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
electronic random
The written examination outline was developed using a proprietary Inc.
outline generator developed by Western Technical Services,
on a true random
The application was developed using Visual Basic code, relying selects topics in a
function based on the PC system clock. The random generator PWR K&A catalogue. The
Microsoft Access Database containing Revision 2 of the process for selection of topics
selected data is then written to a separate data table. The
is similar to the guidance in ES-401, Attachment 1.
report are written
The attached outline report and plant specific suppression profile copies of the data
directly from the data tables created by the software. Electronic
tables are on file.
The process used to develop the outlines is as follows:
included in
- For Tier 1 and Tier 2 generic items, only the items required to be
generation process.
accordance with ES-401, Attachment 2 are included in the
- The Robinson plant suppression profile lists all suppressed items topics, either at the
were
Topic level (System/EPE) or at the statement level. These
suppressed prior to the electronic generation process.
- Outline is generated for all topics with KA importance >2.5.
generic
items, Tier 2 A2 and required generic items, and Tier 3 generic total.
topics are randomly selected to complete the outline, 100 topics
right
- The exam report generated lists the topic (Question) number in the far 76-100.
numbered
column. RO topics are numbered 1-75, and SRO topics are
The SRO topics are written in red ink for ease of identification.
- Items that are rejected after the initial generation process are automatically as an
placed on the rejected items page and the replacement item identified or by
'ADDED' item. The software tracks whether items are added manually generated.
random generation, and a report of outline modification may be
is
- Disposition of any item randomly selected but not included in the outline
documented and included.
PWR Examination Outline Form ES-401-2
Date of Exam: 8/27/2004
Facility: HB Robinson
RO K/A Category Points SRO-Only Points
Tier Group K K K K K K A A A A G Total KA AG Total
1 2 3 4 5 6 1 2 3 4* 2*
7 6 1 18 3 4 7
1. 1 0 04
Emergency 32 5
2 2 22 1 1 1 9
&
Abnormal 8 7 2 27
Plant Tier 2 2 6
Evolutions Totals
1 5 3 0 4 2 28 2 2 4
1 3 4 4 17
2 2 1 0 10 1 1 2
Plant 2 0 0 1 1 1 1
Systems Tier 4 4 4 2 2 2 6 5 2 5 2 38 3 3 6
Totals
1 2 3 4 10 1 2 3 4
3. Generic Knowledge and
Abilities Categories 2 3 2 3 2 3 1 1
within each tier of
Note: 1. Ensure that at least two topics from every K/A category are sampled
be less than two).
the RO outline (i.e., the "Tier Totals" in each K/A category shall not
Refer to Section D.1 .c for additional guidance regarding SRO sampling.
match that specified
2. The point total for each group and tier in the proposed outline must
by +/- from that
in the table. The final point total for each group and tier may deviate
75 points
specified in the table based on NRC revisions. The final RO exam must total
and the SRO-only exam must total 25 points.
two K/A
3. Select topics from many systems and evolutions; avoid selecting more than
priorities.
topics from a given system or evolution unless they relate to plant-specific
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
K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
the
7. On the following pages, enter the K/A numbers, a brief description of each topic,
totals for
topics' importance ratings (IR) for the applicable license level, and the point
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.
on
8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals
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
( (
Fai'O,CS- 4 Ol-2
ES-401 HB Robinson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
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.
2.2.22 Equipment Control Knowledge of limiting conditions for 3.4 39
007-- Recovery/
007 / Reactor Trip - Stabilization Recto Trp 1X
ecovry 1- tabliztio 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
(
-r
ES-401 HB Ro binson l.\
NRC Written Ex*amination Outline
Emergency and Abnormal Pla nt Evolutions - Tier 1 Group 1
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
EM 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 3St am en. ube R up ure E ~ .19 to a SG TR : M FW System status indicator
Ability to operate and / or monitor the following as they
X AA1.13 apply to the Steam Line Rupture: Steam line isolation 4.2 49
040 / Steam Line Rupture - Excessive Heat Transfer 14 valve indications
Ability to determine and interpret the following as they
X AA2.08 apply to the Loss of Main Feedwater (MFW): Steam flow- 2.9 50
054 / Loss of Main Feedwater / 4 feed trend recorder
056 / Loss of Off-site Power/S6 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
X AA2.17 apply to the Loss of Vital AC Instrument Bus: System and 3.1 52
057 / Loss of Vital AC Inst. Bus /6 component status, using local or remote controls
Knowledge of the reasons for the following responses as
X AK3.02 they apply to the Loss of DC Power: Actions contained in 4.0 53
058 / Loss of DC Power 16 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.
5 0 0 4 7 9 Group Point Total: 25
K/A Category Point Totals:
NUREG-1021, Draft Revision 9 3
(
Foh,. ES-41-2
ES-401 HB Robinson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 2
G KI K2 I K3 I Al NK/A Topic(s) Imp. Q#
EI/APE #1/ Name Safety Function
46F
2246 EOP mitigation
Emergency strategies/
Procedures Plan Knowledge symptom based 4.0 83
036/ Accident
036 Fuel Handling / 8X
ue HadlngAccdet
8
Ability to determine and interpret the following as they
E06 /ad. Core Cooling / 4 EA2A1 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,
X 2.4,31 alarms, and indications, and use of the response 3.4 85
E03 / Post-LOCA Cooldown/Depressurization /4 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
X AK2.01 Rod Withdrawal and the following: Rod bank step 2.9 57
001 / Continuous Rod Withdrawal /I
counters
Knowledge of the operational implications of the following
X AK1.21 concepts as they apply to Dropped Control Rod: Delta 2.7 58
003 / Dropped Control Rod / 1
flux (Al)
Knowledge of the reasons for the following responses as
x AK3.02 they apply to the Inoperable ( Stuck Control Rod: Rod 3.6 59
005 / Inoperable/Stuck Control Rod / 1 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
X 2.1.23 and integrated plant procedures during all modes of plant 3.9 61
028 / Pressurizer Level Malfunction / 2 operation.
Ability to operate and / or monitor the following as they
X AA1.02 apply to the Control Room Evacuation: AFW emergency 4.3 62
068 / Control Room Evac. / 8
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
(
TF O.
-S '-4 0 1-2
HB Rob mson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 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
EK..l functions of control and safety systems, including 3.6 64
E06 / Inad. Core Cooling /4
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
X EK3.1 conditions, including coolant chemistry and the effects of 2.9 65
El3 / Steam Generator Over-pressure /4 temperature, pressure, and reactivity changes and
operating limitations and reasons for these operating
characteristics.
3 2 2 2 1 4 Group Point Total: 14
K/A Category Point Total:
NUREG-1 021, Draft Revision 9 5
F-0... c.S-401-2
ES-401 HB Robinson
NRC Written Examination Outline
(' Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
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
X A2 05 on those predictions. use procedures to correct control 35 88
006 Emergency Core Cooling or mitigate the consequences of those malfunctions or
operations Improper amperage to the pump motor
Emergency Procedures ! Plan Knowledge of
x 2 4.31 annunciators alarms and indications, and use of the 3.4 89
012 Reactor Protection 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
X K3.03 RCPS will have on the following: Feedwater and 2.8 1
003 Reactor Coolant Pump
emergency feedwater
003ReatorCooantPum X
X 4.0
A4.07 room: RCP
Ability seal bypass
to manually operate and/or monitor in the control 2.6 2
003 Reactor Coolant Pump
004 Chemical and Volume (203 Knowledge of bus power supplies to the following: 3.3 3
Charging Pumps
Control
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
005 Residual Heat Removal 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
room: to manually of
Recognition leakingand/or
operate PORV/code in the control
monitor safety 3.6 7
Tan
3.0 8
008 Component Cooling Water X K2.02 Knowledge
pump, of bus
including emergency backupto the following: CCW
power supplies
NUREG-1021, Draft Revision 9 6
( (
Fo .. ,-S-40-2
ES-401 HB Robinson
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
G K2 K3 K4 K5 K6 Al A2 A3 K/A Topics Im O#
System #lName
Ability to (a) predict the impacts of the following
malfunctions or operations on the CCWS, and (b) based
X A2.03 on those predictions, use procedures to correct, control, 3.0 9
008 Component Cooling Water
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
X A1.04 (to prevent exceeding design limits) associated with 3.2 13
022 Containment Cooling
operating the CCS controls including: Cooling water flow
Ability to predict and/or monitor changes in parameters
026 Containment Spray 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-
x K1.09 effect relationships between the MRSS and the following 2.7 16
039 Main and Reheat Steam systems: RMS
Knowledge of the physical connections and/or cause-
X K1.03 effect relationships between the Condensate System 2.6 17
056 Condensate
and the following systems: MFW
that a loss or malfunction of the 3.6 18
059 Main Feedwater wX K3.04 Knowledge
MFW will have on effect
of the 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
Forh, ES0-
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
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)
029 064 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
034
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 inthe control 37 24
room Radiation monitoring system control panel
002 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
014
078 nstrmentAir X 4.01
A4.0l room: Pressure
Ability gauges
to manually operate and/or monitor in the control 3.1 27
078 Instrument Air
015
103 Containment X 2.1.2 Conduct of Operations: Knowledge of operator 3.0 28
I I responsibilities during all modes of plant operation.
016 32
K/A Category Point Totals: 4 3 4 4 1 1 5 5 0 4 Group Point Total:
029
034
041
Cor
04E
NL NUREG-1 021, Draft Revision 9 8