55
Scientific Analysis/Calculation Administrative Change Notice Complete only applicable items. 00C.20080314.0004 QA: QA Page 1 of 4 1. Document Number: I ANL-WIS-MD-000024 I 2. Revision: 101 I 3. ACN: I 01 4. Title: I Postclosure Nuclear Safety Design Bases 5. No. of Pages Attached: I 51 I 6. Approvals: ......... Preparer: . :3 /t1/ ';J.A108 Roger J Henning Print Name and Sign /II //1 / Date I Checker: /(1;: ({Sf;/- O.Jj; ";-/2--0 Peter Persoff Print name and sign v- , Date QCS/Lead Lab QA John Devers I< 03/1'1/08 Reviewer: Print name and sig Date Responsible Manager: Palmer Vaughn (!J3J; flo q. Print name and sign (/ Date 7. Affected Pages 8. Description of Change: Changes are a result ofOCRWM LP-7.5Q accepted with conditions, as documented on a Deliverable Review Comment Sheet dated 3/1012008. 4-5 SNL 2007 (DIRS 178519], row for Section 6.4.4, after "Uncertainty in these corrosion rates", insert "has been included in the model." SNL 2007 (DIRS 181953], delete the second occurrence of "Stress cracks are sufficiently small and 4-7 tight to allow only the diffusive transport of radionuclides through the cracks" as a duplicate of two lines above. 4-7 SNL 2008 (DIRS 183478], correct from "The probability of igneous an igneous event ... " to "The probability of an intrusive or eruptive igneous event ... " Delete the extra cell in the last column for the EBS TH Environment Submodel line; merge the cells so the cited reference identifier covers both MSTHM Process Model and MSTHM Abstraction. .. _--- _ .. _--. 6-22, Table 6-4 EBS TH MSTHMProcess Model Environment 6 Submodel MSTHM Abstrac ion 6-31 Delete the lines for core parameters "Closure Materials" and "Preclosure Ventilation" The following changes are in Section 6.1.8 Delete the last sentence in the first paragraph 6-36 In the second paragraph, the sentence starting with "The process presented herein, replace "presented herein" with "as it applies to postclosure activities" Delete first sentence of third paragraph. SCI-PRO-005.2-R2

ANL-WIS-MD-000024, Rev. 01, ACN: 01, 'Postclosure Nuclear Safety Design … · 2012-12-01 · Delete the extra cell in the last column for the EBS TH Environment Submodel line; merge

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Scientific Analysis/CalculationAdministrative Change Notice

Complete only applicable items.

00C.20080314.0004

QA: QAPage 1 of 4

1. Document Number: IANL-WIS-MD-000024 I 2. Revision: 101 I 3. ACN: I01

4. Title: IPostclosure Nuclear Safety Design Bases

5. No. of Pages Attached: I 51 I6. Approvals: .........Preparer: /~A. (J.If~

.:3/t1/';J.A108Roger J Henning

Print Name and Sign /II //1 / Date I

Checker: /(1;: ({Sf;/- O.Jj; ";-/2--0 ~PPeter PersoffPrint name and sign v- , Date

QCS/Lead Lab QAJohn Devers ~ I<~ 03/1'1/08Reviewer:Print name and sig Date

Responsible Manager:Palmer Vaughn ~~1//1V~ (!J3J;flo q.Print name and sign (/ Date

7. Affected Pages 8. Description of Change:Changes are a result ofOCRWM LP-7.5Q accepted with conditions, as documented on a DeliverableReview Comment Sheet dated 3/1012008.

4-5 SNL 2007 (DIRS 178519], row for Section 6.4.4, after "Uncertainty in these corrosion rates", insert"has been included in the model."SNL 2007 (DIRS 181953], delete the second occurrence of "Stress cracks are sufficiently small and

4-7 tight to allow only the diffusive transport of radionuclides through the cracks" as a duplicate of twolines above.

4-7 SNL 2008 (DIRS 183478], correct from "The probability of igneous an igneous event..." to "Theprobability of an intrusive or eruptive igneous event..."Delete the extra cell in the last column for the EBS TH Environment Submodel line; merge the cellsso the cited reference identifier covers both MSTHM Process Model and MSTHM Abstraction.. ._--- _.._--.

6-22, Table 6-4 EBS TH MSTHMProcess ModelEnvironment 6Submodel MSTHM Abstrac ion

6-31 Delete the lines for core parameters "Closure Materials" and "Preclosure Ventilation"The following changes are in Section 6.1.8

• Delete the last sentence in the first paragraph

6-36 • In the second paragraph, the sentence starting with "The process presented herein, replace"presented herein" with "as it applies to postclosure activities"

• Delete first sentence of third paragraph.

SCI-PRO-005.2-R2

Scientific Analysis/Calculation QA:

Administrative Change Notice Page 2 of 4

Complete only applicable items.

1. Document Number: ANL-WIS-MD-000024 2. Revision: 01 3. ACN: 01

4. Title: Postclosure Nuclear Safety Design Bases

6-37

Replace the first paragraph with:

Processes and responsibilities for evaluating proposed changes to repository design, engineering, construction, and operations activities that could impact the postclosure safety analyses will be controlled through configuration management and change control processes. These controls may also be used to evaluate the potential inclusion of items in the Q-List, as necessary.

In the second paragraph, delete “pursuant to this new procedure will” so paragraph reads:

Evaluations conducted include programmatic decision activities, as defined in SCI-PRO-002, Planning for Science Activities as these evaluations consist of “what-if” studies of proposed changes to technical baseline parameters and processes. Approved design changes will be incorporated into the design and technical baseline using applicable procedures. Programmatic decision activities may involve alternative conceptual models, parametric changes, scientific analyses or calculations. Programmatic decision documentation shall fully describe the intended use of the product, and shall fully justify assumptions, inputs, and decisions with respect to its intended use.

In the third paragraph after “concludes”, delete “a report, which will include”, and replace “report” with “evaluation” in two places so the paragraph reads:

The evaluation concludes with documentation of the analysis supporting the results, as well as the results, justifications and conclusions that document the results of the evaluations and any subsequent impacts. Also, the evaluation will define, if warranted, a proposed path forward and any additional actions to be taken. The evaluation will be provided to lead lab senior management for any further action, which includes notification of BSC and/or DOE, as necessary.

7-1

Replace the first paragraph with the following paragraphs: Three barriers important to waste isolation (ITWI) have been identified (Section 6.1.2). These barriers are the Upper Natural Barrier, the Engineered Barrier System, and the Lower Natural Barrier. The specification of these barriers as ITWI is a result of an analysis conducted and documented in this report (Section 6.1.2 and 6.1.5). This analysis considers these barriers to be ITWI consistent with 10 CFR 63.2 and 10 CFR63.142(a) [DIRS 180319] because they have been determined to have one or more core parameter characteristics that either 1) prevent or substantially reduce the rate of movement of water from the repository to the accessible environment; 2) prevent the release or substantially reduce the release rate of radionuclides from the waste; 3) prevent or substantially reduce the rate of movement of radionuclides from the repository to the accessible environment, or 4) prevent or substantially reduce the potential for criticality.

Table 7-1 provides a list of ITWI features / components supporting each of the three barriers as well as the barrier function for each feature/component (Output DTN: MO0801TABLITWI.000). A feature is classified as ITWI if it meets two conditions. The first condition is that the feature is associated with one or more parameter characteristic classified as important to barrier capability (ITBC). The second condition is that the feature is a significant contributor to the barrier capability relative to the other features of the barrier.

Table 7-1 also identifies the relevant design control parameters related to the ITWI feature/component. These control parameters are quantities or variables that define or support a contribution to barrier capability or a model describing that capability (see Section 6.1). These design control parameters reflect the important aspect of the feature/component that must be controlled by either configuration management or procedural safety controls to ensure the postclosure performance assessment analytical bases are established during design, construction, procurement, operations, and closure. Most of these control parameters are identified as derived internal constraints in BSC 2008 [DIRS 183627] and Table 7-5. Other control parameters are related to specific constraints that are identified in other requirements documents such as the Waste Acceptance Systems Requirements Document (DOE 2007 [DIRS 169992]) and performance specifications documents such as Transportation, Aging and Disposal Canister System Performance Specification(DOE 2007 [DIRS 181403]).

SCI-PRO-005.2-R2

Scientific Analysis/Calculation QA:

Administrative Change Notice Page 3 of 4

Complete only applicable items.

1. Document Number: ANL-WIS-MD-000024 2. Revision: 01 3. ACN: 01

4. Title: Postclosure Nuclear Safety Design Bases

7-18 From the Waste Package Feature / Component: delete the line “Drip Shield Early Failure – Control – 2.1.03.10.0A …

7-33 Change the internal derived constraint for parameter 03-14 to say: “The waste package fabrication welds shall be conducted in accordance with standard industry requirements.”

7-35 Change the internal derived constraint for parameter 03-23 to say: “The waste package surface finish shall be specified to be 125 roughness or better as defined in ASME B46.1-2002 [DIRS 166013].”

8-7 Update the TBV references for 183041 - DOC.20080307.0003, 184797- DOC.20080227.0003. 8-8 Update the reference 183478 - DOC.20080312.0001. A-3 In Control Parameter “Emplacement Drift Diameter” replace “Diameter” with “Configuration”. A-9 In Core Parameter “Infiltration and Seepage processes” replace “processes” with “Properties”.

A-11 In Control Parameter “Emplacement Drift Diameter” replace “Diameter” with “Configuration”. A-12 In Control Parameter “Standoff from Quaternary Faults” add “Repository” before “Standoff”. A-19 In Control Parameter “Emplacement Drift Diameter” replace “Diameter” with “Configuration”. A-29 In Control Parameter “Closure Boreholes” add “of” after “Closure”. A-34 In Control Parameter column add a line break between “Configuration” and “Emplacement”.

A-42

Between “… to ensure correct implementation.” and “Accordingly, these features are …” of the “Discussion of effect on barrier capability” column, insert: “The design addresses seals as closure of the shafts and ramps shall include backfilling for the entire depth of the opening. Site investigation boreholes within or near the footprint of the repository block will be backfilled with material compatible with the host rock and plugged. These design features are intended to meet the intrusion scenarios, and are not performance related.”

A-43 In Control Parameter “Design of the Ground Support System” delete “the”. In “Closure Boreholes” add “of” after “Closure”.

A-50 In Control Parameter “Repository Elevation” add “—Standoff from Water Table”. A-52 In Core Parameter column add a line break between “Properties” and “Invert”. A-55 In Control Parameter column add a line break between “Limit” and “Drift”. A-65 In Control Parameter column add a line break between “Configuration” and “Verification”. A-66 Fix page break in table A-67 Fix page break in table A-68 In Control Parameter column add “Non-“ to “ITBC”, delete second “Non-ITBC”. A-77 In Control Parameter column add “Package” between “Waste” and “—Drip”. A-83 In Control Parameter column delete “Marring” after “Damage”. A-84 In Control Parameter column delete “Drip Shield Early Failure”.

A-86 In Control Parameter column add a line break between “Configuration” and “Emplacement”.

Delete the hyphen at the end of “As-emplaced Waste Package-Drip Shield Configuration”- A-88 In Control Parameter column add a line break between “Package” and “Drip”. A-92 In Control Parameter column add “In-drift” after “EBS” and change “Material” to “Materials”.

A-111

In Control Parameter column add “Package” between “Waste” and “—Drip”

Add “In-drift” after “EBS” and change “Material” to “Materials”.

In Core Parameter column, delete “Committed Materials”. A-112 In the Core Parameter column, add a line break between “Heat” and “Radionuclide”. A-115 In the Core Parameter column, after “In-Package Chemical Environment” delete “Parameter”.

A-122 In the Core Parameter column, after “Waste Package Materials, Properties and Configuration” delete “Properties”.

SCI-PRO-005.2-R2

Scientific Analysis/Calculation QA:

Administrative Change Notice Page 4 of 4

Complete only applicable items.

1. Document Number: ANL-WIS-MD-000024 2. Revision: 01 3. ACN: 01

4. Title: Postclosure Nuclear Safety Design Bases

A-123 In the Core Parameter column, after “Waste Form Degradation Corrosion Products” add “Properties” for FEP 2.1.09.08.0A.

A-130 In the Core Parameter column, add a line break between “Heat” and “Radionuclide”. A-135 In the Core Parameter column, add a line break between “Heat” and “Radionuclide”. A-140 In the Core Parameter column, after “Radionuclide Inventory and Source Term” add “Properties”. A-145 In Control Parameter column add “Emplacement” before “Pallet” and add “Function” after. A-146 In Control Parameter column add “Emplacement” before “Pallet” and add “Function” after. A-148 In Control Parameter column add a line break between “Function” and “Verification”. A-154 In the Core Parameter column, after “In-drift Chemical Environment” delete “Properties”.

A-169 In the Control Parameter column, replace “Emplacement Drift Orientation” with “Orientation of Emplacement Drifts”.

A-186 In Control Parameter “Standoff from Quaternary Faults” add “Repository” before “Standoff” A-195 In the Core Parameter column, add “Non-ITBC” above parameters for 1.4.07.02.0A.

SCI-PRO-005.2-R2

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 c

orro

sion

rate

s ha

s be

en in

clud

ed in

the

mod

el10

CFR

63.

200

7[D

IRS

180

319]

10

CFR

63

10 C

FR63

.51(

a)(3

)(i−i

ii), 1

0 C

FR 6

3.72

(a),

and

10

CFR

63.

72(b

)(1−1

1)

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 ACN 01 4-5 March 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,

Ta

ble

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

ss

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 an

intru

sive

or e

rupt

ive

igne

ous

even

t com

prom

isin

g w

aste

em

plac

emen

t drif

ts is

ver

y sm

all

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 ACN 01 4-7 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e 6-

4.

Rel

atio

nshi

p am

ong

TSP

A M

odel

Com

pone

nts,

Sub

mod

els,

and

Abs

tract

ion/

Proc

ess

Mod

el(s

)/Ana

lysi

s(es

)

Bar

rier

TSPA

-LA

Prin

cipa

l Mod

el C

ompo

nent

s Su

bmod

el fo

r TS

PA-L

A

Abs

trac

tion/

Proc

ess

Mod

el(s

)/Ana

lysi

s(es

) R

efer

ence

1

Upp

er N

atur

al B

arrie

r U

nsat

urat

ed Z

one

Flow

Mod

el C

ompo

nent

S

ite-S

cale

UZ

Flow

U

Z Fl

ow F

ield

sA

bstra

ctio

n U

Z Fl

ow F

ield

s A

bstra

ctio

n 1

Site

-Sca

le U

Z Fl

ow P

roce

ss M

odel

A

ctiv

e Fr

actu

re M

odel

D

ual-P

erm

eabi

lity

UZ

Flow

Mod

el

Infil

tratio

n A

naly

sis

Infil

tratio

n S

ubm

odel

In

filtra

tion

Mod

el A

bstra

ctio

n 2

Infil

tratio

n P

roce

ss M

odel

2

Clim

ate

Ana

lysi

s C

limat

e S

ubm

odel

Fu

ture

Clim

ate

Anal

ysis

3

Drif

t See

page

D

rift S

eepa

ge

Subm

odel

D

rift S

eepa

ge A

bstra

ctio

n 4,

5 D

rift S

eepa

ge A

bstra

ctio

n in

clud

ing

Drif

t C

olla

pse

TH S

eepa

ge P

roce

ss M

odel

En

gine

ered

Bar

rier

Sys

tem

E

BS

Env

ironm

ent M

odel

C

ompo

nent

D

rift W

all C

onde

nsat

ion

Drif

t Wal

lC

onde

nsat

ion

Subm

odel

In-D

rift N

atur

al C

onve

ctio

n an

d C

onde

nsat

ion

Proc

ess

Mod

el

7

Drif

t Wal

l Con

dens

atio

n A

bstra

ctio

n E

BS

The

rmal

-Hyd

rolo

gic

Env

ironm

ent

EB

S T

HE

nviro

nmen

t Su

bmod

el

MS

THM

Pro

cess

Mod

el

6 M

STH

M A

bstra

ctio

n

EB

S C

hem

ical

Env

ironm

ent

EB

S C

hem

ical

E

nviro

nmen

t Su

bmod

el

EB

S P

&C

E A

bstra

ctio

n 8

IDP

S P

roce

ss M

odel

15

WP

and

DS

D

egra

datio

n

Mod

el C

ompo

nent

WA

PD

EG

W

P a

nd D

S

Deg

rada

tion

Subm

odel

WP

Gen

eral

Cor

rosi

on A

bstra

ctio

n 10

,11,

12

WP

MIC

Abs

tract

ion

WP

SC

C A

bstra

ctio

nD

S G

ener

al C

orro

sion

Abs

tract

ion

Loca

lized

Cor

rosi

on o

n W

PO

uter

Sur

face

Lo

caliz

ed C

orro

sion

In

itiat

ion

Sub

mod

el

Loca

lized

Cor

rosi

on In

itiat

ion

Abs

tract

ion

Loca

lized

Cor

rosi

on P

enet

ratio

n R

ate

Abs

tract

ion

ANL-WIS-MD-000024 REV 01 ACN 01 6-22 March 2008

Postclosure Nuclear Safety Design Bases

core parameter characteristic was essentially the same as a control parameter, the core parameter characteristic was eliminated and the control parameter characteristic retained.

Core parameter characteristics are listed in Table 6-5 and cited in Appendix A.

Core parameter characteristics are defined in Section 6.1.1. They are associated with core parameters that contribute to barrier capability, support the postclosure technical baseline, and are candidates for performance confirmation. They are related to the events and/or processes that act on a feature as described by a FEP screening justification or report. Core parameter characteristics are generalized, and they include the materials, properties, configurations, and/or orientations.

Table 6-5. Core Parameter Characteristics

Core Parameter Characteristic1

Characterization of Fault Displacement Characterization of Igneous Events Characterization of Seismic Events Corrosion Products Properties Criticality Characteristics Drip Shield Corrosion Drip Shield Materials, Properties, and Configuration Drip Shield Seismic Performance Emplacement Drift Configuration Emplacement Pallet Materials, Properties, and Configuration Extent of Saturated Zone Extent of Unsaturated Zone Geothermal Gradient In-Drift Chemical Environment In-Drift Chemical Environment Properties In-Drift Thermal Environment, Convection, Condensation, and Evaporation Infiltration and Seepage Infiltration and Seepage Properties In-Package Chemical Environment In-Package Thermal Environment, Inside Waste Package Waste Forms Interpretation of Fault Displacement Invert Materials Properties, and Configuration Pallet Materials, Properties, and Configuration Properties of corrosion products Properties of the Host Rock Unit Properties of Unsaturated Zone Radionuclide Inventory and Source Term Properties Radionuclide Properties Repository: location and depth; layout and geometry; construction, operation, and closure Saturated Zone Chemical Environment Saturated Zone Flow

ANL-WIS-MD-000024 REV 01 ACN 01 6-31 March 2008

Postclosure Nuclear Safety Design Bases

Confirmation Plan activities. Thus, PoNSDB identifies all barrier capabilities, whereas, TSPA identifies which of these capabilities are represented in risk and performance determinations.

The activities identified in the Performance Confirmation Plan have been compared to the assumptions, data, and information that comprise the performance assessment models and results of the TSPA and the PoNSDB document. This exercise has confirmed that the existing performance confirmation activities provide a breadth of investigations sufficient to evaluate the performance basis of the license application. None of these activities is identified for deletion at this time (SNL 2008 [DIRS 184797]).

6.1.8 Methodology for Postclosure Change Evaluation

Repository design, engineering, construction, and operations activities may result in changes to design, materials, configurations, and processes that differ from the analyzed technical bases. In addition, advances in scientific research may result in information (data, models, and methodologies) that is different than the analyzed bases. Finally, the regulator may dictate change(s). The evaluation of such changes with respect to the postclosure technical basis and performance assessment is a necessary part of change control management, which involves integration among the preclosure safety analyses of the design organization (currently Bechtel SAIC Company, LLC (BSC)), Postclosure Analysis Organization (currently Sandia National Laboratories), the Department of Energy (DOE), and the Naval Nuclear Propulsion Program.

10 CFR 63.44 [DIRS 180319] provides regulatory requirements associated with change control for the technical basis documented in the Safety Analysis Report, but is not invoked until after construction authorization is granted. It is prudent to design the preconstruction change evaluation process to be consistent with the information needs of the program that will be implemented to comply with 10 CFR 63.44 [DIRS 180319] when it is invoked. The process as it applies to postclosure activities is primarily intended to provide evaluations of changes to postclosure activities and/or SSCs that will be required during the postclosure period during the presubmittal and preconstruction authorization time periods, although the process could additionally be used to address some of the requirements for 10 CFR 63.44 [DIRS 180319]. The requirements related to change control processes in 10 CFR 63.44 [DIRS 180319] addresses preclosure and postclosure changes.

The process of evaluation remains the same regardless of the drivers for the change (e.g., design, operations, or science). Evaluations are made with respect to impacts on the postclosure compliance baseline and performance assessment. The technical basis is defined and documented in the TSPA analysis and/or model report, key supporting postclosure technical documents, the FEPs analysis and Database, and Total System Performance Assessment design interface documents that define the design input parameters and current ranges for those parameters as the required source for postclosure analyses. These documents summarize the postclosure technical bases and will be used as the basis from which to evaluate proposed changes.

ANL-WIS-MD-000024 REV 01 ACN 01 6-36 March 2008

Postclosure Nuclear Safety Design Bases

Processes and responsibilities for evaluating proposed changes to repository design, engineering, construction, and operations activities that could impact the postclosure safety analyses will be controlled through configuration management and change control processes. These controls may also be used to evaluate the potential inclusion of items in the Q-List, as necessary.

Evaluations conducted include programmatic decision activities, as defined in SCI-PRO-002, Planning for Science Activities as these evaluations consist of “what-if” studies of proposed changes to technical baseline parameters and processes. Approved design changes will be incorporated into the design and technical baseline using applicable procedures. Programmatic decision activities may involve alternative conceptual models, parametric changes, scientific analyses or calculations. Programmatic decision documentation shall fully describe the intended use of the product, and shall fully justify assumptions, inputs, and decisions with respect to its intended use.

The evaluation concludes with documentation of the analysis supporting the results, as well as the results, justifications and conclusions that document the results of the evaluations and any subsequent impacts. Also, the evaluation will define, if warranted, a proposed path forward and any additional actions to be taken. The evaluation will be provided to lead lab senior management for any further action, which includes notification of BSC and/or DOE, as necessary.

6.2 SYSTEM DESCRIPTION AND DEMONSTRATION OF MULTIPLE BARRIERS

A critical element for repository safety is a site and system that provides multiple barriers to the movement of water and radionuclides. A barrier is defined in 10 CFR 63.2 as any material, structure, or feature that, for a period to be determined by the NRC, prevents or substantially reduces the rate of movement of water or radionuclides from the Yucca Mountain Repository to the accessible environment, or prevents the release or substantially reduces the release rate of radionuclides from the waste.

The repository system is composed of natural and engineered features that are combined into two natural barriers and an engineered barrier, designated as the UNB, the LNB, and the EBS. These three barriers provide the following principal barrier functions:

• The UNB, by preventing or substantially reducing the amount and the rate of water seeping into the drifts, prevents or substantially reduces the rate of movement of water from the repository to the accessible environment and prevents or substantially reduces the release rate of radionuclides from the waste

ANL-WIS-MD-000024 REV 01 ACN 01 6-37 March 2008

Postclosure Nuclear Safety Design Bases

7. CONCLUSIONS

Three barriers important to waste isolation (ITWI) have been identified (Section 6.1.2). These barriers are the Upper Natural Barrier, the Engineered Barrier System, and the Lower Natural Barrier. The specification of these barriers as ITWI is a result of an analysis conducted and documented in this report (Section 6.1.2 and 6.1.5). This analysis considers these barriers to be ITWI consistent with 10 CFR 63.2 and 10 CFR63.142(a) [DIRS 180319] because they have been determined to have one or more core parameter characteristics that either 1) prevent or substantially reduce the rate of movement of water from the repository to the accessible environment; 2) prevent the release or substantially reduce the release rate of radionuclides from the waste; 3) prevent or substantially reduce the rate of movement of radionuclides from the repository to the accessible environment, or 4) prevent or substantially reduce the potential for criticality.

Table 7-1 provides a list of ITWI features / components supporting each of the three barriers as well as the barrier function for each feature/component (Output DTN: MO0801TABLITWI.000). A feature is classified as ITWI if it meets two conditions. The first condition is that the feature is associated with one or more parameter characteristic classified as important to barrier capability (ITBC). The second condition is that the feature is a significant contributor to the barrier capability relative to the other features of the barrier.

Table 7-1 also identifies the relevant design control parameters related to the ITWI feature/component. These control parameters are quantities or variables that define or support a contribution to barrier capability or a model describing that capability (see Section 6.1). These design control parameters reflect the important aspect of the feature/component that must be controlled by either configuration management or procedural safety controls to ensure the postclosure performance assessment analytical bases are established during design, construction, procurement, operations, and closure. Most of these control parameters are identified as derived internal constraints in BSC 2008 [DIRS 183627] and Table 7-5. Other control parameters are related to specific constraints that are identified in other requirements documents such as the Waste Acceptance Systems Requirements Document (DOE 2007 [DIRS 169992]) and performance specifications documents such as Transportation, Aging and Disposal Canister System Performance Specification(DOE 2007 [DIRS 181403]).

Consumable materials to be incorporated into any engineered item important to waste isolation during fabrication of that item are also included as items important to waste isolation. The control parameters that are related to this specific criteria include 02-03: Committed Materials and 04-09: Waste Package & TAD Canister Excluded Materials.

Additional constraints beyond the control parameters listed are placed on some features or SSCs. Table 7-1 lists these additional controlling mechanisms as control parameter characteristics for the features or SSCs where they apply. These include: the Transportation, Aging, and Disposal Canister System Performance Specification (DOE 2007 [DIRS 181403], and the Waste Acceptance System Requirements Document (DOE 2007 [DIRS 169992]) and information contained in Naval Nuclear Propulsion Program classified documents. In addition, for postclosure purposes, NUREG-1536 and NUREG-1567 are equivalent in their requirements for moisture removal and are therefore acceptable.

ANL-WIS-MD-000024 REV 01 ACN 01 7-1 March 2008

Postclosure Nuclear Safety Design Bases

The methodology for the determination of ITWI barriers is primarily based on the information contained in the screening justifications and screening dispositions of the Features, Events, and Processes (FEPs). As the FEPs form the bases of technical support for the TSPA, this approach is both efficient and comprehensive for ITWI barrier determination. The FEP screening justifications and dispositions can also be associated with specific parameter characteristics. The parameter characteristics associated with each FEP relevant to specific features/components of

ANL-WIS-MD-000024 REV 01 ACN 01 7-1a March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e 7-

3 IT

BC

Fea

ture

s / C

ompo

nent

s an

d IT

BC

Par

amet

er C

hara

cter

istic

s of

Eng

inee

red

Bar

rier S

yste

m (C

ontin

ued)

Feat

ure

/ Com

pone

nt

Cha

ract

eris

tic

Type

A

naly

sis

Bas

isW

aste

Pac

kage

A

s-E

mpl

aced

Was

te P

acka

ge-D

rip S

hiel

d C

onfig

urat

ion

Con

trol

1.2.

03.0

2.0A

- S

eism

ic G

roun

d M

otio

n D

amag

es E

BS

Com

pone

nts

(Incl

uded

) 2.

1.03

.03.

0A -

Loca

lized

Cor

rosi

on o

f Was

te P

acka

ges

(Incl

uded

) 2.

1.03

.11.

0A -

Phy

sica

l For

m o

f Was

te P

acka

ge a

nd D

rip S

hiel

d (In

clud

ed)

Cha

ract

eriz

atio

n of

Sei

smic

Eve

nts

Cor

e 1.

2.03

.02.

0A -

Sei

smic

Gro

und

Mot

ion

Dam

ages

EB

S C

ompo

nent

s (In

clud

ed)

C

omm

itted

Mat

eria

ls

Con

trol

2.1.

09.2

8.0A

-Lo

caliz

ed C

orro

sion

on

Was

te P

acka

ge O

uter

Sur

face

due

to

Del

ique

scen

ce (

Excl

uded

) D

rip S

hiel

d C

orro

sion

Allo

wan

ce

Con

trol

2.1.

03.0

1.0A

- G

ener

al C

orro

sion

of W

aste

Pac

kage

s (In

clud

ed)

2.1.

03.0

3.0A

- Lo

caliz

ed C

orro

sion

of W

aste

Pac

kage

s (In

clud

ed)

2.1.

03.1

0.0A

- A

dvec

tion

of L

iqui

ds a

nd S

olid

s th

roug

h C

rack

s in

the

Was

te

Pack

age

(Exc

lude

d)

Drip

Shi

eld

Des

ign

Con

trol

2.1.

03.0

1.0A

- G

ener

al C

orro

sion

of W

aste

Pac

kage

s (In

clud

ed)

2.1.

03.0

3.0A

- Lo

caliz

ed C

orro

sion

of W

aste

Pac

kage

s (In

clud

ed)

2.1.

03.1

0.0A

- A

dvec

tion

of L

iqui

ds a

nd S

olid

s th

roug

h C

rack

s in

the

Was

te

Pack

age

(Exc

lude

d)

Drip

Shi

eld

Des

ign

and

Inst

alla

tion

Con

trol

2.1.

03.1

0.0A

- A

dvec

tion

of L

iqui

ds a

nd S

olid

s th

roug

h C

rack

s in

the

Was

te

Pack

age

(Exc

lude

d)

Drip

Shi

eld

Mat

eria

ls a

nd T

hick

ness

es

Con

trol

2.1.

03.0

1.0A

- G

ener

al C

orro

sion

of W

aste

Pac

kage

s (In

clud

ed)

2.1.

03.1

0.0A

- A

dvec

tion

of L

iqui

ds a

nd S

olid

s th

roug

h C

rack

s in

the

Was

te

Pack

age

(Exc

lude

d)

Drip

Shi

eld

Mat

eria

ls, P

rope

rties

, and

C

onfig

urat

ion

Cor

e 1.

2.03

.02.

0A -

Sei

smic

Gro

und

Mot

ion

Dam

ages

EB

S C

ompo

nent

s (In

clud

ed)

2.1.

03.0

1.0A

- G

ener

al C

orro

sion

of W

aste

Pac

kage

s (In

clud

ed)

2.1.

03.0

3.0A

- Lo

caliz

ed C

orro

sion

of W

aste

Pac

kage

s (In

clud

ed)

2.1.

03.1

0.0A

- A

dvec

tion

of L

iqui

ds a

nd S

olid

s th

roug

h C

rack

s in

the

Was

te

Pack

age

(Exc

lude

d)

ANL-WIS-MD-000024 REV 01 ACN 01 7-18 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e 7-

5.

Sum

mar

y of

Cla

ssifi

catio

n of

Con

trol P

aram

eter

Cha

ract

eris

tics

by E

ngin

eerin

g S

ubsy

stem

Cat

egor

izat

ion1 (C

ontin

ued)

Cat

egor

y N

umbe

r C

ontr

ol C

hara

cter

istic

D

eriv

ed In

tern

al C

onst

rain

t IT

BC

IT

WI

Rel

evan

t W

aste

Pac

kage

03

-06

Was

te P

acka

ge In

tern

al

Pre

ssur

izat

ion

The

was

te p

acka

ge s

hall

be d

esig

ned

to a

ccom

mod

ate

inte

rnal

pre

ssur

izat

ion

of th

e w

aste

pac

kage

incl

udin

g ef

fect

s of

a h

igh

tem

pera

ture

of 3

50°C

and

fuel

rod

gas

rele

ase.

No

No

Was

teP

acka

ge

03-0

7 W

aste

Pac

kage

C

orro

sion

Allo

wan

ce

For p

ostc

losu

re m

echa

nica

l cal

cula

tions

and

ana

lysi

s, a

cor

rosi

on a

llow

ance

of a

t lea

st

2 m

m p

er s

ide

shal

l be

acco

unte

d fo

r on

expo

sed

was

te p

acka

ge s

urfa

ces.

C

alcu

latio

ns w

ill b

e pe

rform

ed u

sing

mec

hani

cal p

rope

rties

at 1

50°C

or g

reat

er.

Yes

N

o

Was

teP

acka

ge

03-0

8 S

eism

ic D

esig

n of

Was

te

Pac

kage

Th

e in

terfa

ce c

ontro

l mec

hani

sm fo

r the

sei

smic

des

ign

spec

tra, t

ime

hist

orie

s, a

nd

grou

nd a

ccel

erat

ions

for t

he s

ubsu

rface

faci

litie

s is

the

Sei

smic

Dat

a IE

D.

Yes

N

o

Was

teP

acka

ge

03-0

9 W

aste

Pac

kage

Wor

st-

Cas

e D

ose

Rat

e Th

e w

aste

pac

kage

con

tain

ing

the

TAD

can

iste

r with

21

PW

R fu

el a

ssem

blie

s sh

all

repr

esen

t the

wor

st-c

ase

dose

rate

(80

GW

d/M

TU b

urnu

p, 5

% U

-235

enr

ichm

ent a

nd

5 ye

ars

deca

y).

No

No

Was

teP

acka

ge

03-1

0 W

aste

Pac

kage

Des

ign

Bas

is B

ound

ing

Dos

eR

ate

The

inte

rface

con

trol m

echa

nism

for t

he d

esig

n ba

sis

boun

ding

dos

e ra

te c

alcu

latio

ns

for w

aste

pac

kage

s an

d re

pres

enta

tive

neut

ron

flux

is th

e W

aste

Pac

kage

Rad

iatio

n C

hara

cter

istic

s IE

D.

No

No

Was

teP

acka

ge

03-1

1 W

aste

Pac

kage

Dec

ayH

eat

The

inte

rface

con

trol m

echa

nism

s fo

r the

pos

tclo

sure

des

ign

basi

s w

aste

pac

kage

de

cay

heat

are

the

Was

te P

acka

ge D

ecay

Hea

t Gen

erat

ion

IED

s.

No

No

Was

teP

acka

ge

03-1

2 W

aste

Pac

kage

Fa

bric

atio

n Th

e w

aste

pac

kage

out

er c

orro

sion

bar

rier c

ylin

der s

hall

be fa

bric

ated

from

no

mor

e th

an 3

sec

tions

with

long

itudi

nal w

elds

offs

et. T

he w

aste

pac

kage

will

be

insp

ecte

d an

d ev

alua

ted

per a

pplic

able

crit

eria

, e.g

., P

aram

eter

03-

18, a

t the

fabr

icat

or lo

catio

n an

d up

on re

ceip

t at t

he re

posi

tory

loca

tion.

Yes

Y

es

Was

teP

acka

ge

03-1

3 W

aste

Pac

kage

Fa

bric

atio

n W

eld

Insp

ectio

ns

The

was

te p

acka

ge o

uter

cor

rosi

on b

arrie

r fab

ricat

ion

wel

ds s

hall

be n

onde

stru

ctiv

ely

exam

ined

by

mea

ns o

f rad

iogr

aphi

c ex

amin

atio

n (R

T) a

nd u

ltras

onic

test

ing

(UT)

for

flaw

s eq

ual t

o or

gre

ater

than

1/1

6 in

ch. O

uter

cor

rosi

on b

arrie

r fab

ricat

ion

wel

ds s

hall

also

be

exam

ined

usi

ng li

quid

pen

etra

nt p

er th

e ap

plic

able

spe

cific

atio

n.

Yes

Y

es

Was

teP

acka

ge

03-1

4 W

aste

Pac

kage

Wel

ding

M

ater

ials

Th

e w

aste

pac

kage

fabr

icat

ion

wel

ds s

hall

be c

ondu

cted

in a

ccor

danc

e w

ith s

tand

ard

indu

stry

requ

irem

ents

. Y

es

Yes

Was

teP

acka

ge

03-1

5 W

aste

Pac

kage

Fa

bric

atio

n W

eldi

ng

Flaw

s

The

wel

ding

tech

niqu

es fo

r the

fabr

icat

ion

wel

ds s

hall

be c

onst

rain

ed to

GM

AW

(gas

m

etal

arc

wel

ding

) exc

ept f

or s

hort-

circ

uitin

g m

ode,

and

aut

omat

ed G

TAW

(gas

tu

ngst

en a

rc w

eldi

ng) f

or A

lloy

22 (U

NS

N06

022)

mat

eria

l, lim

ited

to <

45 k

J/in

. W

eldi

ng fl

aws

1/16

inch

and

gre

ater

will

be

repa

ired

for t

he o

uter

cor

rosi

on b

arrie

r in

acco

rdan

ce w

ith w

ritte

n pr

oced

ures

that

hav

e be

en a

ccep

ted

by th

e de

sign

orga

niza

tion

prio

r to

thei

r usa

ge.

Yes

Y

es

ANL-WIS-MD-000024 REV 01 ACN 01 7-33 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e 7-

5.

Sum

mar

y of

Cla

ssifi

catio

n of

Con

trol P

aram

eter

Cha

ract

eris

tics

by E

ngin

eerin

g S

ubsy

stem

Cat

egor

izat

ion1 (C

ontin

ued)

Cat

egor

y N

umbe

r C

ontr

ol C

hara

cter

istic

D

eriv

ed In

tern

al C

onst

rain

t IT

BC

IT

WI

Rel

evan

t W

aste

Pac

kage

03

-21

Was

te P

acka

ge H

andl

ing

The

was

te p

acka

ge s

hall

be h

andl

ed in

a c

ontro

lled

man

ner d

urin

g fa

bric

atio

n,

hand

ling,

tran

spor

t, st

orag

e, e

mpl

acem

ent,

inst

alla

tion,

ope

ratio

n, a

nd c

losu

re

activ

ities

to m

inim

ize

dam

age;

sur

face

con

tam

inat

ion;

and

exp

osur

e to

adv

erse

su

bsta

nces

.

Yes

Y

es

Was

teP

acka

ge

03-2

2 W

aste

Pac

kage

Han

dlin

g &

Em

plac

emen

t W

aste

pac

kage

han

dlin

g an

d em

plac

emen

t act

iviti

es s

hall

be m

onito

red

thro

ugh

equi

pmen

t with

reso

lutio

n ca

pabl

e of

det

ectin

g w

aste

pac

kage

dam

age.

An

oper

ator

an

d an

inde

pend

ent c

heck

er s

hall

perfo

rm th

e op

erat

ions

. Rec

ords

dem

onst

ratin

g co

mpl

ianc

e sh

all b

e m

aint

aine

d.

No

No

Was

teP

acka

ge

03-2

3 W

aste

Pac

kage

Sur

face

Fi

nish

Th

e w

aste

pac

kage

sur

face

fini

sh s

hall

be s

peci

fied

to b

e 12

5 ro

ughn

ess

as d

efin

ed in

AS

ME

B46

.1-2

002

[DIR

S 1

6601

3].

Yes

Y

es

Was

teP

acka

ge

03-2

4 W

aste

Pac

kage

Sur

face

D

amag

e P

rior t

o C

losu

re

The

empl

acem

ent d

rift g

roun

d su

ppor

t sys

tem

sha

ll be

insp

ecte

d pr

ior t

o dr

ip s

hiel

d in

stal

latio

n. W

aste

pac

kage

s th

at h

ave

com

e in

con

tact

with

falle

n ro

ck o

r gro

und

supp

ort m

ater

ials

will

be

insp

ecte

d to

ens

ure

the

dam

age

to th

e w

aste

pac

kage

co

rrosi

on b

arrie

r tha

t dis

plac

e m

ater

ial (

i.e. s

crat

ches

), sh

all b

e lim

ited

to 1

.6 m

m (1

/16

in) i

n de

pth.

Mod

ifica

tions

to th

e w

aste

pac

kage

cor

rosi

on b

arrie

r tha

t def

orm

the

surfa

ce, b

ut d

o no

t rem

ove

mat

eria

l (i.e

. den

ts),

shal

l not

leav

e re

sidu

al te

nsile

st

ress

es g

reat

er th

an 2

57 M

Pa.

Yes

Y

es

Was

teP

acka

ge

03-2

6 W

aste

Pac

kage

Moi

stur

eR

emov

al &

Iner

ting

All w

aste

pac

kage

s sh

all b

e va

cuum

drie

d an

d ba

ckfil

led

with

hel

ium

in a

man

ner

cons

iste

nt w

ith th

at d

escr

ibed

in S

tand

ard

Rev

iew

Pla

n fo

r Dry

Cas

k S

tora

ge S

yste

ms

(NU

RE

G-1

536)

(NR

C 1

997

[DIR

S 1

0190

3], S

ectio

n 8.

V.1

).

Yes

Y

es

Was

te F

orm

&TA

D C

anis

ter

04-0

1 Lo

adin

g of

Was

te F

orm

s To

min

imiz

e w

aste

form

dam

age,

was

te p

acka

ge a

nd T

AD

can

iste

r-loa

ding

act

iviti

es

shal

l be

perfo

rmed

and

mon

itore

d in

acc

orda

nce

with

indu

stry

sta

ndar

d pr

actic

es

incl

udin

g an

ope

rato

r and

an

inde

pend

ent c

heck

er. R

ecor

ds d

emon

stra

ting

com

plia

nce

shal

l be

mai

ntai

ned.

No

No

Was

te F

orm

&TA

D C

anis

ter

04-0

2 H

andl

ing

of B

are

SNF

Bare

SN

F sh

all b

e ha

ndle

d in

a s

tand

ard

indu

stry

fash

ion

to li

mit

dam

age

and

prev

ent

unzi

ppin

g of

fuel

rod

clad

ding

. N

o N

o

Was

te F

orm

&TA

D C

anis

ter

04-0

3 W

aste

For

m C

SN

F Fu

el

Rod

Max

imum

Bur

nup

Lim

it

The

CS

NF

fuel

rod

or a

ssem

bly

max

imum

bur

nup

shal

l be

less

than

80

GW

d/M

TU

(this

is b

ound

ed b

y th

e P

WR

bur

nup)

. N

o N

o

Was

te F

orm

&TA

D C

anis

ter

04-0

4 W

aste

For

m M

oist

ure

Rem

oval

& In

ertin

g Al

l TA

D c

anis

ters

sha

ll be

vac

uum

drie

d an

d ba

ckfil

led

with

hel

ium

in a

man

ner

cons

iste

nt w

ith th

at d

escr

ibed

in S

tand

ard

Rev

iew

Pla

n fo

r Dry

Cas

k S

tora

ge S

yste

ms

(NU

RE

G-1

536)

(NR

C 1

997

[DIR

S 1

0190

3], S

ectio

n 8.

V.1

). [N

ote:

Fo

r pos

tclo

sure

moi

stur

e re

mov

al p

urpo

ses,

NU

RE

G-1

567

(NR

C 2

007

[DIR

S 1

4975

6], S

ectio

n 9.

5.4.

1) is

equ

ival

ent t

o N

UR

EG-1

536

and

is th

eref

ore

acce

ptab

le.]2

Yes

Y

es

Was

te F

orm

&TA

D C

anis

ter

04-0

5 C

ladd

ing

Tem

pera

ture

Li

mit

The

max

imum

tem

pera

ture

of t

he C

SN

F cl

addi

ng u

pon

empl

acem

ent s

hall

not e

xcee

d35

0°C

(to

prev

ent d

amag

e fro

m c

reep

or h

ydrid

e re

orie

ntat

ion)

. N

o N

o

ANL-WIS-MD-000024 REV 01 ACN 01 7-35 March 2008

Postclosure Nuclear Safety Design Bases

179394 SNL 2007. Total System Performance Assessment Data Input Package for Requirements Analysis for TAD Canister and Related Waste Package Overpack Physical Attributes Basis for Performance Assessment. TDR-TDIP-ES-000006 REV 00. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20070918.0005.

184614 SNL 2007. UZ Flow Models and Submodels. MDL-NBS-HS-000006 REV 03 AD 01. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080108.0003; DOC.20080114.0001.

177423 SNL 2007. Waste Form and In-Drift Colloids-Associated Radionuclide Concentrations: Abstraction and Summary. MDL-EBS-PA-000004 REV 03. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20071018.0019.

183041 SNL 2008. Features, Events, and Processes for the Total System Performance Assessment: Analyses for the License Application: Analyses. ANL-WIS-MD-000027 REV 00. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080307.0003.

182145 SNL 2008. Simulation of Net Infiltration for Present-Day and Potential Future Climates. MDL-NBS-HS-000023 REV 01 AD 01. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080201.0002.

179476 SNL 2008. Features, Events, and Processes for the Total System Performance Assessment: Methods. ANL-WIS-MD-000026 REV 00. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080211.0010.

184748 SNL 2008. Particle Tracking Model and Abstraction of Transport Processes. MDL-NBS-HS-000020 REV 02 AD 02. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080129.0008.

184797 SNL 2008. Performance Confirmation Plan. TDR-PCS-SE-000001 REV 05 AD 01. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080227.0003.

183750 SNL 2008. Saturated Zone Flow and Transport Model Abstraction. MDL-NBS-HS-000021 REV 03 AD 02. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080107.0006.

173869 SNL 2008. Screening Analysis of Criticality Features, Events, and Processes for License Application. ANL-DS0-NU-000001 REV 00. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080208.0001.

ANL-WIS-MD-000024 REV 01 ACN 01 8-7 March 2008

Postclosure Nuclear Safety Design Bases

184806 SNL 2008. Site-Scale Saturated Zone Transport. MDL-NBS-HS-000010 REV 03 AD 01. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080121.0003.

183478 SNL 2008. Total System Performance Assessment Model /Analysis for the License Application. MDL-WIS-PA-000005 REV 00 AD 01. Las Vegas, Nevada: Sandia National Laboratories. ACC: DOC.20080312.0001.

161058 Wu, Y-S.; Zhang, W.; Pan, L.; Hinds, J.; and Bodvarsson, G.S. 2002. “Modeling Capillary Barriers in Unsaturated Fractured Rock.” Water Resources Research, 38, (11), 35-1 through 35-12. Washington, D.C.: American Geophysical Union. TIC: 253854.

154918 Wu, Y-S.; Zhang, W.; Pan, L.; Hinds, J.; and Bodvarsson, G.S. 2000. Capillary Barriers in Unsaturated Fractured Rocks of Yucca Mountain, Nevada. LBNL-46876. Berkeley, California: Lawrence Berkeley National Laboratory. TIC: 249912.

100520 YMP (Yucca Mountain Site Characterization Project) 1993. Evaluation of the Potentially Adverse Condition “Evidence of Extreme Erosion During the Quaternary Period” at Yucca Mountain, Nevada. Topical Report YMP/92-41-TPR. Las Vegas, Nevada: Yucca Mountain Site Characterization Office. ACC: NNA.19930316.0208.

154386 YMP 2001. Reclamation Implementation Plan. YMP/91-14, Rev. 2. Las Vegas, Nevada: Yucca Mountain Site Characterization Office. ACC: MOL.20010301.0238.

8.2 CODES, STANDARDS, REGULATIONS, AND PROCEDURES

180319 10 CFR 63. 2007. Energy: Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada. Internet Accessible.

177357 70 FR 49014. Public Health and Environmental Radiation Protection Standards for Yucca Mountain, NV. Internet Accessible.

178394 70 FR 53313. Implementation of a Dose Standard After 10,000 Years. Internet Accessible.

166013 ASME B46.1-2002. 2003. Surface Texture (Surface Roughness, Waviness and Lay). New York, New York: American Society of Mechanical Engineers. TIC: 257359.

ANL-WIS-MD-000024 REV 01 ACN 01 8-8 March 2008

Postclosure Nuclear Safety Design Bases

147465 ASTM B 575-99a. 1999. Standard Specification for Low-Carbon Nickel-Molybdenum-Chromium, Low-Carbon Nickel-Chromium-Molybdenum, Low-Carbon Nickel-Chromium-Molybdenum-Copper, Low-Carbon Nickel-Chromium-Molybdenum-Tantalum, and Low-Carbon Nickel-Chromium-Molybdenum-Tungsten Alloy Plate, Sheet, and Strip. West Conshohocken, Pennsylvania: American Society for Testing and Materials. TIC: 247534.

ANL-WIS-MD-000024 REV 01 ACN 01 8-8a March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-1.

ITB

C A

naly

sis

of U

pper

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Feat

ure

/ C

ompo

nent

FEP

Num

ber N

ame,

an

d Sc

reen

ing

Dec

isio

n D

iscu

ssio

n of

Effe

ct o

n B

arrie

r Cap

abili

ty

Rel

ates

to

ITB

C1

Cor

ePa

ram

eter

C

hara

cter

istic

2

Con

trol

Para

met

er

Cha

ract

eris

tic3

Topo

grap

hy a

nd

Sur

ficia

l Soi

ls

2.2.

03.0

2.0A

R

ock

Pro

perti

es o

f H

ost R

ock

and

othe

r U

nits

Incl

uded

The

hydr

olog

ic c

hara

cter

istic

s (e

.g.,

perm

eabi

lity,

por

osity

, cap

illar

ity,

stor

age

capa

city

) of t

he s

urfic

ial s

oils

and

sha

llow

bed

rock

abo

ve th

e re

posi

tory

are

sig

nific

ant i

n af

fect

ing

the

amou

nt o

f net

infil

tratio

n fo

llow

ing

a pr

ecip

itatio

n ev

ent.

The

cha

ract

eris

tics

of th

e su

rfici

al

soils

als

o af

fect

the

soil

rete

ntio

n an

d th

e tim

e in

filtra

ting

wat

er ta

kes

to p

ass

belo

w th

e ro

ot z

one

to b

ecom

e ne

t inf

iltra

tion

(i.e.

, whe

re it

is

not s

ubje

ct to

furth

er e

vapo

trans

pira

tion

proc

esse

s).

The

hydr

olog

ic

char

acte

ristic

s of

the

surfa

ce s

oils

and

sha

llow

bed

rock

at Y

ucca

M

ount

ain,

incl

udin

g as

soci

ated

unc

erta

inty

, mos

t not

ably

the

perm

eabi

lity,

are

incl

uded

in th

e as

sess

men

t of t

he n

et in

filtra

tion

and

dete

rmin

ed to

be

ITB

C.

FEP

Sour

ce:

SN

L 20

08 [D

IRS

183

041]

–- 2

.2.0

3.02

.0A

Yes

IT

BC

:In

filtra

tion

and

Seep

age

Sur

face

Soi

lP

rope

rties

(in

clud

ing

vege

tatio

n)

Non

e

Topo

grap

hy a

nd

Sur

ficia

l Soi

ls

2.2.

06.0

4.0A

E

ffect

s of

Subs

iden

ce

Excl

uded

THM

mod

elin

g sh

owed

that

sub

side

nce

dist

ance

s w

ould

be

indi

stin

guis

habl

e fro

m n

atur

al v

aria

tions

in th

e gr

ound

sur

face

, and

ar

e to

o sm

all t

o af

fect

run

off o

r inf

iltra

tion,

or t

o cr

eate

im

poun

dmen

ts.

In a

dditi

on, c

orro

bora

tive

min

ing

data

indi

cate

no

subs

iden

ce fo

r the

siz

e of

the

drift

ope

ning

rela

tive

to d

rift s

paci

ng.

St

ress

relie

ved

enha

ncem

ents

to fr

actu

re p

erm

eabi

lity

and

capi

llarit

ydu

e to

the

exca

vatio

n ha

ve b

een

incl

uded

in th

e un

certa

inty

of

perm

eabi

lity

and

capi

llarit

y us

ed in

the

seep

age

mod

els.

The

cha

nges

to

frac

ture

cha

ract

eris

tics

arou

nd e

mpl

acem

ent d

rifts

due

to s

tress

re

lief h

ave

been

foun

d to

be

too

smal

l to

caus

e ad

vers

e ef

fect

s on

se

epag

e. S

ubsi

denc

e in

duce

d st

ress

effe

cts

on U

Z flo

w a

rene

glig

ible

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.2

.06.

04.0

A

No

Non

-ITB

C:

Pro

perti

es o

f the

H

ost R

ock

Uni

tU

nsat

urat

edZo

ne P

rope

rties

Non

-ITB

C:

Empl

acem

ent

Drif

tC

onfig

urat

ion

Empl

acem

ent

Drif

t Spa

cing

R

epos

itory

Layo

ut

Rep

osito

ryEl

evat

ion

belo

wth

e S

urfa

ceR

epos

itory

Geo

grap

hic

and

Geo

logi

c Lo

catio

n To

pogr

aphy

and

S

urfic

ial S

oils

2.

2.07

.01.

0A

Loca

lly S

atur

ated

flo

w a

t Bed

rock

/ A

lluvi

um C

onta

ct

Excl

uded

The

poss

ibili

ty o

f loc

ally

sat

urat

ed fl

ow c

ondi

tions

at t

he b

edro

ck–

allu

vium

con

tact

has

bee

n ex

clud

ed in

the

asse

ssm

ent o

f net

in

filtra

tion

for t

wo

reas

ons.

Firs

t, m

ost o

f the

infil

tratio

n m

odel

dom

ain

is c

hara

cter

ized

by

rela

tivel

y lo

w s

lope

, whi

ch c

orre

spon

ds to

a s

mal

l la

tera

l hyd

raul

ic g

radi

ent.

Sec

ond,

bul

k be

droc

k sa

tura

ted

hydr

aulic

co

nduc

tivity

val

ues

are

gene

rally

hig

her t

han

the

satu

rate

d hy

drau

lic

cond

uctiv

ity v

alue

s in

the

over

lyin

g so

il an

d, th

eref

ore,

onc

e w

ater

re

ache

s th

e so

il–be

droc

k in

terfa

ce, i

t wou

ld te

nd to

ent

er b

edro

ck

inst

ead

of fl

owin

g la

tera

lly a

long

the

inte

rface

. FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.2

.07.

01.0

A

No

Non

-ITB

C:

Sur

face

Soi

lP

rope

rties

(in

clud

ing

vege

tatio

n)

Infil

tratio

n an

d Se

epag

e U

nsat

urat

edZo

ne P

rope

rties

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

ANL-WIS-MD-000024 REV 01 ACN 01 A-3 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-1.

ITB

C A

naly

sis

of U

pper

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Feat

ure

/ C

ompo

nent

FEP

Num

ber N

ame,

an

d Sc

reen

ing

Dec

isio

n D

iscu

ssio

n of

Effe

ct o

n B

arrie

r Cap

abili

ty

Rel

ates

to

ITB

C1

Cor

ePa

ram

eter

C

hara

cter

istic

2

Con

trol

Para

met

er

Cha

ract

eris

tic3

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry

1.2.

10.0

1.0A

H

ydro

logi

c R

espo

nse

to S

eism

ic

Act

ivity

Excl

uded

Sei

smic

act

ivity

may

alte

r the

rock

, fra

ctur

e, a

nd fa

ult c

hara

cter

istic

s,

whi

ch m

ay a

ffect

the

hydr

ogeo

logy

of t

he u

nsat

urat

ed z

one

in th

e vi

cini

ty o

f the

repo

sito

ry.

Inve

stig

atio

ns fo

cusi

ng o

n th

e po

tent

iom

etric

hy

drol

ogic

resp

onse

, giv

en c

hang

es in

rock

pro

perti

es a

djac

ent t

o a

faul

t, de

mon

stra

te th

at th

e ch

ange

s in

wat

er-ta

ble

elev

atio

n ar

e no

t ex

pect

ed to

exc

eed

50 m

and

are

tran

sien

t and

loca

l in

natu

re.

Bec

ause

the

empl

acem

ent d

rifts

are

loca

ted

at le

ast 1

20 m

abo

ve th

e cu

rrent

wat

er ta

ble,

suc

h tra

nsie

nt p

ertu

rbat

ions

will

not

hav

e an

y si

gnifi

cant

long

-term

effe

ct to

the

unsa

tura

ted

zone

flow

path

s or

ve

loci

ties

abov

e th

e re

posi

tory

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.2

.10.

01.0

A

No

Non

-ITB

C:

Infil

tratio

n an

d Se

epag

e P

rope

rties

P

rope

rties

of t

he

Hos

t Roc

k U

nit

Uns

atur

ated

Zone

Pro

perti

esC

hara

cter

izat

ion

of S

eism

icE

vent

s

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Rep

osito

ryEl

evat

ion

belo

wth

e S

urfa

ce

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry

1.2.

10.0

2.0A

H

ydro

logi

c R

espo

nse

to Ig

neou

s A

ctiv

ityEx

clud

ed

Igne

ous

intru

sion

s th

at m

ight

occ

ur in

the

time

fram

e of

10,

000

year

s af

ter c

losu

re w

ould

affe

ct a

rela

tivel

y sm

all v

olum

e of

the

host

rock

an

d ar

e ex

pect

ed to

be

orie

nted

sub

para

llel t

o ex

istin

g flo

w d

irect

ions

. C

onse

quen

tly, f

utur

e in

trusi

ons

wou

ld n

ot h

ave

a si

gnifi

cant

effe

ct o

n gr

ound

wat

er fl

ow p

atte

rns

or ra

tes

in th

e un

satu

rate

d zo

ne a

bove

re

posi

tory

. G

iven

the

limite

d ar

ea o

f any

ther

mal

or g

eoch

emic

al

alte

ratio

n, a

nd th

e co

nseq

uent

cha

nge

of ro

ck p

rope

rties

aro

und

an

intru

sion

, any

geo

chem

ical

effe

cts

wou

ld b

e m

inim

al.

The

pote

ntia

l de

velo

pmen

t of a

hyd

roth

erm

al s

yste

m fr

om ig

neou

s ac

tivity

is n

ot

expe

cted

bas

ed o

n an

alog

ue s

tudi

es a

nd w

ould

be

of lo

wco

nseq

uenc

e du

e to

its

limite

d si

ze re

lativ

e to

the

repo

sito

ry fo

otpr

int.

A

ny p

ossi

ble

chan

ges

to to

pogr

aphy

and

soi

ls fr

om e

xtru

sive

act

ivity

are

also

of l

ow c

onse

quen

ce.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.2.1

0.02

.0A

No

Non

-ITB

C:

Infil

tratio

n an

d Se

epag

e pr

oces

ses

Pro

perti

es o

f the

H

ost R

ock

Uni

tU

nsat

urat

edZo

ne P

rope

rties

Cha

ract

eriz

atio

nof

Igne

ous

Eve

nts

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

ANL-WIS-MD-000024 REV 01 ACN 01 A-9 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-1.

ITB

C A

naly

sis

of U

pper

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Feat

ure

/ C

ompo

nent

FEP

Num

ber N

ame,

an

d Sc

reen

ing

Dec

isio

n D

iscu

ssio

n of

Effe

ct o

n B

arrie

r Cap

abili

ty

Rel

ates

to

ITB

C1

Cor

ePa

ram

eter

C

hara

cter

istic

2

Con

trol

Para

met

er

Cha

ract

eris

tic3

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry

1.4.

06.0

1.0A

A

ltere

d S

oil o

r S

urfa

ce W

ater

C

hem

istry

Ex

clud

ed

Hum

an (e

.g.,

agric

ultu

ral o

r ind

ustri

al) a

ctiv

ities

may

affe

ct s

oil a

nd

surfa

ce w

ater

che

mis

try, w

hich

in tu

rn m

ay im

pact

the

chem

istry

of

infil

tratin

g w

ater

. C

urre

nt a

gric

ultu

ral a

nd in

dust

rial a

ctiv

ities

in th

e Y

ucca

Mou

ntai

n re

gion

are

alre

ady

incl

uded

in th

e ch

arac

teriz

atio

n of

th

e un

satu

rate

d zo

ne a

bove

the

repo

sito

ry.

Futu

re c

hang

es in

thes

e ac

tiviti

es a

re e

xclu

ded

base

d on

regu

lato

ry re

quire

men

ts (1

0 C

FR

63.3

05(b

) [D

IRS

178

394]

). Im

pact

s of

indu

stria

l act

iviti

es a

ssoc

iate

d w

ith th

e re

posi

tory

itse

lf on

soi

l and

wat

er c

hem

istry

will

be

min

or, a

nd

will

hav

e no

sig

nific

ant a

dver

se im

pact

s on

long

-term

repo

sito

rype

rform

ance

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.4

.06.

01.0

A

No

Non

-ITB

C:

Seep

age

Wat

er

Che

mis

try

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Rec

lam

atio

n of

La

nds

Dis

turb

edby

Rep

osito

ry

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry

2.1.

08.0

1.0A

W

ater

Influ

x at

the

Rep

osito

ryIn

clud

ed

Influ

x of

liqu

id w

ater

is th

e sa

me

as s

eepa

ge in

to th

e em

plac

emen

t dr

ifts.

See

page

occ

urs

whe

n th

e do

wnw

ard

perc

olat

ion

flux

in th

e ho

st ro

ck is

not

com

plet

ely

dive

rted

arou

nd u

nder

grou

nd o

peni

ngs

byca

pilla

ry fl

ow p

roce

sses

. Th

e pr

inci

pal f

acto

rs th

at d

eter

min

e th

e oc

curre

nce

and

mag

nitu

de o

f se

epag

e, in

add

ition

to th

e pe

rcol

atio

n flu

x, a

re th

e bu

lk p

erm

eabi

lity

and

the

capi

llary

stre

ngth

of t

he fr

actu

red

host

rock

. U

ncer

tain

ty in

thes

e pa

ram

eter

s, b

ased

on

obse

rvat

ions

from

in s

itu te

stin

g, is

in

clud

ed in

the

perfo

rman

ce a

sses

smen

t.

Rep

rese

ntat

iven

ess

of th

e se

epag

e pa

ram

eter

dis

tribu

tions

use

d in

th

e pe

rform

ance

ass

essm

ent (

SN

L 20

07 [D

IRS

181

244]

, Sec

tion

6.6)

w

ithin

the

repo

sito

ry h

ost r

ock

is c

onsi

dere

d im

porta

nt to

cap

abilit

y of

th

e up

per n

atur

al b

arrie

r. N

ote

that

effe

cts

from

rock

exc

avat

ion

and

com

mitt

ed m

ater

ials

are

ad

dres

sed

for o

ther

FE

Ps

(1.1

.01.

01.0

B, 2

.1.0

6.04

.0A,

2.1

.08.

02.0

A).

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

8.01

.0A

Yes

IT

BC

:U

nsat

urat

edZo

ne P

rope

rties

Infil

tratio

n an

d Se

epag

e P

rope

rties

of t

he

Hos

t Roc

k U

nit

Non

-ITB

C:

Empl

acem

ent

Drif

tC

onfig

urat

ion

No

Bac

kfill

in

Empl

acem

ent

Drif

tsR

epos

itory

Elev

atio

n be

low

the

Sur

face

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Rep

osito

ryLa

yout

R

epos

itory

Sta

ndof

f fro

mQ

uate

rnar

y Fa

ult

Rep

osito

ryS

tand

off f

rom

Pai

ntbr

ush

Non

wel

ded

ANL-WIS-MD-000024 REV 01 ACN 01 A-11 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-1.

ITB

C A

naly

sis

of U

pper

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Feat

ure

/ C

ompo

nent

FEP

Num

ber N

ame,

an

d Sc

reen

ing

Dec

isio

n D

iscu

ssio

n of

Effe

ct o

n B

arrie

r Cap

abili

ty

Rel

ates

to

ITB

C1

Cor

ePa

ram

eter

C

hara

cter

istic

2

Con

trol

Para

met

er

Cha

ract

eris

tic3

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry(C

ontin

ued)

2.1.

08.0

1.0A

W

ater

Influ

x at

the

Rep

osito

ryIn

clud

ed(C

ontin

ued)

Hyd

roge

olog

ic

Uni

tV

erifi

catio

n of

D

esig

n R

ock

Pro

perti

es

Min

imum

Thic

knes

s of

P

Tn U

nit A

bove

th

e R

epos

itory

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry

2.1.

08.0

1.0B

E

ffect

s of

Rap

idIn

flux

into

the

Rep

osito

ryEx

clud

ed

This

FE

P p

erta

ins

to th

e po

tent

ial q

uenc

hing

effe

ct fr

om ra

pid

wat

er

influ

x du

ring

the

ther

mal

per

iod.

Tra

nsie

nt p

ulse

s of

wat

er in

the

unsa

tura

ted

zone

at t

he re

posi

tory

hor

izon

, whe

ther

cau

sed

byep

isod

ic in

filtra

tion

even

ts o

r tra

nsie

nt e

ffect

s as

soci

ated

with

clim

ate

chan

ge, a

re n

ot e

xpec

ted

to s

igni

fican

tly re

duce

drif

t wal

l tem

pera

ture

un

less

sub

ject

to s

trong

epi

sodi

c in

filtra

tion

or fo

cuse

d flo

w.

Sen

sitiv

ity a

naly

ses

of th

e S

ite-S

cale

UZ

Flow

Mod

el s

how

that

the

PTn

uni

t dam

pens

and

hom

ogen

izes

epi

sodi

c in

filtra

tion

puls

es,

resu

lting

in a

ste

ady

flow

con

ditio

n be

low

. In

add

ition

, drif

t see

page

st

udie

s al

so in

dica

te th

at s

atur

atio

n bu

ildup

aro

und

the

boili

ng z

one

is

insi

gnifi

cant

, and

pen

etra

tion

of e

piso

dic

and

pref

eren

tial f

low

sor

igin

atin

g fro

m th

e co

nden

satio

n zo

ne a

bove

drif

ts is

not

exp

ecte

d du

ring

the

ther

mal

per

iod.

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.08.

01.0

B

No

Non

-ITB

C:

Uns

atur

ated

Zone

Pro

perti

esIn

filtra

tion

and

Seep

age

Non

-ITB

C:

Floo

d P

rote

ctio

nR

epos

itory

Elev

atio

n be

low

the

Sur

face

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Rep

osito

ryS

tand

off f

rom

Pai

ntbr

ush

Non

wel

ded

Hyd

roge

olog

ic

Uni

tM

inim

umTh

ickn

ess

of

PTn

Uni

t abo

ve

the

Rep

osito

ryR

epos

itory

Sta

ndof

f fro

mQ

uate

rnar

y Fa

ults

ANL-WIS-MD-000024 REV 01 ACN 01 A-12 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-1.

ITB

C A

naly

sis

of U

pper

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Feat

ure

/ C

ompo

nent

FEP

Num

ber N

ame,

an

d Sc

reen

ing

Dec

isio

n D

iscu

ssio

n of

Effe

ct o

n B

arrie

r Cap

abili

ty

Rel

ates

to

ITB

C1

Cor

ePa

ram

eter

C

hara

cter

istic

2

Con

trol

Para

met

er

Cha

ract

eris

tic3

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry

2.2.

06.0

3.0A

S

eism

ic A

ctiv

ityA

lters

Per

ched

Wat

er Z

ones

Ex

clud

ed

Perc

hed

wat

er h

as o

nly

been

foun

d at

Yuc

ca M

ount

ain

near

the

TSw

-CH

n in

terfa

ce.

In p

artic

ular

, the

pre

senc

e of

per

ched

wat

er

appe

ars

to b

e co

rrela

ted

with

the

pres

ence

of z

eolit

ical

ly a

ltere

d m

iner

als

with

in th

e C

alic

o H

ills

nonw

elde

d (C

Hn)

. Th

e fa

ct th

at th

e pe

rche

d w

ater

occ

urre

nce

is s

trong

ly c

orre

late

d w

ith th

e ze

oliti

c lit

holo

gy in

dica

tes

that

the

effe

cts

of s

eism

ic a

nd te

cton

ic p

roce

sses

do

not

pla

y a

sign

ifica

nt ro

le in

the

form

atio

n an

d pe

rsis

tenc

e of

pe

rche

d w

ater

. 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

the

repo

sito

ry, a

nd a

re n

ot e

xpec

ted

even

unde

r fut

ure

clim

ate

chan

ges

(SN

L 20

07 [D

IRS

184

614]

, Sec

tions

6.

2.2.

2 an

d 7.

7.4.

2.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.2.0

6.03

.0A

No

Non

-ITB

C:

Pro

perti

es o

f the

H

ost R

ock

Uni

tIn

filtra

tion

and

Seep

age

Uns

atur

ated

Zone

Pro

perti

esC

hara

cter

izat

ion

of S

eism

icE

vent

s

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Uns

atur

ated

Zon

e ab

ove

the

Rep

osito

ry

2.2.

06.0

4.0A

E

ffect

s of

Subs

iden

ce

Excl

uded

THM

mod

elin

g sh

owed

that

sub

side

nce

dist

ance

s w

ould

be

indi

stin

guis

habl

e fro

m n

atur

al v

aria

tions

in th

e gr

ound

sur

face

, and

ar

e to

o sm

all t

o af

fect

run

off o

r inf

iltra

tion,

or t

o cr

eate

im

poun

dmen

ts.

In a

dditi

on, c

orro

bora

tive

min

ing

data

indi

cate

no

subs

iden

ce fo

r the

siz

e of

the

drift

ope

ning

rela

tive

to d

rift s

paci

ng.

St

ress

relie

ved

enha

ncem

ents

to fr

actu

re p

erm

eabi

lity

and

capi

llarit

ydu

e to

the

exca

vatio

n ha

ve b

een

incl

uded

in th

e un

certa

inty

of

perm

eabi

lity

and

capi

llarit

y us

ed in

the

seep

age

mod

els.

The

cha

nges

to

frac

ture

cha

ract

eris

tics

arou

nd e

mpl

acem

ent d

rifts

due

to s

tress

re

lief h

ave

been

foun

d to

be

too

smal

l to

caus

e ad

vers

e ef

fect

s on

se

epag

e. S

ubsi

denc

e in

duce

d st

ress

effe

cts

on U

Z flo

w a

rene

glig

ible

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.2

.06.

04.0

A

No

Non

-ITB

C:

Pro

perti

es o

f the

H

ost R

ock

Uni

tU

nsat

urat

edZo

ne P

rope

rties

Non

-ITB

C:

Empl

acem

ent

Drif

tC

onfig

urat

ion

Empl

acem

ent

Drif

t Spa

cing

R

epos

itory

Layo

ut

Rep

osito

ryEl

evat

ion

belo

wth

e S

urfa

ceR

epos

itory

Geo

grap

hic

and

Geo

logi

c Lo

catio

n U

nsat

urat

ed Z

one

abov

e th

e R

epos

itory

2.2.

07.0

1.0A

Lo

cally

Sat

urat

ed

Flow

at B

edro

ck/

Allu

vium

Con

tact

Ex

clud

ed

The

poss

ibili

ty o

f loc

ally

sat

urat

ed fl

ow c

ondi

tions

at t

he b

edro

ck–

allu

vium

con

tact

has

bee

n ex

clud

ed in

the

asse

ssm

ent o

f net

in

filtra

tion

for t

wo

reas

ons.

Firs

t, m

ost o

f the

infil

tratio

n m

odel

dom

ain

is c

hara

cter

ized

by

rela

tivel

y lo

w s

lope

, whi

ch c

orre

spon

ds to

a s

mal

l la

tera

l hyd

raul

ic g

radi

ent.

Sec

ond,

bul

k be

droc

k sa

tura

ted

hydr

aulic

co

nduc

tivity

val

ues

are

gene

rally

hig

her t

han

the

satu

rate

d hy

drau

lic

cond

uctiv

ity v

alue

s in

the

over

lyin

g so

il an

d, th

eref

ore,

onc

e w

ater

re

ache

s th

e so

il–be

droc

k in

terfa

ce, i

t wou

ld te

nd to

ent

er b

edro

ck

inst

ead

of fl

owin

g la

tera

lly a

long

the

inte

rface

. FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.2

.07.

01.0

A

No

Non

-ITB

C:

Sur

face

Soi

lP

rope

rties

(in

clud

ing

vege

tatio

n)

Infil

tratio

n an

d Se

epag

e U

nsat

urat

edZo

ne P

rope

rties

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

ANL-WIS-MD-000024 REV 01 ACN 01 A-19 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t 1.

1.01

.01.

0A

Ope

n S

iteIn

vest

igat

ion

Bor

ehol

esEx

clud

ed

Site

inve

stig

atio

n bo

reho

les

that

hav

e be

en le

ft op

en,

degr

aded

, im

prop

erly

sea

led,

or r

eope

ned,

cou

ld

mod

ify fl

ow a

nd tr

ansp

ort p

rope

rties

and

pro

duce

en

hanc

ed p

athw

ays

betw

een

the

surfa

ce a

nd th

e re

posi

tory

.Th

is fe

atur

e is

exc

lude

d on

the

basi

s th

at: 1

) exi

stin

g bo

reho

les

from

site

cha

ract

eriz

atio

n ar

e kn

own,

2)

futu

re d

rillin

g w

ill be

con

trolle

d, 3

) the

regu

lato

ryre

quire

men

ts fo

r bor

ehol

e se

alin

g pr

ior t

o re

posi

tory

cl

osur

e w

ill be

met

, and

4) a

dmin

istra

tive

cont

rols

for

repo

sito

ry c

onst

ruct

ion

and

oper

atio

ns w

ill be

deve

lope

d to

ens

ure

thes

e ou

tcom

es. A

ccor

ding

ly,

thes

e fe

atur

es a

re c

onsi

dere

d no

t to

be im

porta

nt to

ba

rrier

cap

abili

ty.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.1.0

1.01

.0A

No

Non

-ITB

C:

Clo

sure

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Non

-ITB

C:

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Clo

sure

of B

oreh

oles

Empl

acem

ent

Drif

t 1.

1.02

.00.

0A

Che

mic

al E

ffect

s of

Ex

cava

tion

and

Con

stru

ctio

n in

EB

SEx

clud

ed

Adm

inis

trativ

e co

ntro

ls fo

r rep

osito

ry c

onst

ruct

ion

and

oper

atio

ns w

ill b

e de

velo

ped

to a

ssur

e th

at

empl

acem

ent d

rifts

are

dev

elop

ed in

acc

orda

nce

with

the

repo

sito

ry d

esig

n.

Mat

eria

ls u

sed

durin

g dr

ift e

xcav

atio

n an

d de

velo

pmen

t will

be c

ontro

lled

to p

recl

ude

any

pote

ntia

l del

eter

ious

effe

cts

on e

ngin

eere

d ba

rrier

s.

Whi

le e

xclu

ded

from

furth

er c

onsi

dera

tion

in th

e po

stcl

osur

e an

alyz

ed b

asis

, thi

s ex

clus

ion

is b

ased

on

con

trols

bei

ng in

pla

ce.

The

plac

emen

t of a

rbitr

ary

mat

eria

ls in

the

drift

cou

ld n

egat

ivel

y im

pact

bar

rier

capa

bilit

y; h

owev

er, i

t is

unlik

ely

that

thes

e im

pact

s w

ould

sub

stan

tially

effe

ct th

e re

leas

e or

tran

spor

t of

radi

onuc

lides

sin

ce d

evia

tion

from

thes

e co

ntro

ls a

re

man

aged

thro

ugh

the

Cor

rect

ive

Act

ion

Pro

gram

, w

hich

may

requ

ire p

ostc

losu

re im

pact

eva

luat

ion.

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.1

.02.

00.0

A

No

Non

-ITB

C:

In-D

rift C

hem

ical

Env

ironm

ent

Non

-ITB

C:

Exc

avat

ion

Met

hods

E

BS

Drip

Shi

eld

Em

plac

emen

t Drif

t Inv

ert

Mat

eria

ls In

tera

ctio

nsC

omm

itted

Mat

eria

ls

ANL-WIS-MD-000024 REV 01 ACN 01 A-29 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t 1.

2.03

.02.

0A

Sei

smic

Gro

und

Mot

ion

Dam

ages

EB

S C

ompo

nent

sIn

clud

ed

Vibr

ator

y gr

ound

mot

ion

has

the

pote

ntia

l to

caus

e se

ism

ical

ly-in

duce

d ro

ckfa

ll th

at c

hang

es th

e cr

oss-

sect

iona

l sha

pe a

nd v

olum

e of

the

empl

acem

ent d

rifts

(B

SC

200

4 [D

IRS

166

107]

, Sec

tions

6.3

.1.2

and

6.

4.2.

2) a

nd c

hang

es th

e co

nfig

urat

ion

of th

e E

BS

co

mpo

nent

s w

ithin

the

empl

acem

ent d

rifts

(SN

L 20

07

[DIR

S 1

7682

8], S

ectio

ns 6

.1.2

and

6.1

.3).

A c

hang

e in

the

cros

s se

ctio

n of

the

empl

acem

ent d

rifts

can

al

ter t

he s

eepa

ge in

to th

e dr

ifts,

and

the

pres

ence

of

rock

fall

abou

t the

drip

shi

eld

can

alte

r the

mec

hani

cal

resp

onse

and

tem

pera

ture

tim

e hi

stor

y of

the

EB

S

com

pone

nts.

The

resp

onse

of t

he e

mpl

acem

ent d

rift

conf

igur

atio

n an

d pr

oces

ses

to v

ibra

tory

gro

und

mot

ion

is im

porta

nt to

bar

rier c

apab

ility

(ITB

C).

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.2.0

3.02

.0A

Yes

IT

BC

:P

rope

rties

of t

he

Hos

t Roc

k U

nit

Cha

ract

eriz

atio

n of

S

eism

ic E

vent

sN

on-IT

BC

:P

alle

t Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nW

aste

Form

/Pac

kage

In

tern

als

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Cha

ract

eriz

atio

n of

S

eism

ic E

vent

s

ITB

C:

Rep

osito

ry E

leva

tion

-O

verb

urde

n Th

ickn

ess

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

As-

Em

plac

ed W

aste

P

acka

ge-D

rip S

hiel

dC

onfig

urat

ion

Drip

Shi

eld

Sei

smic

P

erfo

rman

ce

Sei

smic

Des

ign

of W

aste

P

acka

geE

BS

Mat

eria

l Int

erac

tions

- C

oppe

r D

rip S

hiel

d M

ater

ials

and

Th

ickn

esse

s N

on-IT

BC

:E

mpl

acem

ent P

alle

t Fa

bric

atio

n an

d C

orro

sion

Al

low

ance

E

mpl

acem

ent D

rift I

nver

t C

onfig

urat

ion

E

mpl

acem

ent D

rift I

nver

t Fu

nctio

n In

vert

Mat

eria

lsV

erifi

catio

n of

Des

ign

Roc

kP

rope

rties

ANL-WIS-MD-000024 REV 01 ACN 01 A-34 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t 2.

1.04

.05.

0A

Ther

mal

-Mec

hani

cal

Pro

perti

es a

nd

Evo

lutio

n of

Bac

kfill

Excl

uded

The

phys

ical

pro

perti

es o

f the

bac

kfill

may

affe

ct

grou

ndw

ater

flow

, was

te p

acka

ge a

nd d

rip s

hiel

ddu

rabi

lity,

and

radi

onuc

lide

trans

port

in th

e w

aste

di

spos

al re

gion

. P

rope

rties

of t

he b

ackf

ill m

ay

chan

ge th

roug

h tim

e, d

ue to

pro

cess

es s

uch

as s

ilica

cem

enta

tion,

ther

mal

effe

cts,

and

phy

sica

lco

mpa

ctio

n. S

ince

bac

kfill

is n

ot to

be

plac

ed in

the

drift

this

pro

cess

is n

ot re

leva

nt a

nd d

oes

not

cont

ribut

e to

bar

rier c

apab

ility.

D

evia

tion

from

des

ign

coul

d ne

gativ

ely

impa

ct b

arrie

r ca

pabi

lity.

Dev

iatio

n fro

m d

esig

n is

man

aged

thro

ugh

the

Cor

rect

ive

Act

ion

Pro

gram

, whi

ch re

quire

s po

stcl

osur

e im

pact

eva

luat

ion.

FEP

Sour

ce:

SN

L 20

08 [D

IRS

183

041]

– 2

.1.0

4.05

.0A

No

Non

e N

on-IT

BC

:N

o B

ackf

ill in

Em

plac

emen

t D

rifts

Empl

acem

ent

Drif

t 2.

1.05

.02.

0A

Rad

ionu

clid

e tra

nspo

rt th

roug

h se

als

Excl

uded

Gro

undw

ater

flow

thro

ugh

seal

s in

the

acce

ss ra

mps

, ve

ntila

tion

shaf

ts, a

nd e

xplo

rato

ry b

oreh

oles

cou

ld

affe

ct lo

ng-te

rm p

erfo

rman

ce o

f the

dis

posa

l sys

tem

. S

ealin

g co

ncep

ts h

ave

been

iden

tifie

d fo

r the

Lic

ense

A

pplic

atio

n, b

ut th

e de

sign

s of

thes

e se

als

have

not

be

en d

eter

min

ed.

The

desi

gns

will

be

supp

orte

d by

eval

uatio

ns o

f per

form

ance

, and

the

appl

icat

ion

of

cons

truct

ion

and

oper

atio

nal m

anag

emen

t and

ad

min

istra

tive

cont

rols

to e

nsur

e co

rrect

im

plem

enta

tion.

The

des

ign

addr

esse

s se

als

as

clos

ure

of th

e sh

afts

and

ram

ps s

hall

incl

ude

back

fillin

g fo

r the

ent

ire d

epth

of t

he o

peni

ng.

Site

inve

stig

atio

n bo

reho

les

with

in o

r nea

r the

foot

prin

t of

the

repo

sito

ry b

lock

will

be

back

fille

d w

ith m

ater

ial

com

patib

le w

ith th

e ho

st ro

ck a

nd p

lugg

ed.

Thes

e de

sign

feat

ures

are

inte

nded

to m

eet t

he in

trusi

on

scen

ario

s, a

nd a

re n

ot p

erfo

rman

ce re

late

d.A

ccor

ding

ly, t

hese

feat

ures

are

con

side

red

not t

o be

im

porta

nt to

bar

rier c

apab

ility

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.05.

02.0

A

No

Non

-ITB

C:

Clo

sure

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Non

-ITB

C:

Rep

osito

ry E

leva

tion

-O

verb

urde

n Th

ickn

ess

Rep

osito

ry L

ayou

t

ANL-WIS-MD-000024 REV 01 ACN 01 A-42 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t 2.

1.06

.01.

0A

Che

mic

al E

ffect

s of

R

ock

Rei

nfor

cem

ent

and

Cem

entit

ious

M

ater

ials

in E

BS

Ex

clud

ed

The

effe

cts

of s

eepa

ge w

ater

inte

ract

ing

with

rock

re

info

rcem

ent a

nd c

emen

titio

us m

ater

ials

use

d in

re

posi

tory

con

stru

ctio

n an

d op

erat

ion,

hav

e be

en

eval

uate

d an

d de

term

ined

to b

e in

sign

ifica

nt w

ith

resp

ect t

o po

stcl

osur

e pe

rform

ance

. In

add

ition

, to

prev

ent o

r lim

it po

tent

ially

del

eter

ious

effe

cts

from

ro

ck re

info

rcem

ent a

nd c

emen

titio

us m

ater

ials

, co

nstru

ctio

n an

d op

erat

iona

l man

agem

ent a

nd

adm

inis

trativ

e co

ntro

ls w

ill be

dev

elop

ed a

nd

impl

emen

ted

(SN

L 20

07 [D

IRS

177

412]

, Sec

tion

6.8)

. Th

eref

ore,

thes

e ef

fect

s ar

e co

nsid

ered

not

to b

e im

porta

nt to

bar

rier c

apab

ility

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.06.

01.0

A

No

Non

-ITB

C:

In-D

rift C

hem

ical

Env

ironm

ent

Clo

sure

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Non

-ITB

C:

Com

mitt

ed M

ater

ials

E

xcav

atio

n M

etho

ds

Des

ign

of G

roun

d S

uppo

rt S

yste

m

Clo

sure

of S

hafts

and

Ram

psC

losu

re o

f Bor

ehol

es

EB

S D

rip S

hiel

d /

Em

plac

emen

t Drif

t Inv

ert

Mat

eria

ls In

tera

ctio

ns

Empl

acem

ent

Drif

t 2.

1.06

.02.

0A

Mec

hani

cal E

ffect

sof

Roc

kR

einf

orce

men

t M

ater

ials

in E

BS

Ex

clud

ed

No

post

clos

ure

barri

er c

apab

ility

is a

ttrib

uted

to th

e ro

ck re

info

rcem

ent m

ater

ials

use

d in

the

EB

S.

Pos

tclo

sure

mod

els

and

anal

yses

neg

lect

the

pote

ntia

l ben

efic

ial e

ffect

s fro

m ro

ck re

info

rcem

ent o

n th

e ro

ck m

ass

resp

onse

to th

erm

o-m

echa

nica

l and

se

ism

ic s

tress

es.

Ther

efor

e, th

ese

effe

cts

are

cons

ider

ed n

ot to

be

impo

rtant

to b

arrie

r cap

abili

ty.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

6.02

.0A

No

Non

-ITB

C:

Clo

sure

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Hos

t Roc

k P

rope

rties

Non

-ITB

C:

Com

mitt

ed M

ater

ials

E

xcav

atio

n M

etho

ds

Em

plac

emen

t Drif

t Gro

und

Sup

port

Des

ign

of G

roun

d S

uppo

rt S

yste

m

ANL-WIS-MD-000024 REV 01 ACN 01 A-43 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t 2.

1.08

.07.

0A

Uns

atur

ated

Flo

w in

th

e E

BS

Incl

uded

Uns

atur

ated

flow

occ

urs

thro

ugh

the

feat

ures

of t

he

EB

S d

ue to

see

page

or c

onde

nsat

ion

proc

esse

s.

The

natu

re o

f thi

s flo

w h

as b

een

incl

uded

in th

e ab

stra

ctio

ns fo

r flo

w a

nd tr

ansp

ort t

hrou

gh th

e E

BS

fe

atur

es (S

NL

2007

[DIR

S 1

7740

7], S

ectio

ns 5

and

6)

. U

nsat

urat

ed fl

ow is

impo

rtant

to b

arrie

r cap

abili

ty,

beca

use

it is

driv

en b

y th

e do

wnw

ard

grav

itatio

nal

pote

ntia

l, an

d m

akes

pos

sibl

e ce

rtain

key

func

tions

of

the

UN

B a

nd E

BS

. Acc

ordi

ngly

, the

par

amet

ers

that

de

scrib

e an

d co

ntro

l uns

atur

ated

flow

con

ditio

ns a

re

cons

ider

ed to

be

impo

rtant

to b

arrie

r cap

abili

ty.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

8.07

.0A

Yes

IT

BC

:In

filtra

tion

and

Seep

age

Prop

ertie

sN

on-IT

BC

:U

nsat

urat

ed Z

one

Pro

perti

es

Pro

perti

es o

f the

H

ost R

ock

Uni

t

ITB

C:

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Rep

osito

ry E

leva

tion

-O

verb

urde

n Th

ickn

ess

Non

-ITB

C:

Ver

ifica

tion

of D

esig

n R

ock

Pro

perti

es

Empl

acem

ent

Drif

t 2.

1.08

.09.

0A

Sat

urat

ed F

low

in

the

EB

SEx

clud

ed

The

flow

regi

me

in th

e E

BS

doe

s no

t res

ult i

n a

sign

ifica

nt d

evel

opm

ent o

f sat

urat

ed fl

ow c

ondi

tions

(i.

e., t

he E

BS

rem

ains

free

dra

inin

g fo

r all

expe

cted

hy

drol

ogic

con

ditio

ns).

The

flow

pat

hs c

onsi

dere

d in

th

e E

BS

tran

spor

t abs

tract

ion

are

appl

icab

le to

all

poss

ible

flow

con

ditio

ns.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

8.09

.0A

No

Non

-ITB

C:

Pro

perti

es o

f U

nsat

urat

ed Z

one

Non

-ITB

C:

Rep

osito

ry E

leva

tion–

Sta

ndof

f fro

m W

ater

Tab

le

ANL-WIS-MD-000024 REV 01 ACN 01 A-50 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t (C

ontin

ued)

2.

1.09

.01.

0A

Che

mic

al

Cha

ract

eris

tics

of

Wat

er in

Drif

tsIn

clud

ed(C

ontin

ued)

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

9.01

.0A

Non

-ITB

C:

Was

te F

orm

Deg

rada

tion

Cor

rosi

on P

rodu

cts

Pro

perti

es

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n Em

plac

emen

t D

rift

2.1.

09.0

2.0A

C

hem

ical

Inte

ract

ion

with

Cor

rosi

on

Pro

duct

sIn

clud

ed

Just

as

the

chem

ical

cha

ract

eris

tics

of w

ater

in th

e dr

ift a

re a

ffect

ed b

y th

e in

com

ing

wat

er c

hem

istry

,th

ey a

re a

lso

sign

ifica

ntly

affe

cted

by

the

wat

er’s

in

tera

ctio

n w

ith th

e co

rrosi

on p

rodu

cts

in th

e dr

ift

(e.g

., w

aste

form

, met

allic

por

tions

of t

he w

aste

pa

ckag

e, ro

ck b

olts

, ste

el in

the

inve

rt, g

antry

rails

).

Thes

e ch

emic

al c

hara

cter

istic

s af

fect

the

likel

ihoo

d of

po

tent

ial d

egra

datio

n, d

eter

iora

tion,

and

alte

ratio

n of

th

e ot

her E

BS

com

pone

nts

as w

ell a

s af

fect

ing

the

trans

port

char

acte

ristic

s of

any

radi

onuc

lides

rele

ased

fro

m th

e w

aste

pac

kage

to th

e in

vert

(SN

L 20

07

[DIR

S 1

7741

2], S

ectio

n 6.

8).

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.09.

02.0

A

No

Non

-ITB

C:

In-D

rift C

hem

ical

Env

ironm

ent

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n W

aste

Form

/Pac

kage

In

tern

als

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Pal

let M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nIn

vert

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Cor

rosi

on P

rodu

cts

Pro

perti

es

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nP

alle

t Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

Non

-ITB

C:

Inve

rt M

ater

ials

Com

mitt

ed M

ater

ials

ANL-WIS-MD-000024 REV 01 ACN 01 A-52 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t 2.

1.11

.01.

0A

Hea

t Gen

erat

ion

in

EB

SIn

clud

ed

The

heat

gen

erat

ed b

y ra

dioa

ctiv

e de

cay

has

mul

tiple

effe

cts

on re

posi

tory

-rel

evan

t pro

cess

es, i

nclu

ding

de

grad

atio

n, d

eter

iora

tion,

and

alte

ratio

n of

the

EB

S.

The

heat

gen

erat

ion

in th

e em

plac

emen

t drif

ts a

ffect

s th

e tim

ing

of th

e on

set o

f see

page

pro

cess

es a

nd th

e di

strib

utio

n of

in-d

rift.

Con

vect

ion

and

cond

ensa

tion.

Th

e he

at g

ener

atio

n an

d re

sulta

nt te

mpe

ratu

re a

lso

affe

ct th

e w

ater

che

mis

try in

the

rock

and

em

plac

emen

t drif

ts.

The

tem

pera

ture

resu

lting

from

he

at g

ener

atio

n, a

s w

ell a

s se

epag

e an

d co

nden

satio

n pr

oces

ses,

affe

cts

the

corro

sion

of t

he

was

te p

acka

ges

and

drip

shi

elds

. Th

e te

mpe

ratu

re

resu

lting

from

hea

t gen

erat

ion

also

affe

cts

the

initi

atio

n of

was

te 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

(SN

L 20

07 [D

IRS

184

433]

, Sec

tion

6.2.

1[a]

), S

NL

2007

[DIR

S 1

8164

8], E

xecu

tive

Sum

mar

y).

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.1

1.01

.0A

Yes

IT

BC

:In

-Drif

t The

rmal

E

nviro

nmen

t C

onve

ctio

n,

Con

dens

atio

n, a

nd

Evap

orat

ion

Drip

Shi

eld

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n Se

epag

e W

ater

P

rope

rties

W

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Non

-ITB

C:

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nW

aste

For

mD

egra

datio

n P

rope

rties

of t

he

Hos

t Roc

k U

nit

ITB

C:

Drip

Shi

eld

Mat

eria

ls a

nd

Thic

knes

ses

Was

te P

acka

ge C

orro

sion

Allo

wan

ce

Was

te P

acka

ge T

herm

al

Lim

itsW

aste

Pac

kage

Dec

ay H

eat

Was

te P

acka

ge S

paci

ng

Was

te P

acka

ge T

herm

al

Lim

itsN

on-IT

BC

:W

aste

Pac

kage

Tem

pera

ture

Lim

itD

rift W

all T

empe

ratu

re

As-

empl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

nW

aste

Pac

kage

Han

dlin

gan

d Em

plac

emen

t V

erifi

catio

n of

Des

ign

Roc

kpr

oper

ties

ANL-WIS-MD-000024 REV 01 ACN 01 A-55 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Empl

acem

ent

Drif

t 2.

2.08

.04.

0A

Re-

Dis

solu

tion

of

Pre

cipi

tate

s D

irect

s m

ore

Cor

rosi

veFl

uids

to W

aste

P

acka

ges

Excl

uded

Re-

diss

olut

ion

of p

reci

pita

tes

in th

e ho

st ro

ck, a

nd

trans

port

of a

ffect

ed w

ater

s to

the

in-d

rift

envi

ronm

ent,

is e

xclu

ded

beca

use

this

set

of

proc

esse

s is

a tr

ansi

ent r

espo

nse

that

occ

urs

only

at

the

end

of th

e bo

iling

per

iod.

See

page

of a

ffect

ed

wat

ers

into

the

drift

s w

ill b

e m

itiga

ted

by th

e dr

ip

shie

lds,

whi

ch p

rote

ct th

e w

aste

pac

kage

s fro

m

corro

sive

wat

ers,

and

are

mad

e fro

m ti

tani

um w

hich

ex

hibi

ts n

o si

gnifi

cant

dep

ende

nce

of c

orro

sion

rate

s on

wat

er c

ompo

sitio

n. T

herm

al-h

ydro

logi

c-ch

emic

al

and

near

-fiel

d ch

emis

try m

odel

s sh

ow th

at a

fter t

he

ther

mal

per

iod,

the

com

posi

tion

of s

eepa

ge w

ill cl

osel

y re

sem

ble

that

of f

ar-fi

eld

and

pre-

heat

ing

form

atio

n w

ater

s.

Acc

ordi

ngly

, thi

s tra

nsie

nt re

spon

se w

ill h

ave

no

sign

ifica

nt im

pact

on

degr

adat

ion

of th

e en

gine

ered

ba

rrier

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.2

.08.

04.0

A

No

Non

-ITB

C:

Pro

perti

es o

f the

H

ost R

ock

Uni

t U

nsat

urat

ed Z

one

Pro

perti

es

In-D

rift C

hem

ical

Env

ironm

ent

Seep

age

Wat

er

Pro

perti

es

Non

-ITB

C:

EB

S M

ater

ials

Inte

ract

ions

- C

oppe

r E

BS

Drip

Shi

eld

/E

mpl

acem

ent D

rift I

nver

t M

ater

ials

Inte

ract

ions

No

Bac

kfill

in E

mpl

acem

ent

Drif

tsC

omm

itted

Mat

eria

ls

Was

te P

acka

ge a

nd T

AD

C

anis

ter E

xclu

ded

Mat

eria

lsD

rip S

hiel

d D

esig

n D

rip S

hiel

d D

esig

n an

d In

stal

latio

n

Empl

acem

ent

Drif

t 2.

2.08

.12.

0A

Che

mis

try o

f Wat

er

Flow

ing

into

the

Drif

t In

clud

ed

The

chem

istry

of t

he s

eepa

ge w

ater

is e

valu

ated

in

the

near

-fiel

d ch

emis

try m

odel

, and

in s

uppo

rting

th

erm

al-h

ydro

logi

c-ch

emic

al m

odel

s. T

hese

mod

els

have

eva

luat

ed th

e ra

nge

of e

xpec

ted

wat

er

com

posi

tion

in th

e ho

st ro

ck, a

nd h

ow th

ese

wat

ers

chan

ge in

resp

onse

to re

posi

tory

hea

ting.

S

eepa

ge c

ompo

sitio

n ca

n af

fect

cor

rosi

on o

f the

w

aste

pac

kage

out

er b

arrie

r, if

the

wat

er c

onta

cts

the

was

te p

acka

ge w

hen

othe

r con

ditio

ns s

uch

aste

mpe

ratu

re, p

rom

ote

initi

atio

n of

loca

lized

cor

rosi

on.

In a

dditi

on, s

eepa

ge c

ompo

sitio

n an

d ev

apor

ativ

e ev

olut

ion

in th

e dr

ift e

nviro

nmen

t can

affe

ct th

e tra

nspo

rt of

dis

solv

ed a

nd c

ollo

id ra

dion

uclid

es in

the

inve

rt.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.2

.08.

12.0

A

Yes

IT

BC

:In

-Drif

t Che

mic

alE

nviro

nmen

t In

-Drif

t The

rmal

E

nviro

nmen

t C

onve

ctio

n,

Con

dens

atio

n, a

nd

Evap

orat

ion

Seep

age

Wat

er

Pro

perti

es

Rad

ionu

clid

e In

vent

ory

and

Sou

rce-

Term

P

rope

rties

C

orro

sion

Pro

duct

sP

rope

rties

W

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Non

-ITB

C:

Was

te P

acka

ge D

ecay

Hea

tW

aste

Pac

kage

The

rmal

Li

mits

Was

te P

acka

ge S

paci

ng

Was

te P

acka

ge T

empe

ratu

reLi

mit

As-

empl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

n

Ver

ifica

tion

of D

esig

n R

ock

Pro

perti

es

ANL-WIS-MD-000024 REV 01 ACN 01 A-65 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Drip

Shi

eld

1.2.

02.0

3.0A

Fa

ult D

ispl

acem

ent

Dam

ages

EB

SC

ompo

nent

s In

clud

ed

The

core

and

con

trol p

aram

eter

cha

ract

eris

tics

iden

tifie

d ar

e no

t con

side

red

to b

e IT

BC

bec

ause

with

adm

inis

trativ

e co

ntro

ls in

pla

ce, o

nly

a ve

ry s

mal

l nu

mbe

r of w

aste

pac

kage

s an

d dr

ip s

hiel

ds w

ould

be

impa

cted

by

unde

tect

ed fa

ults

. It

is n

ot e

xpec

ted

that

fa

ults

will

sign

ifica

ntly

affe

ct th

e de

grad

atio

n of

the

EB

S, a

t ann

ual r

ecur

renc

e in

terv

als

of a

bout

10−

7 per

ye

ar a

nd le

ss (S

NL

2007

[DIR

S 1

7682

8],

Sect

ion

6.11

.4),

and

only

a s

mal

l num

ber o

f drip

sh

ield

s ar

e af

fect

ed.

This

deg

rada

tion

proc

ess

is

muc

h le

ss s

igni

fican

t tha

n th

e m

ore

likel

yse

ism

ical

ly-in

duce

d gr

ound

mot

ion

effe

cts

(SN

L 20

07

[DIR

S 1

7682

8], S

ectio

n 6.

7).

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.2.0

2.03

.0A

No

Non

-ITB

C:

Cha

ract

eriz

atio

n of

Fa

ult D

ispl

acem

ent

Drip

Shi

eld

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Non

-ITB

C:

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

R

epos

itory

Ele

vatio

n -

Ove

rbur

den

Thic

knes

s R

epos

itory

Sta

ndof

f fro

m

Qua

tern

ary

Faul

t A

s-E

mpl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

n

Drip

Shi

eld

1.2.

03.0

2.0A

S

eism

ic G

roun

dM

otio

n D

amag

esE

BS

Com

pone

nts

Incl

uded

This

dam

age

mod

e su

bsta

ntia

lly im

pact

s th

e re

leas

e of

radi

onuc

lides

from

the

repo

sito

ry.

Vibr

ator

y gr

ound

mot

ion

has

the

pote

ntia

l to

caus

e pl

astic

def

orm

atio

n of

drip

shi

eld

com

pone

nts

or

sepa

ratio

n of

adj

acen

t drip

shi

elds

. P

last

icde

form

atio

n of

drip

shi

eld

com

pone

nts

may

resu

lt in

re

sidu

al s

tress

es th

at e

xcee

d a

tens

ile th

resh

old

for

initi

atio

n an

d gr

owth

of s

tress

cor

rosi

on c

rack

s.

How

ever

, the

pre

senc

e of

a c

rack

net

wor

k in

drip

sh

ield

com

pone

nts

does

not

com

prom

ise

its a

bilit

y to

di

vert

seep

age

away

from

the

was

te p

acka

gebe

caus

e ad

vect

ive

flow

thro

ugh

stre

ss c

orro

sion

cr

acks

on

the

drip

shi

eld

is e

xclu

ded

inFE

P 2

.1.0

3.10

.0B

, Adv

ectio

n of

Liq

uids

and

Sol

ids

Thro

ugh

Cra

cks

in th

e D

rip S

hiel

d.

Drip

shi

eld

sepa

ratio

n is

def

ined

as

an a

xial

or v

ertic

al

gap

betw

een

two

adja

cent

drip

shi

elds

that

allo

ws

seep

age

to fl

ow d

irect

ly o

nto

a w

aste

pac

kage

. A

xial

se

para

tion

coul

d oc

cur d

urin

g a

grou

nd m

otio

nbe

caus

e of

hig

h pl

astic

def

orm

atio

n in

the

drip

sh

ield

’s c

onne

ctor

sub

asse

mbl

ies

or b

ecau

se o

f lar

ge

verti

cal d

ispl

acem

ents

bet

wee

n ad

jace

nt d

rip s

hiel

ds.

Axi

al s

epar

atio

n of

adj

acen

t drip

shi

elds

is e

xclu

ded

from

the

TSP

A m

odel

bec

ause

a k

inem

atic

No

Non

-ITB

C:

Pro

perti

es o

f the

H

ost R

ock

Uni

t D

rip S

hiel

d M

ater

ials

, P

rope

rties

, and

Con

figur

atio

nC

hara

cter

izat

ion

of

Sei

smic

Eve

nts

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n

Cha

ract

eriz

atio

n of

Ig

neou

s E

vent

s

Non

-ITB

C:

Rep

osito

ry E

leva

tion

–S

tand

off f

rom

the

Wat

er

Tabl

e R

epos

itory

Geo

grap

hic

and

Geo

logi

c Lo

catio

n A

s-E

mpl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

n

EB

S M

ater

ial I

nter

actio

ns --

C

oppe

r D

rip S

hiel

d S

eism

ic

Per

form

ance

E

mpl

acem

ent P

alle

t Fun

ctio

nS

eism

ic D

esig

n of

Was

te

Pac

kage

Was

te P

acka

ge O

uter

Bar

rier

Mat

eria

l Spe

cific

atio

ns

Was

te P

acka

ge Q

uant

ities

V

erifi

catio

n of

Des

ign

Roc

kP

rope

rties

ANL-WIS-MD-000024 REV 01 ACN 01 A-66 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Drip

Shi

eld

(Con

tinue

d)

1.2.

03.0

2.0A

S

eism

ic G

roun

dM

otio

n D

amag

esE

BS

Com

pone

nts

Incl

uded

(Con

tinue

d)

stud

y in

dica

tes

that

sm

all s

tatic

load

s fro

m ru

bble

or

frict

iona

l loa

ds b

etw

een

EBS

com

pone

nts

are

suffi

cien

t to

elim

inat

e ax

ial s

epar

atio

n of

drip

shi

elds

(S

NL

2007

[DIR

S 1

7682

8], S

ectio

n 6.

7.3.

1).

Sig

nific

ant v

ertic

al s

epar

atio

n be

twee

n ad

jace

nt d

rip

shie

lds

is li

mite

d by

the

sam

e ph

ysic

al m

echa

nism

s th

at li

mit

axia

l sep

arat

ion,

and

the

effe

cts

of a

ver

tical

se

para

tion

are

also

miti

gate

d by

the

pres

ence

of t

he

drip

shi

eld

conn

ecto

r sub

asse

mbl

y w

hich

pro

vide

s an

over

lap

betw

een

adja

cent

drip

shi

elds

(SN

L 20

07

[DIR

S 1

7682

8, S

ectio

n 6.

7.3.

2).

Vibr

ator

y gr

ound

mot

ion

may

als

o ca

use

was

te

pack

age-

to-d

rip s

hiel

d im

pact

s. L

ater

al im

pact

s of

a

was

te p

acka

ge to

the

side

wal

ls o

f a d

rip s

hiel

d do

not

ca

use

cata

stro

phic

failu

re o

f the

drip

shi

elds

(SN

L 20

07 [D

IRS

176

828]

, Sec

tion

6.8.

5).

Long

itudi

nal

impa

cts

of a

was

te p

acka

ge to

an

inte

rior b

ulkh

ead

onth

e un

ders

ide

of th

e dr

ip s

hiel

d ha

ve th

e po

tent

ial t

o te

ar th

e bu

lkhe

ad a

nd ru

ptur

e th

e w

elds

that

atta

ch

the

plat

es to

the

bulk

head

. H

igh-

velo

city

long

itudi

nal

impa

cts

with

the

pote

ntia

l to

dam

age

the

bulk

head

su

ppor

t bea

ms

occu

r with

muc

h lo

wer

pro

babi

lity

than

the

prob

abilit

y of

buc

klin

g th

e si

dew

alls

of t

he d

rip

shie

ld, a

s di

scus

sed

in (S

NL

2007

[DIR

S 1

7682

8]

Sec

tion

6.8.

5). I

t fol

low

s th

at th

e dr

ip s

hiel

d si

dew

alls

ar

e lik

ely

to b

uckl

e be

fore

long

itudi

nal i

mpa

cts

dam

age

the

bulk

head

sup

port

beam

s an

d, a

fter t

he

side

wal

ls b

uckl

e, h

igh-

velo

city

long

itudi

nal i

mpa

cts

are

elim

inat

ed b

ecau

se th

e w

aste

pac

kage

can

no

long

er m

ove

freel

y be

neat

h th

e dr

ip s

hiel

d.It

follo

ws

that

the

drip

shi

eld

resp

onse

to v

ibra

tory

grou

nd m

otio

n do

es n

ot a

ffect

the

rele

ase

of

radi

onuc

lides

from

the

repo

sito

ry to

the

acce

ssib

le

envi

ronm

ent,

and

is n

ot im

porta

nt to

bar

rier c

apab

ility

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.2

.03.

02.0

A

ANL-WIS-MD-000024 REV 01 ACN 01 A-67 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Drip

Shi

eld

1.2.

03.0

2.0B

S

eism

ic-In

duce

d R

ockf

all D

amag

es

Drip

Shi

eld

Excl

uded

This

FE

P d

eals

with

larg

e bl

ock

rock

fall.

Rub

ble

rock

fa

ll is

dea

lt w

ith s

epar

atel

y un

der F

EP

1.2

.03.

02.0

C.

The

rang

e of

sei

smic

effe

cts

enco

mpa

sses

a ra

nge

of

prob

abili

ties

(bot

h lik

ely

and

unlik

ely)

. Fo

r unl

ikel

ype

ak g

roun

d ve

loci

ties

abov

e ab

out 2

m/s

, the

lit

hoph

ysal

hos

t roc

k is

exp

ecte

d to

col

laps

e in

to th

e em

plac

emen

t drif

ts.

(SN

L 20

07 [D

IRS

176

828]

, S

ectio

n 6.

11.1

.3).

Th

e pa

ram

eter

cha

ract

eris

tics

asso

ciat

ed w

ith th

is

FEP

and

failu

re m

ode

are

not c

onsi

dere

d IT

BC

beca

use

seis

mic

ally

indu

ced

rock

fall

calc

ulat

ions

de

mon

stra

te th

at ro

ckfa

ll do

es n

ot d

amag

e th

e dr

ip

shie

ld e

noug

h to

impa

ir its

mec

hani

cal o

r hyd

rolo

gica

lpe

rform

ance

.S

eism

ical

ly-in

duce

d ro

ckfa

ll in

the

empl

acem

ent d

rifts

ha

s th

e po

tent

ial t

o da

mag

e or

rupt

ure

the

drip

sh

ield

s as

bar

riers

to fl

ow a

nd a

s ba

rrier

s to

rock

fall.

La

rge

rock

blo

cks,

prim

arily

in th

e no

nlith

ophy

sal

units

of t

he re

posi

tory

, may

fall

out o

f the

roof

and

w

alls

of a

n em

plac

emen

t drif

t dur

ing

a se

ism

ic e

vent

. Th

e im

pact

of t

hese

blo

cks

on th

e dr

ip s

hiel

ds m

ayca

use

plas

tic d

efor

mat

ion

of th

e dr

ip s

hiel

d pl

ates

, ru

ptur

e of

the

drip

shi

eld

plat

es, o

r rup

ture

of t

he a

xial

st

iffen

ers

bene

ath

the

crow

n of

the

drip

shi

eld.

P

last

ic d

efor

mat

ion

of d

rip s

hiel

d pl

ates

may

resu

lt in

re

sidu

al s

tress

es th

at e

xcee

d a

tens

ile th

resh

old

for

initi

atio

n an

d gr

owth

of s

tress

cor

rosi

on c

rack

s.

How

ever

, the

pre

senc

e of

a c

rack

net

wor

k in

the

plat

es d

oes

not c

ompr

omis

e th

e dr

ip s

hiel

ds’

capa

bilit

y to

div

ert s

eepa

ge a

way

from

the

was

te

pack

age

beca

use

adve

ctiv

e flo

w th

roug

h st

ress

co

rrosi

on c

rack

s on

the

drip

shi

eld

plat

es is

exc

lude

d in

FE

P 2

.1.0

3.10

.0B

, Adv

ectio

n of

Liq

uids

and

Sol

ids

Thro

ugh

Cra

cks

in th

e D

rip S

hiel

d.

No

Non

-ITB

C:

Pro

perti

es o

f the

H

ost R

ock

Uni

t D

rip S

hiel

d M

ater

ials

, P

rope

rties

, and

Con

figur

atio

nC

hara

cter

izat

ion

of

Sei

smic

Eve

nts

Non

-ITB

C:

Rep

osito

ry E

leva

tion

-O

verb

urde

n Th

ickn

ess

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

As-

Em

plac

ed W

aste

P

acka

ge-D

rip S

hiel

dC

onfig

urat

ion

Drip

Shi

eld

Sei

smic

P

erfo

rman

ce

Drip

Shi

eld

Des

ign

Drip

Shi

eld

Des

ign

and

Inst

alla

tion

Drip

Shi

eld

Mat

eria

ls a

nd

Thic

knes

ses

Ver

ifica

tion

of D

esig

n R

ock

Pro

perti

es

ANL-WIS-MD-000024 REV 01 ACN 01 A-68 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Drip

Shi

eld

2.1.

11.0

6.0B

Th

erm

al

Sen

sitiz

atio

n of

Drip

Sh

ield

s Ex

clud

ed

Ther

mal

sen

sitiz

atio

n of

tita

nium

is n

ot e

xpec

ted

for

the

rang

e of

like

ly th

erm

al c

ondi

tions

in th

e em

plac

emen

t.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.1

1.06

.0B

No

Non

-ITB

C:

In-D

rift T

herm

al

Env

ironm

ent

Con

vect

ion,

C

onde

nsat

ion,

and

Ev

apor

atio

n D

rip S

hiel

d M

ater

ials

, P

rope

rties

, and

Con

figur

atio

nW

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Non

-ITB

C:

Drip

Shi

eld

Mat

eria

ls a

nd

Thic

knes

ses

Was

te P

acka

ge T

empe

ratu

reLi

mit

As-

empl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

nW

aste

Pac

kage

Spa

cing

W

aste

Pac

kage

The

rmal

Li

mit

Was

te P

acka

ge D

ecay

Hea

tV

erifi

catio

n of

Des

ign

Roc

kP

rope

rties

D

rip S

hiel

d 2.

1.11

.07.

0A

Ther

mal

Exp

ansi

on/

Stre

ss o

f In-

drift

EB

SC

ompo

nent

s Ex

clud

ed

Rep

osito

ry h

eat a

t Yuc

ca M

ount

ain

coul

d re

sult

in

ther

mal

ly-in

duce

d st

ress

es.

Thes

e st

ress

es c

ould

af

fect

the

EB

S c

ompo

nent

s, th

us c

ausi

ng th

e fo

rmat

ion

of p

athw

ays

for g

roun

dwat

er fl

ow th

roug

h th

e E

BS

or a

lterin

g an

d/or

enh

anci

ng e

xist

ing

path

way

s. A

lthou

gh th

erm

al e

xpan

sion

of t

he d

rip

shie

ld o

ccur

s, th

is e

xpan

sion

is n

ot s

igni

fican

t und

er

repo

sito

ry c

ondi

tions

and

the

desi

gn o

f the

drip

shi

eld

acco

mm

odat

es th

erm

al e

xpan

sion

up

to a

300

°C

tem

pera

ture

, whi

ch is

hig

her t

han

calc

ulat

ed

post

clos

ure

tem

pera

ture

s.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.1

1.07

.0A

No

Non

-ITB

C:

In-D

rift T

herm

al

Env

ironm

ent

Drip

Shi

eld

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

t

Non

-ITB

C:

Drip

Shi

eld

Des

ign

Drip

Shi

eld

Mat

eria

ls a

nd

Thic

knes

ses

Drip

Shi

eld

Ther

mal

Ex

pans

ion

Con

stra

int

Was

te P

acka

ge S

paci

ng

Was

te P

acka

ge D

ecay

Hea

tW

aste

Pac

kage

The

rmal

Li

mits

Ver

ifica

tion

of D

esig

n R

ock

Pro

perti

es

As-

empl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

n D

rip S

hiel

d 2.

1.13

.02.

0A

Rad

iatio

n D

amag

e in

EB

SEx

clud

ed

Beca

use

the

estim

ated

neu

tron

fluen

ce is

sig

nific

antly

belo

w th

e w

aste

pac

kage

met

als’

dam

age

thre

shol

ds,

the

mec

hani

cal p

rope

rties

of t

he E

BS

feat

ures

will

not

be

alte

red

by ra

diat

ion

dam

age.

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.13.

02.0

A

No

Non

-ITB

C:

Rad

ionu

clid

e In

vent

ory

and

Sou

rce-

Term

P

rope

rties

W

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Non

-ITB

C:

Was

te P

acka

ge D

esig

nB

asis

Bou

ndin

g D

ose

Rat

e W

aste

Pac

kage

Wor

st-C

ase

Dos

e R

ate

Was

te P

acka

ge D

ecay

Hea

t

ANL-WIS-MD-000024 REV 01 ACN 01 A-77 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te P

acka

ge

2.1.

03.0

7.0A

M

echa

nica

l Im

pact

on W

aste

Pac

kage

Ex

clud

ed

Mec

hani

cal d

egra

datio

n of

the

was

te p

acka

ge c

an

lead

to in

crea

sed

stre

sses

and

incr

ease

d lik

elih

ood

of

stre

ss c

orro

sion

cra

ckin

g. S

uch

mec

hani

cal

degr

adat

ion

due

to v

ibra

tory

gro

und

mot

ion

is

incl

uded

in th

e TS

PA

Mod

el.

In th

e ab

senc

e of

vi

brat

ory

grou

nd m

otio

ns, m

echa

nica

l im

pact

s ar

e in

sign

ifica

nt to

was

te p

acka

ge d

egra

datio

n.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

3.07

.0A

No

Non

-ITB

C:

Drip

Shi

eld

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n P

rope

rties

of t

he

Hos

t Roc

k U

nit

Pal

let M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

Non

-ITB

C:

Was

te P

acka

ge In

tern

alP

ress

uriz

atio

n W

aste

Pac

kage

Sur

face

D

amag

e P

rior t

o C

losu

re

Was

te P

acka

ge R

adia

l Gap

Was

te P

acka

ge S

urfa

ce

Mar

ring

Prio

r to

Empl

acem

ent

Was

te P

acka

ge Q

uant

ities

M

ater

ials

Con

tact

ing

the

Was

te P

acka

geW

aste

Pac

kage

Out

er B

arrie

rM

ater

ial S

peci

ficat

ions

E

BS

Drip

Shi

eld

/E

mpl

acem

ent D

rift I

nver

t M

ater

ials

Inte

ract

ions

Drip

Shi

eld

Cor

rosi

on

Allo

wan

ce

Drip

Shi

eld

Des

ign

Drip

Shi

eld

Han

dlin

g D

rip S

hiel

d D

esig

n an

d In

stal

latio

nD

rip S

hiel

d M

ater

ials

and

Th

ickn

esse

s

ANL-WIS-MD-000024 REV 01 ACN 01 A-83 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te P

acka

ge

2.1.

03.0

8.0A

Ea

rly F

ailu

re o

fW

aste

Pac

kage

sIn

clud

ed

The

pote

ntia

l for

and

resu

ltant

con

sequ

ence

s of

ear

lyfa

ilure

of t

he w

aste

pac

kage

by

man

ufac

turin

g de

fect

s or

wel

d fla

ws

exis

ts, a

nd h

as b

een

cons

ider

ed in

the

TSP

A N

omin

al S

cena

rio C

lass

(SN

L [D

IRS

181

953]

, S

ectio

n 6.

2).

Bec

ause

of t

he v

ery

limite

d nu

mbe

r of

was

te p

acka

ges

expe

cted

to b

e da

mag

ed b

y th

e ea

rlyfa

ilure

mec

hani

sms,

the

impa

ct is

not

sub

stan

tial.

It is

ITBC

bec

ause

the

desi

gn a

nd h

andl

ing

mus

t rem

ain

as a

naly

zed

for t

he n

umbe

r of e

arly

failu

res

to s

tay

insi

gnifi

cant

. FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.03.

08.0

A

Yes

N

on-IT

BC

:W

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

ITB

C:

Was

te P

acka

ge A

nnea

ling

Was

te P

acka

ge C

losu

re

Was

te P

acka

ge F

abric

atio

n W

aste

Pac

kage

Han

dlin

gW

aste

Pac

kage

Sur

face

D

amag

e P

rior t

o C

losu

re

Was

te P

acka

ge S

urfa

ce

Fini

shW

aste

Pac

kage

Fab

ricat

ion

Wel

d In

spec

tions

Was

te P

acka

ge W

eldi

ngM

ater

ials

Was

te P

acka

ge F

abric

atio

n W

eldi

ng F

law

sN

on-IT

BC

E

mpl

acem

ent D

rift G

roun

d S

uppo

rt W

aste

Pac

kage

2.

1.03

.10.

0A

Adv

ectio

n of

Liq

uids

an

d So

lids

thro

ugh

Cra

cks

in th

e W

aste

P

acka

geEx

clud

ed

Cra

cks

in th

e w

aste

pac

kage

, whi

ch m

ay re

sult

from

m

echa

nica

l deg

rada

tion

asso

ciat

ed w

ith s

eism

ic

activ

ity, a

re o

f ins

uffic

ient

siz

e to

allo

w s

igni

fican

t ad

vect

ive

flux

of w

ater

, and

ther

efor

e th

is p

roce

ss is

ex

clud

ed fr

om th

e pe

rform

ance

ass

essm

ent.

H

owev

er, c

rack

s ca

n al

low

moi

stur

e to

ent

er th

e w

aste

pac

kage

via

diff

usio

n in

suf

ficie

nt a

mou

nts

to

initi

ate

degr

adat

ion

and

alte

ratio

n of

the

mat

eria

ls a

nd

was

te fo

rms

insi

de th

e w

aste

pac

kage

. In

add

ition

, di

ffusi

ve tr

ansp

ort t

hrou

gh th

ese

crac

ks is

the

dom

inan

t tra

nspo

rt pr

oces

s fo

r rad

ionu

clid

es re

leas

ed

from

the

was

te.

The

lack

of s

igni

fican

t adv

ectio

n th

roug

h cr

acks

in th

e w

aste

pac

kage

is a

n im

porta

nt

bene

ficia

l cha

ract

eris

tic o

f the

was

te p

acka

ge fe

atur

e.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.03.

10.0

A

Yes

IT

BC

:In

filtra

tion

and

Seep

age

Prop

ertie

sW

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Drip

Shi

eld

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Was

te F

orm

Deg

rada

tion

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

ITB

C:

Sei

smic

Des

ign

of W

aste

P

acka

geW

aste

Pac

kage

Cor

rosi

onAl

low

ance

D

rip S

hiel

d C

orro

sion

Al

low

ance

D

rip S

hiel

d D

esig

n D

rip S

hiel

d D

esig

n an

d In

stal

latio

nD

rip S

hiel

d M

ater

ials

and

Th

ickn

esse

s D

rip S

hiel

d S

eism

ic

Per

form

ance

ANL-WIS-MD-000024 REV 01 ACN 01 A-84 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te P

acka

ge

2.1.

07.0

1.0A

R

ockf

all

Excl

uded

Roc

kfal

l res

ultin

g fro

m g

ravi

tatio

nal s

tress

es,

exca

vatio

n-in

duce

d st

ress

es, a

nd th

erm

ally

-indu

ced

stre

sses

hav

e be

en e

valu

ated

. Th

e lit

hoph

ysal

rock

un

its g

ener

ally

resu

lt in

sm

all b

lock

s, w

hile

larg

er ro

ck

bloc

ks a

re p

ossi

ble

in th

e no

nlith

ophy

sal r

ock

units

. In

eith

er c

ase,

the

effe

cts

of ro

ckfa

ll on

drip

shi

elds

, ha

ve b

een

cons

ider

ed a

nd d

eter

min

ed to

be

insi

gnifi

cant

due

to th

e lim

ited

exte

nt o

f the

rock

fall,

th

e lim

ited

stre

ss-in

duce

d cr

acki

ng o

f the

drip

shi

eld,

th

e pr

eclu

sion

of f

lux

thro

ugh

the

crac

ked

drip

shi

eld,

an

d th

e lim

ited

defo

rmat

ion

of th

e dr

ip s

hiel

d su

ch

that

it d

oes

not c

onta

ct th

e w

aste

pac

kage

due

to

rock

fall.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

7.01

.0A

No

Non

-ITB

C:

Pro

perti

es o

f the

H

ost R

ock

Uni

t D

rip S

hiel

d M

ater

ials

, P

rope

rties

, and

Con

figur

atio

nW

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Drip

Shi

eld

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Non

-ITB

C:

Sei

smic

Des

ign

of W

aste

P

acka

geA

s-em

plac

ed W

aste

P

acka

ge-D

rip S

hiel

dC

onfig

urat

ion

Was

te P

acka

ge D

imen

sion

san

d C

ompo

nent

Mas

ses

Was

te P

acka

ge Q

uant

ities

D

rip S

hiel

d C

orro

sion

Al

low

ance

D

rip S

hiel

d D

esig

n D

rip S

hiel

d D

esig

n an

d In

stal

latio

nD

rip S

hiel

d M

ater

ials

and

Th

ickn

esse

s D

rip S

hiel

d S

eism

ic

Per

form

ance

V

erifi

catio

n of

Des

ign

Roc

kP

rope

rties

E

BS

Drip

Shi

eld

/E

mpl

acem

ent D

rift I

nver

t M

ater

ials

Inte

ract

ions

Was

te P

acka

ge S

urfa

ce

Dam

age

Prio

r to

Clo

sure

D

esig

n of

Gro

und

Sup

port

Sys

tem

E

mpl

acem

ent D

rift

Con

figur

atio

n

Em

plac

emen

t Drif

t Gro

und

Sup

port

ANL-WIS-MD-000024 REV 01 ACN 01 A-86 Marach 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te P

acka

ge(C

ontin

ued)

2.

1.08

.15.

0A

Con

solid

atio

n of

E

BS

Com

pone

nts

Excl

uded

(C

ontin

ued)

Sei

smic

Des

ign

of W

aste

P

acka

geD

rip S

hiel

d S

eism

ic

Per

form

ance

V

erifi

catio

n of

Des

ign

Roc

kP

rope

rties

W

aste

Pac

kage

2.

1.09

.03.

0B

Vol

ume

Incr

ease

of

Cor

rosi

on P

rodu

cts

Impa

cts

was

te

Pac

kage

Excl

uded

Vol

ume

incr

ease

s as

soci

ated

with

deg

rada

tion

of

Allo

y 22

are

not

exp

ecte

d to

hav

e an

y de

lete

rious

ef

fect

on

the

was

te p

acka

ge b

ecau

se th

ese

volu

mes

ar

e sm

all a

nd th

ere

is li

mite

d po

ssib

ility

of s

uch

corro

sion

pro

duct

s fo

rmin

g be

twee

n th

e A

lloy

22 a

nd

stai

nles

s st

eel s

hells

of t

he w

aste

pac

kage

s.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.09.

03.0

B

No

Non

-ITB

C:

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n C

orro

sion

Pro

duct

sP

rope

rties

Non

-ITB

C:

Was

te P

acka

ge R

adia

l Gap

Was

te P

acka

ge C

orro

sion

Allo

wan

ce

Was

te P

acka

ge O

uter

Bar

rier

Mat

eria

l Spe

cific

atio

ns

Was

te P

acka

ge Q

uant

ities

Was

te P

acka

ge

2.1.

09.2

8.0A

Lo

caliz

ed C

orro

sion

on

Was

te P

acka

ge

Out

er S

urfa

ce d

ue to

Del

ique

scen

ceEx

clud

ed

The

pote

ntia

l for

sal

ts to

del

ique

sce

on th

e w

aste

pa

ckag

e ou

ter s

urfa

ce h

as b

een

eval

uate

d. A

lthou

gh

the

pote

ntia

l for

sal

ts to

del

ique

sce

exis

ts, t

he e

ffect

s of

suc

h de

lique

scen

ce h

ave

been

det

erm

ined

to b

e in

sign

ifica

nt to

per

form

ance

, loc

aliz

ed c

orro

sion

pr

oces

ses

are

not e

xpec

ted

to b

e in

itiat

ed.

Eve

n if

loca

lized

cor

rosi

on w

as in

itiat

ed, d

ue to

the

limite

d vo

lum

es, i

t is

likel

y th

at th

e pr

oces

s w

ould

not

pr

opag

ate

thro

ugh

the

was

te p

acka

ge o

uter

sur

face

.Th

e la

ck o

f sig

nific

ant d

egra

datio

n by

this

pro

cess

is

an im

porta

nt c

hara

cter

istic

con

tribu

ting

to th

e ba

rrier

ca

pabi

lity

of th

e dr

ip s

hiel

d fe

atur

e of

the

EB

S.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

9.28

.0A

Yes

IT

BC

:W

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Seep

age

Wat

er

Pro

perti

es

In-D

rift C

hem

ical

Env

ironm

ent

Non

-ITB

C:

In-D

rift T

herm

al

Env

ironm

ent

Con

vect

ion,

C

onde

nsat

ion,

and

Ev

apor

atio

n

ITB

C:

Com

mitt

ed M

ater

ials

W

aste

Pac

kage

Qua

ntiti

es

Was

te P

acka

ge O

uter

Bar

rier

Mat

eria

l Spe

cific

atio

ns

Mat

eria

ls C

onta

ctin

g th

e W

aste

Pac

kage

EB

S M

ater

ials

Inte

ract

ions

- C

oppe

r E

BS

Drip

Shi

eld

/E

mpl

acem

ent D

rift I

nver

t M

ater

ials

Inte

ract

ions

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Was

te P

acka

ge

2.1.

11.0

3.0A

Ex

othe

rmic

R

eact

ions

in th

e E

BS

Excl

uded

Exo

ther

mic

reac

tions

that

cou

ld li

bera

te h

eat i

n th

e w

aste

and

EB

S, a

re in

sign

ifica

nt in

com

paris

on to

the

heat

gen

erat

ed b

y ra

dioa

ctiv

e de

cay.

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.11.

03.0

A

No

Non

-ITB

C:

In-D

rift T

herm

al

Env

ironm

ent

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

t

Non

-ITB

C:

Drip

Shi

eld

Cor

rosi

on

Allo

wan

ce

Was

te P

acka

ge C

orro

sion

Allo

wan

ce

EB

S D

rip S

hiel

d /

Em

plac

emen

t Drif

t Inv

ert

Mat

eria

ls In

tera

ctio

nsC

omm

itted

Mat

eria

ls

Was

te P

acka

ge &

TA

D

Can

iste

r Exc

lude

d M

ater

ials

ANL-WIS-MD-000024 REV 01 ACN 01 A-88 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Cla

ddin

g (C

ontin

ued)

1.

2.02

.03.

0A

Faul

t Dis

plac

emen

t D

amag

es E

BS

Com

pone

nts

Incl

uded

(Con

tinue

d)

Nav

al S

NF

cani

ster

s ha

ve a

dditi

onal

requ

irem

ents

re

late

d to

em

plac

emen

t aw

ay fr

om fa

ults

. Fo

r nav

al

SN

F pa

ckag

es, t

hese

em

plac

emen

t req

uire

men

ts a

re

impo

rtant

to w

aste

isol

atio

n. T

here

is a

spe

cific

cr

iterio

n fo

r nav

al w

aste

pac

kage

s th

at re

quire

s an

8.

2-ft

(2.5

-m) m

inim

um e

mpl

acem

ent s

tand

off

dist

ance

from

map

ped

faul

ts w

ith v

ertic

aldi

spla

cem

ents

gre

ater

than

6.5

ft (2

m) (

BS

C 2

007

[DIR

S 1

8213

1], S

ectio

n 8.

2.3.

1.1)

. B

ased

on

this

ev

alua

tion,

this

is IT

BC

(and

als

o IT

WI)

spec

ifica

lly fo

r na

val w

aste

pac

kage

s.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.2.0

2.03

.0A

Cla

ddin

g 1.

2.03

.02.

0A

Sei

smic

Gro

und

Mot

ion

Dam

ages

EB

S C

ompo

nent

sIn

clud

ed

This

FE

P d

oes

not c

onsi

der N

aval

cla

ddin

g. F

EP

2.

1.02

.25.

0B:

Nav

al S

NF

stru

ctur

e (in

clud

ing

clad

ding

) dea

ls w

ith N

avy

clad

ding

sep

arat

ely.

S

eism

ic e

ffect

s ar

e in

clud

ed in

the

Sei

smic

Gro

und

Mot

ion

Mod

elin

g C

ase

of th

e S

eism

ic S

cena

rio C

lass

. E

xcep

t for

Nav

al S

NF,

no

cred

it is

take

n fo

r cla

ddin

gin

tegr

ity in

the

TSP

A.

How

ever

, cla

ddin

g pr

ovid

es

barri

er c

apab

ility

and

thus

has

cor

e an

d co

ntro

l pa

ram

eter

s ch

arac

teris

tics

that

lim

it its

deg

rada

tion

at

high

tem

pera

ture

s or

from

mec

hani

cal l

oads

. Th

e co

re a

nd c

ontro

l par

amet

er c

hara

cter

istic

s id

entif

ied

are

not c

onsi

dere

d to

be

ITB

C b

ecau

se th

is

barri

er fe

atur

e/co

mpo

nent

is n

ot a

ccou

nted

for i

n th

e te

chni

cal b

asis

. FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.2

.03.

02.0

A

Yes

IT

BC

:W

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

C

hara

cter

izat

ion

of

Sei

smic

Eve

nts

Non

-ITB

C:

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nP

rope

rties

of t

he

Hos

t Roc

k U

nit

ITB

C:

Sei

smic

Des

ign

of W

aste

P

acka

geD

rip S

hiel

d S

eism

ic

Per

form

ance

W

aste

Pac

kage

Out

er B

arrie

rM

ater

ial S

peci

ficat

ions

E

BS

In-D

rift M

ater

ials

In

tera

ctio

nsN

on-IT

BC

:A

s-em

plac

ed W

aste

P

acka

ge-D

rip S

hiel

dC

onfig

urat

ion

Em

plac

emen

t Pal

let F

unct

ion

Em

plac

emen

t Pal

let

Fabr

icat

ion

and

Cor

rosi

on

Allo

wan

ce

ANL-WIS-MD-000024 REV 01 ACN 01 A-92 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

1.2.

03.0

2.0A

S

eism

ic G

roun

dM

otio

n D

amag

esE

BS

Com

pone

nts

Incl

uded

Vibr

ator

y gr

ound

mot

ion

has

the

pote

ntia

l to

dam

age

the

was

te fo

rms

and

was

te p

acka

ge in

tern

als

from

w

aste

pac

kage

-to-w

aste

pac

kage

impa

cts

and

from

w

aste

pac

kage

-to-p

alle

t im

pact

s th

at m

ay o

ccur

du

ring

a se

ism

ic e

vent

. Th

ese

impa

cts

may

cau

se

axia

l and

late

ral a

ccel

erat

ions

of t

he s

pent

fuel

as

sem

blie

s th

at a

re la

rge

enou

gh to

buc

kle

the

was

te

form

and

the

was

te p

acka

ge in

tern

als.

The

se

impa

cts

may

als

o ca

use

plas

tic d

efor

mat

ion

of w

aste

pa

ckag

e O

CB

. P

last

ic d

efor

mat

ion

of th

e O

CB

may

resu

lt in

resi

dual

stre

sses

that

exc

eed

a te

nsile

th

resh

old

for i

nitia

tion

and

grow

th o

f stre

ss c

orro

sion

cr

acks

. O

nce

the

OC

B is

bre

ache

d by

a c

rack

ne

twor

k, c

orro

sion

of t

he w

aste

form

and

was

te

pack

age

inte

rnal

s w

ill c

ompr

omis

e th

eir c

apac

ity to

su

ppor

t stru

ctur

al lo

ads

and

to is

olat

e th

e w

aste

form

du

ring

vibr

ator

y gr

ound

mot

ion.

The

resp

onse

of t

he

was

te fo

rm a

nd w

aste

pac

kage

inte

rnal

s to

vib

rato

ry

grou

nd m

otio

n is

ITB

C.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.2.0

3.02

.0A

Yes

IT

BC

:D

rip S

hiel

d M

ater

ials

, P

rope

rties

, and

Con

figur

atio

nW

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Pro

perti

es o

f the

H

ost R

ock

Uni

t C

hara

cter

izat

ion

of

Sei

smic

Eve

nts

Non

-ITB

C:

Pal

let M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nIn

vert

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

ITB

C:

Rep

osito

ry E

leva

tion

-O

verb

urde

n Th

ickn

ess

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

As-

Em

plac

ed W

aste

P

acka

ge-D

rip S

hiel

dC

onfig

urat

ion

Drip

Shi

eld

Sei

smic

P

erfo

rman

ce

Sei

smic

Des

ign

of W

aste

P

acka

geE

BS

In-D

rift M

ater

ials

In

tera

ctio

nsN

on-IT

BC

:E

mpl

acem

ent P

alle

t Fun

ctio

nE

mpl

acem

ent P

alle

t Fa

bric

atio

n an

d C

orro

sion

Al

low

ance

E

mpl

acem

ent D

rift I

nver

t C

onfig

urat

ion

Em

plac

emen

t Drif

t In

vert

Func

tion

Inve

rt M

ater

ials

Ver

ifica

tion

of D

esig

n R

ock

Pro

perti

es

Em

plac

emen

t Pal

let D

esig

n

ANL-WIS-MD-000024 REV 01 ACN 01 A-111 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

01.0

1.0A

W

aste

Inve

ntor

y In

clud

ed

The

was

te in

vent

ory

defin

es th

e am

ount

of d

iffer

ent

radi

onuc

lides

pre

sent

in d

iffer

ent w

aste

form

s (S

NL

2007

[DIR

S 1

8047

2], S

ectio

n 6.

1).

Whi

le in

vent

ory

cont

rols

the

initi

al c

ondi

tions

in w

aste

form

, whi

ch is

im

porta

nt to

the

rele

ase

of ra

dion

uclid

e in

vent

ory,

it is

w

ell c

hara

cter

ized

and

any

cha

nge

to in

vent

ory

will

be

man

aged

by

the

chan

ge-e

valu

atio

n pr

oces

s Ad

ditio

nally

, in

the

eval

uatio

n of

bar

rier c

apab

ility,

tra

nspo

rt of

radi

onuc

lides

from

the

was

te in

vent

ory

are

eval

uate

d se

para

tely

in tr

ansp

ort-r

elat

ed F

EP

s.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

1.01

.0A

No

Non

-ITB

C:

Rad

ionu

clid

e In

vent

ory

and

Sou

rce-

Term

P

rope

rties

W

aste

Form

/Pac

kage

In

tern

als

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Crit

ical

ityC

hara

cter

istic

sW

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Rad

ionu

clid

e In

vent

ory

and

Sou

rce-

Term

P

rope

rties

Non

-ITB

C:

Was

te P

acka

ge D

ecay

Hea

tW

aste

Pac

kage

The

rmal

Li

mits

Was

te F

orm

CS

NF

Fuel

Rod

M

axim

um B

urnu

p Li

mit

Was

te P

acka

ge D

esig

nB

asis

Bou

ndin

g D

ose

Rat

e W

aste

Pac

kage

Tem

pera

ture

Lim

itC

ladd

ing

Tem

pera

ture

Lim

it -

- Ven

tilat

ion

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

01.0

2.0A

In

tera

ctio

ns B

etw

een

Co-

loca

ted

Was

te

Excl

uded

Alth

ough

diff

eren

t was

te fo

rms

have

diff

eren

tin

vent

orie

s, a

nd c

hem

ical

and

ther

mal

cha

ract

eris

tics

(e.g

., H

LW g

lass

was

te fo

rms

vers

us S

NF

was

te

form

s), t

hese

diff

eren

ces

do n

ot s

igni

fican

tly a

ffect

the

capa

bilit

y of

the

EB

S.

The

mod

els

cons

ider

thes

e di

ffere

nces

in th

e ev

alua

tion

of th

e re

leas

es fr

om th

e w

aste

form

. H

owev

er, t

here

is n

o si

gnifi

cant

inte

ract

ion

betw

een

the

co-lo

cate

d w

aste

s an

d ba

rrie

r ca

pabi

lity

is n

ot s

ubst

antia

lly im

pact

ed.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

1.02

.0A

No

Non

-ITB

C:

Was

te F

orm

Deg

rada

tion

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nIn

-Pac

kage

Che

mic

al

Env

ironm

ent

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

tIn

-Pac

kage

The

rmal

E

nviro

nmen

t C

ritic

ality

Cha

ract

eris

tics

Non

-ITB

C:

Was

te P

acka

ge C

apac

ities

Was

te P

acka

ge D

ecay

Hea

tW

aste

Pac

kage

The

rmal

Li

mits

Was

te P

acka

ge T

empe

ratu

reLi

mit

Cla

ddin

g Te

mpe

ratu

re L

imit

-- V

entil

atio

n

ANL-WIS-MD-000024 REV 01 ACN 01 A-112 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

02.0

2.0A

C

SNF

Deg

rada

tion

(alte

ratio

n,

diss

olut

ion,

and

ra

dion

uclid

e re

leas

e)

Incl

uded

This

FE

P no

t onl

y en

com

pass

es th

e st

ruct

ure

and

com

posi

tion

of th

e C

SN

F, it

als

o ad

dres

ses

alte

ratio

n,

degr

adat

ion,

and

dis

solu

tion

of th

e w

aste

form

. Th

ese

proc

esse

s ca

n in

fluen

ce th

e m

obili

zatio

n of

ra

dion

uclid

es (B

SC

200

4 [D

IRS

169

987]

, Sec

tions

6.

1 an

d 6.

2).

This

FE

P d

efin

es th

e es

senc

e of

the

CS

NF

was

te fo

rm.

FEP

Sour

ce:

SN

L 20

08 [D

IRS

183

041]

– 2

.1.0

2.02

.0A

Yes

IT

BC

:In

-Pac

kage

Che

mic

al

Env

ironm

ent

In-P

acka

ge T

herm

al

Env

ironm

ent

Was

te F

orm

Deg

rada

tion

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

ITB

C:

Was

te F

orm

CS

NF

Fuel

Rod

M

axim

um B

urnu

p Li

mit

Non

-ITB

C:

Was

te P

acka

ge M

oist

ure

Rem

oval

and

Iner

ting

Was

te P

acka

ge &

TA

D

Can

iste

r Exc

lude

d M

ater

ials

Load

ing

of W

aste

For

ms

Han

dlin

g of

Bar

e S

NF

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

02.0

3.0A

H

LW G

lass

Deg

rada

tion

(alte

ratio

n,

diss

olut

ion,

and

ra

dion

uclid

e re

leas

e)

Incl

uded

This

FE

P no

t onl

y en

com

pass

es th

e st

ruct

ure

and

com

posi

tion

of th

e hi

gh le

vel w

aste

gla

ss w

aste

form

, it

also

add

ress

es a

ltera

tion

and

degr

adat

ion

of th

e w

aste

form

. Th

ese

proc

esse

s, a

long

with

pha

se

sepa

ratio

n, c

ongr

uent

dis

solu

tion,

pre

cipi

tatio

n of

si

licat

es, c

o-pr

ecip

itatio

n of

oth

er m

iner

als,

and

se

lect

ive

leac

hing

, sub

stan

tially

impa

cts

the

mob

iliza

tion

of ra

dion

uclid

es.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

2.03

.0A

Yes

IT

BC

:In

-Pac

kage

Che

mic

al

Env

ironm

ent

In-P

acka

ge T

herm

al

Env

ironm

ent

Was

te F

orm

Deg

rada

tion

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

ITB

C:

Was

te P

acka

ge M

oist

ure

Rem

oval

and

Iner

ting

Load

ing

of W

aste

For

ms

N

on-IT

BC

:H

andl

ing

of B

are

SN

FW

aste

Pac

kage

and

TA

D

Can

iste

r Exc

lude

d M

ater

ials

ANL-WIS-MD-000024 REV 01 ACN 01 A-115 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

09.0

7.0A

R

eact

ion

Kin

etic

s in

W

aste

Pac

kage

Incl

uded

Rea

ctio

n ki

netic

s, li

mit

the

trans

port

of a

hos

t of

radi

onuc

lides

and

are

impl

icitl

y ac

coun

ted

for i

n th

e In

-Pac

kage

Che

mis

try M

odel

, the

Dis

solv

ed

Con

cent

ratio

ns M

odel

, and

the

EB

S R

TA.

The

para

met

er c

hara

cter

istic

s as

soci

ated

with

this

proc

ess

subs

tant

ially

impa

ct th

e tra

nspo

rt of

ra

dion

uclid

es fr

om th

e w

aste

form

. FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.09.

07.0

A

Yes

IT

BC

:In

-Pac

kage

Che

mic

al

Env

ironm

ent

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

tIn

-Pac

kage

The

rmal

E

nviro

nmen

t R

adio

nucl

ide

Inve

ntor

y an

d S

ourc

e-Te

rm

Pro

perti

es

ITB

C:

Was

te P

acka

ge T

herm

al

Lim

itsW

aste

Pac

kage

and

TA

D

Can

iste

r Exc

lude

d M

ater

ials

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

09.0

8.0A

D

iffus

ion

ofD

isso

lved

R

adio

nucl

ides

inE

BS

Incl

uded

Diff

usio

n is

an

impo

rtant

tran

spor

t mec

hani

sm fo

r di

ssol

ved

radi

onuc

lides

from

the

was

te fo

rm s

urfa

ce

to th

e w

aste

pac

kage

inte

rnal

s an

d th

en th

roug

h th

e de

grad

ed w

aste

pac

kage

to th

e in

vert.

Diff

usio

n is

cont

rolle

d by

the

degr

ee o

f deg

rada

tion

of th

e w

aste

pa

ckag

e an

d th

e hy

drol

ogic

cha

ract

eris

tics

with

in th

e w

aste

pac

kage

, whi

ch in

turn

, is

a fu

nctio

n of

the

type

of w

aste

. Th

e di

ffusi

ve tr

ansp

ort i

s co

nser

vativ

ely

spec

ified

to o

ccur

thro

ugh

a co

ntin

uous

wat

er fi

lm o

n th

e su

rface

s of

the

EB

S fe

atur

es (S

NL

2007

[D

IRS

177

407]

, Sec

tion

6.3.

4).

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.09.

08.0

A

Yes

IT

BC

:In

-Pac

kage

Che

mic

al

Env

ironm

ent

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

tIn

-Pac

kage

The

rmal

E

nviro

nmen

t R

adio

nucl

ide

Inve

ntor

y an

d S

ourc

e-Te

rm

Pro

perti

es

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nW

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Non

-ITB

C:

Was

te P

acka

ge O

uter

Bar

rier

Mat

eria

l Spe

cific

atio

ns

Was

te P

acka

ge Q

uant

ities

W

aste

Pac

kage

Dec

ay H

eat

Was

te P

acka

ge T

herm

al

Lim

its

ANL-WIS-MD-000024 REV 01 ACN 01 A-122 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s(C

ontin

ued)

2.1.

09.0

8.0A

D

iffus

ion

ofD

isso

lved

R

adio

nucl

ides

inE

BS

Incl

uded

(Con

tinue

d)

Non

-ITB

C:

Was

te F

orm

Deg

rada

tion

Cor

rosi

on P

rodu

cts

Pro

perti

es

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

09.0

8.0B

A

dvec

tion

ofD

isso

lved

R

adio

nucl

ides

inE

BS

Incl

uded

Adv

ectio

n is

an

impo

rtant

tran

spor

t mec

hani

sm fo

r di

ssol

ved

radi

onuc

lides

from

the

was

te fo

rm s

urfa

ce

to th

e w

aste

pac

kage

inte

rnal

s an

d th

en th

roug

h th

e de

grad

ed w

aste

pac

kage

to th

e in

vert.

Adv

ectio

n is

cont

rolle

d by

the

degr

ee o

f deg

rada

tion

of th

e w

aste

pa

ckag

e an

d th

e hy

drol

ogic

cha

ract

eris

tics

with

in th

e w

aste

pac

kage

, whi

ch in

turn

, is

a fu

nctio

n of

the

type

of w

aste

. Th

e co

nditi

ons

requ

ired

for a

dvec

tive

trans

port

thro

ugh

a w

aste

pac

kage

are

less

like

ly to

occu

r tha

n th

ose

cond

ition

s re

quire

d fo

r diff

usio

n.

How

ever

, whe

n ad

vect

ive

trans

port

thro

ugh

the

was

te

pack

age

does

occ

ur it

s co

nseq

uenc

es a

re m

ore

sign

ifica

nt c

ompa

red

to th

at fr

om d

iffus

ion

mec

hani

sms

beca

use

of th

e am

ount

of w

ater

in

volv

ed. T

here

fore

, adv

ectio

n tro

ugh

the

was

te

pack

age

is id

entif

ied

as IT

BC

. FE

P So

urce

:S

NL

2008

[DIR

S 1

8304

1]- 2

.1.0

9.08

.0B

Yes

IT

BC

:In

-Pac

kage

Che

mic

al

Env

ironm

ent

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

tIn

-Pac

kage

The

rmal

E

nviro

nmen

t R

adio

nucl

ide

Inve

ntor

y an

d S

ourc

e-Te

rm

Pro

perti

es

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nW

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Non

-ITB

C:

Was

te F

orm

Deg

rada

tion

Cor

rosi

on P

rodu

cts

Pro

perti

es

Non

-ITB

C:

Was

te P

acka

ge O

uter

Bar

rier

Mat

eria

l Spe

cific

atio

ns

Was

te P

acka

ge Q

uant

ities

W

aste

Pac

kage

Dec

ay H

eat

Was

te P

acka

ge T

herm

al

Lim

its

ANL-WIS-MD-000024 REV 01 ACN 01 A-123 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

09.2

3.0A

S

tabi

lity

of C

ollo

ids

in E

BS

Incl

uded

The

stab

ility

of c

ollo

ids

is a

func

tion

of th

e ch

emic

al

envi

ronm

ent i

n th

e w

aste

pac

kage

inte

rnal

en

viro

nmen

t (S

NL

2007

[DIR

S 1

7742

3], S

ectio

ns

4.1.

2 an

d 6.

5.1)

and

det

erm

ines

how

man

y co

lloid

s re

mai

n su

spen

ded

in w

ater

Alth

ough

con

side

red

and

acco

unte

d fo

r in

the

post

clos

ure

anal

yzed

bas

is, t

he

cont

ribut

ion

of c

ollo

id tr

ansp

ort p

roce

sses

is le

ss

sign

ifica

nt th

an th

at a

ssoc

iate

d w

ith th

e tra

nspo

rt of

di

ssol

ved

radi

onuc

lides

and

par

amet

er c

hara

cter

istic

s as

soci

ated

with

the

trans

port

of c

ollo

ids

are

not

cons

ider

ed IT

BC

.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

9.23

.0A

No

Non

-ITB

C:

In-P

acka

ge C

hem

ical

E

nviro

nmen

t W

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

In-P

acka

ge T

herm

al

Env

ironm

ent

Rad

ionu

clid

e In

vent

ory

and

Sou

rce-

Term

P

rope

rties

W

aste

For

mD

egra

datio

n W

aste

Form

/Pac

kage

In

tern

als

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

tR

adio

nucl

ide

Inve

ntor

y an

d S

ourc

e-Te

rm

Pro

perti

es

Non

e

ANL-WIS-MD-000024 REV 01 ACN 01 A-130 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

14.1

6.0A

In

-Pac

kage

Crit

ical

ity (d

egra

ded

conf

igur

atio

ns)

Excl

uded

It ha

s be

en d

eter

min

ed th

at th

e co

nditi

ons

requ

ired

to

lead

to in

-pac

kage

crit

ical

ity a

re n

ot li

kely

to o

ccur

an

d th

e pa

ram

eter

cha

ract

eris

tics

asso

ciat

ed w

ith th

is

proc

ess

and

feat

ure

do n

ot s

ubst

antia

lly e

ffect

the

rele

ase

of ra

dion

uclid

es o

r im

pact

the

barri

erca

pabi

lity

of th

is fe

atur

e(S

NL

2007

[DIR

S 1

7386

9],

Sec

tion

6.3)

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.14.

16.0

A

No

Non

-ITB

C:

Crit

ical

ityC

hara

cter

istic

sW

aste

Form

/Pac

kage

In

tern

als

Mat

eria

ls,

Pro

perti

es, a

ndC

onfig

urat

ion

Was

te F

orm

Deg

rada

tion

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n D

rip S

hiel

d M

ater

ials

, P

rope

rties

, and

Con

figur

atio

nIn

filtra

tion

and

Seep

age

Prop

ertie

sR

adio

nucl

ide

Inve

ntor

y an

d S

ourc

e-Te

rm

Pro

perti

es

Drip

Shi

eld

Sei

smic

P

erfo

rman

ce

Pro

perti

es o

f the

H

ost R

ock

Uni

t W

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Rad

ionu

clid

e In

vent

ory

and

Sou

rce-

Term

P

rope

rties

Non

-ITB

C:

Drip

Shi

eld

Sei

smic

P

erfo

rman

ce

Drip

Shi

eld

Cor

rosi

on

Allo

wan

ce

Sei

smic

Des

ign

of W

aste

P

acka

geA

s-em

plac

ed W

aste

P

acka

ge-D

rip S

hiel

dC

onfig

urat

ion

Load

ing

of W

aste

For

ms

Rep

osito

ry L

ayou

t W

aste

Pac

kage

and

TA

D

Can

iste

r Exc

lude

d M

ater

ials

W

aste

Pac

kage

Moi

stur

eR

emov

al a

nd In

ertin

gW

aste

Pac

kage

Spa

cing

W

aste

Pac

kage

Cap

aciti

es

ANL-WIS-MD-000024 REV 01 ACN 01 A-135 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te F

orm

and

W

aste

Pac

kage

Inte

rnal

s

2.1.

14.2

4.0A

In

-pac

kage

Crit

ical

ity

Res

ultin

g fro

m a

n Ig

neou

s E

vent

(in

tact

con

figur

atio

n)

Excl

uded

It ha

s be

en d

eter

min

ed th

at th

e co

nditi

ons

requ

ired

to

lead

to in

-pac

kage

crit

ical

ity a

re n

ot li

kely

to o

ccur

an

d th

e pa

ram

eter

cha

ract

eris

tics

asso

ciat

ed w

ith th

is

proc

ess

and

feat

ure

do n

ot s

ubst

antia

lly e

ffect

the

rele

ase

of ra

dion

uclid

es o

r im

pact

the

barri

erca

pabi

lity

of th

is fe

atur

e(S

NL

2007

[DIR

S 1

7386

9],

Sec

tion

6.6)

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.14.

24.0

A

No

Non

-ITB

C:

Crit

ical

ityC

hara

cter

istic

sW

aste

For

mP

rope

rties

, and

Con

figur

atio

nW

aste

Pac

kage

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Rad

ionu

clid

e In

vent

ory

and

Sour

ce

Term

Pro

perti

es

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

t

Non

-ITB

C:

Load

ing

of W

aste

For

ms

Was

te P

acka

ge a

nd T

AD

C

anis

ter E

xclu

ded

Mat

eria

lsW

aste

Pac

kage

Moi

stur

eR

emov

al a

nd In

ertin

g

ANL-WIS-MD-000024 REV 01 ACN 01 A-140 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te P

acka

geP

alle

t 1.

2.03

.02.

0A

Sei

smic

Gro

und

Mot

ion

Dam

ages

EB

S C

ompo

nent

sIn

clud

ed

Vibr

ator

y gr

ound

mot

ion

has

the

pote

ntia

l to

dam

age

the

empl

acem

ent p

alle

ts fr

om w

aste

pac

kage

-to-

palle

t im

pact

s th

at m

ay o

ccur

dur

ing

a se

ism

ic e

vent

.

Thes

e im

pact

s m

ay d

efor

m o

r eve

n cr

ush

the

empl

acem

ent p

alle

ts o

nce

gene

ral c

orro

sion

of A

lloy

22 re

duce

s th

e th

ickn

ess

of th

e cr

adle

s th

at s

uppo

rt th

e w

aste

pac

kage

. Th

e im

pact

load

s m

ay a

lso

fail

the

stai

nles

s st

eel c

onne

ctor

rods

in th

e pa

llet,

allo

win

g th

e tw

o cr

adle

s to

mov

e in

depe

nden

tlydu

ring

a se

ism

ic e

vent

. W

hile

the

crad

les

rem

ain

inta

ct a

nd c

an s

uppo

rt th

e w

aste

pac

kage

abo

ve th

e in

vert,

the

pres

ence

of t

he

palle

t can

del

ay d

iffus

ive

rele

ases

of r

adio

nucl

ides

fro

m th

e w

aste

pac

kage

to th

e in

vert,

ther

eby

prov

idin

g a

sign

ifica

nt b

arrie

r to

the

rele

ase

of

radi

onuc

lides

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.2

.03.

02.0

A

Yes

IT

BC

:E

mpl

acem

ent P

alle

t M

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n P

rope

rties

of t

he

Hos

t Roc

k U

nit

Cha

ract

eriz

atio

n of

S

eism

ic E

vent

s

ITB

C:

As-

empl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

nE

mpl

acem

ent P

alle

t Fa

bric

atio

n an

d C

orro

sion

Al

low

ance

E

mpl

acem

ent P

alle

t Des

ign

Em

plac

emen

t Pal

let F

unct

ion

EB

S D

rip S

hiel

d /

Em

plac

emen

t Drif

t Inv

ert

Mat

eria

ls In

tera

ctio

nsM

ater

ials

Con

tact

ing

the

Was

te P

acka

ge

Was

te P

acka

geP

alle

t 2.

1.06

.05.

0A

Mec

hani

cal

Deg

rada

tion

ofE

mpl

acem

ent P

alle

t Ex

clud

ed

The

was

te p

acka

ge e

mpl

acem

ent p

alle

t pro

vide

s m

echa

nica

l sta

bilit

y fo

r the

was

te p

acka

ge g

iven

gr

ound

mot

ions

ass

ocia

ted

with

a p

oten

tial s

eism

ic

even

t. Th

e po

tent

ial m

echa

nica

l deg

rada

tion

of th

e w

aste

pac

kage

em

plac

emen

t pal

let h

as b

een

eval

uate

d an

d de

term

ined

to n

ot s

igni

fican

tly a

ffect

th

e ab

ility

of t

he p

alle

t to

mai

ntai

n its

func

tion

of

keep

ing

the

was

te p

acka

ge s

tabl

e an

d ab

ove

the

inve

rt.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.06.

05.0

A

No

Non

-ITB

C:

Em

plac

emen

t Pal

let

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Non

-ITB

C:

Em

plac

emen

t Pal

let D

esig

nE

mpl

acem

ent P

alle

t Fun

ctio

nE

mpl

acem

ent P

alle

t Fa

bric

atio

n an

d C

orro

sion

Al

low

ance

W

aste

Pac

kage

and

E

mpl

acem

ent P

alle

t Sta

tic

Stre

sses

EB

S D

rip S

hiel

d /

Em

plac

emen

t Drif

t Inv

ert

Mat

eria

ls In

tera

ctio

nsE

BS

Mat

eria

ls In

tera

ctio

ns -

Em

plac

emen

t Pal

let F

unct

ion

ANL-WIS-MD-000024 REV 01 ACN 01 A-145 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Was

te P

acka

geP

alle

t 2.

1.06

.05.

0C

Che

mic

al

Deg

rada

tion

ofE

mpl

acem

ent P

alle

t In

clud

ed

The

was

te p

acka

ge e

mpl

acem

ent p

alle

t pro

vide

s ch

emic

al s

tabi

lity

for t

he w

aste

pac

kage

and

a

unifo

rm c

hem

ical

bou

ndar

y co

nditi

on fo

r eva

luat

ion

of

was

te p

acka

ge d

egra

datio

n, in

that

the

was

te

pack

age

does

not

com

e in

to d

irect

con

tact

with

the

inve

rt. T

he p

oten

tial c

hem

ical

deg

rada

tion

of th

e w

aste

pac

kage

em

plac

emen

t pal

let h

as b

een

eval

uate

d an

d de

term

ined

to n

ot s

igni

fican

tly a

ffect

th

e ab

ility

of t

he p

alle

t to

mai

ntai

n its

func

tion

of

keep

ing

the

was

te p

acka

ge s

tabl

e an

d ab

ove

the

inve

rt.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.06.

05.0

C

No

Non

-ITB

C:

Em

plac

emen

t Pal

let

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n

Non

-ITB

C:

Em

plac

emen

t Pal

let D

esig

nE

mpl

acem

ent P

alle

t Fun

ctio

nE

mpl

acem

ent P

alle

t Fa

bric

atio

n an

d C

orro

sion

Al

low

ance

E

BS

In-d

rift M

ater

ials

Inte

ract

ions

As-

empl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

nW

aste

Pac

kage

Out

er B

arrie

rM

ater

ial S

peci

ficat

ions

W

aste

Pac

kage

Pal

let

2.1.

06.0

7.0A

C

hem

ical

Effe

cts

at

EB

S C

ompo

nent

Inte

rface

Excl

uded

Sol

id-to

-sol

id in

tera

ctio

ns a

t the

inte

rface

s be

twee

nth

e va

rious

feat

ures

of t

he E

BS

hav

e be

enco

nsid

ered

in th

e de

sign

and

ana

lysi

s of

the

in-d

rift

chem

ical

env

ironm

ent s

uch

that

gal

vani

c co

uplin

g an

d ot

her c

hem

ical

inte

ract

ions

are

insi

gnifi

cant

to

post

clos

ure

perfo

rman

ce a

sses

smen

t. FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.06.

07.0

A

No

Non

-ITB

C:

Em

plac

emen

t Pal

let

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n

Non

-ITB

C:

EB

S M

ater

ials

Inte

ract

ions

Cop

per

EB

S D

rip S

hiel

d /

Em

plac

emen

t Drif

t Inv

ert

Mat

eria

ls In

tera

ctio

nsE

BS

Mat

eria

ls In

tera

ctio

ns -

Em

plac

emen

t Pal

let F

unct

ion

Was

te P

acka

geP

alle

t 2.

1.06

.07.

0B

Mec

hani

cal E

ffect

sat

EB

S C

ompo

nent

In

terfa

ces

Excl

uded

Adm

inis

trativ

e co

ntro

ls fo

r the

repo

sito

ry c

onst

ruct

ion

and

oper

atio

ns w

ill b

e de

velo

ped

to a

ssur

e th

at w

aste

pa

ckag

es a

nd d

rip s

hiel

ds a

re p

lace

d in

acc

orda

nce

with

the

repo

sito

ry d

esig

n.

Phy

sica

l effe

cts

of s

tead

y-st

ate

cont

act (

stat

ic

load

ing)

that

occ

ur a

t the

inte

rface

s be

twee

nm

ater

ials

in th

e dr

ift m

ay a

ffect

the

perfo

rman

ce o

f th

e sy

stem

. Th

e m

echa

nica

l effe

cts

of s

tatic

load

ing

that

occ

ur a

t int

erfa

ces

betw

een

mat

eria

ls in

the

empl

acem

ent d

rift a

re n

ot s

igni

fican

t to

the

post

clos

ure

perfo

rman

ce o

f the

repo

sito

ry.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

6.07

.0B

No

Non

-ITB

C:

Em

plac

emen

t Pal

let

Mat

eria

ls, P

rope

rties

,an

d C

onfig

urat

ion

Was

te P

acka

geM

ater

ials

, Pro

perti

es,

and

Con

figur

atio

n

Non

-ITB

C:

Em

plac

emen

t Pal

let D

esig

nE

mpl

acem

ent P

alle

t Fun

ctio

nE

mpl

acem

ent P

alle

t Fa

bric

atio

n an

d C

orro

sion

Al

low

ance

W

aste

Pac

kage

and

E

mpl

acem

ent P

alle

t Sta

tic

Stre

sses

As-

Em

plac

ed W

aste

C

onfig

urat

ion

/ Was

te

Pac

kage

Out

er B

arrie

rM

ater

ial S

peci

ficat

ions

ANL-WIS-MD-000024 REV 01 ACN 01 A-146 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Inve

rt 1.

2.03

.02.

0A

Sei

smic

Gro

und

Mot

ion

Dam

ages

EB

S C

ompo

nent

sIn

clud

ed

Vibr

ator

y gr

ound

mot

ion

has

the

pote

ntia

l to

dam

age

the

stee

l fra

mew

ork

and

balla

st in

the

inve

rt. T

he

fram

ewor

k in

the

inve

rt is

car

bon

stee

l tha

t is

expe

cted

to c

orro

de q

uick

ly in

the

moi

st, i

n-dr

ift

envi

ronm

ent.

The

resp

onse

of t

he s

teel

fram

ewor

k is

th

eref

ore

not I

TBC

, with

or w

ithou

t sei

smic

eve

nts.

Th

e ba

llast

in th

e in

vert

is a

n en

gine

ered

mat

eria

l tha

t w

ill b

e pr

oduc

ed fr

om c

rush

ed tu

ff ge

nera

ted

durin

g m

inin

g op

erat

ions

. Th

is c

rush

ed tu

ff is

a h

ighl

ypo

rous

mat

eria

l tha

t may

set

tle o

r com

pact

dur

ing

a se

ism

ic e

vent

, but

is n

ot c

onsi

dere

d to

pro

vide

a

sign

ifica

nt b

arrie

r cap

abili

ty in

com

paris

on to

the

inta

ct tu

ff in

the

unsa

tura

ted

zone

sur

roun

ding

the

empl

acem

ent d

rifts

. Th

e re

spon

se o

f inv

ert t

o vi

brat

ory

grou

nd m

otio

n is

th

eref

ore

not I

TBC

. FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.2

.03.

02.0

A

No

Non

-ITB

C:

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

nP

rope

rties

of t

he

Hos

t Roc

k U

nit

Cha

ract

eriz

atio

n of

Ig

neou

s E

vent

s

Non

-ITB

C:

Inve

rt M

ater

ials

Em

plac

emen

t Drif

t Inv

ert

Con

figur

atio

nE

mpl

acem

ent D

rift I

nver

t Fu

nctio

n

Ver

ifica

tion

of D

esig

n R

ock

Pro

perti

es

Rep

osito

ry G

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Rep

osito

ry E

leva

tion

-O

verb

urde

n Th

ickn

ess

Inve

rt 2.

1.06

.05.

0B

Mec

hani

cal

Deg

rada

tion

of In

vert

Excl

uded

Mec

hani

cal d

egra

datio

n of

the

inve

rt do

es n

ot

sign

ifica

ntly

affe

ct th

e ca

pabi

lity

of th

e ot

her E

BS

fe

atur

es, n

or w

ould

suc

h ch

ange

s af

fect

the

radi

onuc

lide

mig

ratio

n ra

te th

roug

h th

e in

vert

to th

e ed

ge o

f the

EB

S, b

ecau

se c

hang

es in

inve

rt ba

llast

po

rosi

ty d

o no

t sig

nific

antly

affe

ct th

e ra

dion

uclid

e tra

nspo

rt ch

arac

teris

tics.

S

eism

ical

ly in

duce

d ch

ange

s to

the

inve

rt, a

nd th

e ef

fect

from

dea

d lo

adin

g du

e to

drif

t col

laps

e, a

re

cons

ider

ed s

epar

atel

y (s

ee F

EP

1.2

.03.

02.0

A).

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

6.05

.0B

No

Non

-ITB

C:

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

Non

-ITB

C:

As-

empl

aced

Was

te

Pac

kage

-Drip

Shi

eld

Con

figur

atio

nIn

vert

and

EB

S C

ompo

nent

s in

Situ

Stre

ss a

nd T

herm

al

Res

pons

e E

mpl

acem

ent D

rift I

nver

t C

onfig

urat

ion

Em

plac

emen

t Drif

t Inv

ert

Func

tion

Inve

rt M

ater

ials

Inve

rt 2.

1.06

.05.

0D

Che

mic

al

Deg

rada

tion

of In

vert

Excl

uded

The

crus

hed

tuff

inve

rt ba

llast

mat

eria

l is

not s

ubje

ct

to d

isso

lutio

n or

wea

ther

ing

proc

esse

s th

at c

ould

si

gnifi

cant

ly c

hang

e its

hyd

rolo

gica

l, m

echa

nica

l, or

ra

dion

uclid

e tra

nspo

rt ch

arac

teris

tics.

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.1

.06.

05.0

D

No

Non

-ITB

C:

Inve

rt M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

Non

-ITB

C:

EB

S D

rip S

hiel

d /

Em

plac

emen

t Drif

t Inv

ert

Mat

eria

ls In

tera

ctio

nsIn

vert

Mat

eria

lsE

mpl

acem

ent D

rift I

nver

t C

onfig

urat

ion

ANL-WIS-MD-000024 REV 01 ACN 01 A-148 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-2.

ITB

C A

naly

ses

of E

ngin

eere

d B

arrie

r Sys

tem

FE

Ps

(Con

tinue

d)

Feat

ure

FEP

Num

ber,

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es to

ITB

C1

Cor

e Pa

ram

eter

C

hara

cter

istic

2 C

ontr

ol P

aram

eter

C

hara

cter

istic

3

Inve

rt 2.

1.09

.13.

0A

Com

plex

atio

n in

EB

SEx

clud

ed

Che

mic

al a

nd b

iolo

gica

l con

ditio

ns th

at c

ould

co

ntrib

ute

to c

ompl

exat

ion

of ra

dion

uclid

es in

the

inve

rt w

ill no

t occ

ur o

r will

be

pres

ent t

o su

ch li

mite

dex

tent

as

to n

ot e

nhan

ce th

e ra

tes

of tr

ansp

ort o

f ra

dion

uclid

es re

leas

ed fr

om th

e w

aste

pac

kage

. Th

eref

ore,

com

plex

atio

n ef

fect

s in

the

inve

rt ar

e ne

glig

ible

from

a b

arrie

r cap

abilit

y pe

rspe

ctiv

e.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

9.13

.0A

No

Non

-ITB

C:

In-d

rift C

hem

ical

Env

ironm

ent

Was

te P

acka

geS

ourc

e Te

rm,

Inve

ntor

y, In

vent

ory

Dec

ay, a

nd D

ecay

Hea

tIn

vert

Mat

eria

lsP

rope

rties

, and

Con

figur

atio

nR

adio

nucl

ide

Inve

ntor

y an

d S

ourc

e-Te

rm

Pro

perti

es

Non

-ITB

C:

Was

te P

acka

ge a

nd T

AD

C

anis

ter E

xclu

ded

Mat

eria

lsC

omm

itted

Mat

eria

ls

Inve

rt 2.

1.09

.19.

0A

Sor

ptio

n of

Col

loid

s in

EB

SEx

clud

ed

Alth

ough

col

loid

s co

uld

pote

ntia

lly s

orb

on in

vert

balla

st m

ater

ials

, thu

s re

duci

ng th

e ra

te o

f ra

dion

uclid

e re

leas

e, th

is s

orpt

ion

is s

mal

l and

, be

caus

e th

e tra

vel p

ath

thro

ugh

the

inve

rt is

sho

rt co

mpa

red

with

that

thro

ugh

the

unsa

tura

ted

zone

be

low

the

repo

sito

ry, i

s re

lativ

ely

insi

gnifi

cant

. Fo

r ps

eudo

-col

loid

s to

whi

ch ra

dion

uclid

es a

re re

vers

ibly

sorb

ed, s

orpt

ion

of th

e ca

rrier

par

ticle

s ha

s lim

ited

effe

ct o

n ra

dion

uclid

e tra

nspo

rt. B

ecau

se o

f the

limite

d af

fect

on

barri

er p

erfo

rman

ce, c

ollo

id s

orpt

ion

is e

xclu

ded

from

the

TSP

A (S

NL

2008

[DIR

S 1

8304

1]

– 2.

1.09

.19.

0A) a

nd th

e pr

oces

s is

not

ITB

C.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.1.0

9.19

.0A

No

Non

-ITB

C:

In-D

rift C

hem

ical

Env

ironm

ent

In-D

rift T

herm

al

Env

ironm

ent

Con

vect

ion,

C

onde

nsat

ion,

and

Ev

apor

atio

n R

adio

nucl

ide

Inve

ntor

y an

d S

ourc

e-Te

rm

Pro

perti

es

Inve

rt M

ater

ials

Pro

perti

es, a

ndC

onfig

urat

ion

Was

te F

orm

Deg

rada

tion

Cor

rosi

on P

rodu

cts

Pro

perti

es

Was

teFo

rm/P

acka

ge

Inte

rnal

s M

ater

ials

,P

rope

rties

, and

Con

figur

atio

n

Non

e

ANL-WIS-MD-000024 REV 01 ACN 01 A-154 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-3.

ITB

C A

naly

sis

of L

ower

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Feat

ure

/ C

ompo

nent

FEP

Num

ber

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es

to IT

BC

1 C

ore

Para

met

er

Cha

ract

eris

tic2

Con

trol

Par

amet

er

Cha

ract

eris

tic3

Uns

atur

ated

Zone

Bel

ow th

e R

epos

itory

1.2.

04.0

2.0A

Ig

neou

s A

ctiv

ity

Cha

nges

Roc

kP

rope

rties

Ex

clud

ed

Stu

dies

of n

atur

al a

nalo

gue

site

s sh

ow th

at th

e ef

fect

of u

nlik

ely

intru

sive

igne

ous

even

ts is

gen

eral

ly to

alte

r the

pro

perti

es in

the

imm

edia

te v

icin

ity (a

few

met

ers)

from

the

intru

sive

sill

or d

ike.

Th

ese

chan

ges

(whi

ch m

ay b

e in

crea

ses

or d

ecre

ases

in

perm

eabi

lity

and

poro

sity

) are

of s

uch

limite

d sp

atia

l ext

ent.

Inad

ditio

n, b

ecau

se d

ikes

wou

ld b

e ne

arly

ver

tical

, the

form

atio

n of

a

sign

ifica

nt p

erch

ed w

ater

zon

e as

soci

ated

with

a d

ike

is n

otex

pect

ed.

Furth

erm

ore,

alth

ough

late

ral d

iver

sion

and

form

atio

n of

pe

rche

d w

ater

occ

urs

whe

re th

e TS

w c

onta

cts

the

zeol

itic

CH

n,

trans

port

sens

itivi

ty a

naly

ses

indi

cate

that

mos

t of t

he d

elay

in

radi

onuc

lide

mov

emen

t to

the

wat

er ta

ble

occu

rs w

ithin

the

TSw

and

ab

ove

the

zone

of s

trong

late

ral d

iver

sion

. H

ence

, any

cha

nges

in

pote

ntia

l lat

eral

div

ersi

on re

sulti

ng fr

om d

ikes

wou

ld h

ave

negl

igib

le

effe

cts

on ra

dion

uclid

e tra

nspo

rt tim

es.

Oth

er u

nsat

urat

ed z

one

flow

and

trans

port

sens

itivi

ty a

naly

ses

prov

ide

addi

tiona

l sup

port

that

ra

dion

uclid

e tra

nspo

rt be

twee

n th

e re

posi

tory

and

the

wat

er ta

ble

is

inse

nsiti

ve to

cha

nges

in fa

ult p

rope

rties

. Th

eref

ore,

igne

ous

activ

ity-in

duce

d ro

ck p

rope

rty c

hang

es d

o no

t sig

nific

antly

affe

ct th

e ca

pabi

litie

s of

the

unsa

tura

ted

zone

bel

ow th

e re

posi

tory

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.2

.04.

02.0

A

No

Non

-ITB

C:

Cha

ract

eriz

atio

n of

Ig

neou

s E

vent

s U

nsat

urat

ed Z

one

Pro

perti

es

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Uns

atur

ated

Zone

Bel

ow th

e R

epos

itory

1.2.

04.0

5.0A

M

agm

a or

Pyr

ocla

stic

Bas

e Su

rge

Tran

spor

ts

Was

teEx

clud

ed

The

trans

port

of w

aste

thro

ugh

the

UZ

by m

agm

a or

pyr

ocla

stic

bas

e su

rge

follo

win

g an

unl

ikel

y er

uptiv

e ig

neou

s ev

ent i

s in

sign

ifica

nt

com

pare

d to

are

al tr

ansp

ort o

f the

was

te re

sulti

ng fr

om a

sh a

nd

teph

ra e

rupt

ion

that

is in

clud

ed in

per

form

ance

ass

essm

ent.

FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.2

.04.

05.0

A

No

Non

-ITB

C:

Cha

ract

eriz

atio

n of

Ig

neou

s E

vent

s

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Uns

atur

ated

Zone

Bel

ow th

e R

epos

itory

1.2.

04.0

6.0A

E

rupt

ive

Con

duit

to S

urfa

ceIn

ters

ects

Rep

osito

ryIn

clud

ed

Eve

n th

ough

the

poss

ibili

ty o

f an

erup

tive

cond

uit i

nter

sect

ing

the

repo

sito

ry a

nd e

xten

ding

to th

e su

rface

has

bee

n in

clud

ed in

the

perfo

rman

ce a

sses

smen

t, th

e nu

mbe

r of w

aste

pac

kage

s po

tent

ially

in

ters

ecte

d by

suc

h an

eve

nt (S

NL

2007

[DIR

S 1

7743

2], S

ectio

n 7.

2)

is c

onsi

dere

d an

insi

gnifi

cant

con

tribu

tor t

o th

e do

se to

the

reas

onab

ly m

axim

ally

exp

osed

indi

vidu

al (R

ME

I).

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.2.0

4.06

.0A

No

Non

-ITB

C:

Cha

ract

eriz

atio

n of

Ig

neou

s E

vent

s

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Orie

ntat

ion

of

Em

plac

emen

t Drif

tsE

mpl

acem

ent D

rift

Spac

ing

ANL-WIS-MD-000024 REV 01 ACN 01 A-169 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-3.

ITB

C A

naly

sis

of L

ower

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Uns

atur

ated

Zone

Bel

ow th

e R

epos

itory

2.2.

10.0

7.0A

Th

erm

o­ch

emic

al

Alte

ratio

n of

the

Cal

ico

Hill

s U

nit

Excl

uded

Ther

mo-

chem

ical

alte

ratio

n of

the

Cal

ico

Hill

s un

it co

uld

affe

ct

unsa

tura

ted

zone

flow

and

tran

spor

t by:

(1)

min

eral

dis

solu

tion

and

prec

ipita

tion,

whi

ch w

ould

cha

nge

the

fract

ure

poro

sity

and

pe

rmea

bilit

y of

the

fract

ure

netw

ork;

(2) c

hang

ing

the

fract

ure-

mat

rixin

tera

ctio

n th

roug

h th

e A

ctiv

e Fr

actu

re M

odel

�; o

r (3)

cha

ngin

g th

e so

rptio

n co

effic

ient

(Kd )

thro

ugh

min

eral

dis

solu

tion

and

prec

ipita

tion

on th

e fra

ctur

e w

all s

urfa

ces.

How

ever

, sen

sitiv

ity a

naly

ses

indi

cate

th

at:

(a) c

hang

es to

frac

ture

per

mea

bilit

y of

the

CH

n ha

ve a

muc

h le

ss e

ffect

than

var

iatio

ns in

infil

tratio

n ra

tes;

and

(b) c

hang

es in

γ o

r K

d val

ues

of th

e C

Hn

do n

ot s

igni

fican

tly a

ffect

radi

onuc

lide

brea

kthr

ough

, as

trans

port

in th

e u

nsat

urat

ed z

one

is c

ontro

lled

byth

e ov

erly

ing

TSw

uni

t. M

odel

s sh

ow th

at e

leva

tion

of th

e re

posi

tory

abov

e th

e C

Hn

ensu

res

that

the

CH

n w

ill n

ot b

e he

ated

to

tem

pera

ture

rang

es th

at w

ould

cau

se s

igni

fican

t dew

ater

ing

of

zeol

ites

(see

des

crip

tion

of F

EP

2.2

.10.

14.0

A, M

iner

alog

ic

Deh

ydra

tion

Rea

ctio

ns).

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 2

.2.1

0.07

.0A

No

Non

-ITB

C:

Uns

atur

ated

Zon

e C

hem

ical

E

nviro

nmen

t In

-Drif

t The

rmal

E

nviro

nmen

t, C

onve

ctio

n,

Con

dens

atio

n, a

nd

Evap

orat

ion

Uns

atur

ated

Zon

e P

rope

rties

U

nsat

urat

ed Z

one

Tran

spor

t W

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Non

-ITB

C:

Drif

t Wal

lTe

mpe

ratu

re

Was

te P

acka

geSp

acin

g R

epos

itory

Sta

ndof

f fro

m th

e C

Hn

Uni

t

Uns

atur

ated

Zone

Bel

ow th

e R

epos

itory

2.2.

10.0

9.0A

Th

erm

o­ch

emic

al

Alte

ratio

n of

the

Topo

pah

Sprin

gB

asal

Vitr

ophy

reEx

clud

ed

Flui

d in

clus

ion

data

and

ther

mal

his

tory

ana

lysi

s sh

ow th

at th

e cu

rrent

deg

ree

of a

ltera

tion

in T

Sw

bas

al v

itrop

here

resu

lted

from

ex

posu

re to

tem

pera

ture

s of

up

to 8

0-95

ºC fo

r a lo

ng p

erio

d of

tim

e (a

milli

on y

ears

). In

com

paris

on, t

he p

ostc

losu

re th

erm

al p

ulse

will

be

ver

y br

ief r

elat

ive

to th

e ex

tend

ed th

erm

al h

isto

ry o

f the

mou

ntai

n,

and

drift

wal

l tem

pera

ture

s dr

op b

elow

50º

C in

less

than

20,

000

year

s, a

nd w

ill h

ave

little

effe

ct o

n th

e ab

unda

nce

of s

econ

dary

min

eral

s in

the

TSw

bas

al v

itrop

hyre

. Th

eref

ore,

ther

mal

ly-in

duce

d al

tera

tion

of th

is u

nit w

ill be

lim

ited

and

will

not

sig

nific

antly

affe

ct th

e so

rptiv

e or

hyd

rolo

gic

prop

ertie

s of

the

units

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

2.2

.10.

09.0

A

No

Non

-ITB

C:

Uns

atur

ated

Zon

e C

hem

ical

E

nviro

nmen

t In

-Drif

t The

rmal

E

nviro

nmen

t, C

onve

ctio

n,

Con

dens

atio

n, a

nd

Evap

orat

ion

Uns

atur

ated

Zon

e P

rope

rties

U

nsat

urat

ed Z

one

Tran

spor

t W

aste

Pac

kage

Sou

rce

Term

, In

vent

ory,

Inve

ntor

yD

ecay

, and

Dec

ayH

eat

Non

-ITB

C:

Drif

t Wal

lTe

mpe

ratu

re

Was

te P

acka

geSp

acin

g

ANL-WIS-MD-000024 REV 01 ACN 01 A-186 March 2008

Postclosure Nuclear Safety Design Bases

Tabl

e A

-3.

ITB

C A

naly

sis

of L

ower

Nat

ural

Bar

rier F

EP

s (C

ontin

ued)

Feat

ure

/ C

ompo

nent

FEP

Num

ber

Nam

e, a

nd

Scre

enin

g D

ecis

ion

Dis

cuss

ion

of E

ffect

on

Bar

rier C

apab

ility

R

elat

es

to IT

BC

1 C

ore

Para

met

er

Cha

ract

eris

tic2

Con

trol

Par

amet

er

Cha

ract

eris

tic3

Sat

urat

ed Z

one

1.4.

01.0

1.0A

C

limat

eM

odifi

catio

n In

crea

ses

Rec

harg

e In

clud

ed

The

incr

ease

in re

char

ge a

ssoc

iate

d w

ith fu

ture

clim

ate

stat

es

sign

ifica

ntly

incr

ease

s th

e gr

ound

wat

er fl

ux th

roug

h th

e tu

ff an

d al

luvi

al w

ater

-con

duct

ing

feat

ures

, whi

ch re

duce

s th

e ef

fect

iven

ess

of th

e ba

rrier

cap

abili

ty o

f thi

s fe

atur

e. T

his

effe

ct is

inco

rpor

ated

in

to th

e sa

tura

ted

zone

flow

and

tran

spor

t mod

el, a

nd is

det

erm

ined

to

be

ITB

C b

ecau

se o

f its

sig

nific

ant c

ontri

butio

n to

the

barri

er

capa

bilit

y of

the

satu

rate

d zo

ne.

FEP

Sour

ce:

SNL

2008

[DIR

S 18

3041

] – 1

.4.0

1.01

.0A

Yes

IT

BC

:S

atur

ated

Zon

eP

rope

rties

S

atur

ated

Zon

e Fl

owE

xten

t of S

atur

ated

Zo

ne

Non

-ITB

C:

Rep

osito

ryG

eogr

aphi

c an

d G

eolo

gic

Loca

tion

Rep

osito

ry E

leva

tion

abov

e th

e W

ater

Ta

ble

Sat

urat

ed Z

one

1.4.

07.0

2.0A

W

ells

Incl

uded

The

effe

ct o

f pum

ping

wel

ls o

n sa

tura

ted

zone

gro

undw

ater

flow

has

be

en in

corp

orat

ed in

to th

e S

ite-S

cale

SZ

Flow

Mod

el v

ia th

e co

nfig

urat

ion

of th

e w

ater

tabl

e us

ed a

s an

upp

er b

ound

ary

and

the

flow

rate

s ac

ross

the

mod

el b

ound

arie

s as

pro

vide

d by

the

Dea

th

Val

ley

regi

onal

mod

el.

The

regi

onal

mod

el s

peci

fical

ly in

corp

orat

edth

e irr

igat

ion

wel

ls lo

cate

d so

uth

of Y

ucca

Mou

ntai

n in

Am

argo

sa

Val

ley.

In

addi

tion,

mea

sure

d w

ater

leve

ls fr

om th

ese

exis

ting

wel

ls

are

used

in th

e ca

libra

tion

of th

e S

ite-S

cale

SZ

Flow

Mod

el.

Furth

erm

ore,

the

effe

cts

of w

ells

on

the

dose

to th

e R

ME

I are

in

clud

ed in

to th

e TS

PA

by

assu

min

g al

l of t

he ra

dion

uclid

e m

ass

that

re

ache

s th

e 18

-km

acc

essi

ble

envi

ronm

ent,

is c

onta

ined

in th

e re

pres

enta

tive

volu

me

of g

roun

dwat

er fr

om w

hich

the

RM

EI o

btai

ns

all r

equi

red

wat

er.

The

effe

cts

of w

ells

are

not

ITBC

for t

he

satu

rate

d zo

ne b

ecau

se w

ells

dril

led

for d

omes

tic o

r agr

icul

tura

l use

ar

e no

t ant

icip

ated

to s

igni

fican

tly a

ffect

gro

undw

ater

flow

or

radi

onuc

lide

mov

emen

t due

to th

e th

eir l

arge

dis

tanc

es a

way

from

th

e pr

edom

inan

t flo

w p

aths

.FE

P So

urce

:SN

L 20

08 [D

IRS

1830

41] –

1.4

.07.

02.0

A

No

Non

-ITB

C:

Sat

urat

ed Z

one

prop

ertie

s S

atur

ated

Zon

e Fl

ow

Non

-ITB

C:

Non

e

ANL-WIS-MD-000024 REV 01 ACN 01 A-195 March 2008