ML20083Q521
| ML20083Q521 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, 05000000, Cherokee |
| Issue date: | 01/06/1983 |
| From: | Miller R, Snow A DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20083Q427 | List: |
| References | |
| 1.143, NUDOCS 8302250424 | |
| Download: ML20083Q521 (14) | |
Text
. . . . . _ . . _ . . . . . . . ..-. . .........._,_._,_..e FORM NG-1, REV 2 L
DUKE POWER COMPANY
~
Page 1 -
of 10 Nuclear Guide 1.143 NUCLEAR GUIDE Effective D. ate _1/6/83 Revision la
{
2
~ Title *. Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants .
3 Reference NRC Regulatory Guide Number 1.143 Revision 1
. i. Disposition
- of Current Disposition of Previous RG Revisions This RG Revision Revision Number Disposition Plants Affected D0conee Partial Compliance 1
- Partial Compliance Partial Compliance 1 Partial Compliance EMcGuire E Catawba Partial Compliance 1 Partial Compliance Partial Compliance 1 Partial Compliance l E Cherokee
- Note: uidance for radioac comonentsinstagdafterg,8pstemanagement e i D Thisguideprovidesintgrim syste s, structures, an i
- Disposition is either " Adopted, " Adopted with coment", " Partial Compliance",
( "Not Applicable", or "Under Review". If'" Partial Compliance" is indicated, attach Form NG-1A.
6 Coordinatio With- Reviewed By:
Originated By:
Name I M d s Dept Desion Enoineerino Desian Enaineerina Desian Enoineering Date a-(- I L / M - P.t lo-7-1f 2.,
i 7
~
l Approval Action:
O Waived O Waived F Approved . y ' pprov BYf 0 hgo I IL Construction Date Design Engineering 10-742-Date O Waived O Waived o ~
hg E Approved hApprove
.00 llfilk k/A@ y.$y 7uan t_y Msurance va re vate gg Nuclear Productica
FORM NG-1A REY 0 l
(' DUKE POWER COMPANY Page 2 of 10 i Nuclear Guide i.143 .
NUCLEAR SUIDE Revision la 2
Summary of Alternatives taken to Reculatory Guide
. Detailed clarification is provided to enhance implementation of the Guide. As low as reasonably achievable (ALARA) is Duke's criteria for evaluating effectiveness of activities associated with Duke Class E systems.
3 Alternatives (Rewrite the affected Regulatory Guide Section below. Continue on additional sheets as necessary. Position statements should directly correspond to the affected Reg Guide section or be a continuation of the Reg Guide format.)
- .- Refer to pages 3-10 of Nuclear Guide for rewritten sections of
( Regulatory Guide l . 4 Justification (Must be sufficiently detailed to permit evaluation by Department headsandNRC)
All exceptions taken to NP: *iry Guide 1.143 are to:
l 1) Provide additional flu .n design approach to
! achieve same objective, oi ,
- 2) Exclude design scope more properly performed outside jurisdiction of the NRC Regulatory Guide, or
- 3) Provide additional detail and direction on how Regulatory j_ Guide intent will be accomplished, or
- 4) Exclude structures housing radwaste systems from OBE seismic requirements above a height sufficient to contain the maximum .
( liquid inventory expected to be in the building, or
- 5) Exclude Duke's Q A Program condition 2 requi.rements for those i radwaste ALARA structures signi ficance., systems or components that have no 1-9
_t_._ __.____a.: _m.-__ =-_ _-
Rsv. 10 DUKE POWER COM/ANY NUCLEAR GUIDE 1.143, REVISION
,.j A. INTRODUCTION -
See Regulatory Guide 1.143 i
- 8. DISCUS $10N 1
Duke Nuclear Guide 1.26 describes system design classifications used to l differentiate functional, component and quality Assurance requirements.'
-Fluid systems that contain or mav .a tain radioactive materials in solid, liquid or gaseous form may be Ido. til'ed with one of three categories.
Safety related systems are those we os : postulated failure would resu.It in conservatively calculated offsite doses comparable to the values pres'ented in 10 CFR 100. Safety related fluid systems are always classified as A, 8 or C. Duke Class E systems are those whose postulated failure would result in conservatively calculated offsite doses less than the limits of 10 CFR 20. In this context, Duke Class E and Radwaste systems are Inter-changeable terms. Systems that contain or may contain radioactive material whose postulated failure would result in conserd tively calculated offsite doses of a trivial nature are excluded from both safety related and radwaste .
considerations. Examples of this~1atter class-are the steam generator blowdown system, secondary systems in general (condensate /feedwater exclusive of safety related boundary) floor drains, equipment vents beyond valves and auxiliary building HVAC systems exclusive of Spent Fuel Pool
( '
HVAC systems. A trivial dose is small compared to the design guides of 10 CFR 50 Appendix 1.
Duke Nuclear Guide 1.143 addresses Duke Class E systems as described above
- exclusively.
Regalatory Guide 1.143 Section B is adopted subject to the following clarification and discussion.
This Nuclear Guide 1.143 consists of NRC Regulatory Guide 1.143 partially rewritten to reflect additional existing recognized guides and criteria which adequately define design requirements for radioactive waste management systems.
l C. REGULATORY POSITION C.1 ' Systems HandIIng Radioactive Materials in Liquids l C.I.I The IIquid radweste treatment system should meet the follwing criteria:
l C.I.l.1 See Regulatory Guide 1.143 i C.I.1.2 Materials for pressure-retaining components should conform to the requirements of the-specification as shown in Table I except that l
l r
(
___.,.[1. *
- g. , , _ , _ _ . , . , _ .__ ,,
. .,. Pag 3 4 ef 10 6-21-82 l R3v. 10 pollocbio, wrought, cr ccst Ircn matarlais cnd plastic pipa shruld not be used. Exception to these material restrictions may be allowed on
, selected components when other than steel material is justified by
-(- ' documented and approved engineering evaluations. Materials should be compatible with the chemical, physical, and radioactive environment of specific appilcations during normal conditions and anticipated operation occurrences.
C.1.1.3 See Regulatory Guide 1.143 .
C.I.l.4 See Regulatory-Guide 1.143 C.I.2 All tanks located outside reactor containment and containing radioactive materials in liquids should be designed to prevent uncontrolled releases of radioactive materials due to spillage in buildings or from outdoor tanks. The following design features should be included for tanks that may contain radioactive materials: .
C.I.2.1 All tanks inside and outside the plant should have provisions to ,
monitor IIquid levels. Potential overflow conditions should actuate-alarms such that proper action can be taken.
l C.I.2.2 All tank overflows, drains, and le lines should be routed to the liquid radweste treatment system l
! C.I.2 3 Areas containing Indoor tanks should have floor drains routed to the liquid radweste treatment system.4 l l
f C.I.2.4 See Regulatory Guide 1.143 i .
C.1.2 5 See Regulatory Guide 1.143 C.2 Gaseous Redwaste Systems
[
j C.2.1 Gaseous Radwaste Systems classified Duke System Class C are described in Duke Nuclear Cuide 1.26. The following paragraphs apply to Duke Class E systems containing radioactive gases.
C.2.1.1 See Regulatory Guide 1.143 ,
C.2.1.2 See Regulatory Guide 1.143
( C.2.1.3 See Regulatory Guide 1.143 C.3 Solid Radwaste System
.. C . 3.' l DukeClassEsolidradwestesystemsconsistofslurrywestecollectly and settling tanks, spent resin storage tanks, phase separators, and components and subsystems used to solidify, compact, incinerate or otherwise reduce the volume of radwastes prior to offsite shipment.
The solid radweste handling and treatment system should meet the
. following criteria: ,
C.3.1.1 See Regulatory Guide 1.143
_ - _ _ _ _ _ _ _ _ .. = __ - - .- .. .- . . - . ---. - -. -
,,y .. m . .,
,, Pag 35 cf to 6-21-82 Rnv. la C.3.1.2 Materials for pressure-retalning components should conform to the requirements of specifications as shown in Table 1, except that t
malleable, wrought, or cast Iron materials and plastic pipe should not be used. Exception to these material restrictions may be allowed on selected components when other than steel material is justified by ' ~
documented and approved engineering evaluations. Materials should be compatible with the chemical, physical, and radioactive environment of specific applications.during normal conditions and anticipa_ted occur-rences.
C.3.1.3 See Regulatory Guide 1.143 C.3.1.4 See Regulatory Guide 1.143 4
C.4 Additional Design, Construction, and Testing Criteria-C.4.1 See Regulatory Guide 1.143 C.4.2 See C.6 of this Nuclear Guide -
C.4.3 Pressure-retaining components of process systems should use welded construction to the maximum practicab".' extent. Process systems include the first root valve on sample and Instrument lines. Flanged joints or suitable rapid-disconnect fitting should be used only where maintenance or operational requirements clearly Indicate that such construction is preferable. Process lines should not be less than 3/4 inch (nominal).
Socket weld joints should be used on lines 3/4 inches or larger but less than 21/2 inches, except for Instrumentation and components furnished with
! screwed connections. For lines 2 1/2 inches and above, pipe welds should be of the butt-Joint type. Nonconsumable backing rings should not be used in lines carrying resins or other particulate material. All welding constituting the pressure boundary of pressure-retaining components should be performed in accordance with ASME Boller and Pressure Vessel Code Section IX.
C.4.4 Piping systems should be hydrostatically tested in their entirety during the Construction phase except for atmospheric connections where no isolation valves exist.
Pressure testing thould be performed on as large a portion of the Inplace systems as practicable. Testing of piping systems during the Operation phase should be performed in accordance with applicable ASME or ANSI codes.
C.4.5 See Regulatory Guide 1.143 C.5 Seismic Design for Structures Housing Radwaste Management Systems Below a Height Sufficient to Contain the Maximum Liquid Inventory Expected to be in the Structure.
V C.5.1 See Regulatory Guide 1.143
(
.; P:ga 6 cf 10 6-21-82 Rsv. 10 C.5.1.1 Sss R:guletary Guida 1.143
- C.5.1.2 See Regulatory Guide 1.143
.. C.5.1.3. See Regulatory Guide 1.143 C.5.2 See Regulatory Guide 1.143 C.5.2.1 Same as Regulatory Guide 1.143 with the following addition:
These criteria apply to that portion of the structure described in Section C Regulatory Position, subsection 1.1.3 only. In addition, the seismically designed portion of the building structure should include elimination of potential pathways for leakage should a radioactive spIII occur by I) providing curb walls around areas for potential spills that can contain the liquid Inventory, 2) provide a positive means to prevent leakage from all construction joints located below the spill level, and 3) install-Ing leak tight seals over expansion joints located below the spill level.
All other structural portions shall be designed to the sane criteria as conventi snel power plants and treatment facilities with the addition of specif ~u ALARA design features.
The design will assure that the 1 in 100 year wind load, and the I in 100 year flood (both precipitation and river basin flooding are to be considered) are properly accounted to preclude structural failure from these events and allow the facility to remain operable.
C.5.2.2 See Regulatory Guide 1.143 C.S.2.3 See Regulatory Guide 1.143
, C.S.2.4 See Regulatory Guide 1.143
( C.5.2.5 See Regulatory Guide 1.143 C.5 2.6 See Regulatory Guide 1.143 C.5 3 See Regulatory Guide 1.143 C.6 quality Assurance for Radwaste Management Systems Since the impact of these systems on safety is limited, the extent of control required by Appendix B to 10 CFR Part 50 is similarly limited.
To ensure that systems will perform their intended function, a quality assurance program sufficient to ensure that all design, construction, and testing provisions are met should be established and documented.
Quality assurance for radweste management systems conforms to Duke Power Company's quality assurance program for S Condition 2 (Radwaste/ Class E).
A correlation between NRC quality groups, ANS safety classes, and Duke i system classifications is presented in Table 2 of Duke Nuclear Guide 1.26.
i -
Duke's quality assurance program for Duke y Condition 2 adequately meets the QA requirements of ANSI N 199-1976/ANS-55.2 as reprinted in Regulatory Guide 1.143.
- ' General application of Duke's quality Assurance Program to design / l procurement and cor.struction activities for S Condition 2 is summarlzed
(
l l r x__ _ _
,;. Paga 7 cf 10 6-21-82 R3v. Io In Tcbiss 3 and 4 resp:ctivaly of Duka Nucloor Guida 1.26 which document Duke's policy on the applicability of qua:Ity assurance to these activities. Specific details on the degree or extent of quality assur-
~i ance applied and implementation dates therof are defined in Duke's h.--' . quality Assurance Program. .
As Duke's @ Program for S Condition 2 is' limited, performance of quality related functions may be performed by any.one or a combination of Design Engineering, Construction, Steam Production, quality Assur-ance Departments and by satisfactorily meeting the requirements of Duke procedures for ANSI B3'.1.0 Power Piping Systems.
Specific application of Duke's quality Assurance Program to design -
procurement and construction activities is limited to those items which are ALARA related; those items whose failure or loss of function are not judged to be radiologically significant are specifically '
excluded from QA Condition 2 but do require conventional quality
- standards of performance as described in appropriate Duke Power Co.
procedures and specs. A partial list of included and excluded items is provided as Table 2 of this Guide. _ j f ,, g Equipment Codes and Standards for Duke @ Condition 2, described in Table i of this Nuclear Guide. U Sufficient records are maintained to furnish evidence that Duke's quality Assurance Program is being properly implemented during QA procedures as described in appropriate construction procedures but will as a minimum include: .
( 1. Inprocess work will be randomly inspected visually and items of noncon-formance will be documented.
- 2. A final verification of system functional configuration will be documented.
D. IMPLEMENTATION See Regulatory Guide 1.143 REFERENCES See Regulatory Guide 1.143
.s
,_ _ . _ _ . -_ -_-o-. - -- -
~
l -
pgge rS 10 '6-?242
'Ra, .o TABLE 1 t
EQUIPMENT CODES FOR DUKE SYSTEM PIPING CLASSIFICATION E (ALL STATIONS)
I
- EQUIPMENT CODES Welder Qualification 3
Design and Fabrication Materialsl and Procedures inspection and Testinq Prsssure Vessels ASME Code Section Vill, ASME Code Section 11 ASME Code Section IX ASME Code Section Vill, j
Div. I Div. I Atmospheric Tanks ' ASME Code 3 Section Ill, 2 ASME Code Section 11 ASME Code Section IX ASME Code3 Section lit,-
Class 3,ogAPI650,or Class 3 or Agt 650, AWA D-100 , or ASME or AWA D-100 , or ASME_ Code Section Vill, CodeSgctionVill, Div. I k Div. I 2 3 0-15 PSIG Tanks ASME Code 3 SectIon ASME' Code SectIon iI ASME Code SectIon IX ASME Code SectIon Class 3,orAPI620{lI, ,
- Class 3,orAPI620{lI, ,
or ASME Code Section or ASME Codg Section Vill, Div. 1 Vill, Div i Hest Exchangers ASME Code Section Vill, ASME Code Section ll ASME Code Section IX ASME Code Section Vlli,
(
' Div. I and TEMA ,
Div. I Piping &nd Valves ANSI B31.1 ASTM or ASME Code ASME Code Section IX ANSI B31.1 Section 11 (as required) 3 l Pumps Manufacturers' ASME Code Section 11 ASME Code Section IX ASME Code Section lit, Standards or Manufacturers' (as required) Class 3 or Hydraulic Scandards Institute Standards Notss:
1 Material certification only as required of manufacturer for ASME Code Section Vill stamped components. ,
2 Fiberglass reinforced plastic tanks may be used in accordance with appropriate articles of Section 10, ASME Boller and Pressure Vessel Code, for. applications at ambient temperature.
3 ASME Code stamp, material traceability, and the quality assurance criteria of Appendix B to 10 CFR Part 50 are s not required. Therefore, these components are not classified as ASME Code Class 3 j 4 Manufacturer's standard for the, intended service. Hydrotesting should be 1.5 times the design pressure. -l 5 ASME Code stamp, material traceability, and the quality assurance criteria of Appendix B to 10 CFR Part 50.are <
I
., n > -an.. I red Thar rnr. ch. n cennn ne.: ar. noe e,1as,Irt..d as ASMr e nda Sec. tion VIII.
" ' ' *E 6-21-82 Page 9 of 10 R3v. Io
.[a TABLE 2 '
APPLICABILITY OF DUKE QUALITY ASSURANCE PROGRAM QA CONDITION 2 APPLIES TO ALARA RELATED FUNCTIONS AS PRESCRIBED IN REGULATORY GUIDE 1.143* DOES NOT APPLY RADWASTE PROCESS SYSTEM DESIGN FUNCTIONS SPECIFIC NON-ALARA ITEMS SUCN AS VALVE OPERATORS, ASSOCIATED RADWASTE PROCESS SYSTEM PUMP MOTORS, AND READILY FABRICATION & CONSTRUCTION ACTIVITIES REPLACEABLE ITEMS ASSOCIATED RADWASTE PROCESS SYSTEM PROCUREMENT LiqulD RADWASTE BUILDINGS ACTIVITIES RADWASTE PROCESS SYSTEM EFFLUENT CONTROL FEATURE DESIGN FUNCTIONS COMPONENTS BEYOND FLUID PRESSURE BOUNDARY, THAT ASSOCIATED EFFLUENT CONTROL FEATURE IS, SUPPORTS / RESTRAINTS FABRICATION AND CONSTRUCTION ACTIVITIES INSTRUMENTATION AND CONTROLS, ETC.
ASSOCIATED EFFLUENT CONTROL FEATURE ,
PROCUREMENT ACTIVITIES STRUCTURAL ALARA DESIGN FEATURES & AS-BUILT COMPLIANCE STRUCTURAL SEISMIC DESIGN FEATURES l
t
- ALARA related functions are those important to meet Individual station Technical specification design ob,Joct1ves.
(
...,*o*
, m Page 10 of 10 6-21-82 !
R v. le l
l (s
Footnote Paae I
See Regulatory Guide 1.143 2
See Regulatory Guide 1.143 3
See Regulatory Guide 1.1.43 N
See Regulatory Guide 1.143 5see Regulatory Guide 1.143 6
See Regulatory Guide 1.143 7see Regulatory Guide 1.143 8
See Regulatory Guide 1.143 9 See Regulatory' Guide 1.143
.s a - _
n . - .
Revision 1
"'** U.S. NUCLEAR RE2ULATORY COMMISSIEN Octoberas7s
! S REGULATORY GU DE
<' OHICE OF STANDARDS DEVELOPMENT N -
REGULATORY GUIDE 1.143 DESIGN GUIDANCE FOR RADIOACTIVE WASTE MANAGEMENT SYSTEM 3, STRUCTURES, AND COMPONENTS INSTALLED IN LIGHT-WATER-COOLED NUCLEAR POWER PLANTS A. INTRODUCTION This guide furnishes design guidance acceptable to the NRC staff relating to seismic and quality group classifica-Paragraph (a) of $ 50.34," Contents of applications; tech- tion and quality assurance provisions for radioactive waste -
nical information," of 10 CFR Part 50, " Domestic IJcenang management systems, structures, and components. Further, of Production and Utilization Facilities," requires that each it describes provisions for controlling releases of liquids con-application for a construction permit include a prehminary taining radioactive materials, e.g., spills or tank overflows, safety analysis report. Part of the information required is from all plant systems outside reactor containment. The
- j related to quality assurance and the preliminary deagn of Advisory Committee on Reactor Safeguards has been con-the facility, including, among other things, the principal suited corcerning this guide and has concurred in the regu-design criteria for the facility. Appendix B," Quality Amur- latory position.
ance Criteria for Nuclear Power Plants and Fuel Reprocesang Plants," to 10 CFR Part 50 establishes ove,ill quality assur- B. DISCUSSION ance requirements for structures, systems, and components important to safety. Appendix A," General Dessa Criteria One aspect of nuclear power plait operation is the con-for Nuclear Power Plants," to 10 CFR Part 50 :stablishes trol and management of liquid, gaseous, and solid radiosc-minimum requirements for the principal design criteria for tive waste' (radwaste) generated as a byproduct of nuclear light-water cooled nuclear power plants. power. The purpose of this guide is to provide information and criteria that will provide reasonable assurance that com-Criterion I," Quality Standards and Records," of Appen- ponents and structures used in the radioactive waste manage-dix A requires that structures, systems, and components ment and steam generator blowdown systems are designed,
'7 important to safety begiesigned, fabricated, erected, and constructed, installed, and tested on a level c~ommenscrate
( '
tested to quality standards commensurate with the impor- with the need to protect the health and safety of the pub-tance to safety of the safety function to be performed and lic and plant operating personnel. It sets forth minimum that a quality assurance program be established and imple- staff recommendations and is not intended to prohibit the mented in order to provide adequate assurance that these implementation of more r'gorous design considerations, structures, systems, and components will satisfactorily codes, standards, or quality assurance measures.
perform their safety function. Criterion 2, " Design Bases for Protection Against Natural Phenomena,"of Appendix A Working Group ANS-55, Radioactive Waste Systems, of requires, amo'is other things, that structures, systems, and Subcommittee ANS-50, Nuclear Power Plant System Engi-components important to safety be designed to withstand neering, of the American Nuclear Society Standards Com-the effects of nateal phenomena such as earthquakes with- mittee has developed standards that establish requirements out loss of capability to perform their safety functions and and provide recommendations for the design, construction, that the design bases for these structures, systems, and com- and performance of BWR (ANSI N1971976) and PWR ponents reflect the importance of the safety functions to be (ANSI N199-1976) liquid radioactive waste processing performed. Criterion 60, " Control of Releases of Radioac- syetems. Working Group tNS-55.6 is currently develop-tive Materials to the Environment,"of Appendix A requires ing a standard that will combine and eventaally replace that the nuclear power unit design include means to control N197 and N199. Two standards, ANSI /ANS 55.1 1979, suitably the release of radioactive materials in gaseous and ' Solid Radioactive Waste Processing System for IJsht-Water-liquid effluents and to handle radioactive solid waste pro- Reactor Plants," and ANSI /ANS 55.4-1979,"Gassous Radio-duced during normal reactor operation, including .antici- active Wasic Processmg Systems for IJsht Water Reactor pated operational occurrences. , ,
. s ,or u Lin Indicat. a.t tiv. ch.ne Ar pr.vi vor.l.a. op.r. tins sr.d cts c.o.at.ime.s.r.ds weld e.tiv. m.t rt.i. en.: ayproc. d pel ra.to Sn.1 di.
al.or USNRC AEGUL.ATORY SulOES ts s. nt to th. S.c y of C mg.
Wm.t .N N NNc .t m.NtN n.e t u m. roe e i;, m .
.,,,,.,;. ,=,ggo,, ,g, ,,,cy.,.,,,,gyg.g.aff
, .t .
2::="2"4h "Jaa.'l'f.* ':e **lll' 4 ' ,N,
- t..Y." g. ,=-
J.s a k *n*."l".3:'# P n t 1: Ollll",,t.u.o
/. "* t L*f.r.#"t lllMam . -
p " g=j;g,.,,;;;.,,,u a,,,,,it#
r**.'" .*..
U2'., P':":.J"f#.rt"Mio".'lll'. w - ta.2%*."fa."?on.tf,".P".'.
- l".,J'rs: . iw 2o te. r f
e.mm.m. 2l o' E'.*JM'll's.Ol ,*a"* .'.!.' *.* % L*ll""".'
e.',"m;p,'mr===.',=.'==Q.o m : m w h f. i ., - u i.e ,.=:mim.m . o .m
=::cmm = aimwax--- e.== v.awama=p.rr. :
.s
m -
a . m ... . .._. .
Equids and routing them to the liquid radweste treatment Table I supplemented by regulatory positions 3.1.2 and 4 of
, system. this guide.
I
's ,
- 2. GASEOUS RADWASTE SYSTEMS 3.1.2 Materials for possure<etsining componena should conforra to the requirements of the specifications for mate-s 2.1 The gaseous radweste treatmentsystem abouldmeet rials listed in Section II of the ASME Boiler and Pressure the fouowing criteria: Vessel Code,3 except that malleable, wrought, or cast iron l materials and plastic pipe should not be used. Materials 2.1.1 The systems should be designed and tesM to re- should be compatible with the chemical, physical, and l radioactive environment of specific applications during quirements wt forth in the codes and standards listed in Table l normal conditions and anticipated operational occurrences.
i supplemented by regulatory positions 2.1.2 and 4 of this j Manufacturers' material certificates of compliance with I
pide.
! , material specifications such as those contained in the codes 2.1.2 Materials for pressureretaining components referenced in Table ! may be provided in lieu of certified i
l should conform to the requiren.ents of the specifications materialt test reports.
for materials listed in Sectica!! of the ASME Boiler and Pressure Vessel Code,s except that maneable, wrought, or 3.1.3 Foundations and adjacent walls of structures l
l cast iron materials and plastic pipe should not be used. that house the solid radwaste system should be designed to Materials should be cosapetible with the chassical, physical, the seismic criteria given in regulatory position 5 of this and radioactive environment of specific applicaticos during guide to a height sufficient to contain the maximumliquid normal condhions and anticipated operational occurrences. lf inventory expected to be in the building.
I the potential for en explosive mixture of hydrogen and oxygen exists, adequate provisions should be made to 3.1.4 Equipment and cortponents used to collect, l
preclude buildup of explosive mixtures, or the system .
process, or store solid radwas'es need not be designed to should be designed to withstand the effects of an explosion. the seismic criteria in regulatory position 5 of this guide.
"snufacturers' material certificates of compliance with sterial specifications such as those contained la the codes 4. ADDITIONAL DESIGN, CONSTRUCTION, AND TEST-refersacsd in Tsble I may be provided la lieu of certiSed ING CRITERLA materials test reports.
In addition to the requirements inherent in the codes 2.1.3 Those portions of the gaseous radweste treatment and standards listed in Table 1, the following criteria, as a systesa that are intended to store or delay the release of minimum, should be implemented for components and
- k. " gaseous radioactive waste, including portions of structures systems considered in this guide. 1 housing these systems, should be designed to the seismic )
design criteria given in regulatory position 5 of this pide. 4.1 Radioactive waste management structures, systems, l
For the systems that norsaaDy operate at pressares above er.d components should be designed to controlleakage ard ,
l 1.5 etmospheres (absolute), these criteria should apply to facGitate access, operation, inspection, testing, and main-isolation valves, equipraest, in; ir_r ^'=5 piping, and senance in order to maintain radiation exposures to operating l l
components located between tbs upstream and downstressa and maintenance personnel as low as is reasonably achievable. ,
volves used to isolate these componen;s fross the rest of the Regulatory Guide 8.8 provides guidelines acceptable to the i l l system (e.g., waste gas storses tanks la the PWR) sad to the NRC staff on this subject. l building housing this equipment. For systesse that operate near ambient pressure and retain asses on charcoal adsorbers, 4.2 The quality assu.ance provisions descritad in regula-theos criteria should apply to the tank sapport elessents tory position 6 of this guide should be applied. '
7 (e.g., charcoal delay tanks la a BWR) and the building l 4.3 Pressure-retaining components of process systems housing the tasks.
should use welded construction to the maximum practicable
- 3. SOLID RADW4STE SYSTEM extetf. Process systems include the first root valve on l sampis sad instrument lines. Flanged joints or suitabte 3.1 The solid redweste system consists of sharry weste rapid disconnect f*ttings should be used only where main-tensace or operetional requirements clearly indicate that
)
i codaction and settling tanks, spent resia storage tanks,phaos separators, and components and subsystesse used to solidify such construction is prefersble. Screwed connections in 1 redwestes prior to offsite skipassat. The solid redweste han- which threads provide the only seal should not be used l dling and treatassatsystem shouldeset the folkndag criteria: except for instrunsentation and cast pump body drain and I j
. vent connections where veelded connections are not suitable. l' 3.1.1 The systeen should be designed and tested to the Process lines should not be less than 3/4 inch (nominalt Screwed connections besked up by seat welding. mechanical seguiressants set forth la the codes and standards listed la joints, or socket welding may be used on lines 3 l inches or ,
larger but less than 21/2 inches. Forlines 2-1.2 inches and
,/
above, pipe welds should be of the butt-joint type. Noncon-l ( .,
s,,,,,,,,,,,,,,,,,,,,,,,,,
y
.eness entes sessesas nem me asse Mg,,,,,,,,,,,,,
veemen sysosa sumable backing rings should stot be used in lines carrying i
,t'sh'ad's 88,8,,8,pe,ine ,g er,,
son she g
esear g resins or other particulate material. All welding constituting the pressure boundary of pressure retaining components a=*-* et ausse suspeed tross me putmary seasses, I.143 3
.s
~~
___---______m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- - - _. _ _ _ . + - - , - , . , , , _ - ,.* , - . , - _ . . , E &_
. a
.n: . ~ ~ . --
s- . : -
l American Nuolear Seelety from ANSIN199 !ff6/ANS SS.2, of items which have estaafectoruy passed required inspec.
,.- " Liquid Radienstive Weste Prosesslag System for Proens* tions and tests.
land Water Reaster Plants."a
\. "(3) Identifloation and Corrective Action foritems -
"4.2J Quality Control. 'fhe desisi, procurement, of Nonconformance, mesures should' be established to tabeleation and sometruction activities shall conform to the identify items of nonconforreance with neerd to the require-quality control provisloes of too sodes and standards spo- monts of the procurement documents or applicable codes eined herein.' la addition, or where not covered by the and standards and to identify the action taken to correct referenced codes and standards, the fouowing quality such items."
eostrol features sha!! be established.
la Section d.2.3.2(3)," items of nonconformance"should "4.2.3.1 System Desigast and Procurer be laterpnted to include failures, malfunctions, deficiencies, deviations, and defective materiJ and equipment.
"(l) Deelen and Procurement Document Con-trol-Design and procurement documents shall be ladopen. Sufficleat records should be maintained to furnish l destly verifled for conformance to the G ' m teoftijs evidence that the measures identified above are being l standard by ladividual(s) within the design organisation Isaplemented. The records should include results of nviews who are not the origlasters of thw document. Changes to and laspections and should be ide.itifiable and retrievable.
)
these documants shaR be verined or sentroDed to malatala conformance to this standard. D. IMPLEMENTATION
"(2) Control of Purchased Material, Equipsnent The purpose of this section is to provide information to ,
and Services-Measures to ensure that suppliers of material, applicants regarding the NRC staff's plans for using this I equipment and sometruction services are capable of supply. regulatory guide. l las these itsens to the quality spectned la the procurement I documents shan be established, This may be does by an This guide reflects curnat NRC staff practice as out-evaluation or a survey of the suppliers' products and faculties, lined in Standard Review Plan Sections 11.2,11.3,and 11.4 The method presented la this guide has been recognized l "(3) Handling, Storage, and Shipping-Instructices as acceptable for complying with the Commis21on's neula-
, 4 shall be provided la procurement documents to ocetrol the tions since November 1975.
( handling, storage, shipping and preservation of material and
\ v, equipment to prevent damage, deterioration or nduction of Therefore, except in thoes cases in which the applicant steassess, proposes an acceptable alternative method for complying with specified portions of the Commission's regulations. the "4.2.3.2 System Constructor method described herein is being and wGl continue to be
. used in the evaluation of the following applications:
"(1) Inspection. la addition to required code laspec-ticas a program for inspection of activities affeains quality 1. Prehminary Design Approval (PDA) applications and chan be established and executed by, or for, the orqamine- Prolhnimary Duplicate Design Approval (PDDA) appli-tion performing the activity to verify conformasse with cations.
the documented instructions, procedures, and drawings for accomplishing the activity. This shan include the vimal 2. Final Design Approval, Type 2,(FDA 2) applications laspectica of components prior to instaustion for conform- and FinalDuplicate Design Approva!, Type 2.(FDDA 2) anos with procurement documents and the vimaallaspection applications.
of items aad systema foDowing lastanetice, r.semaness and possivatica (where applied). 3. Manufacturing License (Mi.) applications.
"(2) Inspection, Test and Operating Status. Mee- 4. Construction Permit (OP) applications except for sures should be established to provids for the identification those portions of CF opplications that reference standard designs (Le., PDA, FDA l. FDA 2. PDDA.
eAsespasse sedu and seenderes ese lednessed en Tease i er oss FDDA 1, FDDA 2, or ML) or that reference qualifieJ sende. bene plant designs under the replication option.
J.
,a 1.143 5
- - - - - - , . , , - - , - - , - ,,.,-n-n.,,n - , , _ - , - - - , - ,,.,,,-,.-,-y
, --, , ., , - ,,_ , ,,,,se,_,-., , , , ,
- - .= , - . ~ . . - - - - - -
{ '
REFERENCEE
'T .
- 1. Kapur, K. K. and Shao, L. C., " Generation of Selsenc Paper E 4/7, North Holland Publishius Co., Amsterdam, Floor Resposes Spectra for Equipment Design,"Spe- the Nethedaads, cisity Con {mnet on Struerwel Degn of heleer flewer FIsnt Facilitier, December 1718,1773 (ASCE, 3. Tokart, F. J., Arthur D. F.,and Murray, R. C.,"Evalue-Chicago,1973), Vol.1, pp. 29 71. tion of Methods for Seismic Analysis of Mixed 4mide Fuel Fabrication Plants,"* UCRL 51928, October 8,
- 2. Biggs, John M.,"Seisans Respoess Spectra for Equip- 1975.
mest Design la Nuclear Power Plants," F>et inferns-tional Cen/ mace on Struerwel Mechender in Rosetor copies he obeatmed hesi the Ndenes Technical Interme.
TeeAnology, Germany (September 1971), RL'R 4820, een servise7:ss Port Reyel Rose, Springnole, Vereinte 32368.
e'
,1
( .
1.143 7
_ __ _ _ _