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DOC.20080226.0002 QA: QA ANL-WIS-MD-000024 REV 01 February 2008 Postclosure Nuclear Safety Design Bases Prepared for: U.S. Department of Energy Office of Civilian Radioactive Waste Management Office of Repository Development 1551 Hillshire Drive Las Vegas, Nevada 89134-6321 Prepared by: Sandia National Laboratories OCRWM Lead Laboratory for Repository Systems 1180 Town Center Drive Las Vegas, Nevada 89144 Under Contract Number DE-AC04-94AL85000

Transcript of Postclosure Nuclear Safety Design BasesPostclosure Nuclear Safety Design Bases . Prepared for: U.S....

  • DOC.20080226.0002

    QA: QA

    ANL-WIS-MD-000024 REV 01

    February 2008

    Postclosure Nuclear Safety Design Bases

    Prepared for: U.S. Department of Energy Office of Civilian Radioactive Waste Management Office of Repository Development 1551 Hillshire Drive Las Vegas, Nevada 89134-6321

    Prepared by: Sandia National Laboratories OCRWM Lead Laboratory for Repository Systems 1180 Town Center Drive Las Vegas, Nevada 89144

    Under Contract Number DE-AC04-94AL85000

  • DISCLAIMER

    This report was prepared as an account of work sponsored by an agency of the United States Government. Neitherthe United States Government nor any agency thereof, nor any of their employees, nor any of their contractors,subcontractors or their employees, makes any warranty, express or implied, or assumes any legal liability orresponsibility for the accuracy, completeness, or any third party’s use or the results of such use of any information,apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the UnitedStates Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

    DISCLAIMER

    This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third party’s use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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    Postclosure Nuclear Safety Design Bases

    ANL-WIS-MD-000024 REV 01

    February 2008

  • ANL-WIS-MD-000024 REV 01 February 2008

  • ACKNOWLEDGMENTS

    The development of this document reflects much insightful and thorough input from several sources, especially from people mentioned on the signature page which include contributors, checkers, reviewers, and the document preparation staff. All of their efforts are most appreciated.

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    Page v1. Tolal Pages: 412

    POnied Narre

    Roger J. Henning

    James Kam {Le.ld Checker}

    Scientific Analysis/CalculationSignature Page/Change History

    Compjete only applicable items.

    John Devers

    .. ."li;~'~~~V~~~hJ1·····-·--rK~;h~~KI;O~t.i~.~.~.••••...

    6 QCSJLead ,-"b QA He"cwer

    5 Cheder

    4. Originator

    3. 01 (Including RlNisioo No. and AddendUm No.)

    ANL-WIS·MD-000024 REV 01

    9. Remarks

    Contributors: Robert MacKinnon. Ralph Wagner, Steve Goodin and Richard Snell.

    Additional Contributors: ClifTHo, David Sassani, David Sevougian. Frank Hansen, James Blink. JamesIlouseworth, Kathy Turnham. Laura Price, Lorenzo Salgado. Patrick Brady, Ming Zhu, James Cunnane. and NeilBrown.

    Additional Checkers: David Stahl, Emma Thomas. Kenneth Rehfeldt, Russell Jarek, Stephanie Kuzio, StevenAlcorn, Cliff Howard. John W. Kelly, Charles Haukwa. Dwayne Kicker. Jeffrey Gromny.Reviewers: Robert Andrews, David Franklin, Erncslllardin, t'rank Hansen, J. S. Whitcran, Jack Bailey, JamesLinhart, Ming Zhu, Neil Brown, Prasad Nair. Robert H. Spencer. Rob Howard, Robert Gllrren, Terry Crump, AlanRoss. Daniel Levin, and Danny Howard.

    Document-Preparation Slaff: Anita Walker. Bonnie Gabaldon. Connie Beglinger, Danette Nurse, Madbu·Shrivastava. Valerie Kelly, faith Puffer. and Caroline Parks.

    Ch.ng. History................... . .•........•

    10. Re.,ostOn ~anc!.!'

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    CONTENTS

    Page

    ACKNOWLEDGMENTS ............................................................................................................. iii

    ACRONYMS............................................................................................................................... xiii

    1. PURPOSE.............................................................................................................................. 1-1

    2. QUALITY ASSURANCE..................................................................................................... 2-1

    3. USE OF SOFTWARE ........................................................................................................... 3-1

    4. INPUTS.................................................................................................................................. 4-1

    4.1 DIRECT INPUTS......................................................................................................... 4-1

    4.2 CRITERIA.................................................................................................................... 4-9 4.3 CODES, STANDARDS, AND REGULATIONS...................................................... 4-10

    5. ASSUMPTIONS.................................................................................................................... 5-1

    6. SCIENTIFIC ANALYSIS DISCUSSION............................................................................. 6-1

    6.1 BARRIER ANALYSIS ................................................................................................ 6-4

    6.1.1 Definitions ........................................................................................................ 6-5

    6.1.2 Identification of Barriers................................................................................. 6-10

    6.1.3 Identification of Features ................................................................................ 6-16

    6.1.4 Description of Processes and Events .............................................................. 6-19

    6.1.5 Methodology for Important to Barrier Capability/Important to Waste

    Isolation Evaluation ........................................................................................ 6-28

    6.1.6 Core and Control Parameter Characteristics................................................... 6-30

    6.1.7 Integration of the Performance Confirmation Program.................................. 6-35

    6.1.8 Methodology for Postclosure Change Evaluation .......................................... 6-36

    6.2 SYSTEM DESCRIPTION AND DEMONSTRATION OF MULTIPLE

    BARRIERS................................................................................................................. 6-37

    6.2.1 Identification of Barriers................................................................................. 6-40

    6.2.2 Barrier Capability Description........................................................................ 6-51

    6.2.3 Technical Bases for Barrier Capability......................................................... 6-100

    6.2.4 Summary....................................................................................................... 6-108

    6.3 NON-BARRIER-SPECIFIC FEATURES EVENTS AND PROCESSES .............. 6-110

    7. CONCLUSIONS.................................................................................................................... 7-1

    8. INPUTS AND REFERENCES............................................................................................ 7-42

    8.1 DOCUMENTS CITED................................................................................................. 8-1

    8.2 CODES, STANDARDS, REGULATIONS, AND PROCEDURES............................ 8-8

    8.3 PRODUCT OUTPUT................................................................................................... 8-9

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    APPENDIX A �ITBC EVALUATION AND PARAMETER DESCRIPTION FOR THE

    BARRIERS...................................................................................................... A-1

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    FIGURES

    Page

    6-1. Relationship between FEPs; Core Parameter Characteristics; Control Parameter Characteristics; and Design-Related Systems, Structures, and Components .................. 6-8

    6-2. Relationship between ITS, ITWI, ITBC and Control Parameter Characteristics

    and Core Parameter Characteristics and Their Controlling or Monitoring Mechanisms ..................................................................................................................... 6-9

    6-3. Schematic Illustration of the Multiple Barrier Repository System................................ 6-14

    6-4. Schematic of ITBC/ITWI Process with Ties to Performance Confirmation

    Activities ........................................................................................................................ 6-15

    6-5. Schematic of the Upper Natural Barrier ........................................................................ 6-44

    6-6. Schematic of the Engineered Barrier System ................................................................ 6-46

    6-7. Schematic of the Lower Natural Barrier........................................................................ 6-50

    6-8. Unsaturated Zone below the Repository Horizon.......................................................... 6-52

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    TABLES

    Page

    4-1. Source of Inputs ............................................................................................................... 4-2

    4-2. Cross Reference for Information Categories in 10 CFR Part 63 ................................... 4-10

    6-1. Source of Indirect Inputs.................................................................................................. 6-1 6-2. Features/Components for Each of the Three Barriers.................................................... 6-16

    6-3. Mapping of Processes and Events to Features/Components of the Three Barriers ....... 6-18

    6-4. Relationship among TSPA Model Components, Submodels, and

    Abstraction/Process Model(s)/Analysis(es)................................................................... 6-22

    6-5. Core Parameter Characteristics...................................................................................... 6-31

    6-6. Control Parameter Characteristics ................................................................................. 6-33

    6-7. NUREG-1804 and 10 CFR Part 63 Crosswalk Table.................................................... 6-39

    6-8. Non-Barrier-Specific Features and Events .................................................................. 6-110

    7-1. ITWI Features / Components Supporting Each of the Three Barriers............................. 7-5

    7-2. ITBC Features / Components and ITBC Parameter Characteristics of Upper

    Natural Barrier ............................................................................................................... 7-10 7-3. ITBC Features / Components and ITBC Parameter Characteristics of Engineered

    Barrier System ............................................................................................................... 7-12 7-4. ITBC Features / Components and ITBC Parameter Characteristics of Lower

    Natural Barrier ............................................................................................................... 7-26 7-5. Summary of Classification of Control Parameter Characteristics by Engineering

    Subsystem Categorization1 ............................................................................................ 7-29

    A-1. ITBC Analysis of Upper Natural Barrier FEPs .............................................................. A-1

    A-2. ITBC Analyses of Engineered Barrier System FEPs.................................................... A-30

    A-3. ITBC Analysis of Lower Natural Barrier FEPs.......................................................... A-168

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    ACRONYMS

    BSC Bechtel SAIC Co. LLC

    CFR Code of Federal Regulations

    DOE U.S. Department of Energy

    EBS Engineered Barrier System

    FEPs features, events, and processes

    HLW high-level (radioactive) waste

    ITBC important to barrier capability ITWI important to waste isolation

    LNB Lower Natural Barrier

    NRC U.S. Nuclear Regulatory Commission

    PGV peak ground velocity PoNSDB Postclosure Nuclear Safety Design Basis

    RMEI reasonably maximally exposed individual

    SSC structure, system, and component SNF spent nuclear fuel SNL Sandia National Laboratories

    TSPA total system performance assessment TWP technical work plan

    UNB Upper Natural Barrier

    YMP Yucca Mountain Project

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    1. PURPOSE

    This report, the Postclosure Nuclear Safety Design Basis (PoNSDB) has been prepared to meet regulatory requirements of the 10 CFR 63.113(a) and 63.115 [DIRS 180319]), and to provide a risk-informed analysis of the postclosure technical basis for multiple barriers. Specifically, 10 CFR 63.113(a) [DIRS 180319] provides requirements for multiple barriers as part of performance objectives for the geologic repository after permanent closure; and 10 CFR 63.115 [DIRS 180319] provides requirements for the identification of, description of, and technical basis for the multiple barriers.

    This document provides extensive lists of features of the barriers and rationale as to why these barriers are important to waste isolation (ITWI) and why the features important to barrier capability (ITBC) may support such an ITWI classification (if that feature/component contributes significantly to barrier capability relative to the other features/components of the barrier). It also describes some features that are ITBC that are not significant enough to support that feature being classified as ITWI. The methodology for the identification of ITBC core and control parameter characteristics and ITWI barrier features/components is described in this document. The process starts with the examination of features, events, and processes (FEPs) and their screening justifications. As the FEPs form the basis of technical support for the TSPA, this approach is efficient and comprehensive for this purpose. The description of the FEPs and screening justifications suggest a division of the repository system into barriers, and barriers into features/components. Parameter characteristics associated with each FEP relative to the features/components of each barrier are identified. The FEP screening justification supports the further identification of parameter characteristics that are ITBC relative to each barrier feature/component. Finally, if the features/components are associated with at least one ITBC parameter characteristic, and that feature/component contributes significantly to the barrier capability relative to the other features/components of the barrier, then that feature/component is ITWI. All barriers are ITWI and are associated with one or more ITWI feature/components.

    This document identifies features/components of barriers that are important to waste isolation as well as features/components and parameter characteristics that are important to barrier capability (definitions developed specifically for use in this report are contained in Section 6.1.1). Capability as used in this document is not synonymous with performance. Performance, as defined in this report, is the realization of a capability as modeled in the Total System Performance Assessment (TSPA). Capability is broadly used to refer to the ability or potential of a feature/component to contribute to a function of a barrier. The identification of a parameter characteristic as contributing to the capability of a barrier’s feature/component is not intended to suggest any importance of the capability or to suggest that the feature/component is important to waste isolation. The importance of the capability is instead identified through its ITBC status, and the importance of the barrier and its features/components are identified through their ITWI status. While the features/components of all ITWI barriers and their associated ITBC parameter characteristics are considered in the Performance Assessment, some capabilities and features/components may not necessarily be fully realized in the TSPA because some reasonable conservative assumptions are invoked during TSPA implementation or because a capability may be masked by the performance of another capability. Features of the engineered system are identified as structure, system, and component (SSC) in design. For this report, the term features/components will be used to maintain uniformity of terminology between the barriers,

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    some of which are natural. Parameter characteristics are aspects of the barrier feature/component that contribute to the feature/component capability, and support the technical basis of the TSPA. Parameter characteristics are categorized into two groups. The first group, ‘core parameter characteristics,’ contains those characteristics that are not controlled or manipulated by design, construction, or operations and contribute to barrier capability. The second group, ‘control parameter characteristics,’ contains those characteristics that are able to be manipulated, controlled, and monitored by design, construction, or operations and contribute to barrier capability. A core and control parameter characteristic is further specified to be ITBC if it 1) prevents or substantially reduces the rate of movement of water from the repository to the accessible environment; 2) prevents the release or substantially reduces the release rate of radionuclides from the waste; 3) prevents or substantially reduces the rate of movement of radionuclides from the repository to the accessible environment, or 4) prevents or substantially reduces the consequences of disruptive events (e.g. criticality).

    The major activities documented in this report are two: (1) conduct the barrier analysis, and (2) develop core parameter characteristics and analyze control parameter characteristics. For natural and engineered barriers that are ITWI, the tasks associated with these two activities:

    1. Describe the three ITWI barriers (Upper Natural Barrier (UNB), the Engineered Barrier System (EBS), and the Lower Natural Barrier (LNB)).

    2. Evaluate barrier capability, including assessment of the technical bases, and evaluation of ITBC parameter characteristics and supporting the ITWI determination.

    This report serves as a companion document to Nuclear Safety Design Bases for License Application (BSC 2005 [DIRS 175546]). A second report, Postclosure Modeling and Analyses Design Parameters (BSC 2008 [DIRS 183627]), complements this report because of its emphasis on derived requirements and interface control parameters related to postclosure design components. This scientific analysis was conducted consistent with the Technical Work Plan for: Postclosure Nuclear Safety Design Bases (SNL 2007 [DIRS 182648]) except as noted in Section 2.

    This analysis is intended to identify and document technical interfaces between postclosure analyses and repository design regarding the safety classification of systems, structures and components, and the design bases for SSCs classified as important to waste isolation.

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    2. QUALITY ASSURANCE

    The analysis documented herein is subject to the Office of Civilian Radioactive Waste Management Quality Assurance Program as documented in the relevant technical work plan (TWP) TWP-WIS-MD-000015 (SNL 2007 [DIRS 182648], Section 8.1). This work constitutes an analysis report, therefore, the document was prepared in accordance with SCI-PRO-005, Scientific Analyses and Calculations. Approved quality assurance procedures and guidance documents were used to conduct and document the activities described in this report as outlined in the TWP (SNL 2007 [DIRS 182648], Section 4.1). The TWP (SNL 2007 [DIRS 182648], Section 8.4) also identifies applicable controls for the electronic management of data during the analysis and documentation activities. There are three deviations from the TWP. The first deviation is that a methodology for determination of features, events, and processes that are important to performance is now covered in an addendum to the Performance Confirmation Plan (SNL 2008 [DIRS 184797], Appendix A). The methodology (specifically important to dose, and significance to uncertainty) as originally intended in the TWP (SNL 2007 [DIRS 182648]) for this product is now covered in that document (SNL 2008 [DIRS 184797], Appendix A). The second deviation is that, the TWP stated: “Finally, the PoNSDB document will identify performance confirmation activities, as applicable, for FEPs that are ITBC.” That information is now better presented in the Performance Confirmation Plan (SNL 2008 [DIRS 184797], Appendix A) and is not presented in this document. The third deviation is that, because changes are so extensive in this revision, all comments from November 2006 LP 7.5Q OCRWM review of ANL-WIS-MD-000024 were not directly addressed. Technical issues were considered and resolved. Editorial comments were overcome by completely new text and could not be mapped directly to the new text.

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    3. USE OF SOFTWARE

    No software required to be qualified in accordance with IM-PRO-003, Software Management was used in developing this report. Standard functions of Microsoft Excel 2000 commercial-offthe-shelf software were used, but only for organizational purposes.

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    4. INPUTS

    This report uses the information and decisions developed in other reports as references and utilizes professional judgment. This work does not involve separate modeling or analyses using previously developed models and, as such, this report does not require model validation.

    All direct inputs (data, parameters, and other information) used in this scientific analysis are identified in Section 4.1. Direct inputs used in this analysis report were obtained from controlled source documents and other sources in accordance with SCI-PRO-004, Managing Technical Product Inputs. NUREG-1804 (NRC 2003 [DIRS 163274]) lists some specific acceptance criteria that are addressed in this report which are identified in Section 4.2.

    4.1 DIRECT INPUTS

    Direct inputs used in the analyses are listed in Table 4-1. Indirect inputs are described in Section 6. These sources are appropriate for this analysis because they are dedicated to the technical understanding of processes and/or events that act on the features comprising the three barriers (UNB, EBS, and LNB) considered in this analysis. This type of input is directly applicable to the analysis discussed in Section 6 and Appendix A.

    All data used from external sources and non-conclusion sections of direct input sources have either been qualified for intended use in Features, Events, and Processes for the Total System Performance Assessment: Analyses (SNL 2008 [DIRS 183041]) or other Analysis/Model Reports, as cited. The only use in this report is to analyze barrier capabilities, not to present any new information.

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    Tabl

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    n of

    hos

    t roc

    k ar

    ound

    em

    plac

    emen

    t drif

    ts d

    ue to

    was

    te

    cool

    ing

    are

    only

    sig

    nific

    ant f

    or fi

    rst s

    ever

    al h

    undr

    ed to

    a fe

    w 1

    ,000

    yea

    rs, a

    nd

    are

    insi

    gnifi

    cant

    ove

    r the

    per

    iod

    of g

    eolo

    gic

    stab

    ility

    BS

    C 2

    004

    [DIR

    S 1

    7245

    3]

    DS

    NF

    and

    Oth

    er W

    aste

    Fo

    rm D

    egra

    datio

    n A

    bstra

    ctio

    n

    Sec

    tion

    6.3

    Tabl

    e A

    -2

    An

    uppe

    r-bo

    und

    mod

    el is

    use

    d in

    TS

    PA

    to m

    odel

    deg

    rada

    tion

    of a

    ll of

    the

    DS

    NF

    fuel

    type

    s ot

    her t

    han

    Nav

    al S

    NF

    SN

    L 20

    08 [D

    IRS

    173

    869]

    S

    cree

    ning

    Ana

    lysi

    s of

    C

    ritic

    ality

    Fea

    ture

    s,

    Eve

    nts,

    and

    Pro

    cess

    es fo

    rLi

    cens

    e A

    pplic

    atio

    n

    Sec

    tion

    6.3

    Tabl

    e A

    -2

    Con

    ditio

    ns re

    quire

    d to

    lead

    to in

    -pac

    kage

    crit

    ical

    ity a

    re n

    ot li

    kely

    to o

    ccur

    and

    th

    e pa

    ram

    eter

    cha

    ract

    eris

    tics

    asso

    ciat

    ed w

    ith In

    -Pac

    kage

    Crit

    ical

    ity (d

    egra

    ded

    conf

    igur

    atio

    n) d

    o no

    t sub

    stan

    tially

    effe

    ct th

    e re

    leas

    e of

    radi

    onuc

    lides

    or i

    mpa

    ct

    the

    barr

    ier c

    apab

    ility

    Sec

    tion

    6.3

    Tabl

    e A

    -2

    Effe

    cts

    of ra

    dioa

    ctiv

    e ga

    ses

    in th

    e E

    BS

    wer

    e an

    alyz

    ed a

    nd w

    ere

    foun

    d to

    be

    inco

    nseq

    uent

    ial t

    o re

    posi

    tory

    per

    form

    ance

    S

    ectio

    ns 6

    .4, 6

    .5 a

    nd6.

    6 Ta

    ble

    A-2

    C

    ondi

    tions

    requ

    ired

    to le

    ad to

    nea

    r-fie

    ld c

    ritic

    ality

    are

    not

    like

    ly to

    occ

    ur, a

    nd

    the

    para

    met

    er c

    hara

    cter

    istic

    s as

    soci

    ated

    with

    this

    pro

    cess

    and

    feat

    ure

    do n

    ot

    subs

    tant

    ially

    effe

    ct th

    e re

    leas

    e of

    radi

    onuc

    lides

    or i

    mpa

    ct th

    e ba

    rrie

    r

    ANL-WIS-MD-000024 REV 01 4-2 February 2008

  • Postclosure Nuclear Safety Design Bases

    Tabl

    e 4-

    1.

    Sou

    rce

    of In

    puts

    (Con

    tinue

    d)

    Cita

    tion

    Sour

    ce T

    itle

    Spec

    ifica

    lly U

    sed

    From

    Spec

    ifica

    llyU

    sed

    In (t

    his

    AM

    R)

    Inpu

    t Des

    crip

    tion

    SN

    L 20

    07 [D

    IRS

    176

    828]

    S

    eism

    ic C

    onse

    quen

    ce

    Abs

    tract

    ion

    Sec

    tions

    6.1

    1.1.

    3 an

    d6.

    11.2

    Ta

    ble

    A-2

    Li

    thop

    hysa

    l hos

    t roc

    k is

    exp

    ecte

    d to

    col

    laps

    e in

    to th

    e em

    plac

    emen

    t drif

    ts fo

    r un

    likel

    y pe

    ak g

    roun

    d ve

    loci

    ties

    abov

    e 2

    m/s

    Sec

    tion

    6.11

    .4

    Tabl

    e A

    -2

    It is

    not

    exp

    ecte

    d th

    at fa

    ults

    will

    sig

    nific

    antly

    affe

    ct th

    e de

    grad

    atio

    n of

    the

    EB

    S,

    at a

    nnua

    l rec

    urre

    nce

    inte

    rval

    s of

    abo

    ut 1

    0�7

    per y

    ear a

    nd le

    ssS

    ectio

    n 6.

    11.5

    Ta

    ble

    A-2

    P

    oten

    tial d

    amag

    e to

    was

    te p

    acka

    ges

    and

    drip

    shi

    elds

    from

    dis

    plac

    emen

    t on

    thes

    e fa

    ults

    is in

    clud

    ed in

    the

    TSP

    A M

    odel

    Sec

    tion

    6.7

    Tabl

    e A

    -2

    Bar

    rier c

    apab

    ility

    of C

    SN

    F cl

    addi

    ng is

    not

    impo

    rtant

    bec

    ause

    cla

    ddin

    g ca

    n be

    da

    mag

    ed b

    y se

    ism

    ic a

    ctiv

    ity th

    at d

    oes

    not d

    amag

    e th

    e w

    aste

    pac

    kage

    Sec

    tions

    6.7

    .3.1

    ,6.

    7.3.

    2, 6

    .8, a

    nd 6

    .8.5

    Tab

    le A

    -2

    Axi

    al s

    epar

    atio

    n of

    adj

    acen

    t drip

    shi

    elds

    is e

    xclu

    ded

    from

    the

    TSP

    A m

    odel

    be

    caus

    e a

    kine

    mat

    ic s

    tudy

    indi

    cate

    s th

    at s

    mal

    l sta

    tic lo

    ads

    from

    rubb

    le o

    r fri

    ctio

    nal l

    oads

    bet

    wee

    n E

    BS

    com

    pone

    nts

    are

    suffi

    cien

    t to

    elim

    inat

    e ax

    ial

    sepa

    ratio

    n of

    drip

    shi

    elds

    S

    ectio

    ns 6

    .1.2

    , 6.1

    .3

    Tabl

    e A

    -2

    Cha

    nges

    con

    figur

    atio

    n of

    EB

    S c

    ompo

    nent

    s w

    ithin

    the

    empl

    acem

    ent d

    rifts

    SN

    L 20

    07 [D

    IRS

    177

    391]

    S

    atur

    ated

    Zon

    e S

    ite-S

    cale

    Flow

    Mod

    el

    Sec

    tion

    6.6.

    4.1

    Tabl

    e A

    -3

    Clim

    ate

    chan

    ge a

    lters

    the

    flux

    thro

    ugh

    the

    satu

    rate

    d zo

    ne b

    y in

    crea

    sing

    the

    regi

    onal

    rech

    arge

    and

    cau

    sing

    the

    wat

    er ta

    ble

    to ri

    seS

    NL

    2007

    [DIR

    S 1

    7739

    6]

    Rad

    ionu

    clid

    e Tr

    ansp

    ort

    Mod

    els

    Und

    er A

    mbi

    ent

    Con

    ditio

    ns

    Sec

    tions

    6.7

    .5 a

    nd6.

    8.1.

    2 Ta

    ble

    A-3

    Fa

    ults

    are

    impo

    rtant

    to u

    nsat

    urat

    ed z

    one

    trans

    port

    beca

    use

    they

    pro

    vide

    fast

    pa

    thw

    ays

    for r

    adio

    nucl

    ide

    trans

    port

    to th

    e w

    ater

    tabl

    e S

    ectio

    ns 6

    .1.1

    and

    6.1.

    2 Ta

    ble

    A-3

    Fr

    actu

    re-r

    elat

    ed tr

    ansp

    ort p

    roce

    sses

    /pro

    perti

    es in

    clud

    e fra

    ctur

    e pe

    rmea

    bilit

    y,

    poro

    sity

    , fre

    quen

    cy, a

    ctiv

    e fra

    ctur

    e m

    odel

    , mat

    rix d

    iffus

    ion

    coef

    ficie

    nt, s

    orpt

    ion,

    an

    d co

    lloid

    filtr

    atio

    nS

    NL

    2007

    [DIR

    S 1

    7740

    7]

    EB

    S R

    adio

    nucl

    ide

    Tran

    spor

    t Abs

    tract

    ion

    Sec

    tion

    6.2.

    1.1

    Tabl

    e A

    -1

    Dis

    cuss

    ion

    of tw

    o-ph

    ase

    buoy

    ant f

    low

    incl

    uded

    in m

    odel

    s of

    ther

    mal

    see

    page

    an

    d th

    erm

    al h

    ydro

    logy

    Sec

    tion

    5, 6

    Ta

    ble

    A-2

    S

    eepa

    ge o

    r con

    dens

    atio

    n pr

    oces

    ses

    are

    sign

    ifica

    nt m

    ode

    of re

    leas

    e th

    at

    subs

    tant

    ially

    impa

    cts

    the

    trans

    port

    of ra

    dion

    uclid

    esS

    ectio

    n 6.

    3.1.

    1 Ta

    ble

    A-2

    A

    dvec

    tive

    rele

    ases

    are

    mor

    e si

    gnifi

    cant

    from

    a s

    yste

    m p

    erfo

    rman

    ce

    pers

    pect

    ive

    beca

    use

    rele

    ases

    occ

    ur in

    to th

    e fra

    ctur

    es o

    f the

    uns

    atur

    ated

    zon

    e be

    low

    the

    repo

    sito

    ry, w

    hile

    diff

    usiv

    e re

    leas

    es a

    re re

    leas

    ed to

    the

    slow

    ertra

    nspo

    rt in

    the

    mat

    rix o

    f the

    uns

    atur

    ated

    feat

    ures

    Sec

    tion

    6.3.

    1.2

    Tabl

    e A

    -2

    Col

    loid

    s an

    d as

    soci

    ated

    radi

    onuc

    lides

    are

    imm

    obili

    zed,

    and

    true

    col

    loid

    s m

    aydi

    ssol

    ve b

    ecom

    ing

    subj

    ect t

    o aq

    ueou

    s tra

    nspo

    rt if

    cond

    ition

    s ar

    e no

    t sta

    ble

    Sec

    tion

    6.3.

    1.2

    Tabl

    e A

    -2

    The

    proc

    ess

    of d

    ecay

    and

    ingr

    owth

    of r

    adio

    nucl

    ides

    is in

    clud

    ed in

    the

    TSP

    A

    Sec

    tion

    6.3.

    2.4

    Tabl

    e A

    -2

    Ther

    mal

    env

    ironm

    ent h

    as a

    dire

    ct e

    ffect

    on

    tem

    pera

    ture

    and

    hum

    idity

    in th

    e em

    plac

    emen

    t drif

    ts, w

    hich

    con

    trol t

    he c

    orro

    sion

    env

    ironm

    ent,

    and

    the

    cond

    ition

    s fo

    r rad

    ionu

    clid

    e m

    obili

    zatio

    n an

    d re

    leas

    eS

    ectio

    n 6.

    3.3

    Tabl

    e A

    -2

    Flow

    div

    ersi

    on, w

    hen

    com

    bine

    d w

    ith th

    e la

    ck o

    f adv

    ectio

    n th

    roug

    h th

    e w

    aste

    pa

    ckag

    e, re

    sults

    in o

    nly

    the

    pote

    ntia

    l for

    diff

    usiv

    e re

    leas

    es fr

    om th

    e w

    aste

    form

    an

    d w

    aste

    pac

    kage

    if th

    e w

    aste

    pac

    kage

    has

    deg

    rade

    d fe

    atur

    esS

    ectio

    n 6.

    3.4

    Tabl

    e A

    -2

    Diff

    usiv

    e tra

    nspo

    rt is

    con

    serv

    ativ

    ely

    spec

    ified

    to o

    ccur

    thro

    ugh

    a co

    ntin

    uous

    w

    ater

    film

    on

    the

    surfa

    ces

    of th

    e E

    BS

    feat

    ures

    ANL-WIS-MD-000024 REV 01 4-3 February 2008

  • Postclosure Nuclear Safety Design Bases

    Tabl

    e 4-

    1.

    Sou

    rce

    of In

    puts

    (Con

    tinue

    d)

    Cita

    tion

    Sour

    ce T

    itle

    Spec

    ifica

    lly U

    sed

    From

    Spec

    ifica

    llyU

    sed

    In (t

    his

    AM

    R)

    Inpu

    t Des

    crip

    tion

    SN

    L 20

    07 [D

    IRS

    177

    407]

    (C

    ontin

    ued)

    E

    BS

    Rad

    ionu

    clid

    eTr

    ansp

    ort A

    bstra

    ctio

    n (C

    ontin

    ued)

    Sec

    tion

    6.3.

    4,Ta

    ble

    6.6-

    1 Ta

    ble

    A-2

    D

    iffus

    ion

    of c

    ollo

    ids

    is n

    ot a

    sig

    nific

    ant m

    ode

    of re

    leas

    e

    Sec

    tion

    6.3.

    4.4

    Tabl

    e A

    -2

    If dr

    ip s

    hiel

    d an

    d w

    aste

    pac

    kage

    are

    not

    bre

    ache

    d, a

    dvec

    tive

    trans

    port

    of

    collo

    ids

    thro

    ugh

    the

    inve

    rt is

    mor

    e si

    gnifi

    cant

    than

    diff

    usiv

    eS

    ectio

    n 6.

    5.2.

    6 Ta

    ble

    A-2

    P

    artit

    ioni

    ng o

    f rel

    ease

    d ra

    dion

    uclid

    es fr

    om th

    e E

    BS

    to th

    e LN

    B is

    sen

    sitiv

    e to

    ad

    vect

    ive

    flow

    , but

    is re

    lativ

    ely

    inse

    nsiti

    ve to

    hyd

    rolo

    gic

    prop

    ertie

    s of

    the

    inve

    rtS

    ectio

    n 6.

    5.2.

    6, T

    able

    6.

    4-1

    Tabl

    e A

    -2

    Uns

    atur

    ated

    flow

    occ

    urs

    thro

    ugh

    the

    inve

    rt as

    a re

    sult

    of s

    eepa

    ge o

    r drif

    t-wal

    l co

    nden

    satio

    n, im

    bibi

    tion

    from

    the

    host

    rock

    , or c

    apill

    ary

    cond

    ensa

    tion,

    and

    af

    fect

    s th

    e re

    leas

    e of

    radi

    onuc

    lides

    from

    the

    EB

    S to

    the

    LNB

    feat

    ures

    Sec

    tions

    5, 6

    Ta

    ble

    A-2

    U

    nsat

    urat

    ed fl

    ow h

    as b

    een

    incl

    uded

    in th

    e ab

    stra

    ctio

    ns fo

    r flo

    w a

    nd tr

    ansp

    ort

    thro

    ugh

    the

    EB

    S fe

    atur

    esS

    ectio

    ns 6

    .1.1

    , Tab

    le6.

    3-2

    Tabl

    e A

    -2

    Onl

    y th

    e sm

    alle

    st o

    f col

    loid

    al p

    artic

    les,

    toge

    ther

    with

    any

    ass

    ocia

    ted

    radi

    onuc

    lides

    , may

    be

    trans

    porte

    d si

    gnifi

    cant

    ly b

    y di

    ffusi

    on in

    the

    EB

    S.

    Adv

    ectio

    n is

    a m

    ore

    sign

    ifica

    nt m

    etho

    d of

    tran

    spor

    t in

    the

    inve

    rtS

    ectio

    ns 6

    .3.1

    .1,

    6.3.

    1.2

    Tabl

    e A

    -2

    If dr

    ip s

    hiel

    d an

    d w

    aste

    pac

    kage

    are

    not

    bre

    ache

    d, a

    dvec

    tive

    rele

    ases

    are

    m

    ore

    sign

    ifica

    nt th

    an d

    iffus

    ive

    from

    a s

    yste

    m p

    erfo

    rman

    ce p

    ersp

    ectiv

    eS

    ectio

    ns 6

    .4.1

    , 6.6

    .1

    Tabl

    e A

    -2

    Rel

    ease

    pul

    ses

    caus

    ed b

    y ba

    thtu

    b be

    havi

    or o

    f the

    was

    te p

    acka

    ge h

    ave

    been

    an

    alyz

    ed

    SN

    L 20

    07 [D

    IRS

    177

    412]

    E

    ngin

    eere

    d B

    arrie

    r S

    yste

    m: P

    hysi

    cal a

    nd

    Che

    mic

    al E

    nviro

    nmen

    t

    Sec

    tions

    6.8

    , 6.8

    .4,

    6.13

    , 6.1

    3.4,

    6.1

    4,

    and

    6.15

    Tabl

    e A

    -2

    Che

    mic

    al c

    hara

    cter

    istic

    s of

    wat

    er in

    the

    drift

    affe

    ct th

    e lik

    elih

    ood

    of p

    oten

    tial

    degr

    adat

    ion,

    det

    erio

    ratio

    n, a

    nd a

    ltera

    tion

    of th

    e ot

    her E

    BS

    com

    pone

    nts,

    as

    wel

    l as

    affe

    ctin

    g th

    e tra

    nspo

    rt ch

    arac

    teris

    tics

    of a

    ny ra

    dion

    uclid

    es re

    leas

    ed fr

    om th

    e w

    aste

    pac

    kage

    to th

    e in

    vert

    SN

    L 20

    07 [D

    IRS

    177

    418]

    D

    isso

    lved

    Con

    cent

    ratio

    n Li

    mits

    of E

    lem

    ents

    with

    R

    adio

    activ

    e Is

    otop

    es

    Sec

    tion

    8.1

    Tabl

    e A

    -2

    Unc

    erta

    inty

    in th

    ese

    solu

    bilit

    ies

    and

    the

    effe

    cts

    of w

    aste

    pac

    kage

    inte

    rnal

    ch

    emis

    try v

    aria

    bilit

    y an

    d un

    certa

    inty

    hav

    e be

    en in

    clud

    ed in

    the

    mod

    els

    of w

    aste

    fo

    rm re

    leas

    e S

    NL

    2007

    [DIR

    S 1

    7742

    3]

    Was

    te F

    orm

    and

    In-D

    rift

    Col

    loid

    s-A

    ssoc

    iate

    d R

    adio

    nucl

    ide

    Con

    cent

    ratio

    ns

    Sec

    tions

    4.1

    .2, 6

    .3.1

    ,6.

    5.1,

    6.6

    .8, 6

    .3.9

    Ta

    ble

    A-2

    C

    orro

    sion

    pro

    duct

    col

    loid

    s in

    clud

    ed in

    the

    collo

    id m

    odel

    s en

    viro

    nmen

    t

    Sec

    tion

    6.6.

    8 Ta

    ble

    A-2

    C

    ollo

    id s

    tabi

    lity

    in th

    e in

    vert

    is a

    func

    tion

    of th

    e aq

    ueou

    s ch

    emic

    al c

    ondi

    tions

    Ta

    ble

    4-2;

    Sec

    tions

    6.

    3.2.

    2, 7

    .0

    Tabl

    e A

    -2

    Co-

    prec

    ipita

    tion

    of c

    ollo

    ids

    due

    to th

    e de

    grad

    atio

    n of

    HLW

    gla

    ss w

    aste

    form

    s ha

    s be

    en in

    clud

    ed in

    the

    asse

    ssm

    ent o

    f tot

    al c

    ollo

    idal

    rele

    ase

    from

    the

    codi

    spos

    al w

    aste

    pac

    kage

    s en

    viro

    nmen

    tS

    NL

    2007

    [DIR

    S 1

    7743

    0]

    Dik

    e/D

    rift I

    nter

    actio

    ns

    Sec

    tion

    6.7

    Tabl

    e A

    -2

    Follo

    win

    g an

    unl

    ikel

    y m

    agm

    a in

    trusi

    on in

    to th

    e re

    posi

    tory

    , it i

    s po

    ssib

    le th

    at th

    e w

    ater

    che

    mis

    try in

    the

    empl

    acem

    ent d

    rifts

    will

    be

    alte

    red

    by b

    asal

    t-wat

    er

    inte

    ract

    ions

    ANL-WIS-MD-000024 REV 01 4-4 February 2008

  • Postclosure Nuclear Safety Design Bases

    Tabl

    e 4-

    1.

    Sou

    rce

    of In

    puts

    (Con

    tinue

    d)

    Cita

    tion

    Sour

    ce T

    itle

    Spec

    ifica

    lly U

    sed

    From

    Spec

    ifica

    llyU

    sed

    In (t

    his

    AM

    R)

    Inpu

    t Des

    crip

    tion

    SN

    L 20

    07 [D

    IRS

    177

    432]

    N

    umbe

    r of W

    aste

    P

    acka

    ges

    Hit

    by Ig

    neou

    s E

    vent

    s

    Sec

    tion

    6 Ta

    ble

    A-2

    P

    oten

    tial c

    onse

    quen

    ce o

    f an

    erup

    tive

    cond

    uit,

    to th

    e su

    rface

    inte

    rsec

    ting

    the

    repo

    sito

    ry is

    that

    was

    te p

    acka

    ges

    entra

    ined

    with

    in a

    con

    duit

    may

    be

    brea

    ched

    , re

    leas

    ing

    radi

    onuc

    lides

    in a

    n er

    uptin

    g as

    h pl

    ume

    whe

    re th

    ey c

    an b

    e di

    sper

    sed

    dow

    nwin

    d to

    the

    reas

    onab

    ly m

    axim

    ally

    exp

    osed

    indi

    vidu

    al

    Sec

    tion

    7.2

    Tabl

    e A

    -3

    Dis

    cuss

    ion

    of p

    ossi

    bilit

    y of

    an

    erup

    tive

    cond

    uit i

    nter

    sect

    ing

    the

    repo

    sito

    ry a

    nd

    exte

    ndin

    g to

    sur

    face

    70 F

    R 5

    3313

    [DIR

    S 1

    7839

    4]

    70 F

    R 5

    3313

    . Im

    plem

    enta

    tion

    of a

    Dos

    e S

    tand

    ard

    Afte

    r 10,

    000

    Year

    s. In

    tern

    et A

    cces

    sibl

    e

    10 C

    FR 6

    3.30

    5(b)

    Ta

    ble

    A-1

    Fu

    ture

    cha

    nges

    in a

    gric

    ultu

    ral a

    nd in

    dust

    rial a

    ctiv

    ities

    are

    exc

    lude

    d ba

    sed

    on

    regu

    lato

    ry re

    quire

    men

    ts

    SN

    L 20

    07 [D

    IRS

    178

    519]

    G

    ener

    al C

    orro

    sion

    and

    Lo

    caliz

    ed C

    orro

    sion

    of

    Was

    te P

    acka

    ge O

    uter

    Bar

    rier

    Sec

    tion

    1 Ta

    ble

    A-2

    S

    tain

    less

    ste

    el in

    ner s

    hell

    of w

    aste

    pac

    kage

    has

    bee

    n co

    nser

    vativ

    ely

    mod

    eled

    to

    pro

    vide

    no

    dela

    y of

    pen

    etra

    tion

    of w

    aste

    pac

    kage

    onc

    e w

    aste

    pac

    kage

    Allo

    y22

    out

    er b

    arrie

    r has

    bee

    n br

    each

    edS

    ectio

    n 6.

    4.4

    Tabl

    e A

    -2

    Pos

    sibi

    lity

    of lo

    caliz

    ed c

    orro

    sion

    als

    o re

    quire

    s pa

    rticu

    lar a

    ntec

    eden

    t ge

    oche

    mic

    al c

    ondi

    tions

    that

    are

    gen

    eral

    ly n

    ot p

    rese

    nt

    Sec

    tion

    6.4

    Tabl

    e A

    -2

    Unc

    erta

    inty

    in th

    ese

    corr

    osio

    n10

    CFR

    63.

    200

    7[D

    IRS

    180

    319]

    10

    CFR

    63

    10 C

    FR63

    .51(

    a)(3

    )(i�

    iii),

    10

    CFR

    63.

    72(a

    ), an

    d 10

    C

    FR 6

    3.72

    (b)(1

    �11)

    Tabl

    e A

    -1

    To p

    recl

    ude

    any

    pote

    ntia

    l del

    eter

    ious

    effe

    cts,

    con

    stru

    ctio

    n an

    d op

    erat

    iona

    l m

    anag

    emen

    t, an

    d ad

    min

    istra

    tive

    cont

    rols

    will

    be

    deve

    lope

    d

    SN

    L 20

    07 [D

    IRS

    180

    472]

    In

    itial

    Rad

    ionu

    clid

    eIn

    vent

    orie

    s S

    ectio

    n 6

    Tabl

    e A

    -2

    With

    in th

    e w

    aste

    pac

    kage

    , rad

    ioac

    tive

    deca

    y an

    d in

    grow

    th c

    ontri

    bute

    to th

    e w

    aste

    inve

    ntor

    y, w

    hich

    def

    ines

    the

    amou

    nt o

    f diff

    eren

    t rad

    ionu

    clid

    es p

    rese

    nt in

    di

    ffere

    nt w

    aste

    form

    sS

    ectio

    n 6.

    1 Ta

    ble

    A-2

    O

    ther

    radi

    onuc

    lides

    hav

    e m

    oder

    ate

    half-

    lives

    and

    dec

    ay to

    pro

    duct

    s th

    at m

    aybe

    rele

    ased

    from

    the

    was

    teS

    ectio

    n 6.

    1 Ta

    ble

    A-2

    W

    aste

    inve

    ntor

    y de

    fines

    the

    amou

    nt o

    f diff

    eren

    t rad

    ionu

    clid

    es p

    rese

    nt in

    di

    ffere

    nt w

    aste

    form

    sS

    ectio

    n 6.

    1.10

    Ta

    ble

    A-2

    A

    ny c

    hang

    e to

    inve

    ntor

    y w

    ill b

    e m

    anag

    ed b

    y th

    e ch

    ange

    eva

    luat

    ion

    proc

    ess

    Sec

    tion

    6.3

    Tabl

    e A

    -2

    The

    proc

    ess

    of d

    ecay

    and

    ingr

    owth

    of r

    adio

    nucl

    ides

    is in

    clud

    ed in

    the

    TSP

    A

    Sec

    tions

    6.4

    , 6.6

    .2an

    d 6.

    6 Ta

    ble

    A-2

    D

    iffer

    ence

    s in

    was

    te in

    vent

    ory

    of th

    e di

    ffere

    nt w

    aste

    form

    s ha

    ve b

    een

    incl

    uded

    in

    the

    eval

    uatio

    n of

    bar

    rier c

    apab

    ility

    SN

    L 20

    07 [D

    IRS

    180

    778]

    G

    ener

    al C

    orro

    sion

    and

    Lo

    caliz

    ed C

    orro

    sion

    of t

    heD

    rip S

    hiel

    d

    Sec

    tion

    6 Ta

    ble

    A-2

    G

    ener

    al c

    orro

    sion

    rate

    s of

    tita

    nium

    in th

    e ra

    nge

    of li

    kely

    env

    ironm

    enta

    l co

    nditi

    ons

    are

    low

    dur

    ing

    the

    regu

    lato

    ry p

    erio

    d. T

    his

    proc

    ess

    has

    been

    in

    clud

    ed in

    mod

    els

    of d

    rip s

    hiel

    d de

    grad

    atio

    n

    ANL-WIS-MD-000024 REV 01 4-5 February 2008

  • Postclosure Nuclear Safety Design Bases

    Tabl

    e 4-

    1.

    Sou

    rce

    of In

    puts

    (Con

    tinue

    d)

    Cita

    tion

    Sour

    ce T

    itle

    Spec

    ifica

    lly U

    sed

    From

    Spec

    ifica

    llyU

    sed

    In (t

    his

    AM

    R)

    Inpu

    t Des

    crip

    tion

    SN

    L 20

    08 [D

    IRS

    184

    748]

    P

    artic

    le T

    rack

    ing

    Mod

    elan

    d A

    bstra

    ctio

    n of

    Tr

    ansp

    ort P

    roce

    sses

    Sec

    tion

    6.8.

    2.2

    Tabl

    e A

    -2

    The

    proc

    ess

    of d

    ecay

    and

    ingr

    owth

    of r

    adio

    nucl

    ides

    Sec

    tion

    D.2

    Ta

    ble

    A-2

    O

    ther

    radi

    onuc

    lides

    hav

    e m

    oder

    ate

    half-

    lives

    and

    dec

    ay to

    pro

    duct

    s th

    at m

    aybe

    rele

    ased

    from

    the

    was

    teS

    ectio

    n 8.

    2.2

    Tabl

    e A

    -3

    Pro

    cess

    es a

    re in

    clud

    ed in

    the

    UZ

    Tran

    spor

    t Abs

    tract

    ion

    Mod

    el

    Sec

    tions

    6.5

    .12,

    6.5.

    13 a

    nd 6

    .6.2

    Ta

    ble

    A-3

    S

    mal

    l fra

    ctio

    n of

    the

    collo

    ids

    are

    cons

    erva

    tivel

    y m

    odel

    ed to

    be

    unre

    tard

    ed in

    th

    e un

    satu

    rate

    d zo

    ne. S

    orpt

    ion

    of c

    ollo

    idal

    tran

    spor

    t of r

    adio

    nucl

    ides

    is

    incl

    uded

    in th

    e U

    Z Tr

    ansp

    ort A

    bstra

    ctio

    n M

    odel

    SN

    L 20

    07 [D

    IRS

    181

    244]

    A

    bstra

    ctio

    n of

    Drif

    t S

    eepa

    ge

    Sec

    tions

    6.1

    [a] a

    nd 6

    12

    [a]

    Tabl

    e A

    -1

    Unc

    erta

    inty

    in fl

    ow fo

    cusi

    ng h

    as b

    een

    incl

    uded

    in th

    e as

    sess

    men

    t of t

    he

    likel

    ihoo

    d an

    d m

    agni

    tude

    of s

    eepa

    ge in

    to th

    e em

    plac

    emen

    t drif

    tsS

    ectio

    n 6.

    4.3.

    3 Ta

    ble

    A-1

    E

    ffect

    s of

    resa

    tura

    tion

    of th

    e ho

    st ro

    ck a

    roun

    d th

    e em

    plac

    emen

    t drif

    ts d

    ue to

    w

    aste

    coo

    ling

    are

    depe

    nden

    t on

    loca

    tion

    of th

    e re

    posi

    tory

    Sec

    tion

    6.5

    Tabl

    e A

    -1

    Effe

    cts

    of d

    ryou

    t of t

    he h

    ost r

    ock

    arou

    nd th

    e em

    plac

    emen

    t drif

    ts d

    ue to

    was

    te

    heat

    dep

    ends

    on

    loca

    tion

    of th

    e re

    posi

    tory

    Sec

    tions

    6.6

    , 6.6

    .5.2

    ,an

    d 6.

    7 Ta

    ble

    A-1

    R

    epre

    sent

    ativ

    enes

    s of

    the

    seep

    age

    para

    met

    er d

    istri

    butio

    ns u

    sed

    in P

    A w

    ithin

    re

    posi

    tory

    hos

    t roc

    k is

    con

    side

    red

    impo

    rtant

    to c

    apab

    ility

    of u

    pper

    nat

    ural

    ba

    rrie

    r S

    ectio

    n 6.

    4 Ta

    ble

    A-2

    Th

    erm

    al-h

    ydro

    logi

    c ef

    fect

    s fro

    m d

    rift c

    olla

    pse

    indu

    ced

    by a

    sei

    smic

    eve

    nt

    incl

    ude

    an in

    crea

    se in

    the

    tem

    pera

    ture

    and

    an

    incr

    ease

    in th

    e pr

    obab

    ility

    and

    m

    agni

    tude

    of s

    eepa

    geS

    NL2

    008

    [DIR

    S 1

    8443

    3]

    Mul

    tisca

    leTh

    erm

    ohyd

    rolo

    gic

    Mod

    el

    Sec

    tion

    6.2.

    1[a]

    Ta

    ble

    A-2

    Te

    mpe

    ratu

    re re

    sulti

    ng fr

    om h

    eat g

    ener

    atio

    n al

    so a

    ffect

    s th

    e in

    itiat

    ion

    of w

    aste

    fo

    rm a

    ltera

    tion

    and

    radi

    onuc

    lide

    trans

    port

    proc

    esse

    s de

    pend

    ent o

    n th

    e pr

    esen

    ce o

    f an

    aque

    ous

    film

    Sec

    tion

    6.2[

    a]

    Tabl

    e A

    -2

    Non

    unifo

    rm h

    eat h

    as b

    een

    cons

    ider

    ed in

    the

    mod

    els

    of in

    -drif

    t the

    rmal

    hy

    drol

    ogy

    Sec

    tion

    6.3.

    17[a

    ] Ta

    ble

    A-2

    Th

    erm

    al-h

    ydro

    logi

    c ef

    fect

    s fro

    m d

    rift c

    olla

    pse

    indu

    ced

    by a

    sei

    smic

    eve

    nt

    incl

    ude

    an in

    crea

    se in

    the

    tem

    pera

    ture

    and

    an

    incr

    ease

    in th

    e pr

    obab

    ility

    and

    m

    agni

    tude

    of s

    eepa

    geS

    ectio

    ns 6

    .2.1

    5[a]

    ,6.

    2.17

    [a]

    Tabl

    e A

    -2

    Pre

    clos

    ure

    vent

    ilatio

    n re

    mov

    es h

    eat a

    nd m

    oist

    ure

    from

    the

    host

    rock

    dur

    ing

    the

    vent

    ilatio

    n pe

    riod

    Sec

    tion

    6.3.

    3 Ta

    ble

    A-2

    E

    ffect

    of w

    icki

    ng (w

    ithou

    t see

    page

    ) slig

    htly

    incr

    ease

    s th

    e ad

    vect

    ive

    flux

    thro

    ugh

    the

    inve

    rt

    ANL-WIS-MD-000024 REV 01 4-6 February 2008

  • Postclosure Nuclear Safety Design Bases

    Tabl

    e 4-

    1.

    Sou

    rce

    of In

    puts

    (Con

    tinue

    d)

    Cita

    tion

    Sour

    ce T

    itle

    Spec

    ifica

    lly U

    sed

    From

    Spec

    ifica

    llyU

    sed

    In (t

    his

    AM

    R)

    Inpu

    t Des

    crip

    tion

    SN

    L 20

    07 [D

    IRS

    181

    648]

    In

    -Drif

    t Nat

    ural

    Con

    vect

    ion

    and

    Con

    dens

    atio

    n E

    xecu

    tive

    Sum

    mar

    y Ta

    ble

    A-2

    Th

    erm

    al e

    nviro

    nmen

    t has

    a d

    irect

    effe

    ct o

    n te

    mpe

    ratu

    re a

    nd h

    umid

    ity in

    the

    empl

    acem

    ent d

    rifts

    , whi

    ch c

    ontro

    l the

    cor

    rosi

    on e

    nviro

    nmen

    t, an

    d th

    e co

    nditi

    ons

    for r

    adio

    nucl

    ide

    mob

    iliza

    tion

    and

    rele

    ase

    Exe

    cutiv

    e S

    umm

    ary,

    Tabl

    e 6.

    1.2-

    1,S

    ectio

    ns 6

    .1, 6

    .2, 6

    .3an

    d 6.

    4

    Tabl

    e A

    -2

    Con

    vect

    ive

    flow

    of a

    ir an

    d m

    oist

    ure

    in th

    e em

    plac

    emen

    t drif

    ts h

    as b

    een

    incl

    uded

    in m

    odel

    s of

    in-d

    rift t

    herm

    al h

    ydro

    logy

    . How

    ever

    , it d

    oes

    not c

    reat

    e an

    ad

    ditio

    nal s

    ourc

    e of

    moi

    stur

    e

    Sec

    tion

    6.2.

    1 Ta

    ble

    A-2

    Fl

    ow d

    iver

    sion

    , whe

    n co

    mbi

    ned

    with

    the

    lack

    of a

    dvec

    tion

    thro

    ugh

    the

    was

    te

    pack

    age,

    resu

    lts in

    onl

    y th

    e po

    tent

    ial f

    or d

    iffus

    ive

    rele

    ases

    from

    the

    was

    te fo

    rm

    and

    was

    te p

    acka

    ge if

    the

    was

    te p

    acka

    ge h

    as d

    egra

    ded

    feat

    ures

    SN

    L 20

    07 [D

    IRS

    181

    953]

    S

    tress

    Cor

    rosi

    on C

    rack

    ing

    of W

    aste

    Pac

    kage

    Out

    er

    Bar

    rier a

    nd D

    rip S

    hiel

    d M

    ater

    ials

    Sec

    tion

    6.8.

    6 Ta

    ble

    A-2

    S

    tress

    cra

    cks

    are

    suffi

    cien

    tly s

    mal

    l and

    tigh

    t to

    allo

    w o

    nly

    the

    diffu

    sive

    tran

    spor

    t of

    radi

    onuc

    lides

    thro

    ugh

    the

    crac

    ksS

    ectio

    n 6.

    2 Ta

    ble

    A-2

    Th

    e po

    tent

    ial f

    or a

    nd re

    sulta

    nt c

    onse

    quen

    ces

    of e

    arly

    failu

    re o

    f the

    was

    te

    pack

    age

    by m

    anuf

    actu

    ring

    defe

    cts

    or w

    eld

    flaw

    s ex

    ists

    , and

    has

    bee

    n co

    nsid

    ered

    in th

    e TS

    PA

    Nom

    inal

    Sce

    nario

    Cla

    ssS

    ectio

    n 6.

    8.6

    Tabl

    e A

    -2

    Stre

    ss c

    rack

    s ar

    e su

    ffici

    ently

    sm

    all a

    nd ti

    ght t

    o al

    low

    onl

    y th

    e di

    ffusi

    ve tr

    ansp

    ort

    of ra

    dion

    uclid

    es th

    roug

    h th

    e cr

    acks

    BS

    C 2

    007

    [DIR

    S 1

    8213

    1]

    Bas

    is o

    f Des

    ign

    for t

    he

    TAD

    Can

    iste

    r-B

    ased

    R

    epos

    itory

    Des

    ign

    Con

    cept

    .

    Sec

    tion

    8.2.

    3.1.

    1 Ta

    ble

    A-2

    R

    equi

    rem

    ents

    for N

    aval

    was

    te p

    acka

    ges

    empl

    acem

    ent s

    tand

    off d

    ista

    nce

    from

    m

    appe

    d fa

    ults

    S

    ectio

    n 8.

    2.3.

    1.1

    Tabl

    e A

    -2

    Nav

    al w

    aste

    pac

    kage

    s th

    at re

    quire

    s an

    8.2

    -ft (2

    .5-m

    ) min

    imum

    em

    plac

    emen

    t st

    ando

    ff di

    stan

    ce fr

    om m

    appe

    d fa

    ults

    SN

    L 20

    08 [D

    IRS

    183

    041]

    Fe

    atur

    es, E

    vent

    s, a

    nd

    Pro

    cess

    es fo

    r the

    Tot

    alS

    yste

    m P

    erfo

    rman

    ce

    Ass

    essm

    ent:

    Ana

    lyse

    s

    Sec

    tion

    6, b

    yin

    divi

    dual

    FE

    P

    Tabl

    e A

    -1

    Dis

    cuss

    ion

    of F

    EP

    rela

    ted

    to th

    e U

    pper

    Nat

    ural

    Bar

    rier a

    s ei

    ther

    an

    incl

    uded

    or

    excl

    uded

    scr

    eeni

    ng d

    ecis

    ion.

    Sec

    tion

    6, b

    yin

    divi

    dual

    FE

    P

    Tabl

    e A

    -2

    Dis

    cuss

    ion

    of F

    EP

    rela

    ted

    to th

    e E

    ngin

    eere

    d B

    arrie

    r Sys

    tem

    as

    eith

    er a

    n in

    clud

    ed o

    r exc

    lude

    d sc

    reen

    ing

    deci

    sion

    . S

    ectio

    n 6,

    by

    indi

    vidu

    al F

    EP

    Ta

    ble

    A-3

    D

    iscu

    ssio

    n of

    FE

    P re

    late

    d to

    the

    Low

    er N

    atur

    al B

    arrie

    r as

    eith

    er a

    n in

    clud

    ed o

    r ex

    clud

    ed s

    cree

    ning

    dec

    isio

    n.S

    NL

    2008

    [DIR

    S 1

    8347

    8]

    Tota

    l Sys

    tem

    Per

    form

    ance

    A

    sses

    smen

    t Mod

    el/A

    naly

    sis

    for t

    he L

    icen

    se

    App

    licat

    ion

    Sec

    tion

    6.5

    and

    Tabl

    e 6.

    5-2

    Tabl

    e A

    -2

    The

    prob

    abili

    ty o

    f ign

    eous

    an

    igne

    ous

    even

    t com

    prom

    isin

    g w

    aste

    em

    plac

    emen

    t dr

    ifts

    is v

    ery

    smal

    l

    SN

    L 20

    08 [D

    IRS

    183

    750]

    S

    atur

    ated

    Zon

    e Fl

    ow a

    nd

    Tran

    spor

    t Mod

    el

    Abs

    tract

    ion

    Sec

    tion

    6.7.

    2 Ta

    ble

    A-2

    O

    ther

    radi

    onuc

    lides

    hav

    e m

    oder

    ate

    half-

    lives

    and

    dec

    ay to

    pro

    duct

    s th

    at m

    aybe

    rele

    ased

    from

    the

    was

    te

    Sec

    tions

    7.4

    .2, 6

    .7.2

    Ta

    ble

    A-3

    R

    adio

    activ

    e de

    cay

    and

    ingr

    owth

    ANL-WIS-MD-000024 REV 01 4-7 February 2008

  • Postclosure Nuclear Safety Design Bases

    Tabl

    e 4-

    1.

    Sou

    rce

    of In

    puts

    (Con

    tinue

    d)

    Cita

    tion

    Sour

    ce T

    itle

    Spec

    ifica

    lly U

    sed

    From

    Spec

    ifica

    llyU

    sed

    In (t

    his

    AM

    R)

    Inpu

    t Des

    crip

    tion

    SN

    L 20

    07 [D

    IRS

    184

    614]

    U

    Z Fl

    ow M

    odel

    s an

    d S

    ubm

    odel

    s S

    ectio

    n 7.

    7.4.

    2 Ta

    ble

    A-1

    P

    erch

    ed-w

    ater

    con

    ditio

    ns d

    o no

    t pre

    sent

    ly e

    xist

    in th

    e un

    satu

    rate

    d zo

    ne a

    bove

    th

    e re

    posi

    tory

    , and

    are

    not

    exp

    ecte

    d ev

    en u

    nder

    futu

    re c

    limat

    e ch

    ange

    s S

    ectio

    ns 6

    .1.2

    , 6.

    2.4,

    6.1.

    2; T

    able

    4.1

    -1

    Tabl

    e A

    -3

    Frac

    ture

    -rel

    ated

    tran

    spor

    t pro

    cess

    es/p

    rope

    rties

    incl

    ude

    fract

    ure

    perm

    eabi

    lity,

    po

    rosi

    ty, f

    requ

    ency

    , act

    ive

    fract

    ure

    mod

    el, m

    atrix

    diff

    usio

    n co

    effic

    ient

    , sor

    ptio

    n,

    and

    collo

    id fi

    ltrat

    ion

    SN

    L 20

    07 [D

    IRS

    180

    506]

    In

    -Pac

    kage

    Che

    mis

    tryA

    bstra

    ctio

    n S

    ectio

    n 6.

    3.1.

    3.4

    Tabl

    e A

    -2

    The

    diffe

    rent

    cha

    ract

    eris

    tics

    of th

    ese

    was

    te fo

    rms

    (in p

    artic

    ular

    the

    hygr

    osco

    pic

    natu

    re o

    f the

    HLW

    gla

    ss) h

    ave

    been

    con

    side

    red

    in th

    e w

    aste

    form

    alte

    ratio

    n m

    odel

    s an

    d is

    not

    foun

    d to

    sub

    stan

    tially

    impa

    ct b

    arrie

    r cap

    abili

    ty o

    f thi

    s fe

    atur

    e S

    ectio

    n 6.

    3.1.

    1 Ta

    ble

    A-2

    C

    hem

    istry

    effe

    cts

    of v

    oids

    in th

    e w

    aste

    pac

    kage

    inte

    rnal

    s ar

    e in

    clud

    ed in

    m

    odel

    s of

    in-p

    acka

    ge c

    hem

    istry

    Sec

    tions

    6.1

    0.8

    and

    8.1

    Tabl

    e A

    -2

    The

    chem

    ical

    cha

    ract

    eris

    tics

    of th

    e w

    ater

    in c

    onta

    ct w

    ith th

    e w

    aste

    pac

    kage

    in

    tern

    als,

    incl

    udin

    g vo

    id s

    pace

    s, a

    nd th

    e w

    aste

    form

    , affe

    ct th

    e de

    grad

    atio

    n ch

    arac

    teris

    tics

    of th

    e w

    aste

    form

    , the

    sol

    ubili

    ty o

    f rad

    ionu

    clid

    es in

    the

    diss

    olve

    d ph

    ase,

    and

    the

    stab

    ility

    of c

    ollo

    idal

    par

    ticle

    s Ta

    ble

    6-1a

    Ta

    ble

    A-2

    Th

    e in

    -pac

    kage

    redo

    x st

    ate

    is a

    ssum

    ed to

    be

    set b

    y th

    e ox

    idat

    ion

    stat

    e in

    the

    empl

    acem

    ent d

    rifts

    onc

    e th

    e w

    aste

    pac

    kage

    is b

    reac

    hed

    and

    ther

    efor

    e se

    t to

    0.2

    Sec

    tion

    6.3.

    1.3.

    3 Ta

    ble

    A-2

    Th

    e ch

    emis

    try o

    f the

    wat

    er th

    at c

    omes

    into

    con

    tact

    with

    the

    was

    te fo

    rm a

    nd

    was

    te p

    acka

    ge in

    tern

    als

    is a

    ltere

    d by

    reac

    tion

    with

    the

    expo

    sed

    met

    allic

    and

    w

    aste

    form

    sur

    face

    s in

    side

    the

    was

    te p

    acka

    ge.

    Res

    ults

    of a

    naly

    ses

    indi

    cate

    th

    at th

    e ch

    emis

    try is

    mor

    e af

    fect

    ed b

    y th

    e ra

    te a

    nd a

    mou

    nt o

    f wat

    er in

    tera

    ctin

    g w

    ith th

    e w

    aste

    pac

    kage

    inte

    rnal

    s th

    an th

    e ch

    emis

    try o

    f thi

    s w

    ater

    ANL-WIS-MD-000024 REV 01 4-8 February 2008

  • Postclosure Nuclear Safety Design Bases

    4.2 CRITERIA

    Technical requirements to be satisfied by this document are based on 10 CFR 63.113(a) [DIRS 180319] and 10 CFR 63.115(a)-(c) [DIRS 180319]; as shown in Table 4-2. The acceptance criteria that will be used by the U.S. Nuclear Regulatory Commission (NRC) to determine whether the technical requirements have been met are identified in NUREG-1804 (NRC 2003 [DIRS 163274], Section 2.2.1.1.3) and Technical Work Plan for: Postclosure Nuclear Safety Design Bases (SNL 2007 [DIRS 182648]), Section 3.4). This document meets Criterion 1. Part of Criteria 2 and 3, the quantitative analysis and technical basis, are met by the TSPA (SNL 2008 [DIRS 183478]). These acceptance criteria are included below:

    � Acceptance Criterion 1—Identification of Barriers Is Adequate

    Barriers relied on to achieve compliance with 10 CFR 63.113(b) [DIRS 180319], as demonstrated in the Total System Performance Assessment, are adequately identified, and are clearly linked to their capabilities. The barriers identified include at least one from the engineered system and one from the natural system.

    � Acceptance Criterion 2—Description of Barrier Capability to Isolate Waste Is Acceptable

    The capability of the identified barriers to prevent or substantially reduce the rate of movement of water or radionuclides from the Yucca Mountain repository to the accessible environment, or prevent the release or substantially reduce the release rate of radionuclides from the waste is adequately identified and described:

    (1) The information on the time period over which each barrier performs its intended function, including any changes during the compliance period, is provided

    (2) The uncertainty associated with barrier capabilities is adequately described

    (3) The described capabilities are consistent with the results from the Total System Performance Assessment

    (4) The described capabilities are consistent with the definition of a barrier in 10 CFR 63.2 [DIRS 180319].

    � Acceptance Criterion 3—Technical Basis for Barrier Capability Is Adequately Presented

    The technical bases are consistent with the technical basis for the Performance Assessment. The technical basis for assertions of barrier capability is commensurate with the importance of each barrier’s capability and their associated uncertainties.

    The information presented in Table 4-2 summarizes the information category and the corresponding regulatory requirements of 10 CFR Part 63 [DIRS 180319].

    ANL-WIS-MD-000024 REV 01 4-9 February 2008

  • Table 4-2. Cross Reference for Information Categories in 10 CFR Part 63

    Information Category 10 CFR Part 63 Reference System Description and Demonstration of Multiple Barriers 63.113(a)

    63.115(a)-(c) Identification of Barriers 63.113(a)

    63.115(a) Barrier Capability Description 63.113(a)

    63.115(b) Technical Bases for Barrier Capability 63.115(c)

    Identifying Postclosure Performance Assessment Controlling Parameters and 63.21(c)(9) Classifying ITWI Structures, Systems and Components. 63.21(c)(10)

    63.21(c)(14) 63.21(c)(15)

    NOTE: Meeting 10 CFR 63.115(c) [DIRS 180319] regulations also requires that the technical basis for each barrier capability shall be based on, and consistent with, the technical basis for the performance assessments used to demonstrate compliance with 10 CFR 63.113(b) and 10 CFR 63.113(c) [DIRS 180319], which also invoke 10 CFR 63.114 [DIRS 180319] and other requirements from Subpart L of 10 CFR Part 63 [DIRS 180319].

    Postclosure Nuclear Safety Design Bases

    4.3 CODES, STANDARDS, AND REGULATIONS

    Other than the regulatory requirements and Yucca Mountain Review Plan acceptance criteria identified in Section 4.2, no other codes, standards, or regulations are used in this report.

    ANL-WIS-MD-000024 REV 01 4-10 February 2008

  • Postclosure Nuclear Safety Design Bases

    5. ASSUMPTIONS

    The only assumptions in this scientific analysis that are used in the ITBC evaluations of FEPs are the enabling assumptions identified in Section 6.1.

    ANL-WIS-MD-000024 REV 01 5-1 February 2008

  • Postclosure Nuclear Safety Design Bases

    INTENTIONALLY LEFT BLANK

    ANL-WIS-MD-000024 REV 01 5-2 February 2008

  • Postclosure Nuclear Safety Design Bases

    6. SCIENTIFIC ANALYSIS DISCUSSION

    This report has been prepared to meet regulatory requirements of 10 CFR 63.113(a) and 63.115 [DIRS 180319]), and to provide a risk-informed analysis of the postclosure technical basis for multiple barriers. Specifically, 10 CFR 63.113(a) [DIRS 180319] provides requirements for multiple barriers as part of performance objectives for the geologic repository after permanent closure, and 10 CFR 63.115 [DIRS 180319] provides requirements for the identification of, description of, and technical basis for the multiple barriers.

    The major activities documented in this report that address, in part, the above regulations are two: conduct the barrier analysis, and develop core and control parameter characteristics. For natural and engineered barriers that are ITWI, the tasks associated with these two activities include:

    1. Describing the three ITWI barriers (UNB, EBS, and LNB)

    2. Evaluating barrier capability, including assessment of the technical bases, evaluation of ITBC parameter characteristics and supporting the ITWI determination.

    The approach used to identify parameter characteristics that support the postclosure technical basis, the TSPA and contribute to barrier capability, begins by analyzing the FEP descriptions and screening justifications. The barrier analysis uses supporting information from FEP screening reports, which document the processes and events that are included in or excluded from performance assessment models; it also uses information from process models and model abstraction reports that describe the technical basis for implementation of processes and events in the performance assessment models. The use of information from these reports to support the barrier analysis ensures that the technical basis for barrier capability is consistent with the technical basis for the performance assessment models. Direct inputs supporting this analysis are listed in Table 4-1. Indirect inputs are listed in Table 6-1.

    Table 6-1. Source of Indirect Inputs

    Reference and DIRS Citation Name 10 CFR 63. 2007 [DIRS 180319] 10 CFR 63 70 FR 49014 [DIRS 177357] 40 CFR 197 70 FR 53313 [DIRS 178394] 70 FR 53313. Implementation of a Dose Standard After 10,000 Years ASME B46.1-2002. 2003 [DIRS 166013]

    Surface Texture (Surface Roughness, Waviness and Lay). New York, New York: American Society of Mechanical Engineers. TIC: 257359.

    ASTM B 575-99a. 1999 [DIRS 147465] Standard Specification for Low-Carbon Nickel-Molybdenum-Chromium, Low-Carbon Nickel-Chromium-Molybdenum, Low-Carbon NickelChromium-Molybdenum-Copper, Low-Carbon Nickel-ChromiumMolybdenum-Tantalum, and Low-Carbon Nickel-Chromium-Molybdenum-Tungsten Alloy Plate, Sheet, and Strip

    BSC 2004 [DIRS 166107] Drift Degradation Analysis BSC 2004 [DIRS 167652] Seepage Model for PA Including Drift Collapse BSC 2004 [DIRS 168138] Estimation of Mechanical Properties of Crushed Tuff for Use as Ballast

    Material in Emplacement Drifts

    ANL-WIS-MD-000024 REV 01 6-1 February 2008

  • Postclosure Nuclear Safety Design Bases

    Table 6-1. Source of Indirect Inputs (Continued)

    Reference and DIRS Citation Name BSC 2004 [DIRS 169218] Natural Analogue Synthesis Report BSC 2004 [DIRS 169987] CSNF Waste Form Degradation: Summary Abstraction BSC 2004 [DIRS 169988] Defense HLW Glass Degradation Model

    BSC 2004 [DIRS 169989] Characterize Framework for Igneous Activity at Yucca Mountain, Nevada BSC 2004 [DIRS 170002] Future Climate Analysis BSC 2004 [DIRS 170035] Conceptual Model and Numerical Approaches for Unsaturated Zone Flow

    and Transport BSC 2004 [DIRS 171764] Seepage Calibration Model and Seepage Tes