ML19308A627

Design Guidance for Radwaste Mgt Sys Installed in Light Water Cooled Nuclear Power Reactor Plants, Effluent Treatment Sys Branch Technical Position 11-1

ML19308A627
Person / Time
Site:	Oconee
Issue date:	09/11/1975
From:	Office of Nuclear Reactor Regulation
To:
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ML19308A626	List: ML19308A625 ML19308A627
References
11-1, ETSB-11-1, NUDOCS 7911270700
Download: ML19308A627 (12)

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v, 9-)] /5 BPE Cl! TECH?i iL POSIT 10?! - ETSE NO.-11-1 O

Design Guidance for Padioact ive Uast e ibur.ntrent Syster.s Installed in Light-Unter-Cooled t'uclear roect heactor Plnnts A.

lin ckground_

An aspect of nuclear power plant operation is the control and manage-ment of liquid, gaseous and solid radioactive vastr / generated as 1

a' byproduct _of nuc1 car power.

We have established acceptabic design guidance, scismic and quality group classifications, and quality assurance provisions for radioactive vast e nanagenent systens in-cluding stenn generator bloudoun systens.

For the purpose of this position paper, the radioactive waste nananenent systens are consid-cred to begin at the-interf ace valvc(s) in each line f ron other systens provided for collecting wastes that nay contain radioactive natcrials and to terminate at the point of controlled discharge to the environnent, at the point of recycle back to storage for reuse in the reactor, or at the point of storage of packaged solid vastcc prior to shiprent offsite to a licensed burial ground.

Tne stcan generator b]oudom nycten begins at, but does not include, the outer-r..ost containnent isolation valve or. the blowdoun line and ter6inates at tiic point of contro] Icd discharge to the environment, at the point of interface uith other liquid vaste systens, or at the point of recycle back to the secondary system.

Except as noted below the positions set forth in this paper do not apply to the reactor coolant cicanup systen, the condensate cicanup systc=,

the chemical and volume control systen, sumps and floor drains provided for collecting liquid wastes, the boron recovery system, building i

ventilation systc=s (heating, ventilating and air conditioning) and chemicalJfute hood exhaust' systems.

Positions [ctforthinthis 1/

- Radioactive.vaste used in this guide neans liquid, gascous, or solids containing radioactive material resulting frca operation of a LtIR uhich by design or operating practice nay be or will be processed' prior to final ~ disposition.

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. paper regarding p ovisions.to costrol.releasen of.;idloactive materials in liquids duento tank overf3ces apply to all plant systems, outside

! reactor containment, having the potential to incur such releaues.

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'The design and construction of radioactive waste nanagenent and

~ steam generator blowdown systens should' provide assurance that radiation exposures to operating personnel and to the general public are maintained at low and acceptab]c levels, by assuring that these systems are designed to quality standards conducive to. increasing system reliability, operability, and availability.

'In developnent of this denign guidance, the NRC staff has reviewed a number of designs and concepts submitted in license applications and operating system histories.

The KRC staff has been guided by current industry practices and the cost of design features, taking in account the potential impact on the health and safety of operating personnel and the general public.

The design guidance given in this position paper provides reasonabic assurance that equipnent and component s used in the radioactive vast e nanagenent and blowdown systens are designed, constructed,

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installed and tested on a level commensurate with the health and safety of the public and plant operating personnel.

Instrumentation and controls" associated with the waste nanagement and blowdown m.._...z._..r...

systens should be designed to a quality com=ensurate uith their intended function.

.This position paper sets forth nininum branch requirements and is not. intended _to prohibit the implccentation of more rigorous. design I

codes, standards, or quality assurance measures than those indicated-

.herein. !

In addition to' the design Euidance given for radwaste syste e, recom-mendations are given_ for provisions to preclude:the inadvertent

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relen e cf radioactive naterials in liquids due to r. pills or over-flows from botl. raduaste and non-raduaste system tanks located inside

' or-outside of plant structures.

- B. ' Branch Technical Position l~

1.

Systems llandling Radioactive Materials In Liquids a.- The liquid radwaste_ treatment system, including the steam generator blowdown system downstream of the

- second containment isolation, valve should meet the follouing: criteria:

(1) The systems should be designed and tested in accordance with the codes and standards listed in Table 1, to include the provisions in (2) below and in Section IV of this position paper.

(2) Materials for pressure retaining components should conform to the requirements of one of the specifications for naterials listed in Section 11 of the AMIE Boiler and Pressure Vessel Codr...

except that malleabic, wrought, or cast iron naterials and plastic pipe should not be used.

Manufacturer's naterial certificates of confor-mance with material specifications may be pro-vided in lieu of certified natcrials test reports.

(3)

Foundations and adjacent walls of structures that house the liquid radwaste system should be designed to the seismic criteria described

-in Section V to a height sufficient to contain the liquid inventory in the building.

(4) Equipment an'd components used to collect, pro-cess, and store liquid radioactive vaste need not be designed to the seismic criteria given

' n Section V.

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b...All'tankt, ucated'outside reae. tor contain

.t..t and cont:.inIng radioactive materials.in liquids chould be designed to prevent

. uncon' trolled releases of radioactive materials due to spillage in. buildings.or from outdoor storage tanks.

The following

. design features should be included for tanks that may contain radioactive caterials:

(1) All-tanks, both inside and outside the plant including the condensate storage tank (s) should have provisions to 'saonitor liquid 1cvels and to alarm potential overflow conditions.

(2) All tanks should have overflows, drains, and sample lines should be. routed to the liquid radwaste treatment system /

1 (3)

Indoor tanks should have curbs or elevated thresholds with

- f3oor drains routed to the liquid radwaste treatment.

- systen /.

1 (4)

Outdoor tanks should have a dike or retention pond capabic of preventing runoff in the event of a tank overflow and have provisions for sampling collected liquids and routing thcu to the liquid radwaste treatment system.

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11.

Gaseous Radioactive Waste (Radwaste) Systen I'

a.

The gaseous radwaste treatr. cat system, including systens providea for treatment of normal offgas releases from the main condenser vacuum systen for a EUR and for the trear-ment of gases stripped from the primary coolant for a Pt.'R should meet the follo..'ing criteria:

(1) The systems should be designed and tested in accord-

-ance with the codes.and standards listed in Table r

1,toincludbtheprovisions in (2) below and in S,cetionIVo[tiiispositionpaper.

t b' Retention by an intermediate su=p or drain tank,- designed for' handling radioactive materials and:having provisions for routing to the liquid radwaste system is acceptabic.

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. (2) : Mat Jrials f or pres. ore re! n ining co,,ione at t. shotib' conforn t o. the requi re." v

• of one of the-rpu if'ca-tic,ns for. naterialn Jia;ted in Section II of t he A';:'

IJoiler and Pressure Vesse] Code except that nalleab)c, vrought, or cast iron naterials r.nd plastic-pipc

.should not be used. Manuf acturer's nat erial cert.i-ficates of conformance with :natorial specificat. ion:.

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may be provided in lieu of certified natcrials test reports.

1 (3)

Those port. ions of the gacecus raduaste treatrent systen.vhich by-design are intended to store or delay the release of nascous radioactive '.:astc, in-cluding porticas of structures housing these system, k

should be designed to the seisnic design criteria

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given in Section V of this position paper.

For systens that nornally operate at pressures above 3.5 at to.4pherca (absolute),. thi:. should include isolatien valves, equipncnt, interconnecting pipinr,, and con-

.ponents located between the upstrean and do.nstrean valves used to isolate these conponents fren the rest of the systen (c.n., vaste gas st orar,e tanks in a Pl"l).

For systens that operate near anhicat pressure and

retain rases on charcoal adsorbers, only the tank cle-ncnts and tho building housing the tanks arc included (e.g,,. charcoal delay tanks in a INTR),

11I.

Solid Radioactive 11aste (Raduaste) Systen

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n. The solid raduaste systen consists of slurry vaste collec-tion'.and settling tanks, spent resin storage tanhs, phase separators, and tanks, equipnent, and conponents used to solidify vastes prior'to offsite shipacnt.

The solid rad-vaste handling and treatment system should ccet the fol. lowing criteria:

(1) ' The system should be designed and - tested in accord-ance with the codes and. standards listed in Table 4

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1 to include the provisions $u (?) below and in

- Section ' lV of.t hin paper.

(2) !!aterials for preucure ret aining conponents s'

ould conforn t o the requirenent s of one of the spec ifi-cations for r;tterials listed in Section 11 of the ASME Boiler and. Pressure Vessel Code except that mallcable, uronght, or cast iron riaterials end plastic pipe should not be used.

Manufacturer's natcrial certificates of confornance with natorial specifi-cations inny be provided in 31cu of certified natcric1s test reports.

(3) ;roundations and cdjacent valls of structures that house the solid radwaste systen should he designed to the scismic criteria given in Section V of this position paper to a height sufficient to contain the-]tquid inventory in the building.

- (4)_' rquipn:nt and components used to collect, process or store solid radioactive easte need not be designed to seisnic criteria referenced above.

IV.

Additional Design, Construction, and Testing Criteria In addition t'o the requirenents inherent in the codes and standcrds listed in Tchle 1, the follouing criteria, as minfrun, should be inplenented for.,conponents and systens

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considered in this guide.

a.

The Quality Assurance provisions described in VI of

.this guide should be applied.

b.: Pressure retaining conponents on process systens shou]<'

utilize uc1ded construction to-he maxinun practicabic extent.

Process' piping systens include the first root valve on-sarple and instrument lines.

Flanged joints-

.or's?titable rapid disconnect fittings should be used only

.where maintenance or operational.requirencnts clearly indicate.that such construction' is preferable.

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(connecti..s in which thrende. provide the

.ly ven!

j-s should 'not be used except - f or imitruan t a t i..n er,nac :.: 6:...

uhere we)ded connections are r.ot. suitable. ' Proces:. lir.o.

should not be less-than'3/4-inch.

Screved connectionn backed -up by-scal s.e] ding, suchet. weldin;t or techanical joints may be' used on lines 3/4'-inch or. greater, but le:4.

than 2'J/2-inch,-noninal size.

For lines of 2 1/2-inch ne'ninal cire and above, pipe velds should be of the but t-joint type.

EacP.ing ringo.should not. he used in lines carrying resins or other particu3nt e rat.cria).

All velding constitutin;; the prescure houndary of

pressure retaining. conponents rbould be perfon.ed in accordance uith AS'E Pressure and Vessel Code Section IX.

c.

Conpleted-process systenn r.hou]d be pressure tested to tha naxinun practicable e:: tent.

piping r.yst e..is should

. bc hydrostatically tested in their entiret.y except c t.

att.acpheric - t.ank connectir.ns chs r: no iso)ation va]ves exist.

Testing of piping syst.en.s.should be perforced i:-

accordance.uith applicabic ASE or ANSI codec., but in no case-less than 7.5 psig.

The test pressure should be hcid for a nininun of 30 ninutes with no leakage indicated.

Testing provisions should be incorporated to enabic periodic

-,cvaluation of the operabil:ity and required functional performance of ' active co:::ponents of the systen.

Scisnic _Desi ;n Requirements f or Radioactive Uaste ?!anagement V..

t Systens and Structurcs !!ousing ' Radioactive Waste !!anagement.

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a. -Seismic Design Requirerents for Gascous Radioactive Waste 1

linnagcnent Systems- /-

(1). For the evaluation of support elements in the'i:ascous vaste systen, a..sinplified scismic analysis proce.durc O r which seismic capabilitics are required in Section II(3).

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to c.eterr.ine reismic, J oadu ay be u.cd.

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. ficd proccdure consists of consi& rat io. of the systen as a single degren of f reedon nyst en and o

picking up n seisnic response value.fron applicable fjoor r sponse spectra, once the fundanental fre-q(icncy of the systen is deternined.

The floor response spectra should be obtained analytically (Section V.h) fron the application of Regulatory Guide 1 60 design response spectra normalized to-0DE Icyc1 nny.irun' ground acceleration at the foundation of the building housing the garcous raduante synter.

(2)

The allowahic stresses to be used for the systen support elene.a r.hould be those given in the ATSC Manual of Steel Construction, 7th edition 1970, including tbc one-third allocahic stress increase provision for lono cocbinations involving earthquake loads.

For cesign of concrete foundationc of the cysrca, chere applicable, use of the ACI 318-71 code eith one-third increase in allouah]c stress for scis:Ic loads is acceptab]c.

(3) The construction and inspection recuirencut.s for the support elements should comply with those stipulated in isISC or ACI Codes as appropriate.

b.

Scisnic Dcsign Requirer. cats for Buildings Housing Radwaste Systems-

-(1). Define input motion at the foundation of the building

-housing the radwaste systems.

The r::otion should be defined by normalizing t.hc Regulatory Guide 1.60 i

spectra to the OBE naximun ground accelerat ion se -

l lected for the plant.

A sicplificd analysis should be perforced to deterninc appropriate scismic loads and floor responce spectra pertinent to'the location of the systems; i.e., an analysis.of the building by a "several degrees of

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for redvaste syste:m and the. scirmic load:. f or t h-buildings. ~ No ti:.:e history or dynn=J e analyuls J-

-requircd.

_(2). The si: plified nothod for deternination of seitmic loads for the building consists of (a) eniculatic:

-of. Zirst several nodal Irequenales and participation factors f or the building, (b) determination of nodal scisnic loads by iten (1) input spectrn, and (c) cen-binatien of nodal ocinnic lo: ds by the square root of tha. r.un of squares - (SMSS) rule.

(3) Uith regard to generation of floor response spectra for radvaste systens, nethods such as the Biggs or other ec:uivalent procedures rhich give approxinate floor response spectra without need for perforning a ti=c history analysis nay be used.

(4) The Joad factors nnd load conbinations to be used for the building should be those given in the ACI-318-71 Code.

The allowable stresses for steci conponents should be those given in the AlSC Manual f

of Steel Construction, 7th edition, 1970.

(5) The construction and inspection requirements for the building-clenents should comply uith those stipu-i lated in the A1SC or ACI Code es appropriate.

i (6) ' The foundation-nedia of structures housing the rad-vaste systens should not liquify during the Operating U

Basis Earthquake.

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'c.- 'In licu'of the requirencnts and procedures defined above,

. optional shield structures constructed around and sup-l porting the raduaste systems may be crected to protect the radwaste systems from effects of housing structural failure.

If this option is adopted, the procedures described in Section V.b only need to be applied to the 9

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shield c ructures wh!]c t r eating t he t ent of the hmmin;-

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VI.

Quality Assurance for Radioact.jve b'aste !!anagement Syst enn A quality accurance progran should be established that is.

sufficient to assure that the design, construction, and test-inn requircucats are net.

The quality assurance progran shou 3d include the follcminr,:

a.

Design and Procurencnt Dacument Control

':canures should be ertabli:hed to insure that the requirenents of this position paper are rpecified and included in design and procurtnent docunents and that deviations therefron are

. controlled, b.

Control of purchased !!aterial, Equipacnt and Services -

Measures should be established to assure that purchased naterial, equipacnt and construction services conforn to the procure: cnt doeurents.

c.

Inspection - A pro;;rau f or inspection of activities aff ect-ing quality should be established and e:secuted by, or for, the organization perforuing the activity to verify confor-nance with the docunented instructions, procedures, and drawings for accomplishin:t the activity.

d.

llandling, Storage, and Shipping - Measures should be

-established to control the handlin'g, storage, shipping, c1 caning and preservation of material and equipnent in accordance with work and inspection instructions to prevent damage or deterioration.

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Inspect. ion, Test and Operating Status - Measures should be establishcp to provide for the identification of itens which have satisfactorily passed required inspections and testc.

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f.

Corrective /iction - N asuren r!.> 'd be cut d'J inia J t u arnorr-that conditio:ss adverse t <> quali t:c, nuch ci failu.u,, ral-functions, deficientjert deviations, defective r.steria] to s,i equipacnt cad nonconformances are prongstly identified and 1

corrected.

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P00R DRIGINE.

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EQUIPT"',NT CODES i

EQUIPTENT C00P.S k'elde r i

Design'and Qualification Inspection g)

.I Fabrication Material s A:d Procedure And Tentine t

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Pressure Vessels ASME Code ASME Code ASME Code ASME Code Section VIII, Div. 1 Section II Sectica IX

'Section'VIII, Div. 1 ASME Code (3)

ASME Code (4)

AS'!E Code ASME Code (3) i Atr.ospheric or L

0-15 psig tanks Section TII, Class 3,Section II Sectinn IX Section III, or API 620 6 650, Class 3 or API t,,.0;6:

Ak".s'A D-100 A'#..'A D-100 t'*

!! cat Exchanger ASME Code AS:2 Code AS'IE Code AS:E Code Section VIII. Div. 1 Section III Section I'.

Section VIII, Div. 1 and TE"A Piping and Valves ANSI 31.1 ASTM or AS!'E Code ANSI E 31.1 ASME Code S<.ction IX l

Section II Pu npa Manufacturers AS'*C Ccdc ASME Code AS:iE(

StandardsSection II or Section IX Section III "enufacturers (as required)

Class 3: er Standard llydraulic Institute W

a OQ Notes:

(1)

Manufacturer's standard for the intended service.

Ilydrotesting should be 1.5 times the design pressure.

(2) Material Manufacturer's certified test reports should be ebtained sehenever possibic.

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• (3) ASME, Code stanp and I:aterial traceability not required.

Fibergicas reinforced plastic tan':s r ay be used In accordance teith Part 'i, Section 10, AF.'G Deller

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(4) and I'rcssure Vessel Code. Cer npelicatiens at 09 ient tenparature.

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