ML050950489
| ML050950489 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/26/2004 |
| From: | Division of Nuclear Materials Safety II |
| To: | |
| References | |
| 50-261/04-301 | |
| Download: ML050950489 (10) | |
See also: IR 05000261/2004301
Text
Draft Submittal
ROBINSON AUG/SEPT 2004
EXAM NO. 05000261/2004-301
AUG. 27 - SEPT. 3, 2004
Written Exam Sample outlines
Robinson
2004 NRC Initial License Written Examination
Written Examination Outline Methodology
The written examination outline was developed using a proprietary electronic random
outline generator developed by Western Technical Services, Inc.
The application was developed using Visual Basic code, relying on a true random
function based on the PC system clock. The random generator selects topics in a
Microsoft Access Database containing Revision 2 of the PWR K&A catalogue. The
selected data is then written to a separate data table. The process for selection of topics
is similar to the guidance in ES-401, Attachment 1.
The attached outline report and plant specific suppression profile report are written
directly from the data tables created by the software. Electronic copies of the data
tables are on file.
The process used to develop the outlines is as follows:
- For Tier 1 and Tier 2 generic items, only the items required to be included in
accordance with ES-401, Attachment 2 are included in the generation process.
- The Robinson plant suppression profile lists all suppressed topics, either at the
Topic level (System/EPE) or at the statement level. These items were
suppressed prior to the electronic generation process.
- Outline is generated for all topics with KA importance >2.5.
- 25 SRO topics are randomly selected from Tier 1 AA2 and required generic
items, Tier 2 A2 and required generic items, and Tier 3 generic items (All). 75 RO
topics are randomly selected to complete the outline, 100 topics total.
- The exam report generated lists the topic (Question) number in the far right
column. RO topics are numbered 1-75, and SRO topics are numbered 76-100.
The SRO topics are written in red ink for ease of identification.
- Items that are rejected after the initial generation process are automatically
placed on the rejected items page and the replacement item identified as an
'ADDED' item. The software tracks whether items are added manually or by
random generation, and a report of outline modification may be generated.
- Disposition of any item randomly selected but not included in the outline is
documented and included.
PWR Examination Outline
Form ES-401-2
Facility:
HB Robinson
Date of Exam:
8/27/2004
RO K/A Category Points
SRO-Only Points
Tier
Group
K K K K
K
K
A
A
A
A G
Total
AG
Total
1
2
3
4
5
6
1
2
3
4*
2*
1.
1
0 04
7
6
1
18
3
4
7
Emergency
&
2
2
22
1
1
1
9
32
5
Abnormal
Plant
Tier
2
2
6
8
7
2
27
Evolutions
Totals
1
3
4
4 17
1
5
3
0
4
2
28
2
2
4
Plant
2
0
0
1
1
1
1
2
2
1
0
10
1
1
2
Systems
Tier
4
4
4
2
2
2
6
5
2
5
2
38
3
3
6
Totals
3. Generic Knowledge and
1
2
3
4
10
1
2
3
4
Abilities Categories
2
3
2
3
2
3
1
1
Note:
1.
Ensure that at least two topics from every K/A category are sampled within each tier of
the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two).
Refer to Section D.1 .c for additional guidance regarding SRO sampling.
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 +/- 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.
Select topics from many systems and evolutions; avoid selecting more than two K/A
topics from a given system or evolution 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 (G) 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. The SRO
K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
7.
On the following pages, enter the K/A numbers, a brief description of each topic, the
topics' importance ratings (IR) for the 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; summarize all the SRO-only knowledge and non-A2 ability categories in the
columns labeled "K" and "A". Use duplicate pages for RO and SRO-only exams.
8.
For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on
Form ES-401-3.
9.
Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate
K/A statements.
NUREG-1021, Draft Revision 9
1
(
(
HB Robinson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
Fai'O,
CS-4Ol-2
E/APE#lName Safety Function
G
K1i
K I K3
All
A2
Number
K/A Topic(s)
Imp.
Q#
009 / Small Break LOCA / 3
X
EA204
Ability to determine or interpret the following as they apply
40
76
009 Smal Brak OCA 3
E204
to a small break LOCA: PZR level
Emergency Procedures / Plan Ability to perform without
027 / Pressurizer Pressure Control System Malfunction!
24.49
reference to procedures those actions that require
4.0
77
3
immediate operation of system components and controls.
029 / ATWS / 1
x
EA2.09
Ability to determine or interpret the following as they apply
4.5
78
to a ATWS: Occurrence of a main turbine/reactor trip
Emergency Procedures / Plan Ability to verify system
056 / Loss of Off-site Power / 6
x
24.50
alarm setpoints and operate controls identified in the
3.3
79
alarm response manual.
Ability to determine and interpret the following as they
062 / Loss of Nuclear Svc. Water / 4
X
AA2.02
apply to the Loss of Nuclear Service Water: The cause of
3.6
80
possible CCW loss
E04 / LOCA Outside Containment! 3
X
2,1.28
Conduct of Operations: Knowledge of the purpose and
33
81
function of major system components and controls.
E05 / Inadequate Heat Transfer - Loss of Secondary
x
2.1.27
Conduct of Operations: Knowledge of system purpose
2.9
82
Heat Sink / 4
and or function.
007 / Reactor Trip - Stabilization - Recovery/ 1X
2.2.22
Equipment Control Knowledge of limiting conditions for
3.4
39
007 Recto Trp - tabliztio
-
ecovry 1
2..22
operations and safety limits.
Ability to determine and interpret the following as they
008 / Pressurizer Vapor Space Accident /3
X
AA2.23
apply to the Pressurizer Vapor Space Accident: Criteria
3.6
40
for throttling high-pressure injection after a small LOCA
009/1Small Break LOCA / 3
XEA.17
Ability to operate and monitor the following as they apply
3.4
41
X
to a small break LOCA: PRT
Knowledge of the reasons for the following responses as
011 / Large Break LOCA / 3
X
EK3.03
the apply to the Large Break LOCA: Starting auxiliary feed
4.1
42
pumps and flow, ED/G, and service water pumps
Ability to operate and / or monitor the following as they
015 /17 / RCP Malfunctions /4
X
AA .22
apply to the Reactor Coolant Pump Malfunctions (Loss of
4.0
43
RC Flow): RCP seal failure/malfunction
Ability to operate and / or monitor the following as they
025 / Loss of RHR System 14
X
Al .20
apply to the Loss of Residual Heat Removal System: HPI
2.6
pump control switch, indicators, ammeter running lights,
and flow meter
Ability to determine and interpret the following as they
026 / Loss of Component Cooling Water 18
X
AA2.02
apply to the Loss of Component Cooling Water: The
2.9
45
cause of possible CCW loss
I
NUREG-1021, Draft Revision 9
2
HB Ro
NRC Written Ex*
Emergency and Abnormal Pla
(
binson
amination Outline
nt Evolutions - Tier 1 Group 1
-r
l.\\
E/APE #/ Name Safety Function
G
Ki
K2
K3
Al [A2
Number
K/A Topic(s)
Imp.
Q#
Ability to determine and interpret the following as they
027 / Pressurizer Pressure Control System Malfunction
X
AA2.17
apply to the Pressurizer Pressure Control Malfunctions:
3.1
46
3
Allowable RCS temperature difference vs. reactor power
Ability to operate and monitor the following as they apply
4.0
47
029 / AWNS /1
Eto
a ATWS: Manual rod control
038 / Steam Gen. Tube Rupture / 3
EM.19
Ability to operate and monitor the following as they apply
3.4
48
038 St am
en.
ube R up ure
3
E ~ .19
to a SG TR : M FW System status indicator
Ability to operate and / or monitor the following as they
040 / Steam Line Rupture - Excessive Heat Transfer 14
X
AA1.13
apply to the Steam Line Rupture: Steam line isolation
4.2
49
valve indications
Ability to determine and interpret the following as they
054 / Loss of Main Feedwater / 4
X
AA2.08
apply to the Loss of Main Feedwater (MFW): Steam flow-
2.9
50
feed trend recorder
056 / Loss of Off-site Power/S 6
AA256
Ability to determine and interpret the following as they
3.6
51
apply to the Loss of Offsite Power: RCS T-ave
Ability to determine and interpret the following as they
057 / Loss of Vital AC Inst. Bus /6
X
AA2.17
apply to the Loss of Vital AC Instrument Bus: System and
3.1
52
component status, using local or remote controls
Knowledge of the reasons for the following responses as
058 / Loss of DC Power 16
X
AK3.02
they apply to the Loss of DC Power: Actions contained in
4.0
53
EOP for loss of dc power
Ability to operate and f or monitor the following as they
062 / Loss of Nuclear Svc. Water /4
AA.07
apply to the Loss of Nuclear Service Water: Flow rates to
2.9
54
the components and systems that are serviced by the
CCWS; interactions among the components
Knowledge of the reasons for the following responses as
65 /Loss of
AK3.03
they apply to the Loss of Instrument Air: Knowing effects
2.9
55
/ L
Instrument Air / 8
on plant operation of isolating certain equipment from
instrument air
Knowledge of the reasons for the following responses as
they apply to the (Loss of Secondary Heat Sink) RO or
E05 / Inadequate Heat Transfer - Loss of Secondary
X
EK3.4
SRO function as a within the control room team as
3.7
56
Heat Sink / 4
appropriate to the assigned position, in such a way that
procedures are adhered to and the limitations in the
facilities license and amendments are not violated.
K/A Category Point Totals:
5
0
0
4
7
9
Group Point Total:
25
NUREG-1021, Draft Revision 9
3
(
E
HB Robinson
NRC Written Examination Outline
mergency and Abnormal Plant Evolutions - Tier 1 Group 2
Foh,. ES-41-2
EI/APE #1/ Name Safety Function
G
KI
K2 I K3 I Al
NK/A
Topic(s)
Imp.
Q#
036 Fuel Handling Accident / 8
246
Emergency Procedures / Plan Knowledge symptom based
4.0
83
036/ ue HadlngAccdet
8X
2 46F
EOP mitigation strategies
Ability to determine and interpret the following as they
E06 /ad.
Core Cooling / 4
EA2A 1
apply to the (Degraded Core Cooling) Facility conditions
42
84
and selection of appropriate procedures during abnormal
and emergency operations
Emergency Procedures / Plan Knowledge of annunciators,
E03 / Post-LOCA Cooldown/Depressurization /4
X
2.4,31
alarms, and indications, and use of the response
3.4
85
instructions
Ability to determine and interpret the following as they
EA2
apply to the (High Containment Pressure) Facility
3.8
86
E14 / Loss of CTMT Integrity / 5
2
conditions and selection of appropriate procedures during
abnormal and emergency operations.
Ability to determine and interpret the following as they
EA21
apply to the (High Containment Radiation) Facility
33
87
E16 HighContainment Radiation/ 9EA
conditions and selection of appropriate procedures during
abnormal and emergency operations.
Knowledge of the interrelations between the Continuous
001 / Continuous Rod Withdrawal /I
X
AK2.01
Rod Withdrawal and the following: Rod bank step
2.9
57
counters
Knowledge of the operational implications of the following
003 / Dropped Control Rod / 1
X
AK1.21
concepts as they apply to Dropped Control Rod: Delta
2.7
58
flux (Al)
Knowledge of the reasons for the following responses as
005 / Inoperable/Stuck Control Rod / 1
x
AK3.02
they apply to the Inoperable ( Stuck Control Rod: Rod
3.6
59
insertion limits
04/EeecX
AA204
Ability to determine and interpret the following as they
34
60
024 Emergency
oration / 1
Xapply
to the Emergency Boration: Availability of BWST
Conduct of Operations: Ability to perform specific system
028 / Pressurizer Level Malfunction / 2
X
2.1.23
and integrated plant procedures during all modes of plant
3.9
61
operation.
Ability to operate and / or monitor the following as they
068 / Control Room Evac. / 8
X
AA1.02
apply to the Control Room Evacuation: AFW emergency
4.3
62
pump
Knowledge of the operational implications of the following
E02 / Rediagnosis & SI Termination 13
X
EKi2
aconcepts as they apply to the (SI Termination) Normal,
3.4
63
abnormal and emergency operating procedures
associated with (SI Termination).
NUREG-1021, Draft Revision 9
4
(
HB Rob mson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 2
T F
O.
-S '- 4 0 1 -2
E/APE #,/ Name Safety Function
G
KI1
K2
K3
Al
A2
Number
KIA Topic(s)
mp,. IQ
Knowledge of the interrelations between the (Degraded
Core Cooling) and the following: Components, and
E06 / Inad. Core Cooling /4
EK..l
functions of control and safety systems, including
3.6
64
instrumentation, signals, interlocks, failure modes, and
automatic and manual features.
Knowledge of the reasons for the following responses as
they apply to the (Steam Generator Overpressure)
Facility operating characteristics during transient
El3 / Steam Generator Over-pressure /4
X
EK3.1
conditions, including coolant chemistry and the effects of
2.9
65
temperature, pressure, and reactivity changes and
operating limitations and reasons for these operating
characteristics.
K/A Category Point Total:
3
2
2
2
1
4
Group Point Total:
14
NUREG-1 021, Draft Revision 9
5
( '
HB Robinson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
F-0... c.S-401-2
System #/Name
G
K1
K2
K3
K4
K5
KS
Al
A
A3
A4
Number
KnA Topics
Imp.
Q#
Ability to (a) predict the impacts of the following
malfunctions or operations on the ECCS: and (b) based
006 Emergency Core Cooling
X
A2 05
on those predictions. use procedures to correct control
35
88
or mitigate the consequences of those malfunctions or
operations Improper amperage to the pump motor
Emergency Procedures ! Plan Knowledge of
012 Reactor Protection
x
2 4.31
annunciators alarms and indications, and use of the
3.4
89
response instructions
Ability to (a) predict the impacts of the following
malfunctions or operations on the CCS: and (b) based
022 Containment Cooling
A2.03
on those predictions. use procedures to correct, control,
or mitigate the consequences of those malfunctions or
operations: Fan motor thermal overload/high-speed
operation
Conduct of Operations: Knowledge of system status
d061
Auxilary/Emergency
X
21 14
criteria which require the notification of plant personnel
33
91
Knowledge of the effect that a loss or malfunction of the
003 Reactor Coolant Pump
X
K3.03
RCPS will have on the following: Feedwater and
2.8
1
emergency feedwater
003 Reactor Coolant Pump
X
A4.07
Ability to manually operate and/or monitor in the control
2.6
2
003ReatorCooantPum
X
4.0
room: RCP seal bypass
004 Chemical and Volume
(203
Knowledge of bus power supplies to the following:
3.3
3
Control
Charging Pumps
Ability to (a) predict the impacts of the following
malfunctions or operations on the RHRS, and (b) based
X
A2,04
on those predictions, use procedures to correct, control,
2.9
4
or mitigate the consequences of those malfunctions or
operations: RHR valve malfunction
Knowledge of the physical connections and/or cause-
X
K1.01
effect relationships between the RHRS and the following
3.2
5
systems: CCWS
Ability to predict and/or monitor changes in parameters
(to prevent exceeding design limits) associated with
3.6
6
006 Emergency Core Cooling
XAl.06
operating the ECCS controls including: Subcooling
margin
007 Pressurizer Relief/Quench
X
A4.10
Ability to manually operate and/or monitor in the control
3.6
7
Tan
room: Recognition of leaking PORV/code safety
008 Component Cooling Water
X
K2.02
Knowledge of bus power supplies to the following: CCW
3.0
8
pump, including emergency backup
NUREG-1021, Draft Revision 9
6
(
(
HB Robinson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
Fo .. ,-S-40-2
System #lName
G
K2
K3
K4
K5
K6
Al
A2
A3
K/A Topics
Im
O#
Ability to (a) predict the impacts of the following
malfunctions or operations on the CCWS, and (b) based
008 Component Cooling Water
X
A2.03
on those predictions, use procedures to correct, control,
3.0
9
or mitigate the consequences of those malfunctions or
operations: High/low CCW temperature
Ability to predict and/or monitor changes in parameters
010 Pressurizer Pressure Control
Al.04
(to prevent exceeding design limits) associated with
3.6
10
operating the PZR PCS controls including: Effects of
temperature change during solid operation
012 Reactor Protection
K3.02
Knowledge of the effect that a loss or malfunction of the
3.1
11
I RPS will have on the following: TIG
013 En
daf
Features
KKnowledge of the effect that a loss or malfunction of the
4.3
12
AcuaEngineered SaetF
e
X
K3.03
ESFAS will have on the following: Containment
Actuation
__________________________
___
Ability to predict and/or monitor changes in parameters
022 Containment Cooling
X
A1.04
(to prevent exceeding design limits) associated with
3.2
13
operating the CCS controls including: Cooling water flow
Ability to predict and/or monitor changes in parameters
X
At .01
(to prevent exceeding design limits) associated with
39
14
operating the CSS controls including: Containment
pressure
Ability to predict and/or monitor changes in parameters
039 Main and Reheat Steam
Al1.06
(to prevent exceeding design limits) associated with
3.0
15
operating the MRSS controls including: Main steam
pressure
Knowledge of the physical connections and/or cause-
039 Main and Reheat Steam
x
K1.09
effect relationships between the MRSS and the following
2.7
16
systems: RMS
Knowledge of the physical connections and/or cause-
056 Condensate
X
K1.03
effect relationships between the Condensate System
2.6
17
and the following systems: MFW
059 Main Feedwater
K3.04
Knowledge of the effect that a loss or malfunction of the
3.6
18
wX
MFW will have on the following: RCS
061 Auxillary/Emergency
x
K6.02
Knowledge of the effect of a loss or malfunction of the
x
following will have on the AFW components: Pumps
2.6
19
Knowledge of ac distribution system design feature(s)
062 AC Electrical Distribution
X
K4.02
and/or interlock(s) which provide for the following: Circuit
2.5
20
breaker automatic trips
Knowledge of bus power supplies to the following: Major
2.9
21
3DEtibution
X
K2.01
Idc loads
NUREG-1021, Draft Revision 9
7
"I1
HB Robinson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
Forh, E S0-
029
034
System #/Name
G
K
K2
K3
K4
K5
KS
A
A2
A3
A4
Number
K/A Topics
Imp.
I0
Ability to (a) predict the impacts of the following
malfunctions or operations on the ED/G system; and (b)
064 Emergency Diesel Generator
X
A2.13
based on those predictions, use procedures to correct,
2.6
22
control, or mitigate the consequences of those
malfunctions or operations: Consequences of opening
auxiliary feeder bus (ED/G sub supply)
Knowledge of the operational implications as they apply
073 Process Radiation Monitoring
x
K5.02
to concepts as they apply to the PRM system: Radiation
2.5
23
intensity changes with source distance
073 Process Radiation Monitoring
X
A4.02
Ability to manually operate and/or monitor in the control
37
24
room Radiation monitoring system control panel
Conduct of Operations: Ability to recognize indications
076 Service Water
X
2.1.33
for system operating parameters which are entry-level
3.4
25
conditions for technical specifications.
078 Instrument Air
X
K2.02
Knowledge of bus power supplies to the following
3.3
26
078 nstumen Ai
X
K.02
Emergency air compressor
078 Instrument Air
X
A4.0l
Ability to manually operate and/or monitor in the control
3.1
27
078 nstrmentAir
4.01
room: Pressure gauges
103 Containment
X
2.1.2
Conduct of Operations: Knowledge of operator
3.0
28
I
I responsibilities during all modes of plant operation.
K/A Category Point Totals:
4
3
4
4
1
1
5
5
0
4
Group Point Total:
32
002
014
015
016
029
034
041
Cor
04E
NL
NUREG-1 021, Draft Revision 9
8