rt i r U. t . ~ ': n c m 1/. decurcance t n u L e tt t s. I.nicii Criteric 60 ef i m rt h

-A te 10 CFP Part 50 were c'se reviu.ec.

4 Ti.e. i t.; tu ted in the report that tPey tr.t c it.l.rm eu c ..hC c ;qparets -

tcpical rapart, TR-002, "~or ict! Fer.crt cr.10 CFR 61 OualiNC ia citactive

'.las te Fcncs' cr it e l'r; 2PN for staff to reviev tre o .- I t:e t t the stability of racicacti te s:Es'.t .c "tHicd by the IWS Systen as rect.'r u. b., Section 01.56 ti R (.FI Far- C1 and the NRC Brarch Tertt.'c:' rositic: Or 'laste Form. This topichl repcrt ir beirc reviewed by the sta## i r !T.E E . Upcn cercpieticn of the staff revier, a seperrte D.fety Evaluation Report on 1G CFR Part 61 Waste Forp fa.c;cirmrts will be provided to sur.picri.er.t this

. evaluation.

c e aa .c , . r.c . . t r d e r fe..,r. -iechnical n,ssista i us.t cct, ha e ui;o r= ic.ct the LUS Tepical Report anc pre prei e Technicti Evaluatior. Perert 4 r IT C.

F.C?.C Icerc staff observed the IR'S Systu., it. c;eration processing i.ctual

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c. y s - 'cr cf :ne t?US System are dee.ch i t tete,, ir. th:
.w r e i...

. W 'igicci Een.rt, if-53-0378 and in the liUS resrcr:.es ated a.ly 9,19c4 ar.c .g r):

.c. c :. It ti c ..

i n. 3itensing revicu c,t.es';u.:.. D. tr.e ituff.s

.< U:. tic.; cf the "L'S syster , t!.c stati carisiceree:

systen cesist. criterih Lt.c cesirr

. ., .....e res.

,,e -ru.. : t t.upcci ty in corr.pariscr. s.i t,. cerip basis in vo)ures

- gc. ,.

expected during a:eral plant crertticr. ir.clucinc cn.icirz:tcc' coeratior,al occurrercer.

( a. ) de quE,ity roup classi,. icatiot, ti,c c,ccl 4.ty trsurance progran fcr ttc citis,n, fabrication anc testir,9 c.f '.he s" stem.

(4) Desion previsicrs 1rcerptratec in the equip:nerit and s;stcr; ccrier

  • ca u. teL q e aaa to ccr,trci sr.t r,ca etc r n ic.cscs of -adioscrive 6ffluents to tlie Grn'irc.r.! cht.

d.) f f OCe3. CGG*,rol progch!n 101.0st!rr crFflete 50lidificitio! C i 'i.t' t

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. . . . 3. .t . u.L -1

..anitcrit, u.. ccr.'.rcliec from c central ccrtrrl pr e' .

. .u c h. l. U . c . in ic': cr clerries are pumped fer.i. h eteri i 4cic rec.aste systets tc t?.s hCE c rrest.ble lir.er. Once in the lire r. tLe t.1.:,a uc Le i

pre:r -r e :' t cri ttered as necessat;/ to cdjurt u its. ;6t a sters o the cptic.u:,: poir.; for sciiC.*.icc" c" ir accordance t:ith the F M ;.rtcu , contrc'. l t

/_*.cr gretreatreet, cenert it pren ;tictily conycycc to the .r i n<. : .

pr: , r. r .

tier. cec ,r.0 tho tecste and then allowed to core 1.hile curing, the vaste terpercturc is closely monitored c cu;firrr, that.

the hycratiu. ef the traste form is takinc place. Thit ter..pt:rature profile is use:. n c: .ect S ( 9.r. < : n ? t ire tha t cene r.t c . .= 4 t u. ; . u te .

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. u;,.;Ainer ce tig i t u. . I,?c* volures of reste. erri+' < r >.t .t ut . dr:

'r s sr,ic,. 1cet., o n ,. e ,- . r. .

m . _ . , .

t i cic;.ict' reccticns and physical ciert*.io>:, u.ciuding weste pretrestrc4r.t.

crry debatem.. , g! af t
rert erd sclificicaticr. cre ccreaccec it. c cis-gestsie liner, r c . . a. u a. .clidification, the lira teca..es ti.c -(ir.cl dis-
n i cent.
f r c.-
t c citien to the large tuli. ctra.i. tri.iier, the hUS System is cti..posu t'

m #nlloting co'"recerts:

.,.j n. .is.hecc assem..any which ctreches. tc i risposable liner and allot
s (a) chcricci ccnditioning of the liquic k.wces prier tc solidificitier , .2) cewatering of slurries, coc (:) "ir r ccrtrel
r. - a. .. . csee cs the solic 1.cti;;; t r rfiur . It cor.tcins ti'e FiTer drive F.~:IC" Ofid "I C LI..t.1 c. .

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.r c ,*.er tc erraest sir dirr..ccec L; c u. e r,t

.tcciticn to the liner.

M; -C$ u.ict' tc'cition pumps for adding cl uc.iccis te assure tae cc:.. pie:t

- ro:1cificatier frctes!.. .

.ti e s t a n. . - : rc 1 :.e . -5,a a sten compcasat; are Ut:'ttre cr,. ccrstruc,.c,.. to cu'es anc tterderds ef. Fqtittery Guide 1.143 and. Brancn lecht.ict'. Por itic.n FEP ;; L. M1 ccipcaents of the IWS 5;. ster. tre cirssified ts Outli'r Grce; fc..n:tet,- in Regulatory Guice .3.tC.

it.e rttff estirates the quartitiet ef t.tt' solid waste genereted ficr L trin c ed 5400 til!: U!R :o be approximately 20.000 cubic feet per year for e PMF

'r tt P.-deep ted conde9s?te pcl ub.i.c sistem atic 10,Cu c sit 1 n . pO ' y:t r fe r .

i a IiIfr Wi tb ,2 f rECr 7 CC: tel. Sale - poiIShi119 SyS L6h. bd5cC' Cl. Ut" CL' CulatiV6 reviss JC# the liCC:Mee' C Ltl. '.-ir;r.Udl Ef f lUefit reietLL PcfCrt!.

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cf c s :ar.cc r: D; a s i _ c. o.t Lia r ec,uirtnair.s i:t .crth 'r h re ci Desic:.

. -i s- zu ct -;a. u t ., ,- ;c h C.20 ?trt 50.

'L . . , '

. m a rf e t, _ fabrication, tert.t ti t i;.e r a ticr: ci i,cc id ,: ayi .t;

..cco
r.pi u..d:; uncer pres tric LL (,un,:1.y assurance recuirerer,*. t:it,-

o r 4 rr te tre evtent practicata , citi. e tLe c.uicelines pre,iceC i: ht t. i. i t + e r.u t- nu_... . .

-es.t.. cu i aa r.c c ict Racioactnc .. s te ..anaceaent avs. tear. .

Structures ant' Crr. c; em:c li.;.tc ;iet ir. Light-1.ater-Ceclec' t t rierr Power T'r r' <: u: .n-fi;us anc contrcis ti.c st t .o.cnu of '!US Process

-Picnts."

Services c: . tin . .tg .icri' perforr.unce tQich v.tect tlc reality of the

" n.q .e t ., e. . c .,. .

TN .*:US Systets crE cesigned to prever.t ur:cc'rtrolled releases of redir; active w ta ici:: by t enitorir.g licuid levels ir ttc. lii e:s and alarrr.: in th- contrul pr.el to desigr.cte liig I'c;t.'r: level cenditions. Curbs er e h r t.e6ns tc

c. ,016 ac i ri t u - r t r 'li ? .e r.d overfic.'s r# t- p ( iuc L.; . i e user t.1 u.

fl C er'Crd ih0 Ti.,t;*..-6 tr, t[,i t ee r's licuid radW tc cr ',I ;c * (u. .j sica.s. t

f~

-c.

. N r.. ial. L.:, ..t iL1 $;'Itcri Uill b3 exh2DC'+r' tr +. u tq 's  ; . . i i. h

.mt:.. . ...'t: 't t r e f C re , the '".'S S;rr. tcr d >: i; . . r. . t u u.e : c, : ; 3.. .. u

. ... .; o ,. 1 : ...;,..c.

. C-. ,

. 'r ':?rc5 it'd!

,.c

. ia s. < ,-. I'25 pr0' lit 60 cct g c k 11.ie r T uce i r.7 ;, ci... ,, i y t .

4 I t3 , .i . r ': I i" th0 topical report fer Urf1 r .

ira ; Cpi O Li r t T.", . 6e C; 'I r f i PTCC955 CCSt*01 PPCgr'.r. (EC.', t.;L} sr!'rds .

I. hd prcCUcticL L '. i Eclic' !sDr.'CESDODUS, DOD0 lithic . VCitr-frte UCS'.e icr L.

Th: F's Sr.cifici.'13 cr e crentitativel;r addraitt:

(1) Tre crit ir t ct C ti.aiysis of waste si:riplEL.

(2) Prereceiriter ana sj5tew ci:stLtitt 9;

af rccy ter.cc criteria

( c. ) ed. Justing the chetistry cria cor. centration or I.ne haste in ,.t varicus additiver.

(6) Settir.g it.cc rhtes and ratios of ceit.ent Lt.C ut.stE irtC the disposable liner.

a ;.craturc contre s c7. t.oe s o . w. '. .; r[ irrtes.

/,

'o) t c r ectutic: s tr.d ,a lm tations.

(5f) keCOrd ar d. $dl. 7;I': test ShertS.

.- -..~._

l

.g.

Tra sicff fir.ds the i;e5 Pr;; css Centrol Program caets i.RC Eranch Technicci 2:s'tien ETES 11-2, P.e 'sier 2 and, therefers, is c:cc:. table.

Ina i.US Sys:em i: ces1gr.ec' to oe operated cy a single cperator frcm c

~ ::ively isclated contrei c;nsole. Arrancemsnt c# tre MUS Systcr ccmpo-at::a is ocsed on .caintaining the operator raciaticn exposure as loe as is

  • 13scrable achievable cnsistent .cith Reg. Guica E.8. The main features that provide this assurance are:
i. Components are rerr.oved from radioactive areas for servic,ing.
2. Most of'the crocessing operation is centrolled by remotely operated mechanical systems.
3. The operator does r.ot need to be in proxinity to the disposable liner except during the fillhead removal and liner closure.

Total annual radiation dose for the NUS Syst'em operator will be less than 5 rem limit for year-round processing, most of which would be obtained during sample solidification testing. The operation of the NUS System mus.

ei included in the plant elARA progran and actual cctes are expected to be vieil belc'.. the limit.

l l

1 J

?

-inE ;.U5 Syster.coes no: incluce any radiaticr. c..ani torir.g instrur.er:: tion

US sticulctes in the topicti

' for the purpc;se of personnel rtdiaticc safety.

. ...: .2 .s:e 11i _r. 1.;- cx u c. r ~,s . . i ..

,n Contrdi p r0 g ri~ .

ina stiff 1s currently reviewing a separate GJ5 topical report, " Topical Espert on 10 CFR c1 Qualified Radioactive Waste Forns" submittec by RUS, the staff will previde an evaluation on 10 CFR 61 waste form requirements upon ccmpletion of its review in a separate Safety Evaluation Report.

3.0 CCGCLUSIO:l

' Based on the-foregoing evaluation, and the findings and conclusions in the EG&G Technicci Evaluation Report, EGG-PBS-6851, dated April 18, 1985, the.

staff finds the NUS Topical Report, PS-53-0378, Rev. O, to be acceptable.

The basis for our acceptance is our conclusion that the NUS System is designed and can be operated in accordance with current guidance of appli-cable regulator / guides, standard review plans, branch technical positions, and Federal regulations.

~

ihe capability of the plant radioactive waste treatment systems to meet the s

c-i eria of Apoendix i :o 10 CFR Part 50 with the HUS Syster in operatien

. . . . , - - c. . u .. . u.aigand fer i; . ,ia.i ii;...;e a,;ii;.c; m.s.

'n addition, the packaging and shipping of all processed wastes including

.lste' classification in accorcance with tne applicable recuirements of l 20 FD ? art 51 3r.d 'I. snd 49 CFR Parts 170-17E, vill be determined fer u.tivicuai license applications. The consequences of a liquid radwaste

, tank failure releasing radioactive materials to a potable water supply is i l

also site dependent anc will be evaluated for individual license appli-l cations. .

.The staff concludes that the NUS Topical Report is acceptable for reference in future license applications for light water reactors. Any application incorpcrating this report by reference should include the following infor-V n,ation:

(1) Any exceptions or deviations from the NUS Topical Report, PS-53-378, Rev. O, dated April 1983, and NUS response to the HRC licensing review questions dated July 9, 1984 and April 2, 1965.

(2) Interfaces between the plant and the NUS System.

b. - _ _ _ . _ _ - _ - _ _ _ _ _

, . , , ... . - . . . . , . . . _ - - . .. - _ ~ . - - . . . . . . . . _ - . - . . - - . . _ . . . . ..

( '.

t- .:. .,

1, .

T J

(3[ Loc,s tion and arrar.gement= d: ',iings cf the f!US Sjste.? in th? ;iant.

i, ,,n u cices t ci.;.oa prefric ta a:s.;n;trcc ; c... ti c . :s , 2 5 .c prcduct-is classified in accordance with 10 CFR 61,.Section 61.55 and i:RC Branch Tschnical Fosition on Waste Classification.

' (5) Serific charccteristics ar.d volumes cf "vtat" r dioactive'v:aste-

.to be processed by the liUS System.

. (6) Tne capability of the. plant to n:eet the criteria of Appendix I to

.-10 CFR Part 50 with.the NUS System in operation.

O 4