ML091130420
| ML091130420 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/25/2008 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-259/08-301, 50-260/08-301, 50-296/08-301 | |
| Download: ML091130420 (14) | |
See also: IR 05000259/2008301
Text
.. 1:1
Written Examination Outline
r~""'I '
- '13 tF m ES-401-1
Facility:
06 i 0 NRC Exam Outline
.-...... '
Date of Exam: 02/2512008
.
RO KIA Category Points
SRO-Only Points
Tier
Group
K
K
K
K
K
K
A
A
A
A
G
1
2
3
4
5
6
I
2
3
4
Total
A2
G*
Total
1.
1
3
3
3
3
4
4
20
4
3
7
Emergency
2
1
1
1
1
2
1
7
1
2
3
&
Plant
Tier
!:'~l
Evolutions
Totals
4
4
4
4
6
5
27
5
5
10
"
!"
1
2
3
2
2
2
2
2
3
3
3
2
26
3
2
5
2.
Plant
2
I
1
1
1
1
2
1
1
1
1
1
12
0
2
1
3
Systems
Tier
Totals
3
4
3
3
3
4
3
4
4
4
3
38
5
3
8
3. Generic Knowledge & Abilities
1
2
3
4
1
2
3
4
Categories
10
7
3
2
2
3
1
2
2
2
Note:
1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and
SRO-onlyoutlines (i.e., except for one category in Tier 3 ofthe SRO-only outline, the "Tier Totals" in each KIA
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 +/-I from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not
apply at the facility should be deleted and justified; operationally important, site-specific systems that are not
included on the outline should be added. Refer to section D.l.b ofES-401, for guidance regarding elimination of
inappropriate KIA statements.
4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group
before selecting a second topic for any system or evolution.
5.
Absent a plant specific priority, only those KAs having an importance rating (IR) of2.5 or higher shall be
selected, Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6.
Select SROtopics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be
relevant to the applicable evolution or system. Refer to Section D.l.b ofES-401 for the applicable KIA's
8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings
(IR) fanhe applicable license level, and the point totals (#) for each system and category. Enter the group and
tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or
G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the KIA Catalog, and enterthe KIA numbers, descriptions, IRs, and
point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to lOCFR55.43
-
DR FT
2
Form ES-401-1
0610 NRC Exam Outline
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
II EAPE # / Name Safety Function
K1
K2
K3 I A1
A2
G
KIA Topic(s)
295006 SCRAM /1
295021 Loss of Shutdown Cooling / 4
295024 High Drywell Pressure / 5
295026 Suppression Pool High Water
Temp./5
295037 SCRAM Condition Present
and Power Above APRM Downscale
or Unknown /1
295038 High Off-site Release Rate / 9
600000 Plant Fire On-site / 8
295001 Partial or Complete Loss of
Forced Core Flow Circulation / 1 & 4
295001 Partial or Complete Loss of
X
Forced Core Flow Circulation / I & 4
295003 Partial or Complete Loss of
AC/6
AKl.03 - Knowledge of the operational
295004 Partial or Total Loss of DC
implications of the following concepts as they
Pwr/6
X
apply to P ARTlAL OR COMPLETE LOSS OF
D.C. POWER: Electrical bus divisional
AA1.04 - Ability to operate and/or monitor
295005 Main Turbine Generator Trip /
X
the following as they apply to MAIN
3
TURBINE GENERATOR TRIP: Main
295006 SCRAM / I
X
AA2.04 - Ability to determine and/or
295016 Control Room Abandonment /
interpret the following as they apply to
7
CONTROL ROOM ABANDONMENT:
295018 Partial or Total Loss ofCCW /
X
8
295019
lnst.
Air /8
Imp. I Q# II
4.6
76
3.1
77
3.3
78
4.2
79
4.3
80
4.1
81
3.8
82
2.5
39
3.4
40
3.4
41
2.9
42
2.7
43
3.8
44
3.9
45
3.3
46
3.6
47
2
Form ES-401-1
0610 NRC Exam Outline
"
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
~ EAPE # I Name Safet:t Function
K1
K2
K3 I A1 I A2 I G
KIA To~ic(s}
Im~. I Q# II
PARTIAL OR
INSTRUMENT AIR: Status of safety-
related instrument air system loads (see
AK2.1 - AK2.1
2.4.50 - Emergency Procedures I Plan
295021 Loss of Shutdown Cooling I 4
Ability to verify system alarm setpoints and
3.3
48
operate controls identified in the alarm
manual.
AK1.02 - Knowledge of the operational
295023 Refueling Acc Cooling Mode /
X
implications of the following concepts as
3.2
49
8
they apply to REFUELING ACCIDENTS:
Shutdown
.1.33 -
295024 High Drywell Pressure / 5
3.4
50
295025 High Reactor Pressure / 3
X
3.7
51
295026 Suppression Pool High Water
4.1
52
Temp. 15
295028 High Drywell Temperature / 5
X
3.6
53
295030 Low Suppression Pool Water
X
3.4
54
Level15
295031 Reactor Low Water Level / 2
3.1
55
295037 SCRAM Condition Present
and Power Above APRM Downscale
X
3.8
56
or Unknown 11
295038 High Off-site Release Rate 19
X
2.5
57
to operate
600000 Plant Fire On-site I 8
X
the following as they apply to PLANT FIRE
2.6
58
ON SITE: Fire fighting equipment used on
each class of fire
KIA Category Totals:
3
3
3
3
Group Point Total:
2017
3
Form ES-401-1
0610 NRC Exam Outline
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 2
~ EAPE # I Name Safe~ Function
K1
K2
K3 I A1
A2
G
KIA To~ic(s)
Im~. I Q# II
2.4.6 - Emergency Procedures I Plan
295002 Loss of Main Condenser Vac / 3
Knowledge symptom based EOP mitigation
4.0
83
295009 Low Reactor Water Level / 2
3.4
84
500000 High CTMT Hydrogen Conc. /
3.5
85
5
295009 Low Reactor Water Level / 2
X
3.9
59
295012 High Drywell Temperature / 5
3.4
60
295015 Incomplete SCRAM / 1
X
3.9
61
295020 Inadvertent Cont. Isolation / 5 &
X
3.3
62
7
EAl.Ol - Ability to operate
295032 High Secondary Containment
X
following as they apply to HIGH SECONDARY
3.6
63
Area Temperature / 5
CONT~NTAREATEMPERATURE:
Area
EA2.01 - Ability to determine
295033 High Secondary Containment
the following as they apply to HIGH
3.8
64
Area Radiation Levels / 9
RADIATION LEVELS: Area radiation levels
EA2.02 - Ability to
295035 Secondary Containment High
the following as they apply to SECONDARY
CONTAINMENT HIGH DIFFERENTIAL
2.8
65
Differential Pressure / 5
PRESSURE: Off-site release rate: Plant-
KIA Category Totals:
7/3
System # / Name
K
K
1
2
203000 RHRlLPCI: Injection
Mode
215003 IRM
259002 Reactor Water Level
Control
259002 Reactor Water Level
Control
259002 Reactor Water Level
Control
203000 RHRILPCI: Injection
Mode
205000 Shutdown Cooling
206000 HPCI
209001 LPCS
211000 SLC
X
4
Form ES-401-1
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 1
K
K
K
K A A A A G
3
4
5
6
1
2
3
4
I,"
I'!;:;/
A2.16 - Ability to (a) predict the impacts
l~
of the following on the RHRlLPCI:
INJECTION MODE (PLANT SPECIFIC) ;
and (b) based on those predictions, use
<k
'.<<
procedures to correct, control, or mitigate
li/r~
the consequences ofthose abnormal
conditions or operations: Loss of coolant
accident
.'.' .**...
!,~
2.1.14 - Conduct of Operations Knowledge
of system status criteria which require the
"
- . r.' ...* ***.
,/ *.,.r notification of plant personnel.
ri
2.1.23 - Conduct of Operations Ability to
perform specific system and integrated
r
plant procedures during all modes of plant
'rt
operation.
Xl
A2.06 - Abiiity to (a) predict the impacts
of the following on the SHUTDOWN
';
COOLING SYSTEM (RHR SHUTDOWN
)
COOLING MODE); and (b) based on
....
those predictions, use procedures to correct,
~i
control, or mitigate the consequences of
!<
those abnormal conditions SDCIRHR
pumJ'trips
r.\\
A2.12 - Ability to (a) predict the impacts
b:,< of the following on the REACTOR
i~;~~
PROTECTION SYSTEM; and (b) based
r~~
on those predictions, use procedures to
correct, control, or mitigate the
,~
<<
consequences of those abnormal conditions
le,.<l
or operations: Main turbine stop control
.~ .*.. ' .. " .
valve closure
I;;
1*<
AI.Ot - Ability to predict and/or monitor
changes in parameters associated with
X I .**... *
I!l<
operating the RHRlLPCI: INJECTION
><.
Ii
MODE (PLANT SPECIFIC) controls
......
including: Reactor water level
- <<t
~
K4.02 - Knowledge of SHUTDOWN
COOLING SYSTEM (RHR
X
<
SHUTDOWN COOLING MODE)
design feature(s) and/or interlocks
r,:;
which provide for the following: High
L< iJressure isolation: Plant-Specific
'i>
l;t~l/;'
K6.09 - Knowledge of the effect that a
loss or malfunction of the following will
- /
have on the HIGH PRESSURE
X
X~~i
COOLANT INJECTION SYSTEM:
j'
Condensate storage and transfer
system: BWR-2,3,4
~~
<
K5.04 - Knowledge of the operational
<if
implications of the following concepts
X
as they apply to LOW PRESSURE
CORE SPRAY SYSTEM: Heat
"j
removal (transfer) mechanisms
\\i
~.:ir
K2.01 - Knowledge of electrical power
supplies to the following: SBLC pumps
Imp.
Q#
4.5
86
3.3
87
4.0
88
3.5
89
4.1
90
4.2
1
3.7
2
3.5
3
2.8
4
2.9
5
System # / Name
K
K
1
2
212000 RPS
215003 IRM
215004 Source Range Monitor
217000RCIC
218000 ADS
X
218000 ADS
223002 PCIS/Nuciear Stearn
Supply Shutoff
223002 PCIS/Nuciear Stearn
Supply Shutoff
239002 SRVs
239002 SRVs
4
Form ES-401-1
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 1
K
K
K
K
A
A
A
A
G
3
4
5
6
1
2
3
4
x
to (a) predict the impacts
of the following on the AVERAGE
POWER RANGE MONITOR/LOCAL
POWER RANGE MONITOR SYSTEM;
and (b) based on those predictions, use
procedures to correct, control, or
mitigate the consequences of those
abnormal conditions Inoperative trip (all
electrical power
supplies to the following: RCIC flow
controller
.05 - Knowledge ofthe physical
connections and/or cause- effect
relationships between AUTOMATIC
DEPRESSURIZATION SYSTEM and
the following: Remote shutdown
predict the impacts
of the following on the PRIMARY
CONTAINMENT ISOLATION
SYSTEM/NUCLEAR STEAM SUPPLY
SHUT-OFF; and (b) based on those
predictions, use procedures to correct,
control, or mitigate the consequences
of those abn cond or ops. Containment
instrumentation failures
res
A4.08 - Ability to
operate
and/or monitor in the control room:
Plant air system pressure: Plant-
Imp.
Q#
3.5
6
3.1
7
3.6
8
3.6
9
2.7
10
3.9
11
2.8
12
3.0
13
3.4
14
3.6
15
3.2
16
System # / Name
K
K
1
2
259002 Reactor Water Level
Control
261000 SGTS
262001 AC Electrical
Distribution
262002 UPS (ACIDC)
263000 DC Electrical
Distribution
X
264000EDGs
300000 Instrument Air
X
300000 Instrument Air
400000 Component Cooling
Water
400000 Component Cooling
Water
KIA Category Totals:
2
3
4
Form ES-401-1
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 1
K
K
K
K
A
A
A
A
G
3
4
5
6
1
2
3
4
'i'ji
I.****.* ** *** A4.03 - Ability to manually operate
I!~~ .* and/or monitor in the control room: All
.v
X
individual component controllers when
l.;(*
I'~'> transferring from manual to automatic
modes
i
i~
K3.03 - Knowledge of the effect that a
<.
loss or malfunction of the STANDBY
X
GAS TREATMENT SYSTEM will have
- l!'
- .....
on following: Primary containment
pressure: Mark-I&II
'.;! .....
X~;
K4.04 - Knowledge of A.C.
i;~
ELECTRICAL DISTRIBUTION design
X
feature(s) and/or interlocks which
/
provide for the following: Protective
';;'.'
relaying
t;~
'l
A 1.02 - Ability to predict and/or monitor
changes in parameters associated with
X
operating the UNINTERRUPTABLE
\\
POWER SUPPLY (A.C.lD.C.) controls
!
including: Motor generator outputs
......
ili: K1.02 - Knowledge of the physical
1;l'\\!
connections and/or cause- effect
~;:~!
relationships between D.C.
ELECTRICAL DISTRIBUTION and the
./
following: Battery charger and battery
if
ii
K5.06 - Knowledge of the operational
implications of the following concepts
X
as they apply to EMERGENCY
li.;i GENERATORS (DIESEUJET) : Load
sequencing
':;'
K2.02 - Knowledge of electrical power
supplies to the following: Emergency
.*.. :
air compressor
! .. ~)!
Iii <
K3.01 - Knowledge of the effect that a
loss or malfunction of the
X
.l .* ' ** [
- :!; (INSTRUMENT AIR SYSTEM) will
have on the following: Containment air
- .
i
system
"
- ~ *. ~
2.4.31 - Emergency Procedures / Plan
ill
Knowledge of annunciators alarms and
indications, and use of the response
.';
instructions.
I'~:'
~ij
A2.02 - Ability to (a) predict the impacts
of the following on the CCWS and (b)
[~
based on those predictions, use
procedures to correct, control, or
I;)';';
mitigate the consequences of those
abnormal operation: High/low surge
tank level
2
2
2
2
2
~.
3
31;;~ ***
Group Point Total:
Imp.
Q#
3.8
17
3.6
18
2.8
19
2.5
20
3.2
21
3.4
22
3.0
23
2.7
24
3.3
25
2.8
26
I
26/5
System # / Name
K
K
1
2
268000 Radw3.ste
271000 Off-gas
288000 Plant Ventilation
201003 Control Rod and Drive
Mechanism
201006RWM
202001 Recirculation
215001 Traversing In-core Probe
216000 Nuclear Boiler lnst.
X
219000 RHRlLPCI: ToruslPooI
X
Cooling Mode
226001 RHRILPCI: CTMT Spray
Mode
234000 Fuel Handling Equipment
245000 Main Turbine Gen. / Aux.
5
Form ES-401-1
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 2
K
K
K
K A
A
A
A
G
3
4
5
6
1
2
3
4
S(~(T
(' A2.01 - Ability to (a) predict the impacts
of the following on the RADWASTE ; and
~~ *. ~
- .
"
(b) based on those predictions, use
procedures to correct, control, or mitigate
the consequences of those abnormal
>d.
- .f conditions or operations: System rupture
.;(i~.
.'.~(~( ..
2.4.36 - Emergency Procedures I Plan
"'~
- .
Knowledge of chemistry / health physics
tasks during emergency operations.
>>
( ** '
...
A2.03 - Ability to (a) predict the impacts
if
of tile following on the PLANT
1;;<
VENTILATION SYSTEMS; and (b)
- x
based on those predictions, use procedures
......*.
I;~:
to correct, control, or mitigate the
I(
consequences ofthose abnormal conditions
or operations: Loss of coolant accident:
Plant-Specific
1.<
I;*.*****
K3.03 - Knowledge of the effect that a
X
I'
loss or malfunction of the CONTROL
....
1<<
ROD AND DRIVE MECHANISM will
I
have on following: Shutdown margin
1*<< ic';!
K4.09 - Knowledge of ROD WORTH
MINIMIZER SYSTEM (RWM) (PLANT
X
<
SPECIFIC) design feature(s) and/or
~~i
interlocks which provide for the following:
".< ...
System initialization: P-Spec(Not-BWR6)
~;<
K6.09 - Knowledge of the effect that a
cit loss or malfunction of the following will
X
have on the RECIRCULA nON SYSTEM
'.
.
......*.
- Reactor water level
I
A 1.01 - Ability to predict and/or monitor
<
...
changes in parameters associated with
X
operating the TRAVERSING IN-CORE
1<<
- .< ..*.
PROBE controls including: Radiation
levels: (Not-BWR1)
i;
I/<!;~
K1.10 - Knowledge of the physical
connections and/or cause- effect
relationships between NUCLEAR
BOILER INSTRUMENTATION and the
<.
following: Recirculation flow control
> system
I~;<.<
.*.....*......
K2.02 - Knowledge of electrical power
supplies to the following: Pumps
.......
.. <
..*. A4.12 - Ability to manually operate
i<
<.
X £
and/or monitor in the control room:
Containmentldrvwell pressure
2.4.50 - Emergency Procedures I Plan
,i<'"
~;X Ability to verify system alarm setpoints
.. '
and operate controls identified in the
<
,':
alarm response manual.
.
ii . K6.04 - Knowledge of the effect that a
loss or malfunction of the following will
X
1/
k;; have on the MAIN TURBINE
GENERATOR AND AUXILIARY
>
.'
SYSTEMS: Hydrogen coolinR
Imp.
3.5
2.8
3.7
3.2
3.2
3.4
2.8
3.2
3.1
3.8
3.3
2.6
Q#
91
92
93
27
28
29
30
31
32
33
34
35
System # I Name
K
K
1
2
268000 Radwaste
272000 Radiation Monitoring
KIA Category Totals:
1
1
5
Form ES-401-1
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 2
K
K
K
K
A
A
A
A
G
3
4
5
6
1
2
3
4
i/
I"
A2.01 - Ability to (a) predict the
".?(t
impacts of the following on the
~:~i
';~l
RADWASTE ; and (b) based on those
predictions, use procedures to correct,
control, or mitigate the consequences
/<
of those abnormal conditions or
{;
operations: System rupture
,ii;~
"'TI' K5.01 - Knowledge of the operational
implications of the following concepts
X
11~@;
tt~i~
as they apply to RADIATION
MONITORING SYSTEM: Hydrogen
~
injection operation's effect on process
radiation indications: Plant-Specific
!~k
.....* A3.01 - Ability to monitor automatic
....
X
, *** i .. operations of the CONTROL ROOM
' **....*.. ,
..
HVAC including:
Initiation/reconfiguration
1
1
1
2
1 I~{ 1
1 I~
Group Point Total:
Imp.
Q#
2.9
36
3.2
37
3.3
38
I
12/3
Generic Knowledge and Abilities Outline (Tier3)
Form ES-401-3
Facility:
0610 NRC Exam Outline
Date:
KIA #
Topic
SRO-Only
Category
IR
Q#
IR
Q#
2.1.12
Ability to apply technical specifications for a system.
4.0
94
1.
Ability to recognize indications for system operating
2.1.33
parameters which are entry-level conditions for
3.4
66
Conduct
technical specifications.
of Operations
Ability to operate plant phone, paging system, and
2.1.16
two-way radio.
2.9
67
2.1.18
Ability to make accurate, clear and concise logs,
2.9
68
records, status boards, and reports.
Subtotal
lii;iiiiii,;~;ii
3
L'~iii
1
Fir;;ii?iii.:4i!iiiiITj'
2.2.22
Knowledge of limiting conditions for operations and
4.1
95
safety limits.
2.2.24
Ability to analyze the affect of maintenance activities
3.8
96
on LCO status.
2.
Equipment
Control
2.2.l3
Knowledge of tagging and clearance procedures.
3.6
69
2.2.33
Knowledge of control rod programming.
2.5
70
Subtotal
ii<.**...~*****.
2
~iiX*S** .. 3i0~*!*
2
Knowledge of SRO responsibilities for auxiliary
2.3.3
systems that are outside the control room (e.g., waste
2.9
97
disposal and handling systems).
2.3.9
Knowledge ofthe process for perfonning a
3.4
98
containment purge.
3.
Radiation
Ability to perfonn procedures to reduce excessive
Control
2.3.10
levels of radiation and guard against personnel
2.9
71
exposure.
2.3.9
Knowledge of the process for perfonning a
2.5
72
containment purge.
Subtotal
i*.****/;l*
2
r~ 2
4.
Knowledge ofthe parameters and logic used to
Emergency
assess the status of safety functions including: 1
Procedures /
2.4.21
Reactivity control 2. Core cooling and heat removal 3.
4.3
99
Plan
Reactor coolant system integrity 4. Containment
conditions 5. Radioactivity release control.
2.4.30
2.4.47
2.4.15
2.4.8
Tier 3 Point Total
Generic Knowledge and Abilities Outline (Tier3)
Knowledge
which events related to system
operations/status should be reported to outside
Ability to diagnose and recognize trends in an
accurate and timely manner utilizing the appropriate
control room reference material.
Knowledge of
associated with
Knowledge of how the event-based
emergency/abnormal operating procedures are used in
with the
EOPs.
Form ES-401-3
3.6
100
3.4
73
3.0
74
3.0
75
Record of Rejected KIA's
Form ES-401-4
(
Tier / Group
Randomly Selected
Reason for Rejection
KIA
111
2950161 AA2.07
Replaced by NRC Chief Examiner
2/1
218000/2.1.14
Replaced by NRC Chief Examiner
2/1
600000 1 2.2.25
Replaced by NRC Chief Examiner
2/1
2120001 A2.17
Replaced by NRC Chief Examiner
2/1
205000 1 A2.04
Replaced by NRC Chief Examiner
2/1
400000/2.4.30
Replaced by NRC Chief Examiner
Admin
AJPM 501
Replaced due to conflict with independently developed Audit
examination.
In-plant
PJPM63
Removed from exam by direction of Chief Examiner.
In-plant
PJPM66
Removed from exam by direction of Chief Examiner.
In-plant
PJPM 311
Removed from exam by direction of Chief Examiner.
In-plant
PJPM 76F
Removed from exam by direction of Chief Examiner.
In-plant
PJPM 1-8
Developed for Unit-1 by direction of Chief Examiner.
In-plant
PJPM 1-108
Developed for Unit-1 by direction of Chief Examiner.
Simulator
HLTS 3-3
Revised to remove Event 4 at direction of Chief Examiner.
Scenario
Simulator
HLTS 3-4
Revised to add Event 3 at direction of Chief Examiner.
Scenario
Admin
AJPM 511
Replaced due to unsat evaluation by Chief Examiner.
2/1
2610001 K3.06
Replaced by NRC Chief Examiner
(
Administrative Topics Outline
Form ES-301-1
Facility: Browns Ferry Date of Examination: 2/25/08
Examination Level (circle one): RO/SRO Operating Test Number HLT0610
Administrative Topic
(see Note)
Type
Code*
Describe Activity to be performed
Conduct of Operations
0610 AJPM 542F
M
Perform 2-SR-3.4.9.3&4 Reactor Recirculation Pump
Start Limitations (RO/SRO)
Conduct of Operations
0610 AJPM 504
M
Determination of Active/Inactive License Status
(RO/SRO)
Equipment Control
0610 AJPM 120F
P
Perform 2-SR-3.4.2.1 Jet Pump Mismatch and
Operability (OPERATION) (RO/SRO)
Radiation Control
0610 AJPM 511
D
RADCON Dose Limitations (RO/SRO)
0610 AJPM 487TCF
N/S
Classify the Event per the REP (Torus exceeds
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless
they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room
(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
(S)imulator
ES-301, Page 22 of 27
ES-301 Control Room/In Plant Systems Outline Form ES-301-2
Facility: BFN Date of Examination: 2/25/08
Exam Level (circle one): RO / SRO-I / SRO-U Operating Test Number:HLT0610
Control Room Systems (8 for RO; 7for SRO-I; 2 or 3 for SRO-U)
System / JPM Title
Type
Code*
Safety
Function
a.
Respond to a Dual Recirc Pump Trip (OPRM'S Operable)
(0610 SJPM-610F)
ADES
1
b. Perform Control Room Transfer of 4KV Unit Board 3B Power
Supplies (U3 Control Room) (0610 SJPM-222)
NS
6
c.
Restoration to Normal following RPS Bus Power Loss (0610
SJPM-132)
DES
7
d. Respond to Offgas Post Treat HI HI HI (0610 SJPM-190)
DSP
9
e.
Respond to Stuck Open SRV (0610 SJPM-3136F)
AMELS
3
f.
Placing Standby Steam Jet Air Ejector in Operation (0610
SJPM-3116F)
AMES
4
g. Respond to Drywell Pressure and/or Temperature High or
Excessive Leakage into the Drywell - FAULTED - SBGT C
Failed (0610 SJPM-3126F)
ADEMS
5
h. Injection system lineup-CS SYS I (0610 SJPM-322F) (RO)
ADELS
2
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
i.
Bypassing RCIC Test Mode Isolation Interlocks (0610 PJPM-
63)
EMR
3
j.
Place a 250V Battery Charger in Service (0610 PJPM-86)
DL
6
k. Bypassing HPCI High Suppression Pool Water Level Suction
transfer Interlock (0610 PJPM-66)
DEL
2
l.
Respond to Stuck Open SRV (0610 PJPM-76F)
ADE
3
m. Vent and Repressurize the Scram Pilot Air Header (0610
PJPM-8)
DEPR
1
n. Removal and Replacement of RPS Scram Solenoid Fuses
(0610 PJPM-311)
1
- Type Codes
Criteria for RO / SRO-I / SRO-U
(A)lternate Path
(C)ontrol Room
(D)irect from bank
(E)mergency or abnormal in-plant
(L)ow-Power
(N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams
(R)CA
(S)imulator
4-6 / 4-6 / 2-3
9 / 8 / 4
1 / 1 / 1
1 / 1 / 1
2 / 2 / 1
3 / 3 / 2
1 / 1 / 1