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-
ES-401 FORM ES-401-1
BWR SRO EXAMINATION OUTLINE
Facility: GRAND GULF NUCLEAR STATION Date of Exam: 6 FEBRUARY 2004 K/A CATEGORY
POINTS
TIER GROUP K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G *
POINT TOTAL
1. 1 6 3 2 8 3 4 26 Emergency &
Abnormal 2 0 2 3 4 5 3 17 Plant
Evolutions TIER TOTAL
6 5 5 12 8 7 43
1 1 1 3 3 0 3 3 1 1 3 4 23 2.
Plant 2 1 1 1 0 3 2 0 2 2 0 1 13 Systems
3 0 0 0 0 0 1 1 1 0 1 0 4 TIER
TOTAL 2 2 4 3 3 6 4 4 3 4 5 40
CAT 1 CAT 2 CAT 3 CAT 4 3. Generic Knowledge & Abilities 5 4 2 6 17
Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier
(i.e., the “Tier Totals” in each K/A category shall not be less than two) 2. The point total for each group and tier in the proposed outline must match that specified
in the table. The final point total for each group and tier may deviate by ± 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant specific priorities.
4. Systems / evolutions within each group are identified on the associated outline. 5. The shaded areas are not applicable to the category tier. 6.* The generic K/As in Tiers 1 and 2 shall be selected from section 2 of the K/A Catalog,
but the topics must be relevant to the applicable evolution or system. 7. On the following pages, enter the K/A numbers, a brief description of each topic, the
topics’ importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
REVISION 0 11/5/2003 NUREG 1021, REVISION 8 SUPPLEMENT 1
-
GR
AN
D G
UL
F N
UC
LE
AR
ST
AT
ION
FE
BR
UA
RY
200
4
B
WR
SR
O E
XA
MIN
AT
ION
OU
TL
INE
E
ME
RG
EN
CY
& A
BN
OR
MA
L P
LA
NT
E
VO
LU
TIO
NS
- TIE
R 1
GR
OU
P 1
ES-
401-
1
E/A
PE #
/NA
ME
/SA
FET
Y F
UN
CT
ION
K 1
K 2 K 3
A 1 A 2
G
T
OPI
C(S
)IM
P SR
O/R
O/B
OT
H
RE
C#
R
EL
AT
ED
K
/A
OR
IGIN
NO
TE
S:
2950
03 P
artia
l or C
ompl
ete
Loss
of A
C P
ower
/ 6
CFR
41.7
02
Giv
en p
lant
con
ditio
ns d
escr
ibe
the
diffe
renc
e of
how
lo
ads o
n B
OP
and
ESF
buss
es a
re re
mov
ed a
nd
subs
eque
ntly
rest
ored
dur
ing
unde
rvol
tage
con
ditio
ns.
3.1
A
K1.
02: 3
.4A
K1.
03: 3
.2
AK
2.03
: 3.9
A
K3.
01: 3
.5
AK
3.03
: 3.6
A
A1.
01: 3
.8
2950
06 S
CR
AM
/ 1
CFR
41.5
03
Giv
en c
ondi
tions
of a
reac
tor s
cram
, des
crib
e th
e re
spon
se o
f the
Tur
bine
Pre
ssur
e C
ontro
l Sys
tem
. 3.
7
AK
2.07
: 4.1
AA
2.04
: 4.1
29
5007
Hig
h R
eact
or P
ress
ure
/ 3
CFR
41.6
01
Giv
en R
eact
or p
ress
ure,
det
erm
ine
syst
ems a
vaila
ble
to
inje
ct in
to th
e R
PV fo
r lev
el c
ontro
l. 3.
2
AK
2.03
: 3.2
AK
2.04
: 3.3
29
5009
Low
Rea
ctor
Wat
er L
evel
/ 2
CFR
41.4
/41.
5/41
.7/4
3.5
02
G
iven
a st
eam
flow
/ fe
ed fl
ow m
ism
atch
and
pla
nt
cond
ition
s, de
term
ine
the
reac
tor w
ater
leve
l res
pons
e an
d re
spon
se o
f Rea
ctor
Wat
er L
evel
con
trol.
3.7
MO
DN
RC
8/
2002
2950
10 H
igh
Dry
wel
l Pre
ssur
e / 5
C
FR41
.4/4
1.5
05
G
iven
pla
nt p
aram
eter
s, de
term
ine
the
affe
cts o
n D
ryw
ell
Pres
sure
. (Lo
ss o
f coo
ling
to th
e D
ryw
ell C
hille
d W
ater
Sy
stem
with
the
plan
t at p
ower
.)
3.8
22
3001
K6.
01: 3
.8
A4.
12: 3
.6
MO
D
NR
C
3/19
98
2950
13 H
igh
Supp
ress
ion
Pool
Wat
er T
emp.
/ 5
CFR
41.1
0/43
.2/4
3.5
01
D
urin
g a
surv
eilla
nce
oper
atin
g R
CIC
, det
erm
ine
how
of
ten
Supp
ress
ion
Pool
Tem
pera
ture
is re
quire
d to
be
mon
itore
d an
d th
e th
resh
old
for a
ltern
ate
actio
ns.
4.0
AA
1.02
: 3.9
2.
1.33
: 4.0
2.
4.4:
4.3
MO
D
NR
C
8/20
02
2950
14 I
nadv
erte
nt R
eact
ivity
Add
ition
/ 1
CFR
41.1
/41.
2/41
.6/4
3.6
2.
1. 30
With
the
reac
tor i
n st
artu
p co
nditi
ons s
uch
that
the
reac
tor
is c
lose
to c
ritic
ality
, wha
t are
the
oper
ator
act
ions
if a
hi
gh w
orth
con
trol r
od is
with
draw
n.
3.4
AA
1.04
: 3.3
AA
2.02
: 3.9
A
A2.
03: 4
.3
2.1.
2: 4
.0
Pi
lgrim
even
t2/
2003
2950
15 I
ncom
plet
e SC
RA
M /
1 C
FR41
.6/4
3.5
04
G
iven
con
trol p
anel
indi
catio
ns, d
eter
min
e th
e ca
use
prev
entin
g fu
ll in
serti
on o
f con
trol r
ods u
nder
scra
m
cond
ition
s.
3.7
A
A1.
01: 3
.9A
A1.
02: 4
.2
2.1.
31: 3
.9
2950
16 C
ontro
l Roo
m A
band
onm
ent /
7
CFR
41.7
05
Giv
en a
loss
of D
C e
lect
rical
pow
er, d
escr
ibe
the
stat
us o
f op
erat
ion
of th
e Sa
fety
Rel
ief V
alve
s ope
rate
d fr
om th
e R
emot
e Sh
utdo
wn
Pane
ls.
2.9
2950
17 H
igh
Offs
ite R
elea
se R
ate
/ 9
CFR
41.1
1/41
.13/
43.4
01
With
a re
leas
e of
radi
oact
ive
mat
eria
l in
prog
ress
, de
term
ine
the
resp
onse
of s
yste
ms t
o pr
otec
t the
safe
ty o
f co
ntro
l roo
m p
erso
nnel
and
mai
ntai
n ha
bita
bilit
y.
3.9
A
K3.
05: 3
.6
PAG
E 1
TOTA
L TI
ER 1
GR
OU
P 1
1 1
2 3
2 1
PAG
E TO
TAL
# Q
UES
TIO
NS
10
R
EVIS
ION
0 1
1/5/
2003
PA
GE
1 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
E
EM
ER
GE
NC
Y &
AB
NO
RM
AL
PL
AN
T
EV
OL
UT
ION
S - T
IER
1 G
RO
UP
1
CO
NT
.
ES-
401-
1
E/A
PE #
/NA
ME
/SA
FET
Y F
UN
CT
ION
K 1
K 2 K 3
A 1 A 2
G
T
OPI
C(S
)IM
P SR
O/R
O/B
OT
H
RE
C#
R
EL
AT
ED
K
/A
OR
IGIN
NO
TE
S:
2950
23 R
efue
ling
Acc
iden
ts /
8
CFR
41.4
/41.
5/41
.10/
43.5
/43.
7
02
With
a R
efue
ling
outa
ge in
pro
gres
s, de
term
ine
the
effe
cts o
f a lo
ss o
f Fue
l Poo
l Coo
ling
and
Cle
anup
on
the
Fuel
Sto
rage
poo
ls.
3.1
2950
24 H
igh
Dry
wel
l Pre
ssur
e / 5
C
FR41
.7/4
1.10
/43.
5
06
Giv
en a
hig
h dr
ywel
l pre
ssur
e co
nditi
on, d
eter
min
e th
e op
erat
ion
of th
e D
ivis
iona
l Die
sel G
ener
ator
s. 4.
0
EA1.
06: 3
.7
2950
25 H
igh
Rea
ctor
Pre
ssur
e / 3
C
FR41
.5/4
1.6/
41.7
04
With
a ri
sing
reac
tor p
ress
ure,
det
erm
ine
the
resp
onse
of
the
RPS
and
ATW
S A
RI/R
PT.
4.1
EK2.
01: 4
.1
2950
26 S
uppr
essi
on P
ool H
igh
Wat
er T
emp.
/ 5
CFR
41.1
0/41
.12/
43.4
/43.
5
2.
3. 2
With
RH
R o
pera
ting
in S
uppr
essi
on P
ool C
oolin
g in
re
spon
se to
a h
igh
Supp
ress
ion
Pool
Tem
pera
ture
, de
scrib
e th
e ba
sis f
or c
onta
ctin
g R
adia
tion
Prot
ectio
n pe
rson
nel.
2.9
2.1.
32: 3
.8M
OD
NR
C
6/20
01
2950
27 H
igh
Con
tain
men
t Tem
pera
ture
/ 5
CFR
41.9
/41.
10/4
3.2/
43.5
03
Det
erm
ine
the
Con
tain
men
t Tem
pera
ture
at w
hich
Em
erge
ncy
Dep
ress
uriz
atio
n is
requ
ired.
3.
8
EK3.
01: 3
.8
2950
30 L
ow S
uppr
essi
on P
ool W
ater
Lev
el /
5 C
FR41
.8/4
1.10
/43.
5 02
Det
erm
ine
the
Supp
ress
ion
Pool
Wat
er le
vel a
t whi
ch
ECC
S pu
mp
NPS
H is
que
stio
nabl
e.
3.8
2950
31 R
eact
or L
ow W
ater
Lev
el /
2
CFR
41.2
/41.
3/41
.10/
41.1
4/43
.5
01
G
iven
pla
nt c
ondi
tions
and
a lo
w re
acto
r wat
er le
vel,
dete
rmin
e co
re c
oolin
g m
echa
nism
and
ade
quac
y.
4.7
2.
1.1:
3.8
2.4.
6: 4
.0
2.4.
18: 3
.6
2.4.
21: 4
.3
MO
D
NR
C
8/20
02
2950
37 S
CR
AM
Con
ditio
n Pr
esen
t and
Rea
ctor
Po
wer
Abo
ve A
PRM
Dow
nsca
le o
r Unk
now
n / 1
C
FR41
.10/
43.5
2. 4. 40
Giv
en A
TWS
cond
ition
s, de
term
ine
the
Emer
genc
y Pl
an
Emer
genc
y A
ctio
n Le
vel.
4.0
2.4.
41: 4
.1
A
lert
vs. S
ite
Are
a Em
erge
ncy
2950
38 H
igh
Offs
ite R
elea
se R
ate
/ 9
CFR
41.1
0/41
.12/
43.4
/43.
5
02
Giv
en m
eteo
rolo
gica
l dat
a, m
aps a
nd a
radi
oact
ive
rele
ase,
det
erm
ine
prot
ectiv
e ac
tion
reco
mm
enda
tions
to
be is
sued
.
3.8
2.4.
44: 4
.0
5000
00 H
igh
Con
tain
men
t Hyd
roge
n C
onc.
/ 5
CFR
41.9
01
Det
erm
ine
the
base
s for
the
Hyd
roge
n C
ontro
l leg
of E
P-3.
3.
9
2950
31 R
eact
or L
ow W
ater
Lev
el /
2 C
FR41
.7/4
1.10
/43.
5
2.
1. 31
Det
erm
ine
actu
al re
acto
r wat
er le
vel w
hen
oper
atin
g fr
om
the
Rem
ote
Shut
dow
n Pa
nels
usi
ng th
e as
soci
ated
gra
phs
and
give
n in
dica
tions
.
3.9
EK
2.01
: 4.4
EA
2.01
: 4.6
2.
1.25
: 3.1
2.
4.11
: 3.6
MO
D
NR
C
8/20
02
PAG
E 2
TOTA
L TI
ER 1
GR
OU
P 1
3 2
0 3
0 3
PAG
E TO
TAL
# Q
UES
TIO
NS
11
R
EVIS
ION
0 1
1/5/
2003
PA
GE
2 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
E
EM
ER
GE
NC
Y &
AB
NO
RM
AL
PL
AN
T
EV
OL
UT
ION
S - T
IER
1 G
RO
UP
1
CO
NT
.
ES-
401-
1
E/A
PE #
/NA
ME
/SA
FET
Y F
UN
CT
ION
K 1
K 2 K 3
A 1 A 2
G
T
OPI
C(S
)IM
P
SRO
/RO
/B
OT
H
RE
C#
RE
LA
TE
D
K/A
O
RIG
IN
N
OT
ES:
2950
25 H
igh
Rea
ctor
Pre
ssur
e / 3
C
FR41
.4/4
1.5/
41.1
4
05
Giv
en p
lant
con
ditio
ns, d
escr
ibe
the
resp
onse
of R
CIC
to
a ris
ing
reac
tor p
ress
ure.
3.
7
21
7000
A
1.04
: 3.6
2950
17 H
igh
Off-
Site
Rel
ease
Rat
e / 9
C
FR41
.10/
41.1
3/43
.2/4
3.4/
43.5
01
With
a li
quid
radw
aste
dis
char
ge re
quire
d an
d a
disc
harg
e pe
rmit,
det
erm
ine
whe
ther
a re
leas
e is
allo
wed
. 3.
1
2.3.
3: 2
.92.
3.6:
3.1
29
5015
Inc
ompl
ete
SCR
AM
/ 1
CFR
41.1
/41.
2/41
.5/4
3.6
04
D
escr
ibe
the
reac
tion
of th
e co
re w
ith a
n A
TWS
and
low
erin
g of
reac
tor p
ress
ure.
3.
8
A
K1.
02: 4
.1M
OD
NR
C
4/20
00
2950
30 L
ow S
uppr
essi
on P
ool W
ater
Lev
el /
5 C
FR41
.7/4
1.9/
41.1
0/43
.5
01
G
iven
the
failu
re o
f Con
trol R
oom
Sup
pres
sion
Poo
l Le
vel i
ndic
atio
n, d
eter
min
e Su
ppre
ssio
n Po
ol le
vel u
sing
al
tern
ate
mea
ns.
4.2
2.
1.25
: 3.1
2.4.
21: 4
.3
EO
P2
Atta
chm
ent 2
9
2950
26 S
uppr
essi
on P
ool H
igh
Wat
er T
emp.
/ 5
CFR
41.5
/41.
9/41
.10/
43.2
/43.
5 02
Des
crib
e th
e re
latio
nshi
p be
twee
n R
eact
or P
ress
ure,
Su
ppre
ssio
n Po
ol T
empe
ratu
re, a
nd th
e ab
ility
of t
he
Supp
ress
ion
Pool
to ta
ke re
acto
r pre
ssur
e.
3.8
2.
4.18
: 3.6
2.4.
6: 4
.0
2.4.
14: 3
.9
MO
D
NR
C
3/19
98
PAG
E 3
TOTA
L TI
ER 1
GR
OU
P 1
2 0
0 2
1 0
PAG
E TO
TAL
# Q
UES
TIO
NS
5
PAG
E 1
TOTA
L TI
ER 1
GR
OU
P 1
1 1
2 3
2 1
PAG
E TO
TAL
# Q
UES
TIO
NS
10
PA
GE
2 TO
TAL
TIER
1 G
RO
UP
1 3
2 0
3 0
3 PA
GE
TOTA
L #
QU
ESTI
ON
S 11
K/A
CA
TEG
OR
Y T
OTA
LS:
6 3
2 8
3 4
TIER
1 G
RO
UP
1 G
RO
UP
POIN
T TO
TAL
26
REV
ISIO
N 0
11/
5/20
03
PAG
E 3
OF
13
NU
REG
102
1, R
EVIS
ION
8 S
UPP
LEM
ENT
1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
E
EM
ER
GE
NC
Y &
AB
NO
RM
AL
PL
AN
T
EV
OL
UT
ION
S - T
IER
1 G
RO
UP
2
ES-
401-
1
E/A
PE #
/NA
ME
/SA
FET
Y F
UN
CT
ION
K 1
K 2 K 3
A 1 A 2
G
T
OPI
C(S
)IM
P
SRO
/RO
/B
OT
H
RE
C#
RE
LA
TE
D
K/A
O
RIG
IN
N
OT
ES:
2950
01 P
artia
l or C
ompl
ete
Loss
of F
orce
d C
ore
Flow
Circ
ulat
ion
/ 1 &
4
CFR
41.5
/41.
10/4
3.5
2.
2. 34
Giv
en p
lant
con
ditio
ns a
nd a
redu
ctio
n in
cor
e flo
w,
dete
rmin
e th
e ef
fect
s on
Ther
mal
Lim
its a
nd c
ore
stab
ility
.
3.2
AK
1.03
: 4.1
AK
1.04
: 3.3
2950
02 L
oss o
f Mai
n C
onde
nser
Vac
uum
/ 3
C
FR41
.4/4
1.5/
41.7
03
Giv
en p
lant
con
ditio
ns, d
eter
min
e ho
w a
loss
of
cond
ense
r vac
uum
will
affe
ct th
e ab
ility
of t
he p
lant
to
rem
ain
oper
atin
g. (R
PS)
3.5
A
A1.
04: 3
.4A
K2.
01: 3
.5
AK
2.03
: 3.6
Lo
w P
ower
2950
04 P
artia
l or C
ompl
ete
Loss
of D
C P
ower
/ 6
CFR
41.5
/41.
7
03
Giv
en a
loss
of D
C c
ontro
l pow
er a
nd c
ondi
tions
that
w
ould
nor
mal
ly re
sult
in tr
ips o
f the
AC
Ele
ctric
al
Dis
tribu
tion
Syst
em, d
eter
min
e th
e op
erat
ion
of th
e A
C
circ
uit b
reak
ers.
3.6
2950
05 M
ain
Turb
ine
Gen
erat
or T
rip /
3 C
FR41
.5/4
1.6
03
G
iven
a tr
ip o
f the
Mai
n G
ener
ator
, det
erm
ine
the
affe
cts
on F
eedw
ater
tem
pera
ture
to th
e re
acto
r. 3.
0
2950
08 H
igh
Rea
ctor
Wat
er L
evel
/ 2
CFR
41.4
/41.
5
03
Dur
ing
a re
acto
r sta
rtup
from
col
d sh
utdo
wn,
det
erm
ine
the
mea
ns fo
r con
trol o
f rea
ctor
wat
er le
vel d
urin
g re
acto
r he
at u
p. (R
WC
U B
low
dow
n)
3.0
AA
2.05
: 3.1
AA
2.04
: 3.3
2950
11 H
igh
Con
tain
men
t Tem
pera
ture
/ 5
CFR
41.5
/41.
9/41
.10/
43.5
01
Giv
en p
lant
con
ditio
ns, d
eter
min
e C
onta
inm
ent c
oolin
g m
echa
nism
s and
ava
ilabl
e ad
ditio
nal c
oolin
g.
3.9
AK
2.01
: 4.0
MO
DN
RC
12
/200
0
2950
12 H
igh
Dry
wel
l Tem
pera
ture
/ 5
29
5018
Par
tial o
r Com
plet
e Lo
ss o
f CC
W /
8
2950
19 P
artia
l or C
ompl
ete
Loss
of I
nst.
Air
/ 8
CFR
41.4
/41.
10/4
3.5
01
G
iven
a lo
ss o
f Ins
trum
ent A
ir, d
eter
min
e Sa
fety
Rel
ief
Val
ves t
hat c
an b
e op
erat
ed u
sing
nitr
ogen
inst
alle
d pe
r of
f nor
mal
eve
nt p
roce
dure
s.
3.4
GG
NS
Scra
m #
10
7
2950
20 I
nadv
erte
nt C
ont.
Isol
atio
n / 5
& 7
C
FR41
.4/4
1.7/
41.9
/41.
10/4
3.5
06
G
iven
pla
nt c
ondi
tions
and
an
isol
atio
n of
the
Con
tain
men
t, A
uxili
ary
Bui
ldin
g an
d D
ryw
ell,
dete
rmin
e va
lidity
and
abi
lity
to re
stor
e sy
stem
.
3.8
2950
21 L
oss o
f Shu
tdow
n C
oolin
g / 4
C
FR41
.5/4
1.10
/43.
5
02
Giv
en p
lant
con
ditio
ns w
ith A
DH
R in
serv
ice
for
Shut
dow
n C
oolin
g, d
eter
min
e th
e af
fect
s of a
pla
nt
trans
ient
on
AD
HR
ope
ratio
n.
3.4
PAG
E 1
TOTA
L TI
ER 1
GR
OU
P 2
0 0
3 2
3 1
PAG
E TO
TAL
# Q
UES
TIO
NS
9
REV
ISIO
N 0
11/
5/20
03
PAG
E 4
OF
13
NU
REG
102
1, R
EVIS
ION
8 S
UPP
LEM
ENT
1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
E
EM
ER
GE
NC
Y &
AB
NO
RM
AL
PL
AN
T
EV
OL
UT
ION
S - T
IER
1 G
RO
UP
2
CO
NT
.
ES-
401-
1
E/A
PE #
/NA
ME
/SA
FET
Y F
UN
CT
ION
K 1
K 2 K 3
A 1 A 2
G
T
OPI
C(S
)IM
P
SRO
/RO
/B
OT
H
RE
C#
RE
LA
TE
D
K/A
O
RIG
IN
N
OT
ES:
2950
22 L
oss o
f CR
D P
umps
/ 1
CFR
41.5
/41.
10/4
3.5
2.
1. 7
Giv
en p
lant
con
ditio
ns a
nd a
trip
of t
he o
pera
ting
CR
D
pum
p, d
eter
min
e th
e ac
tions
to b
e ta
ken.
4.
4A
K1.
01: 3
.42.
4.4:
4.3
2.
4.49
: 4.0
29
5028
Hig
h D
ryw
ell T
empe
ratu
re /
5 C
FR41
.5/4
1.7/
41.1
0/43
.5
03
G
iven
pla
nt c
ondi
tions
and
EO
P gr
aphs
, det
erm
ine
the
accu
racy
of r
eact
or w
ater
leve
l ind
icat
ions
. 3.
9
EK1.
01: 3
.7
2950
29 H
igh
Supp
ress
ion
Pool
Wat
er L
evel
/ 5
29
5032
Hig
h Se
cond
ary
Con
tain
men
t Are
a Te
mpe
ratu
re /
5
CFR
41.4
/41.
10/4
3.5
04
G
iven
ent
ry in
to th
e Se
cond
ary
Con
tain
men
t EO
P on
hig
h te
mpe
ratu
re in
an
ECC
S R
oom
, ide
ntify
syst
ems n
ot
requ
ired
to b
e is
olat
ed fr
om P
rimar
y C
onta
inm
ent.
3.4
2950
33 H
igh
Seco
ndar
y C
onta
inm
ent A
rea
Rad
iatio
n Le
vels
/ 9
CFR
41.1
2/43
.4
04
G
iven
hig
h ar
ea ra
diat
ion
leve
ls in
Sec
onda
ry
Con
tain
men
t, de
term
ine
whe
n St
andb
y G
as T
reat
men
t w
ill b
e re
quire
d to
be
for o
pera
ted.
4.2
2950
34 S
econ
dary
Con
tain
men
t Ven
tilat
ion
Hig
h R
adia
tion
/ 9
CFR
41.4
/41.
10/4
1.13
/43.
4
2.
1. 7
Giv
en p
lant
par
amet
ers,
dete
rmin
e op
erat
ion
of
vent
ilatio
n sy
stem
s. 4.
4
2950
35 S
econ
dary
Con
tain
men
t Hig
h D
iffer
entia
l Pr
essu
re /
5
CFR
41.4
/41.
7/41
.13
01
D
escr
ibe
the
oper
atio
n of
the
Seco
ndar
y C
onta
inm
ent
Ven
tilat
ion
Syst
ems d
ue to
hig
h di
ffere
ntia
l pre
ssur
e.
3.6
2950
36 S
econ
dary
Con
tain
men
t Hig
h Su
mp/
Are
a W
ater
Lev
el /
5
CFR
41.4
/41.
10/4
3.5
03
G
iven
pla
nt c
ondi
tions
, ide
ntify
the
avai
labl
e ro
utes
to
rem
ove
wat
er fr
om E
CC
S pu
mp
room
s. 3.
0
6000
00 P
lant
Fire
On
Site
/ 8
CFR
41.1
0/43
.5
03
D
eter
min
e th
e ac
tions
that
will
occ
ur u
pon
activ
atio
n of
a
fire
alar
m.
3.2
PAG
E 2
TOTA
L TI
ER 1
GR
OU
P 2
0 2
0 2
2 2
PAG
E TO
TAL
# Q
UES
TIO
NS
8
PAG
E 1
TOTA
L TI
ER 1
GR
OU
P 2
0 0
3 2
3 1
PAG
E TO
TAL
# Q
UES
TIO
NS
9
K/A
CA
TEG
OR
Y T
OTA
LS:
0 2
3 4
5 3
TIER
1 G
RO
UP
2 G
RO
UP
POIN
T TO
TAL
17
R
EVIS
ION
0 1
1/5/
2003
PA
GE
5 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
EPL
AN
T S
YST
EM
S - T
IER
2 G
RO
UP
1 E
S-40
1-1
SYST
EM
#/N
AM
E
K 1 K 2
K 3 K 4
K 5 K 6
A 1 A 2
A 3 A 4
G
T
OPI
C(S
)IM
P
R
EC
#
SRO
/RO
/B
OT
H
RE
LA
TE
D
K/A
O
RIG
INN
OT
ES:
2010
05 R
CIS
C
FR41
.6/4
3.6
01
Giv
en a
failu
re o
f the
Mai
n St
eam
Byp
ass
valv
es to
ope
n w
ith th
e pl
ant a
t pow
er,
dete
rmin
e th
e af
fect
s on
RC
IS.
3.3
A
2.04
: 3.2
K6.
01: 3
.2
K5.
10: 3
.3
K1.
02: 3
.5
2020
02 R
ecirc
ulat
ion
Flow
Con
trol
CFR
41.6
06
D
escr
ibe
the
oper
atio
n of
the
Rec
irc F
low
C
ontro
l Val
ves d
urin
g a
Flow
Con
trol V
alve
R
unba
ck w
hen
a H
PU a
larm
s.
3.7
A
1.08
: 3.4
2030
00 R
HR
/LPC
I: In
ject
ion
Mod
e C
FR41
.8
10D
escr
ibe
the
affe
cts o
n LP
CI i
njec
tion
whe
nth
e as
soci
ated
Sta
ndby
Ser
vice
Wat
er S
yste
m
trips
.
3.1
2090
01 L
PCS
CFR
41.7
10
Des
crib
e th
e op
erat
ion
of th
e LP
CS
Inje
ctio
nva
lve
with
out E
CC
S in
ject
ion
sign
als p
rese
nt.
2.9
2090
02 H
PCS
CFR
41.7
/41.
8/43
.1/4
3.2
2.
1. 10
Giv
en p
lant
con
ditio
ns a
nd a
failu
re o
f the
H
PCS
syst
em, d
eter
min
e th
e ac
tions
with
re
spec
t to
Tech
Spe
cs.
3.9
2.2.
22: 4
.12.
2.25
: 3.7
2110
00 S
LC
CFR
41.6
/41.
7
04
D
urin
g an
initi
atio
n of
SLC
with
a fa
ilure
of
the
SLC
pum
ps to
star
t, de
term
ine
the
final
va
lve
posi
tions
.
3.7
A
2.06
: 3.3
A2.
07: 3
.2
2120
00 R
PS
CFR
41.7
12
Des
crib
e th
e af
fect
on
Seco
ndar
y C
onta
inm
ent
with
a lo
ss o
f pow
er to
RPS
. 3.
3
2150
04 S
ourc
e R
ange
Mon
itor
CFR
41.5
/41.
6 06
Des
crib
e th
e ha
zard
s inv
olve
d w
ith m
ovem
ent
of S
RM
det
ecto
rs fo
llow
ing
unde
r ves
sel
wor
k.
2.8
PAG
E 1
TO
TAL
TIER
2 G
RO
UP
1 1
0 2
1 0
1 2
0 0
0 1
PAG
E TO
TAL
# Q
UES
TIO
NS
8
REV
ISIO
N 0
11/
5/20
03
PAG
E 6
OF
13
NU
REG
102
1, R
EVIS
ION
8 S
UPP
LEM
ENT
1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
B
WR
SR
O E
XA
MIN
AT
ION
OU
TL
INE
PLA
NT
SY
STE
MS
- TIE
R 2
GR
OU
P 1
CO
NT
. E
S-40
1-1
SYST
EM
#/N
AM
E
K 1 K 2
K 3 K 4
K 5 K 6
A 1 A 2
A 3 A 4
G
T
OPI
C(S
)IM
P
R
EC
#
SRO
/RO
/B
OT
H
RE
LA
TE
D
K/A
O
RIG
INN
OT
ES:
2150
05 A
PRM
/ LP
RM
C
FR41
.6/4
1.7
01G
iven
LPR
M/A
PRM
stat
us a
nd a
loss
of
pow
er to
an
LPR
M, d
eter
min
e th
e re
actio
n of
th
e R
PS &
RC
IS sy
stem
s.
2.6
K1.
01: 4
.0K
5.06
: 2.6
K
4.01
: 3.7
K
4.02
: 4.2
21
6000
Nuc
lear
Boi
ler I
nstru
men
tatio
n C
FR41
.5/4
1.7
03G
iven
leak
age
on th
e in
stru
men
t lin
e fo
rR
eact
or V
esse
l Lev
el in
dica
tion,
det
erm
ine
the
indi
catio
ns a
nd re
actio
n of
syst
ems s
uppl
ied
that
indi
catio
n.
3.1
K1.
22: 3
.8
2170
00 R
CIC
C
FR41
.5/4
1.7/
41.1
0/43
.5
04W
ith R
CIC
ope
ratin
g fo
r a su
rvei
llanc
e,de
term
ine
the
affe
cts o
f a m
anua
l iso
latio
n si
gnal
.
3.6
A2.
03: 3
.3
2180
00 A
DS
CFR
41.7
/43.
1/43
.2
2.
2. 23
Giv
en p
lant
con
ditio
ns, d
eter
min
e th
e LC
O
stat
us fo
r ino
pera
ble
AD
S va
lves
. 3.
82.
2.25
: 3.7
2.2.
22: 4
.1
2230
01 P
rimar
y C
TMT
and
Aux
iliar
ies
CFR
41.9
/41.
10/4
3.5
.
2 4. 2
Giv
en p
lant
con
ditio
ns, d
eter
min
e re
quire
men
ts fo
r ent
ry in
to th
e Em
erge
ncy
Ope
ratin
g Pr
oced
ures
.
4.1
2230
02 P
CIS
/ N
ucle
ar S
team
Sup
ply
Shut
off
CFR
41.7
/41.
9/41
.11/
43.4
03G
iven
radi
atio
n m
onito
r rea
ding
s and
radi
ogra
phy
in C
onta
inm
ent,
dete
rmin
e th
e st
atus
of p
lant
syst
ems.
3.1
2720
00K
1.09
: 3.8
2260
01 R
HR
/LPC
I: C
TMT
Spra
y M
ode
CFR
41.7
/41.
8/41
.10/
43.5
08
Giv
en in
dica
tions
from
pla
nt in
stru
men
tatio
n,de
term
ine
the
oper
atio
n of
the
Con
tain
men
t Sp
ray
Syst
em.
2.8
A2.
10: 3
.1
2390
02 S
RV
s C
FR41
.7
08G
iven
SR
V o
pera
tion,
det
erm
ine
the
mea
ning
of in
dica
tions
and
SR
V st
atus
. 3.
6A
3.03
: 3.6
A1.
01: 3
.4
2410
00 R
eact
or /
Turb
ine
Pres
sure
R
egul
ator
C
FR41
.7
06
Iden
tify
the
cond
ition
s of t
he R
eact
or/T
urbi
nePr
essu
re C
ontro
l sys
tem
that
wou
ld re
sult
in a
M
ain
Turb
ine
Trip
.
3.7
PAG
E 2
TOTA
LS T
IER
2 G
RO
UP
1 0
1 0
1 0
2 0
1 1
1 2
PAG
E 2
TOTA
L #
QU
ESTI
ON
S 9
R
EVIS
ION
0 1
1/5/
2003
PA
GE
7 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
B
WR
SR
O E
XA
MIN
AT
ION
OU
TL
INE
PLA
NT
SY
STE
MS
- TIE
R 2
GR
OU
P 1
CO
NT
. E
S-40
1-1
SYST
EM
#/N
AM
E
K 1 K 2
K 3 K 4
K 5 K 6
A 1 A 2
A 3 A 4
G
T
OPI
C(S
)IM
P
R
EC
#
SRO
/RO
/B
OT
H
RE
LA
TE
D
K/A
O
RIG
INN
OT
ES:
2590
02 R
eact
or W
ater
Lev
el C
ontro
l C
FR41
.4/4
1.5/
41.7
02
With
the
Dig
ital F
eedw
ater
Lev
el C
ontro
lSy
stem
sele
cted
for a
utom
atic
ope
ratio
n,
dete
rmin
e th
e re
actio
n of
the
syst
em fo
r a
give
n fa
ilure
.
3.6
2610
00 S
GTS
C
FR41
.7/4
1.10
/41.
11/4
3.4
2.
4. 10
Giv
en o
pera
tion
of th
e St
andb
y G
as T
reat
men
t Sy
stem
follo
wed
by
alar
ms t
hat w
ould
indi
cate
a
chan
ge in
pla
nt st
atus
, det
erm
ine
actio
ns to
be
take
n.
3.1
K4.
01: 3
.8
2620
01 A
C E
lect
rical
Dis
tribu
tion
CFR
41.4
/41.
7
01
G
iven
the
plan
t at f
ull p
ower
and
a lo
ss o
f bus
11
HD
, det
erm
ine
the
final
ope
ratio
n of
the
Rec
ircul
atio
n sy
stem
.
3.7
20
2001
K1.
08: 3
.2
K6.
03: 3
.0
2640
00 E
DG
s C
FR41
.8/4
3.2
07
Giv
en sy
stem
alig
nmen
t, de
term
ine
the
oper
atio
nal c
ondi
tion
of th
e di
esel
gen
erat
or.
3.4
2900
01 S
econ
dary
CTM
T C
FR41
.10/
43.5
03
Iden
tify
the
prop
er a
lignm
ent o
f the
Aux
iliar
yB
uild
ing
Ven
tilat
ion
syst
ems t
o m
aint
ain
prop
er b
uild
ing
diffe
rent
ial p
ress
ure.
2.7
2620
01 A
C E
lect
rical
Dis
tribu
tion
CFR
41.1
0/43
.5
02
Det
erm
ine
the
met
hod
empl
oyed
to c
ontro
l the
re
turn
of l
oads
dur
ing
a st
atio
n bl
acko
ut w
hen
cros
s con
nect
ing
Div
isio
n II
I to
Div
isio
n II
.
3.5
PAG
E 3
TOTA
LS T
IER
2 G
RO
UP
1 0
0 1
1 0
0 1
0 0
2 1
PAG
E TO
TAL
# Q
UES
TIO
NS
6
PAG
E 1
TOTA
LS T
IER
2 G
RO
UP
1 1
0 2
1 0
1 2
0 0
0 1
PAG
E TO
TAL
# Q
UES
TIO
NS
8
PAG
E 2
TOTA
LS T
IER
2 G
RO
UP
1 0
1 0
1 0
2 0
1 1
1 2
PAG
E TO
TAL
# Q
UES
TIO
NS
9
K/A
CA
TEG
OR
Y T
OTA
LS:
1 1
3 3
0 3
3 1
1 3
4 TI
ER 2
GR
OU
P 1
GR
OU
P PO
INT
TOTA
L 23
. REV
ISIO
N 0
11/
5/20
03
PAG
E 8
OF
13
NU
REG
102
1, R
EVIS
ION
8 S
UPP
LEM
ENT
1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
EPL
AN
T S
YST
EM
S - T
IER
2 G
RO
UP
2 E
S-40
1-1
SYST
EM
#/N
AM
E
K 1 K 2
K 3 K 4
K 5 K 6
A 1 A 2
A 3 A 4
G
T
OPI
C(S
)IM
P
R
EC
#
SRO
/RO
/ BO
TH
R
EL
AT
ED
K
/A
OR
IGIN
NO
TE
S:
2010
01 C
RD
Hyd
raul
ic
CFR
41.5
/41.
6
10
G
iven
ala
rms a
nd li
ght s
tatu
s, de
term
ine
the
stat
us o
f the
CR
D H
ydra
ulic
syst
em.
2.9
2020
01 R
ecirc
ulat
ion
CFR
41.3
/41.
5
06
G
iven
pla
nt c
ondi
tions
and
a fa
ilure
of t
he
Rec
ircul
atio
n Pu
mp
Mot
or G
ener
ator
, de
term
ine
final
syst
em c
onfig
urat
ion.
3.1
2040
00 R
WC
U
CFR
41.4
09
W
ith a
loss
of t
he ro
om c
oolin
g fo
r the
R
WC
U e
quip
men
t are
as a
nd te
mpe
ratu
res,
dete
rmin
e th
e af
fect
s on
the
RW
CU
syst
em.
2.8
2050
00 S
hutd
own
Coo
ling
CFR
41.2
/41.
3/41
.4/4
1.5/
43.2
01
Id
entif
y th
e in
dica
tions
of a
mod
e ch
ange
fo
llow
ing
a lo
ss o
f shu
tdow
n co
olin
g.
3.3
2150
03 I
RM
21
9000
RH
R /L
PCI S
uppr
essi
on P
ool
Coo
ling
Mod
e C
FR41
.7
01
With
RH
R in
Sup
pres
sion
Poo
l Coo
ling
and
an e
xten
ded
loss
of p
ower
, des
crib
e th
e ac
tions
requ
ired
to re
stor
e R
HR
to
Supp
ress
ion
Pool
Coo
ling.
(Sys
tem
Ven
t)
2.7
O
NEP
Cau
tion
2340
00 F
uel H
andl
ing
Equi
pmen
t C
FR41
.4/4
1.9/
41.1
2/43
.4/4
3.7
03
Des
crib
e th
e af
fect
s of a
low
erin
g Fu
el P
ool
wat
er le
vel o
n fu
el h
andl
ing
oper
atio
ns.
3.4
K
6.05
: 3.3
2390
03 M
SIV
Lea
kage
Con
trol
2450
00 M
ain
Turb
ine
Gen
., an
d A
uxili
arie
s
25
9001
Rea
ctor
Fee
dwat
er
CFR
41.4
/41.
10/4
3.5
06
Des
crib
e th
e ac
tions
to b
e ta
ken
for a
loss
of
Plan
t Ser
vice
Wat
er w
ith re
gard
to th
e C
onde
nsat
e an
d Fe
edw
ater
syst
ems.
2.7
PAG
E 1
TOTA
L TI
ER 2
GR
OU
P 2
0 0
1 0
2 2
0 1
1 0
0 PA
GE
TOTA
L #
QU
ESTI
ON
S 7
REV
ISIO
N 0
11/
5/20
03
PAG
E 9
OF
13
NU
REG
102
1, R
EVIS
ION
8 S
UPP
LEM
ENT
1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
EPL
AN
T S
YST
EM
S - T
IER
2 G
RO
UP
2 C
ON
T.
ES-
401-
1
SYST
EM
#/N
AM
E
K 1 K 2
K 3 K 4
K 5 K 6
A 1 A 2
A 3 A 4
G
T
OPI
C(S
)IM
P
R
EC
#
SRO
/RO
/ B
OT
H
RE
LA
TE
D
K/A
O
RIG
INN
OT
ES:
2620
02 U
PS (A
C/D
C)
CFR
41.7
/41.
10/4
3.5
03
Des
crib
e th
e op
erat
ion
of th
e St
atic
Inve
rter
(sta
tic sw
itch)
with
an
osci
llatin
g fr
eque
ncy
outp
ut o
f the
Inve
rter a
nd a
loss
of
sync
hron
izat
ion
betw
een
sour
ces.
2.6
2630
00 D
C E
lect
rical
Dis
tribu
tion
2710
00 O
ffgas
C
FR41
.4/4
1.10
/41.
13/4
3.4/
43.5
02
G
iven
a c
hang
e in
Offg
as fl
ow, d
eter
min
e a
pote
ntia
l cau
se a
nd it
s affe
cts o
n th
e pl
ant a
nd
Offg
as S
yste
m.
2.8
A
2.01
: 3.3
A2.
10: 3
.3
2720
00 R
adia
tion
Mon
itorin
g C
FR41
.10/
41.1
1/43
.4/4
3.5
05
Giv
en a
loss
of p
ower
to U
PS, d
eter
min
e th
e af
fect
s on
Fuel
Han
dlin
g A
rea
and
Fuel
Poo
l Sw
eep
Exha
ust R
adia
tion
Mon
itors
.
2.9
2860
00 F
ire P
rote
ctio
n
CFR
41.1
0/41
.11/
41.1
3/43
.4/4
3.5
2.
3. 8
Giv
en a
fire
in th
e Tu
rbin
e B
uild
ing,
des
crib
e th
e ac
tions
to b
e ta
ken
to u
tiliz
e th
e Tu
rbin
e B
uild
ing
Roo
f hat
ches
for v
entin
g an
d sm
oke
rem
oval
.
3.2
2900
03 C
ontro
l Roo
m H
VA
C
CFR
41.4
03
D
escr
ibe
the
basi
s for
mai
ntai
ning
con
trol o
f C
ontro
l Roo
m te
mpe
ratu
re.
2.7
3000
00 I
nstru
men
t Air
CFR
41.4
/41.
10/4
3.5
02
Des
crib
e th
e pr
oces
s of u
tiliz
ing
Serv
ice
Air
to su
pply
the
Inst
rum
ent A
ir sy
stem
dur
ing
a lo
ss o
f the
Inst
rum
ent A
ir co
mpr
esso
rs.
2.8
4000
00 C
ompo
nent
Coo
ling
Wat
er
PAG
E 2
TOTA
LS
1 1
0 0
1 0
0 1
1 0
1 PA
GE
3 TO
TAL
# Q
UES
TIO
NS
6
PAG
E 1
TOTA
LS
0 0
1 0
2 2
0 1
1 0
0 PA
GE
1 TO
TAL
# Q
UES
TIO
NS
7
K/A
CA
TEG
OR
Y T
OTA
LS:
1 1
1 0
3 2
0 2
2 0
1 TI
ER 2
GR
OU
P 2
GR
OU
P PO
INT
TOTA
L 13
. REV
ISIO
N 0
11/
5/20
03
PAG
E 1
0 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
EPL
AN
T S
YST
EM
S - T
IER
2 G
RO
UP
3 E
S-40
1-1
SYST
EM
#/N
AM
E
K 1 K 2
K 3 K 4
K 5 K 6
A 1 A 2
A 3 A 4
G
T
OPI
C(S
)IM
P
R
EC
#
SRO
/RO
/ BO
TH
R
EL
AT
ED
K
/A
OR
IGIN
NO
TE
S:
2010
03 C
ontro
l Rod
and
Driv
e M
echa
nism
21
5001
Tra
vers
ing
In-c
ore
Prob
e
23
3000
Fue
l Poo
l Coo
ling
and
Cle
anup
C
FR41
.4/4
1.9
02
Des
crib
e th
e op
erat
ion
of th
e Fu
el P
ool
Coo
ling
and
Cle
anup
Sys
tem
with
a lo
wer
ing
leve
l in
the
Spen
t Fue
l Poo
l.
3.1
2390
01 M
ain
and
Reh
eat S
team
C
FR41
.4/4
1.7/
41.9
09
D
eter
min
e th
e re
spon
se o
f the
MSI
Vs t
o a
parti
al a
ctua
tion
of is
olat
ion
logi
c.
4.1
2560
00 R
eact
or C
onde
nsat
e C
FR41
.4
15G
iven
par
amet
ers a
nd p
lant
con
ditio
ns,
dete
rmin
e th
e so
urce
of i
n-le
akag
e in
to th
e R
eact
or C
onde
nsat
e/ F
eedw
ater
syst
ems.
3.1
2680
00 R
adw
aste
C
FR41
.13/
43.4
01
D
eter
min
e th
e op
erat
ion
of fl
oor d
rain
sum
p pu
mps
with
one
pum
p re
mov
ed fr
om se
rvic
e.
3.6
M
OD
2880
00 P
lant
Ven
tilat
ion
2900
02 R
eact
or V
esse
l Int
erna
ls
K/A
CA
TEG
OR
Y T
OTA
LS:
0 0
0 0
0 1
1 1
0 1
0 TI
ER 2
GR
OU
P 3
GR
OU
P PO
INT
TOTA
L 4
REV
ISIO
N 0
11/
5/20
03
PAG
E 1
1 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
-
G
RA
ND
GU
LF
NU
CL
EA
R S
TA
TIO
N
FEB
RU
AR
Y 2
004
BW
R S
RO
EX
AM
INA
TIO
N O
UT
LIN
E
GE
NE
RIC
KN
OW
LE
DG
E A
ND
AB
ILIT
IES
TIE
R 3
ES-
401-
5
CA
TE
GO
RY
C1
C2
C3
C4
TO
PIC
(S)
IMP
RE
C#
SR
O/R
O/B
OT
H
RE
LA
TE
D
K/A
O
RIG
INN
OT
ES:
CO
ND
UC
T O
F O
PER
ATI
ON
S –
Shift
Tur
nove
r C
FR41
.10/
43.5
2.
1.3
D
eter
min
e th
e ac
tions
requ
ired
for p
erso
nnel
to
assu
me
shift
dut
ies d
urin
g of
f tur
nove
r tim
es.
3.4
MO
DN
RC
6/
2001
CO
ND
UC
T O
F O
PER
ATI
ON
S –
Proc
edur
al
Adh
eren
ce
CFR
41.1
0/43
.5
2.1.
20
G
iven
a si
tuat
ion
that
requ
ires p
roce
dure
cha
nges
to
acco
mpl
ish
a ta
sk, d
eter
min
e th
e ac
tions
to b
e ta
ken.
4.
2
2.
1.23
: 4.0
2.
1.2:
4.0
CO
ND
UC
T O
F O
PER
ATI
ON
S –
Proc
edur
es
CFR
41.1
0/43
.5
2.1.
21
D
escr
ibe
the
usag
e an
d lim
its o
n pr
oced
ural
line
up
chec
k sh
eets
. 3.
2
CO
ND
UC
T O
F O
PER
ATI
ON
S –
Ope
ratio
nal M
ode
CFR
43.2
2.
1.22
Giv
en p
lant
con
ditio
ns, d
eter
min
e th
e pl
ant T
ech
Spec
Mod
e of
ope
ratio
n.
3.3
CO
ND
UC
T O
F O
PER
ATI
ON
S –
Plan
t Per
sonn
el
Con
trol
C
FR41
.6/4
1.10
/43.
5
2.1.
9
Giv
en c
ondi
tions
det
erm
ine
who
se a
utho
rity
is
requ
ired
to st
op w
ork
in th
e pl
ant.
4.0
EQU
IPM
ENT
CO
NTR
OL
– C
onfig
urat
ion
Con
trol
CFR
41.1
0/43
.5
2.
2.15
G
iven
a c
ompo
nent
tem
pora
rily
out o
f nor
mal
al
ignm
ent p
er sy
stem
ope
ratin
g in
stru
ctio
ns,
dete
rmin
e th
e tra
ckin
g m
echa
nism
to b
e em
ploy
ed.
2.9
2.2.
11:
3.4
C
onfig
urat
ion
cont
rol S
OER
98-
1
EQU
IPM
ENT
CO
NTR
OL
– M
aint
enan
ce W
ork
Ord
ers
CFR
41.1
0/43
.5
2.
2.19
G
iven
con
ditio
ns, i
dent
ify w
hen
a PA
SSPO
RT
wor
k or
der i
s req
uire
d to
be
issu
ed.
3.1
NEW
Wor
k C
ontro
l Sy
stem
EQU
IPM
ENT
CO
NTR
OL
– M
aint
enan
ce a
ffect
ing
LCO
s
CFR
41.1
0/43
.2/4
3.5
2.
2.24
G
iven
an
inop
erab
le c
ompo
nent
on
an L
CO
de
term
ine
the
affe
cts o
f mai
nten
ance
. 3.
8
EQU
IPM
ENT
CO
NTR
OL
– C
ore
Alte
ratio
ns
CFR
43.6
/43.
7
2.2.
34
Det
erm
ine
whe
ther
an
activ
ity c
onst
itute
s a C
ore
Alte
ratio
n.
3.2
2.2.
32: 3
.3
MO
D
RA
DIA
TIO
N C
ON
TRO
L –
SRO
Res
pons
ibili
ties f
or
Syst
ems
CFR
41.1
2/41
.10/
43.4
/43.
5
2.3.
3
Des
crib
e th
e Sh
ift M
anag
er re
spon
sibi
litie
s for
sh
ipm
ents
of R
adio
activ
e m
ater
ials
offs
ite.
2.9
M
OD
H
azar
dous
Mat
eria
ls
Tran
spor
tatio
n pl
an
NR
C
12/2
000
RA
DIA
TIO
N C
ON
TRO
L –
Rad
iatio
n W
ork
Perm
its
CFR
41.1
0/41
.12/
43.4
/43.
5
2.
3.7
G
iven
con
ditio
ns a
nd p
roce
dure
s, de
term
ine
appl
icab
ility
of r
adia
tion
wor
k pe
rmits
. 3.
3
M
OD
NR
C
8/20
02
PAG
E 1
TOTA
L TI
ER 3
5
4 2
0 PA
GE
TOTA
L #
QU
ESTI
ON
S 11
REV
ISIO
N 0
11/
5/20
03
PAG
E 1
2 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
-
REV
ISIO
N 0
11/
5/20
03
PAG
E 1
3 O
F 13
N
UR
EG 1
021,
REV
ISIO
N 8
SU
PPLE
MEN
T 1
.
GR
AN
D G
UL
F N
UC
LE
AR
ST
AT
ION
FE
BR
UA
RY
200
4
B
WR
SR
O E
XA
MIN
AT
ION
OU
TL
INE
G
EN
ER
IC K
NO
WL
ED
GE
AN
D A
BIL
ITIE
S T
IER
3
CO
NT
ES-
401-
5
CA
TE
GO
RY
C
1
TO
PIC
(S)
IGIN
N
O
C2
C3
C4
IMP
#R
EC
SRO
/RO
/BO
TH
R
EL
AT
ED
K
/A
OR
TE
S:
EMER
GEN
CY
PR
OC
EDU
RES
/ PL
AN
– A
OP’
s an
d us
age
CFR
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-
ES-301 Administrative Topics Outline Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 2/9/2004 - 2/11/2004
Examination Level (circle one): RO / SRO Operating Test Number: __1___
Administrative Topic/Subject Description
Describe method of evaluation: 1. ONE Administrative JPM, OR 2. TWO Administrative Questions
Knowledge / Ability
IMP AdditionalK/A’s
ORIGIN NOTES
A.1 Technical Specifications
JPM GJPM-SRO-ADM50 Given a component, determine Limiting Condition for Operations and complete entry into ESOMS.
2.1.12 4.0 2.2.23: 3.8 2.2.22: 4.1
MOD Different component
using ESOMS
computer CFR 55.45 (a)12 &
13 Plant Chemistry JPM GJPM-OP-ADM-52
Given a chemistry report and procedures, determine the plant conditions and actions to be taken.
2.1.34 2.9 2.1.6: 4.3 NEW CFR 55.45(a)12 &
13
A.2 Post-Maintenance Operability
JPM GJPM-SRO-ADM51 Given a work order, determine the retestrequirements for the component and enter into PASSPORT system.
2.2.21 3.5 2.2.24: 3.8 NEW New PASSPORT Work Mgmt System
CFR 55.45 (a)12 &
13 A.3 Radiation
Control JPM GJPM-SRO-ADM33 Perform required actions to access the Controlled Access Area (CAA), determine requirements to enter a High Contamination Area and authorization required, and exit the CAA.
2.3.1 3.0 2.3.4: 3.1
2.3.2: 2.9
BANK
NRC 6/2001
CFR 55.45 (a)9 & 10
A.4 Emergency Plan Action Levels
JPM GJPM-SRO-A&E55 Given conditions, determine the appropriate emergency classification, actions to be taken for a security threat compromising the Remote Shutdown Panels and complete the required notification form.
2.4.41 4.1 2.4.30: 3.6 2.4.40: 4.0 2.4.28: 3.3
NEW CFR55.45 (a)11
Security Threat
REVISION 0 9/30/2003
-
ES-301 Individual Walk-Through Test Outline Form ES-301-2
Facility: GRAND GULF NUCLEAR STATION Date of Examination: 2/9/2004 – 2/9/2004 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ___1___
System / JPM Title / Type Codes* Safety Function
Knowledge / Ability
IMP. AdditionalK/A’s
ORIGIN NOTES
B.1. CONTROL ROOM SYSTEMS 1. 205000 SHUTDOWN COOLING SYSTEM (RHR) (D)(S)(A)(L)
4 A4.01 3.7 A4.02: 3.5A4.03: 3.5
BANK CFR 55.45(a)1; 3, 4;
Startup RHR in Shutdown Cooling (E12-F053x fail on stroke) GJPM-RO-E1212
A4.09: 3.1A2.10: 2.9 A2.12: 3.0 A1.02: 3.2
NRC 3/1998
5; 6 & 7
2. 262001 AC ELECTRICAL DISTRIBUTION (M)(S)
6 A4.01 3.7 A4.02: 3.4A4.04: 3.7
MOD CFR55.045(a)6
Distribute loads between Service Transformers 11 & 21 GJPM-RO-R2731
A4.05: 3.32.1.31: 3.9 2.1.30: 3.4
NRC 8/2002
& 8
3. 212000 REACTOR PROTECTION SYSTEM (RPS) (D)(C)
7 A4.17 4.1 295037EA1.01: 4.6
BANK CFR55.45(a)8
Defeat RPS Scram Signals per EP-2 Attachment 19 GJPM-RO-EP031
295015AA1.02: 4.2 2.1.30: 3.4 2.1.20: 4.2
NRC 6/2001
4. 218000 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) (D)(S)(A)
3 A4.01 4.4 A4.02: 4.2 BANK CFR55.45(a)8
Manually initiate ADS. (No pump permissive) GJPM-RO-E2222
NRC 3/1998
5. 223001 PRIMARY CONTAINMENT SYSTEM (D)(S)
5 A2.11 3.8 A1.08: 3.6 209002
BANK CFR55.45(a)8
Raise Suppression Pool water level using HPCS GJPM-RO-E2205
A4.01: 3.7 A4.04: 3.1 A4.09: 3.5
NRC 8/2002lowered level
6. 202002 RECIRCULATION FLOW CONTROL SYST. (D)(S)
1 A2.08 3.3 A1.08: 3.4 2.1.30: 3.4
BANK CFR55.45(a)
Recover Recirculation Flow Control Valve following an automatic runback. GJPM-RO-B3311
2; 6 & 8
REVISION 0 9/30/2003
-
Facility: GRAND GULF NUCLEAR STATION Date of Examination: 2/9/2004 – 2/9/2004 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ___1___
System / JPM Title / Type Codes* Safety Function
Knowledge / Ability
IMP. Additional K/A’s
ORIGIN NOTES
B.1. CONTROL ROOM SYSTEMS (cont) 7. 259001 REACTOR FEEDWATER SYSTEM
(N)(S)(L)(A) 2 A4.04 2.9 A4.05: 3.9
A2.07: 3.8 NEW CFR
55.45(a) Shift from Long Cycle Cleanup to Startup Level Control with Condensate (S/U Level Control Valve fails full OPEN). GJPM-RO-N2102
A3.03: 3.2 A3.04: 3.7 A4.01: 3.5 2.1.30: 3.4
259002 A1.05: 2.9 A4.03: 3.6
1; 3; 4; 6 & 8
B.2. FACILITY WALK-THROUGH 8. 286000 FIRE PROTECTION SYSTEM
(D)(P)(A) 8 A4.06 3.4 BANK CFR
55.45(a) Perform a local start of a diesel driven fire pump (failure of first manual local bank start). GJPM-RO-P6402
NRC 8/2002
6 & 8 Abnormal
9. 295019 LOSS OF INSTRUMENT AIR (D)(P)(R)
8 AA1.01 3.3 BANK CFR55.45(a) 8 & 9
Lineup makeup Nitrogen to the ADS Valve Accumulators per ONEP. GJPM-NLO-P5301
NRC 6/2001
GGNS Scram 4/2003
Emergency/ Abnormal
10. 295016 CONTROL ROOM ABANDONMENT (N)(P)(A)
2 AA1.06 4.1 2.1.30: 3.4AK2.01: 4.5
NEW CFR55.45(a)
Startup RCIC from the Remote Shutdown Panel to control RPV Water Level (Failed flow controller). GJPM-RO-C6106
3.7 AK3.03:AA1.07: 4.3 AA2.02: 4.3
4; 6; & 8 Other Safety Function 7 Emergency/ Abnormal
* Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA
REVISION 0 9/30/2003
-
ES-301 Administrative Topics Outline Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 2/9/2004 - 2/11/2004
Examination Level (circle one): RO / SRO Operating Test Number: __1___
Administrative Topic/Subject Description
Describe method of evaluation: 1. ONE Administrative JPM, OR 2. TWO Administrative Questions
Knowledge / Ability
IMP AdditionalK/A’s
ORIGIN NOTES
A.1 Technical Specifications
JPM GJPM-SRO-ADM50 Given a component, determine Limiting Condition for Operations and complete entry into ESOMS.
2.1.12 4.0 2.2.23: 3.8 2.2.22: 4.1
MOD Different component
using ESOMS
computer CFR 55.45 (a)12 &
13 Plant Chemistry JPM GJPM-OP-ADM-52
Given a chemistry report and procedures, determine the plant conditions and actions to be taken.
2.1.34 2.9 2.1.6: 4.3 NEW CFR 55.45(a)12 &
13
A.2 Post Maintenance Operability
JPM GJPM-SRO-ADM51 Given a work order, determine the retest requirements for the component and enter into PASSPORT system.
2.2.21 3.5 2.2.24: 3.8 NEW New PASSPORT Work Mgmt system
CFR 55.45 (a)12 &
13 A.3 Radiation
Control JPM GJPM-SRO-ADM33 Perform required actions to access the Controlled Access Area (CAA), determine requirements to enter a High Contamination Area and authorization required, and exit the CAA.
2.3.1 3.0 2.3.4: 3.1
2.3.2: 2.9
BANK
NRC 6/2001
CFR 55.45 (a)9 & 10
A.4 Emergency Plan Action Levels
JPM GJPM-SRO-A&E55 Given conditions, determine the appropriate emergency classification, actions to be taken for a security threat compromising the Remote Shutdown Panels and complete the required notification form.
2.4.41 4.1 2.4.30: 3.6 2.4.40: 4.0 2.4.28: 3.3
NEW CFR55.45(a)
11 Security Threat
REVISION 0 9/30/2003
-
REVISION 0 9/30/2003
ES-301 Individual Walk-Through Test Outline Form ES-301-2
Facility: GRAND GULF NUCLEAR STATION Date of Examination: 2/9/2004 – 2/9/2004 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ___1___
System / JPM Title / Type Codes* Safety Function
Knowledge / Ability
IMP. Additional K/A’s
ORIGIN NOTES
B.1. CONTROL ROOM SYSTEMS 1. 205000 SHUTDOWN COOLING SYSTEM (RHR) (D)(S)(A)(L)
4 A4.01 3.7 3.5 BANK CFR A4.02: A4.03: 3.5
55.45(a) 1; 3; 4
Startup RHR in Shutdown Cooling (E12-F053x fail on stroke) GJPM-RO-E1212
3.1 A4.09: A2.10: 2.9 A2.12: 3.0 A1.02: 3.2
NRC 3/1998
5; 6 & 7
2. 262001 AC ELECTRICAL DISTRIBUTION (M)(S)
6 A4.01 3.7 3.4 A4.02: A4.04: 3.7
MOD CFR55.45(a)
Distribute loads between Service Transformers 11 & 21 GJPM-RO-R2731
3.3 A4.05: 2.1.31: 3.9 2.1.30: 3.4
NRC 8/2002
6 & 8
3. 212000 REACTOR PROTECTION SYSTEM (RPS) (D)(C)
7 A4.17 4.1 295037EA1.01: 4.6
BANK CFR55.45(a)8
Defeat RPS Scram Signals per EP-2 Attachment 19 GJPM-RO-EP031
295015AA1.02: 4.1 2.1.30: 3.4 2.1.20: 4.2
NRC 6/2001
B.2. FACILITY WALK-THROUGH 4. 295019 LOSS OF INSTRUMENT AIR (D)(P)(R)
8 AA1.01 3.3 BANK CFR55.45(a) 8 & 9
Lineup makeup Nitrogen to the ADS Valve Accumulators GJPM-NLO-P5301
NRC 6/2001
GGNS Scram 4/2003
Emergency/ Abnormal
5. 295016 CONTROL ROOM ABANDONMENT (N)(P)(A)
2 AA1.06 4.1 2.1.30: 3.4AK2.01: 4.5
NEW CFR55.45(a)
Startup RCIC from the Remote Shutdown Panel to control RPV Water Level (Faulted) GJPM-RO-C6106
3.7 AK3.03:AA1.07: 4.3 AA2.02: 4.3
4; 6; & 8 Other Safety Function 7 Emergency/ Abnormal
* Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA
-
Appendix D Scenario Outline Form ES-D-1
Facility: GRAND GULF NUCLEAR STATION Scenario No.: 1 Op-Test No.: Day 1 Examiners: _________________________ Operators:__________________________ _________________________ __________________________ _________________________ __________________________ Objectives: To evaluate the candidates’ ability to operate the facility in response to the following evolutions: 1. Complete a shift of Reactor Recirculation Pumps to Fast Speed. 2. Take actions in response to a Control Rod Drift and complete actions of the CRD
Malfunctions ONEP. 3. Respond to a trip of RPS ‘A’ MG set and the implications of having both RPS buses on
Alternate Source of power. 4. Make determination of a second Control Rod Drift following insertion and disarming
CRD and taking actions for multiple Control Rod Drifts per CRD Malfunctions ONEP. 5. Take actions per the EOPs in response to an ATWS and mitigate the consequences of
the ATWS with no Main Steam Bypass Valves. 6. Take actions for a failure of Standby Liquid Control to inject to the Reactor during an
ATWS. Initial Conditions: Reactor Power is at 34 %. INOPERABLE Equipment APRM ‘H’ is INOP due to a failed power supply card RHR ‘C’ Pump is tagged out of service for motor oil replacement CCW Pump ‘B’ is tagged out of service for pump seal replacement RPS ‘B’ Motor Generator is out of service for EPA circuit breaker replacement, RPS ‘B’ is on its
Alternate Source. Appropriate clearances and LCOs are written. Turnover: The plant is operating at 34% power. Reactor Recirculation Pump ‘A’ has been shifted to Fast speed. Continue operations to shift Reactor Recirculation Pump ‘B’ to Fast speed at step 5.11.4 of IOI-2. There are scattered thundershowers reported in the Tensas Parish area. Event No.
Malf. No.
Event Type*
Event
Description 1
R (RO) N (SS)
Shift Reactor Recirculation Pump ‘B’ to fast speed. (SOI 04-1-01-B33-1 section 4.2)
-
Appendix D Scenario Outline Form ES-D-1
Scenario 1 Day 1 (Continued)
Event No.
Malf. No.
Event Type*
Event
Description 2
z161161_ 56_53
C(RO)
Respond to Control Rod Drift. Perform actions per ONEP 05-1-02-IV-1. Isolate/valve out of service the affected control rod.
3
c71077a
C(ALL)
Respond to trip of RPS ‘A’ Motor Generator trip. Complete Technical Specification/procedural determinations.
4
z161161_ 32_09
C(RO)
Recognize and respond to a second control rod drift and insert a manual Reactor SCRAM per ONEP 05-1-02-IV-1.
5
c11164 @ 30%
M (ALL)
Upon Reactor Scram recognize the failure of all control rods to fully insert and take actions per EOPs for ATWS.
tc084a, b, c
C (BOP)
Recognize the failure of Main Steam Bypass Valves to open and control reactor pressure using SRVs within specified band.
Recognize the loss of both Alternate Divisions of RPS EPAs when Low
Pressure ECCS is manually initiated and restore power to RPS to allow insertion of control rods.
c41263 @ 80%
C (BOP)
Recognize the failure of Standby Liquid Control to meet the parameters to inject into the Reactor when initiated and actions taken for Alternate Boron Injection.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks - Insert manual scram on second Control Rod Drift. - Inject Standby Liquid Control prior to Suppression Pool Temperature reaching 110 �F. - Identify the need for Alternate Standby Liquid Control injection. - Terminate and prevent injection from Feedwater and ECCS when conditions require entry
into Level/Power Control. - Commence injection into the reactor using Feedwater or RHR ‘A’ or ‘B’ through Shutdown
Cooling when reactor level reaches –192”. - Insert Control Rods in response to ATWS conditions.
-
Appendix D Scenario Outline Form ES-D-1
Facility: GRAND GULF NUCLEAR STATION Scenario No.: 2 Op-Test No.: Day 2 Examiners: _________________________ Operators:__________________________ _________________________ __________________________ _________________________ __________________________ Objectives: To evaluate the candidates’ ability to operate the facility in response to the following evolutions: 1. Raise Reactor Power by withdrawing control rods. 2. Perform operator actions for a stuck control rod per ONEP. 3. Startup 2nd Reactor Feed Pump. 4. Respond to a failure of ESF UPS bus 1Y89 (inverter 1Y87). 5. Respond to a momentary loss of Grid per ONEPs. 6. Respond to a failure of Feedwater Line in the Drywell, initiate a reactor
scram based on rising Drywell Pressure per EOPs. 7. Respond to a failure of Division 2 ECCS failure to initiate. 8. With a small break LOCA in the Drywell and reduced injection systems
maintain reactor level per the EOPs. Initial Conditions: Reactor Power is at 44 % bringing the plant up following an outage; Reactor Recirculation pumps are in Fast Speed at 60 % co