ANL-WIS-MD-000024, Rev. 01, ACN: 01, 'Postclosure Nuclear Safety Design … · 2012-12-01 ·...
Transcript of ANL-WIS-MD-000024, Rev. 01, ACN: 01, 'Postclosure Nuclear Safety Design … · 2012-12-01 ·...
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