ML020510569
| ML020510569 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/06/2002 |
| From: | Operator Licensing and Human Performance Branch |
| To: | |
| References | |
| 50-302/02301 | |
| Download: ML020510569 (42) | |
See also: IR 05000302/2002301
Text
Draft Submittal
(Pink Paper)
Written Exam Sample outlines
CRYSTAL RIVER EXAM
50-302/2002-301
JAN. 28 - FEB. 6, 2002
C (
PWR RO Examination Outline Worksheet
IKIA/GI Totals 12 9 15 4 4 2 10 12 3 6 10 1
( C (
Emergency and Abnormal Plant Evolutions - Tierl/Groupl
EIAPE # I Name / Safety Function K1 K2 K3 Al A2 G KJA Topic(s) Imp. Points
000005 Inoperable/Stuck Control Rod / I
AA1.03 Ability to operate and / or monitor
the following as they apply to the Reactor
0G0015/17 RCP Malfunctions IV 1 Coolant Pump Malfunctions (Loss of RC
Flow): Reactor trip alarms, switches, and
indicators 3.7
E09 Natural Circ. I IV
000024 Emergency Boration / I
AA2.01 Ability to determine and interpret
the following as they apply to the Loss of
000026 Loss of Component Cooling Water VIll Nuclear Services / Decay Heat Closed
Cycle Cooling: Location of a leak in the
NOTE 1 2.9
AA1.01 Ability to operate and / or monitor
000027 Pressurizer Pressure Control System Malfunction Ill 1 the following as they apply to the
Pressurizer Pressure Control Malfunctions:
PZR heaters, sprays, and PORVs 4.0
000040 (EO5) Steam Line Rupture (Excessive Heat Transfer) / IV
AA2.02 Ability to determine and interpret
the following as they apply to the Loss of 3.9 1
Condenser Vacuum: Conditions requiring
reactor and/or turbine trip
000051 Loss of Condenser Vacuum I IV 1
2.4.48 Ability to interpret control room
indications to verify the status and operation
of system, and understand how operator
actions and directives affect plant and
system conditions. 3.5 1
(
Emergency and Abnormal Plant Evolutions Tierl/Groupl
EIAPE # / Name I Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
EA1.06 Ability to operate and monitor the
following as they apply to a Station
Blackout: Restoration of power with one 4.1
ED/G
0)00055 Station Blackout I VI1 1 EA2. 0 4A Ability to determine
or interpret
the following as they apply to a Station
Blackout Instruments and controls
operable with only dc battery power
available 3.7 1
AK3.01 Knowledge of the reasons for the
following responses as they apply to the 4.1 1
Loss of Vital AC Instrument Bus: Actions
contained in EOP for loss of vital ac
000057 Loss of Vital AC Elec. Inst. Bus I VI electrical instrument bus
AA1.05 Ability to operate and I or monitor
the following as they apply to the Loss of
Vital AC Instrument Bus: Backup
instrument indications 3.2
000062 Loss of Nuclear Service Water / IV
AKI.01 Knowledge of the operational
000067 Plant Fire On-site / IX implications of the following concepts as
they apply to Plant Fire on Site: Fire
classifications, by type 2.9 1
AK2.07 Knowledge of the interrelations 3.3 1
between the Control Room Evacuation and
the following: ED/G
000068 (ADS) Control Room Evac. / VIII
2.4. 3 4A Knowledge of RO tasks performed
outside the main control room during
emergency operations including system
1000069 Loss of CTMT Integrity I V geography and system implications. 3.8
000069 LOSS of CTMT Integrity i V
! !
Emergency and Abnormal Plant Evolutions - Tierl/Groupl
E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
2.4.21A Knowledge of the parametersand
logic used to assess the status of safety
functions including:
000074 Inad. Core Cooling i IV 1 . Reactivity contro
2. Core cooling and heat removal
3. Reactor coolant system integrity
4. Reactor Building conditions
5. Radioactivity releasecontrol. 3.7
EK1.2 Knowledge of the operational
implications of the following concepts as
they apply to the (Inadequate Subcooling
Monitor): Normal, abnormal and emergency
operating procedures associated with (HPI
Termination). 3.8
E03 Inadequate Subcooling Margin / IV EK3.1 Knowledge of the reasons for the
following responses as they apply to the
(Inadequate Subcooling Monitor): Facility
operating characteristics during transient
conditions, including coolant chemistry and
the effects of temperature, pressure, and
reactivity changes and operating limitations
and reasons for these operating
characteristics. 3.2
AA2.02 Ability to determine and interpret
the following as they apply to the High
0o0076 High Reactor Coolant Activity /IX Reactor Coolant Activity: Corrective actions
required for high fission product activity in
______________________NOTE 1 2.8
/ VII
A02&A03 Loss of NNI-XIY
K/A Category Totals: 2 1 2 4 4 3 Group Point Total= 16
!' (.
Emergency and Abnormal Plant Evolutions - Tierl/Group2
E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
000001 Continuous Rod withdrawal / I
AK1.13 Knowledge of the operational
implications of the following concepts as
000003 Dropped Control Rod /I they apply to Dropped Control Rod:
Interaction of ICS control stations as well as
purpose, function, and modes of operation
of ICS 3.2
EK2.02 Knowledge of the interrelations
000007 (E02&E1O) Reactor Trip - Stabilization - Recovery /II between a reactor trip and the following:
Breakers, relays and disconnects 2.6
A01 Plant Runback / I
AK3.2 Knowledge of the reasons for the
following responses as they apply to the
A04 Turbine Trip / IV (Turbine Trip): Normal, abnormal and
emergency operating procedures
associated with (Turbine Trip). 3.4
AK3.02 Knowledge of the reasons for the
following responses as they apply to the
000008 Pressurizer Vapor Space Accident I 1 Pressurizer Vapor Space Accident: Why
PORV or code safety exit temperature is
below RCS or PZR temperature 3.6 1
000009 Small Break LOCAI/ III 2.4.2 4A Knowledge of loss of cooling water
vrocedures. 3.3 1
EK2.02 Knowledge of the interrelations
000011 Large Break LOCA /1III between the Large Break LOCA and ECCS
pumps. 2.6
2.1.28 Knowledge of the purpose and
E08 LOCA Cooldown/Depress. / IV 1 function of major system components and
controls. 3.2
000022 Loss of Reactor Coolant Makeup 1Il
000025 Loss of RHR System I IV
EK1.03 Knowledge of the operational
000029 Anticipated Transient w/o Scram I I implications of the following concepts as
they apply to the ATWS: Effects of boron
on reactivity 3.6
( ( r
Emergency and Abnormal Plant Evolutions - Tierl/Group2
E/APE # I Name i Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
AA2.02 Ability to determine and interpret
the following as they apply to the Loss of
000032 Loss of Source Range NI / VII 1 Source Range Nuclear Instrumentation:
Expected change in source range count rate
when rods are moved 3.6
AK3.01 Knowledge of the reasons for the
following responses as they apply to the
Loss of Intermediate Range Nuclear
000033 LossofntermediateRangeNi/VII 1Instrumentation: Termination of startup
following loss of intermediate-range
instrumentation 3.2
AKI.01 Knowledge of the operational
000037 Steam Generator Tube Leak / III implications of the following concepts as
they apply to Steam Generator Tube Leak:
Use of steam tables 2.9
EA2. 1 5A Ability to determine or interpret
000038 Steam Generator Tube Rupture/ilII the following as they apply to a SGTR:
Pressureat which to maintain RCS durinQ
S/G cooldown 4.2
AK3.01 Knowledge of the reasons for the
000054 Loss of Main Feedwater / IV following responses as they apply to the
Loss of Main Feedwater (MFW): Reactor
and/or turbine trip, manual and automatic 4.1
EK2.1 Knowledge of the interrelations
between the (Inadequate Heat Transfer) and
the following: Components, and functions of
E04 Inadequate Heat Transfer - Loss of Secondary Heat Sink / IV 1 control and safety systems, including
instrumentation, signals, interlocks, failure
modes, and automatic and manual
features. 3.8
000058 Loss of DC Power I VI
AK2.01 Knowledge of the interrelations
000059 Accidental Liquid Radlaste Rel. I IX 1between the Accidental Liquid Radwaste
Release and the following: Radioactive
liquid monitors 2.7
!
Emergency and Abnormal Plant Evolutions - Tierl/Group2
EIAPE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points
000060 Accidental Gaseous Radwaste Rel. IX 1A1-02 Ability to operate and / or monitor
the following as they apply to the Accidental
Gaseous Radwaste: Ventilation system 2.9
AA1.01 Ability to operate and / or monitor
000061 ARM SystemnAlarmss/VII 1 the following as they apply to the Area
Radiation Monitoring (ARM) System Alarms:
Automatic actuation 3.6
K/A Category Totals: 3 4 4 2 2 2 Group Point Total = 17
(
Emergency and Abnormal Plant Evolutions Tierl/Group3
E/APE # I Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
000028 Pressurizer Level Malfunction / II
000036 (A08) Fuel Handling Accident / VIii
AK3.02 Knowledge of the reasons for the
000056 Loss of Off-site Power/VI 1following responses as they apply to the
Loss of Offsite Power: Actions contained in
EOP for loss of offsite power 4.4
AK3.08 Knowledge of the reasons for the
000065 Loss of Instrument Air I VIII following responses as they apply to the
Loss of Instrument Air: Actions contained in
AOP for loss of instrument air 3.7
E13&E14 EOP Rules and Enclosures
AK2.1 Knowledge of the interrelations
between the (Emergency Diesel Actuation)
A05 Emergency Diesel Actuation I VI and the following: Components, and
functions of control and safety systems,
including instrumentation, signals,
interlocks, failure modes, and automatic and
manual features. 4.0
A07 Flooding / VIII
K/A Category Totals: 01 1I I0 I° I°0 I Group Point Total = 3j
/I
(
Plant Systems - Tier2/Groupl
System # Name KI K2 K3 K4 KS K6 Al A2 A3 A4 G K/A Topic Imp. Points
K1.09 Knowledge of the physical connections
and/or cause-effect relationships between the 2.8 1
CRDS and the SW system (must be cut in
before energizing CRDS).
001 Control Rod Drive 1 1 A4.04A Ability to manually operate and/or 3.9 1
monitor APSR rod position.
2.1.32 Ability to explain and apply all system
limits and precautions.
NOTE 1 3.4 1
K3.05 Knowledge of the effect that a loss or
malfunction of the RCPs will have on the
following: ICS
A2.01A Ability to (a) predict the impacts of the
003 Reactor Coolant Pump 1 1 following malfunctions or operationson the
RCPs; and (b) based on those predictions,use
oroceduresto correct, control, or mitiqate the
consequences of those malfunctions or
operations: Problems with RCP seals,
especially rates of seal leak-off
K3.04 Knowledge of the effect that a loss or
malfunction of the MUPS will have on the RCP's
004 Chemical and Volume Control 1.71
2.1.30 Ability to locate and operate
components, including local controls. 39
Plant Systems - Tier2/Groupl
System #/ Name K1 K2 K3 K4 KS K6 Al A2 A3 A4 G K/A Topic Imp. Points
K2.01 Knowledge of bus power supplies to the
ESFAS / safeguards equipment control. 3.6 1
NOTE 3
K3.02 Knowledge of the effect that a loss or 4.3 1
malfunction of the ESFAS will have on the RCS.
013 Engineered Safety Features Actuation
A2.06^ Ability to (a) predict the impacts of the
following malfunctions or operationson the
ESFAS: and (b) based Ability on those
Predictions, use Proceduresto correct, control,
or mithgate the consequences of those
malfunctions or operations; Inadvertent ESFAS
actuation 3.7
A4.01 Ability to manually operate and/or
015 Nuclear Instrumentation monitor in the control room: Selection of
controlling NIS channel 3.6 1
A 1.01^ Ability to predict and/ormonitor
changes in Parameters(to prevent exceeding 3.7 1
design limits) associatedwith operatingthe ITM
system controls including: Core exit
017 In-core Temperature Monitor 1 temperatur
2.2.34^ Knowledge of the process for
determining the internaland external effects on
core reactivity. 3.2
K2.01 Knowledge of power supplies to the 3.0 1
following: Reactor Building cooling fans
022 containment Cooling K3.01^ Knowledge of the effect that a loss or
malfunction of the CCS will have on the
following: ReactorBuilding equipment subject
to damage by high or low temperature,
humidity, and pressure 2.9 1
( (
Plant Svstenmns - Tier2/Grounl
System #/ Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic Imp. Points
K1.03 Knowledge of the physical connections
and/or cause-effect relationships between the
056 Condensate 1 Condensate System and the following systems:
NOTE 1 2.6 1
K1.07 Knowledge of the physical connections
and/or cause-effect relationships between the
MFW and the following systems: ICS 3.2 1
059 Main Feedwater 1 K4. 18A Knowledge of MFWdesiqn feature(s)
and/orinterlock(s) which provide for the
following: Automatic feedwater reduction on
plant trip.
NOTE 4 2.8
K1.01 Knowledge of the physical connections
061 Auxiliary/Emergency Feedwater 1 and/or cause-effect relationships between the
EFW and the following systems: S/G system
NOTE 5 (RO only) 4.1 1
K6. 10 Knowledge of the effect of a loss or
068 Liquid Radwaste 1 malfunction on the following will have on the
Liquid Radwaste System: Radiation monitors 2.5 1
K5.04A Knowledge of the operational
implication of the following concepts as they
071 Waste Gas Disposal 1 apply to the Waste Gas Disposal System:
Relationship of hydrogen/oxygen
concentrationsto flammability 2.5 1
( ( (
Plant Systems - Tier2/Groupl
System #1 Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic Imp. Points
A4.03 Ability to manually operate and/or
monitor in the control room: Check source for 3.1 1
operability demonstration
072 Area Radiation Monitoring
A3.01A Ability to monitorautomatic operation of
the ARM system, including: Changes in
ventilation alignment
NOTE 4 2.9 1
K/A Category Totals:j 41214 1 1 1 .I211 2 31 31 Group Point Total= 23
!
Plant Systems - Tier21Group2
System #/ Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KIA Topic Imp. Points
K5.10 Knowledge of the operational
implications of the relationship between reactor
002 Reactor Coolant power and RCS differential temperature as it
applies to the RCS.
NOTE 1 3.6
006 Emergency Core Cooling 1A3.03 Ability to monitor automatic operation of
the ECMS, including: ESFAS-operated valves 4.1
K2.03 Knowledge of bus power supplies to the
010 Pressurizer Pressure Control following: Indicator for PORV position
NOTE 4/5 2.8
011 Pressurizer Level Control
K6.04 Knowledge of the effect of a loss or
012 Reactor Protection malfunction of the following will have on the
RPS: Bypass-block circuits
NOTE 3 3.3 1
K4.04 Knowledge of RPIS design feature(s) 2.6 1
which provide zone reference lights.
NOTE I
A2.04 A Ability to (a) predict the impacts of a
misaliqned rod on the RPIS: and (b) based on 3.4 1
those predictions, use procedures to correct,
control, or mitiqate the consequences of this
014 Rod Position Indication 1 2 malfunction.
A2.01 Ability to (a) predict the impacts of the
following malfunctions or operations on the
RPIS; and (b) based on those predictions, use
procedures to correct, control, or mitigate the
consequences of those malfunctions or
operations: Loss of offsite power
___ ______
__ ___ __ ___ ___ __ ___ ___ NOTE__1 ___ ___ __ ___ ___ __ ___ ___ __ 2.81
( (
Plant Systems - Tier2IGroun2
System # Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic Imp. Points
2.1.31 Ability to locate control room switches,
016 Non-nuclear Instrumentation controls
they are and indications
correctly andthe
reflecting to determine that
desired plant
lineup. 4.2 1
A1.06 Ability to predict and/or monitor changes
in parameters (to prevent exceeding design
026 Containment Spray limits) associated with operating the BSS
controls including: Reactor Building spray pump
cooling 2.7 1
K1.01 Knowledge of the physical connections
029 Containment Purge and/or cause-effect relationships between the
Containment Purge System and the following:
Gaseous radiation release monitors
3.4 1
K3.03A Knowledqe of the effect that a loss or
033 Spent Fuel Pool Cooling malfunction of the Spent Fuel Pool Cooling
System will have on the following: Spent fuel
temperature 3.0 1
K4.01A Knowledge of SIGS design feature(s) 3.6 1
and/or interlock(s) which provide for S/G level
control
035 Steam Generator
K5.01 Knowledge of the effect of secondary
parameters, pressure, and temperature on
reactivity as they apply to the S/GS. 3.4 1
A4.03 Ability to manually operate and/or
monitor in the control room: MFW pump 2.8 1
turbines
039 Main and Reheat Steam 2
A4.01A Ability to manually operate and/or
monitorin the control room: Main steam supply
valves 2.9 1
r (.
Plant Systems* - Tier21/Groun2
System # Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic Imp. Points
K3.01 Knowledge of the effect that a loss or
055 Condenser Air Removal 1malfunction of the CARS will have on the
following: Main condenser
NOTE 1 2.5 1
A3.04 Ability to monitor automatic operation of
062 AC Electrical Distribution the AC distribution system, including: Operation
of inverter (e.g., precharging synchronizing light,
static transfer) 2.7 1
063 DC Electrical Distribution
K3.02 Knowledge of the effect that a loss or
064 Emergency Diesel Generator 1 malfunction of the ED/G system will have on the
following: ESFAS controlled or actuated
systems 4.2 1
073 Process Radiation Monitoring
K1.01 Knowledge of the physical connections
075 Circulating Water and/or cause-effect relationships between the
CW system and the following systems: RW
System 2.5 1
079 Station Air
A1.01 Ability to predict and/or monitor changes
in parameters (to prevent exceeding design
086 Fire Protection 1 limits) associated with Fire Protection System
Plant pressure
operating the controls including: Fire header 2-9 1
K/A Category Totals: 2 1 3 2 2 1 2 2 2 2 1 Group Point Total = 20
/ (
Plant Systems - Tier2/Group3
System # I Name K1 I K2 K31 K4 K5 K6 Al A21 A31 A4 G K/A Topic Imp. Points
K5.02 Knowledge of the operational
implications of the following concepts as they
apply the Decay Heat System: Need for
adequate subcooling 3.4
007 Pressurizer Relief/Quench Tank
K4.09 Knowledge of SWS / DCS design
008 Component Cooling Water feature(s) and/or interlock(s) which provide for
the standby feature of the SWS / DCS pumps. 2.7
2.1.28 Knowledge of the purpose and function
027 Containment Iodine Removal of major system components and controls.
NOTE 1 3.2
028 Hydrogen Recombiner and Purge Control
A2.02 Ability to (a) predict the impacts of the
following malfunctions or operations on the Fuel
Handling System ; and (b) based those
predictions, use procedures to correct, control,
or mitigate the consequences of those
034 Fuel Handling Equipment 1
malfunctions or operations: Dropped cask
3.4 1
NOTE 1
A4.02A Ability to manually operate and/or
monitor in the control room: Neutron levels
3.5
041 Steam Dump/Turbine Bypass Control
K1.18 Knowledge of the physical connections
'045 Main Turbine Generator and/or cause-effect relationships between the
MT/G system and the RPS.
NOTE 1 3.6
t (1
Plant Svystems - Tier21Gr~niin
System #/ Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic Imp. Points
A2.01 Ability to (a) predict the impacts of the
following malfunctions or operations on the
076 Service Water 1 RWS; and (b) based on those predictions, use
procedures to correct, control, or mitigate the
consequences of those malfunctions or
operations: Loss of RWS 3.5
078 Instrument Air
A1.01 Ability to predict and/or monitor changes
in parameters (to prevent exceeding design
103 Containment limits) associated with operating the reactor
building system controls including: Reactor
Building pressure and temperature 3.7
K/A Category Totals: 1 0 0 1 1 0 1 2 0 1 1 Group Point Total = 8
(
Generic Knowledges and Abilities
Category KA # KIA Topic Imp. Points
2.1.17A
2.1.17^ Ability to make accurate, clearand concise verbal reports 3.5 1
Conduct of 2.1.19A 2.1.19" Ability to use plant computer to obtain and evaluate parametric 3.0
information on system or component status.
Operations 2.1.23^ Ability to perform specific system and integratedplant procedures
2.1.23^ during all modes of plant operation. 3.9 1
Total Points 3
2.2.2" Ability to manipulate the console controls as required to operate the
facility between shutdown and desiqnated power levels. 4.0 1
Equipment 2.2.22^ 2.2.22A Knowledge of limiting conditions for operations and safety limits. 3.4 1
Control 2.2.25^ 2.2.25A Knowledge of bases in technical specifications for limiting
conditions for operationsand safety limits. 2.5 1
2.2.2A .2.28A Knowledge of new and spent fuel movement procedures. 2.6 1
Total Points 4
2.3.2 2.3.2 Knowledge of facility ALARA program. 2.5 1
Radiation 2.3.9 2.3.9 Knowledge of the process for performing a containment purge. 2.5 1
Control 2.3.11 A 2.3.11* Ability to control radiation releases. 2.7 1
Total Points 3
2.4.2 2.4.2 Knowledge of system set points, interlocks and automatic actions 3.9 1
Emergency 2.4.12 2.4.12 Knowledge of general operating crew responsibilities during
Procedures/ emergency operations. 3.4 1
Plan 2.4.25 2.4.25 Knowledge of fire protection procedures. 2.9 1
Total Points 3
TIER 3 Category Totals: 13
Generic Knowledges and Abilities
Category KA # K/A Topic Imp. Points
NOTE 1 : Random generator chose a category with no RO K/As with an
importance factor of 2.5 or greater. Chose a different category to obtain a
K/A with an importance factor greater than 2.5.
NOTE 2: New K/A chosen for the same topic to obtain a K/A supporting
plant specific SRO objectives and /or 10 CFR 55.43 lAW NUREG 1021
Revision 8, Supplement 1.
NOTE 3: Random generator did not meet the requirement for 2 items in a
category. Chose a system and K/A that would complete the category
requirements.
NOTE 4: K/A moved within topic per NRC request 7/27/2001 to provide
more uniform coverage of K/As
NOTE 5: Movement of K/As per NRC request created a separate question
for RO. Considered a common question.
RO ONLY QUESTIONS are identified by Aitalicized print and underlined.
ES-401 Record of Rejected K/As Form ES-410-10
Tier/ Randomly
Group Selected K/A Reason for Rejection
Required an additional question to meet minimum sampling in a tier
category of two (2) questions. Selected 013K2.01 based on random
T2/G1 017A4.02 drawing and within the required category.
Required an additional question to meet minimum sampling in a tier
category of two (2) questions. Selected 012K6.04 based on random
T2/G2 01 lK1.01 drawing and within the required category.
Per NRC request for a more uniform coverage of K/As. Selected 059K4.18
T2/G1 059K1.02 based on random drawing within the required category.
Per NRC request for a more uniform coverage of K/As. Selected 072A3.01
T2/G1 072A4.01 based on random drawing within the required category.
Per NRC request for a more uniform coverage of K/As. Selected 010K2.03
based on random drawing within the required category. This resulted in an
T2/G2 01OK1.01 RO only question.
NUREG-1021, Rev. 8, Supplement 1 46 of 46
/ (I
PWR SRO Examination Outline Worksheet
Based on NUREG-1021 Form ES-401-3 Pg 26 of 45 Rev.8
K/A Category Points
Tier Group Point
Group
_Total
A4 G
K5 K6 Al A2 A3
KI K2 K3 K4
Tier1 1 4 3 2 3 6 6 24
Plant 2 1 2 5 3 3 2 16
Evolutions 3 0 1 2 0 0 0 3
Tier
Totals 5 6 9 6 9 8 43
Tier 2 1 3 2 3 1 1 1 1 2 0 2 3 19
Plant 2 2 0 2 1 2 1 2 2 2 1 2 17
Systems 3 1 0 0 1 1 0 0 1 0 0 0 4
Tier 6 2 5 3 4 2 3 5 2 3 5 40
Totals
Tier 3 Cati Cat2 Cat3 Cat4
Generic j 5 3 415 MM M M _MM 17
IKAJGI Totals 11 8 14 3 4 2 9 14 2 3 13 1
Ii
Emergency and Abnormal Plant Evolutions - Tierl/Groupl
E/APE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points
000001 Continuous Rod Withdrawal / I
AK1.13 Knowledge of the operational
implications of the following concepts as
they apply to Dropped Control Rod:
000003 Dropped Control Rod I 1 Interaction of ICS control stations as well as
purpose, function, and modes of operation
of ICS
3.6
2.1.12* Ability to apply technical
000005 Inoperable/Stuck Control Rod 1 1 specifications for a system.
4.0
EK2.02 Knowledge of the interrelations
between the Large Break LOCA and ECCS 2.7
pumps.
000011 Large Break LOCA I III
2.4.5* Knowledge of the organization of
the operating procedures network for
normal, abnormal, and emergency
evolutions. 3.6
AA1 .03 Ability to operate and / or monitor
the following as they apply to the Reactor
000015117 RCP Malfunctions IV Coolant Pump Malfunctions (Loss of RC
Flow): Reactor trip alarms, switches, and
indicators
3.8
E0g Natural Circ. / IV
AA2.05* Ability to determine and
000024 Emergency Boration / I interpret the following as they apply to
the Emergency Boration: Amount of
boron to add to achieve required SDM
1 3.9
Emergency and Abnormal Plant Evolutions Tierl/Groupl
E/APE # / Name I Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points
AA2.01 Ability to determine and interpret
the following as they apply to the Loss of
000026 Loss of Component Cooling Water I Vii Nuclear Services / Decay Heat Closed
Cycle Cooling: Location of a leak in the
NOTE 1 3.5
EK1.03 Knowledge of the operational
implications of the following concepts as
they apply to the ATWS: Effects of boron
000029 Anticipated Transient w/o Scram I on reactivity 3.8
EA2.07* Ability to determine or interpret
the following as they apply to a ATWS:
Reactor trip breaker indicating lights
NOTE 2 4.3
000040 (E05) Steam Line Rupture - Excessive Heat Transfer I IV
AA2.02 Ability to determine and interpret
the following as they apply to the Loss of
Condenser Vacuum: Conditions requiring
reactor and/or turbine trip 4.1 1
000051 Loss of Condenser Vacuum / IV 2.4.48 Ability to interpret control room
indications to verify the status and operation
of system, and understand how operator
actions and directives affect plant and
system conditions.
3.8 1
f
Emergency and Abnormal Plant Evolutions - TierllGroupl
EIAPE # / Name I Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points
EA1.06 Ability to operate and monitor the
following as they apply to a Station
Blackout: Restoration of power with one
ED/G 4.5 1
000055 Station Blackout I Vi 1 1
EA2.03* Ability to determine or
interpret the following as they apply to a
Station Blackout: Actions necessary to
restore power 4.7 1
AK3.01 Knowledge of the reasons for the
following responses as they apply to the
Loss of Vital AC Instrument Bus: Actions
contained in EOP for loss of vital ac
electrical instrument bus 4.4 1
000057 Loss of Vital AC Elec. Inst. Bus / VI
AA1.05 Ability to operate and / or monitor
the following as they apply to the Loss of
Vital AC Instrument Bus: Backup
instrument indications
3.4 1
AK2.01 Knowledge of the interrelations
between the Accidental Liquid Radwaste
000059 Accidental Liquid RadWaste Rel. IX Release and the following: Radioactive
liquid monitors
2.8 1
000062 Loss of Nuclear Service Water / IV
AK1.01 Knowledge of the operational
implications of the following concepts as 3.9 1
they apply to Plant Fire on Site: Fire
000067 Plant Fire On-site ; IX 1 classifications, by type
2.4.27* Knowledge of fire in the plant
Drocedure. 3.5 1
Emergency and Abnormal Plant Evolutions Tierl/Groupl
EIAPE # / Name I Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
AK2.07 Knowledge of the interrelations
between the Control Room Evacuation and 3.4 1
the following: ED/G
3000068 (A06) Control Room Evac. / VIII11
2.4.35* Knowledge of
local auxiliary
operator tasks during emergency
operations including system geography
and system implications. 3.5
000069 Loss of CTMT Integrity I V
2.4.21* Knowledge of the parameters
and logic used to assess the status of
safety functions including:
000074 trad. Core Cooling / IV 1. Reactivity control
2. Core cooling and heat removal
3. Reactor coolant system integrity
4. Reactor Building conditions
5. Radioactivity release control 4.3
EK1.2 Knowledge of the operational
implications of the following concepts as
they apply to the (Inadequate Subcooling
Monitor): Normal, abnormal and emergency
operating procedures associated with (HPI
Termination). 4.0
EK3.1 Knowledge of the reasons for the
E03 Inadequate Subcooling Margin / IV following responses as they apply to the
(Inadequate Subcooling Monitor): Facility
operating characteristics during transient
conditions, including coolant chemistry and
the effects of temperature, pressure, and
reactivity changes and operating limitations
and reasons for these operating
characteristics.
3.8
(
Emergency and Abnormal Plant Evolutions - Tierl/Group2
E/APE # I Name ! Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
EK2.02 Knowledge of the interrelations
000007 (E02&E10) Reactor Trip - Stabilization - Recovery/I I between a reactor trip and the following:
Breakers, relays and disconnects
2.8
A01 Plant Runback /I
AK3.2 Knowledge of the reasons for the
following responses as they apply to the
A04 Turbine Trp / IV (Turbine Trip): Normal, abnormal and
emergency operating procedures
associated with (Turbine Trip).
3.6
AK3.02 Knowledge of the reasons for the
following responses as they apply to the
000008PressurizerVaporSpameAccidentIII Pressurizer Vapor Space Accident: Why
PORV or code safety exit temperature is
below RCS or PZR temperature
4.1
2.4.22* Knowledge of the bases for
000009 Small Break LOCA /III 1 prioritizing safety functions during
abnormallemergency operations. 4.0
1 2.1.28 Knowledge of the purpose and
E08 LOCA Cooldown - Depress. i IV function of major system components and
controls. 3.3
000022 Loss of Reactor Coolant Makeup I
000025 Loss of RHR System / IV
AA1.01 Ability to operate and / or monitor
000027 Pressurizer Pressure Control System Malfunction / III the following as they apply to the
Pressurizer Pressure Control Malfunctions:
PZR heaters, sprays, and PORVs
3.9
(
Emergency and Abnormal Plant Evolutions - Tierl/Group2
E/APE # / Name I Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
AA2.02 Ability to determine and interpret
the following as they apply to the Loss of
000032 Loss of Source Range NI / VII Source Range Nuclear Instrumentation:
Expected change in source range count rate
when rods are moved
3.9
AK3.01 Knowledge of the reasons for the
following responses as they apply to the
Loss of Intermediate Range Nuclear
000033 Loss of Intermediate Range NIl VII 1 Instrumentation: Termination of startup
following loss of intermediate-range
instrumentation
3.6
AK1.01 Knowledge of the operational
implications of the following concepts as
000037 Steam Generator Tube Leak / n1 they apply to Steam Generator Tube Leak:
Use of steam tables
3.3
EA2.01* Ability to determine or
000038 Steam Generator Tube Rupture III *interpret the following as they apply to a
SGTR: When to isolate one or more
S/Gs 4.7
AK3.01 Knowledge of the reasons for the
following responses as they apply to the
000054 Loss of Main Feedwater / IV 1 Loss of Main Feedwater (MFW): Reactor
and/or turbine trip, manual and automatic
4.4
EK2.1 Knowledge of the interrelations
between the (Inadequate Heat Transfer) and
the following: Components, and functions of
E04 Inadequate Heat Transfer - Loss of Secondary Heat Sink / IV control and safety systems, including
instrumentation, signals, interlocks, failure
modes, and automatic and manual
features.
4.0
{ (
Emergency and Abnormal Plant Evolutions Tierl/Group3
E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
000028 Pressurizer Level Malfunction 1I1
000036 (A08) Fuel Handling Accident /VIll
AK3.02 Knowledge of the reasons for the
following responses as they apply to the
000056 Loss of Off-site Power / VI Loss of Offsite Power: Actions contained in
EOP for loss of offsite power
4.7
E14EA2.2* Adherence to appropriate
procedures and operation within the
E13&E14 EOP Rules and Enclosures limitations in the facility's license and
amendments.
NOTE 2 4.0
AK2.1 Knowledge of the interrelations
between the (Emergency Diesel Actuation)
and the following: Components, and
A05 Emergency Diesel Actuation I VI functions of control and safety systems,
including instrumentation, signals,
interlocks, failure modes, and automatic and
manual features.
3.8
A07 Flooding I VIii
K/A Category Totals: 0 1 2 0 0 0 Group Point Total = 3
( f
Plant Svstems - Tier2/Grounl
System #/ Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KJA Topic Imp. Points
K1.09 Knowledge of the physical connections
and/or cause-effect relationships between the
CRDS and the SW system (must be cut in
001 Control Rod Drive before energizing CRDS). 3.1 1
2.1.32 Ability to explain and apply all system
limits and precautions.
NOTE 1 3.8 1
K3.05 Knowledge of the effect that a loss or
003 Reactor Coolant Pump 1 malfunction of the RCPs will have on the
following: ICS 3.7 1
K3.04 Knowledge of the effect that a loss or
malfunction of the MUPS will have on the RCP's
004 Chemical and Volume Control 1
2.1.30 Ability to locate and operate
components, including local controls. 3.4 1
K2.01 Knowledge of bus power supplies to the
ESFAS / safeguards equipment control. 3.8 1
NOTE 3
K3.02 Knowledge of the effect that a loss or
malfunction of the ESFAS will have on the RCS. 4.5 1
013 Engineered Safety Features Actuation 1 1 A2.05* Ability to (a) predict the impacts of
the following malfunctions or operations on
the ESFAS: and (b) based Ability on those
predictions, use procedures to correct,
control, or mitigate the consequences of
those malfunctions or operations; Loss of
dc control power
4.2
fr
Plant Systems - Tier2/Groupl
System #/ Name K1 K2 K3 K4 KS K6 Al A2 A3 A4 G KIA Topic Imp. Points
K4.04 Knowledge of RPIS design feature(s)
which provide zone reference lights.
NOTE 1 2.9 1
A2.01 Ability to (a) predict the impacts of the
014 Rod Position Indication following malfunctions or operations on the
RPIS; and (b) based on those on those
predictions, use procedures to correct, control,
or mitigate the consequences of those 3.3 1
malfunctions or operations: Loss of offsite
power
NOTE I
A4.01 Ability to manually operate and/or
015 Nuclear Instrumentation monitor in the control room: Selection of
controlling NIS channel
3.6 1
017 n-oore TemperatureMonitor 2.1.12* Ability to apply technical
specifications for a system. 4.0 1
022 Containment Cooling K2.01 Knowledge of power supplies to the
following: Reactor Building cooling fans 3.1 1
A1.06 Ability to predict and/or monitor changes
in parameters (to prevent exceeding design
026 Containment Spray 1 limits) associated with operating the BSS
controls including: Reactor Building spray pump
cooling 3.0 1
K1.03 Knowledge of the physical connections
and/or cause-effect relationships between the
056 Condensate Condensate System and the following systems:
NOTE 1 2.6 1
K1.07 Knowledge of the physical connections
059 Main Feedwater and/or cause-effect relationships between the
MFW and the following systems: ICS 3.2 1
( (
Plant Svstems - Tier2/Grounl
System #/ Name K1 K2 K3 K4 KS K6 Al A2 A3 A4 G K/A Topic Imp. Points
K5.01 Knowledge of the operational
implications of the following concepts as they
061 Auxiliary/Emergency Feedwater apply to the AFW: Relationship between AFW
flow and RCS heat transfer
NOTE 4/5 (SRO only) 3.9 1
063 DC Electrical Distribution
K6. 10 Knowledge of the effect of a loss or
068 Liquid Radwaste malfunction on the following will have on the
Liquid Radwaste System: Radiation monitors 2.9 1
071 Waste Gas Disposal
A4.03 Ability to manually operate and/or monitor
072 Area Radiation Monitoring 1 in the control room: Check source for
operability demonstration 3.1 1
K/A Category Totals: 3 2 3 1 1 1 1 2 0 2 3 Group Point Total = 19
C , K
Plant Systems - Tier2/Group2
System # I Name K1 K2 K3 K41 K5 K6 I Al A21 A31 A4 G K/A Topic Imp. I Points
K5.10 Knowledge of the operational
implications of the relationship between reactor
002 Reactor Coolant power and RCS differential temperature as it
applies to the RCS.
NOTE 1 4.1 1
A3.03 Ability to monitor automatic operation of
006 Emergency Core Cooling
the ECCS, including: ESFAS-operated valves 4.1
K4.03 Knowledge of PZR PCS design feature(s)
and/or interlock(s) which provide for the
010 Pressurizer Pressure Control
following: Over pressure control
NOTE 4/5 (SaR ony 4.1 1
11 Pressurizer Level Control
K6.04 Knowledge of the effect of a loss or
012 Reactor Protection
malfunction of the following will have on the
RPS: Bypass-block circuits
NOTE 3 3.6 1
2.1.31 Ability to locate control room switches,
016 Non-nuclear Instrumentation
controls and indications and to determine that
they are correctly reflecting the desired plant
lineup. 3.9 1
2.1.28 Knowledge of the purpose and function
027 Containment Iodine Removal of major system components and controls.
NOTE 1
3.3 1
028 Hydrogen Recombiner and Purge Control
K1.01 Knowledge of the physical connections
029 Containment Purge
and/or cause-effect relationships between the
Containment Purge System and the following:
Gaseous radiation release monitors 37 1
f
Plant Systems - Tier2/Group2
System #1 Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic Imp. Points
A2.03" Ability to (a) predict the impacts of
the following malfunctions or operations on
the Spent Fuel Pool Cooling System; and (b)
based those predictions, use procedures to
033 Spent Fuel Pool Cooling correct, control, or mitigate the
consequences of those malfunctions or
operations: Abnormal spent fuel pool water
level or loss of water level
NOTE 2
3.5 1
A2.02 Ability to (a) predict the impacts of the
following malfunctions or operations on the Fuel
Handling System ; and (b) based those
034 Fuel Handling Equipment predictions, use procedures to correct, control,
or mitigate the consequences of those
malfunctions or operations: Dropped cask
NOTE I
3.9 1
K5.01 Knowledge of the effect of secondary
035 Steam Generator parameters, pressure, and temperature on
reactivity as they apply to the S/GS. 3.9 1
A4.03 Ability to manually operate and/or
039 Main and Reheat Steam 1 monitor in the control room: MFW pump
turbines 2.8 1
K3.01 Knowledge of the effect that a loss or
055 CondenserAir Removal malfunction of the CARS will have on the
following: Main condenser
NOTE 1 2.7
A3.04 Ability to monitor automatic operation of
062 AC Electrical Distribution the AC distribution system, including: Operation
of inverter (e.g., precharging synchronizing light,
static transfer) 2.9
( /
(
Plant Systems - Tier2lGroup2
System # Name K1 K2 K3 K4 KS K6 Al A2 A3 A4 G K/A Topic Imp. Points
K3.02 Knowledge of the effect that a loss or
064 Emergency Diesel Generator malfunction of the ED/G system will have on the
following: ESFAS controlled or actuated
systems 4.4 1
073 Process Radiation Monitoring
K1.01 Knowledge of the physical connections
075 Circulating Water and/or cause-effect relationships between the
CW system and the following systems: RW
System 2.5 1
079 Station Air
A1.01 Ability to predict and/or monitor changes
in parameters (to prevent exceeding design
086 Fire Protection limits) associated with Fire Protection System
operating the controls including: Fire header
pressure 3.3 1
A1.01 Ability to predict and/or monitor changes
in parameters (to prevent exceeding design
103 Containment 1 limits) associated with operating the reactor
building system controls including: Reactor
Building pressure and temperature 4.1 1
K/A Category Totals: 2 0 2 1 2 1 2 2 2 1 2 Group Point Total = 17
(
Plant Systems - Tier21flrnun3
System #/ Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic Imp. Points
K5.02 Knowledge of the operational
005 Residual Heat Removal 1 implications of the following concepts as they
apply the Decay Heat System: Need for
adequate subcooling 3.5
007 Pressurizer Relief/Quench Tank
K4.09 Knowledge of SWS / DCS design
008 Component cooling Water feature(s) and/or interlock(s) which provide for
the standby feature of the SWS / DCS pumps. 2.9
041 Steam Dump/Turbine Bypass Control
K1.18 Knowledge of the physical connections
045 Main Turbine Generator and/or cause-effect relationships between the
MT/G system and the RPS.
NOTE 1 3.7
A2.01 Ability to (a) predict the impacts of the
following malfunctions or operations on the
076 Service Water RWS; and (b) based on those predictions, use
procedures to correct, control, or mitigate the
consequences of those malfunctions or
operations: Loss of RWS 37
078 Instrument Air
K/A Category
Totals1 I0 o I1
O1 0 0 1 j0 0 I0 I Group Point Total, 4
Generic Knowledges and Abilities
Category KA # K/A Topic Imp. Points
2.1.4* 2.1.4* Knowledge of shift staffing requirements
NOTE 2 3.4 1
2.1.12* 2.1.12* Ability to apply technical specifications for a system. 4.0 1
2.1,20" 2.1.20* Ability to execute procedure steps.
NOTE 2 4.2 1
Conduct of
2.1.32" 2.1.32* Ability to explain and apply all system limits and precautions.
Operations NOTE 2 3.8 1
2.1.33* Ability to recognize indications for system operating
parameters which are entry-level conditions for technical
2.1.33* specifications.
NOTE 2 4.0 1
Total Points 5
2.2.22* 2.2.22* Knowledge of limiting conditions for operations and safety
limits. 4.1 1
Equipment 2.2.25* 2.2.25* Knowledge of bases in technical specifications for limiting
Control conditions for operations and safety limits. 3.7 1
2.2.28* 2.2.28* Knowledge of new and spent fuel movement procedures. 3.5 1
Total Points 3
/
6
Generic Knowledges and Abilities
Category KA # K/A Topic Imp. Points
2.3.2
2.3.2 Knowledge of facility ALARA program. 2.9 1
2.3.6* Knowledge of the requirements for reviewing and approving
2.3.6* release permits.
Radiation NOTE 2 3.1 1
Control 2.3.8* Knowledge of the process for performing a planned gaseous
2.3,8* radioactive release.
NOTE 2 3.2 1
2.3.9 2.3.9 Knowledge of the process for performing a containment purge. 3.4 1
Total Points 4
2.4.2 2.4.2 Knowledge of system set points, interlocks and automatic actions
associated with EOP entry conditions. 4.1 1
2.4.12 2.4.12 Knowledge of general operating crew responsibilities during
emergency operations. 3.9 1
Emergency 2.4.25 2.4.25 Knowledge of fire protection procedures. 3.4 1
Procedures/ 2.4.27* Knowledge of fire in the plant procedure.
Plan NOTE 2 3.5 1
2.4.30* Knowledge of which events related to system
2.4.30* operationsistatus should be reported to outside agencies.
NOTE 2 3.6 1
Total Points 5
TIER 3 Category Totals: 17
( C
Generic Knowledges and Abilities
Category KA # K/A Topic Imp. Points
NOTE 1 : Random generator chose a category with no SRO K/As with an
importance factor of 2.5 or greater. Chose a different category to obtain a
K/A with an importance factor greater than 2.5.
NOTE 2: New K/A chosen for the same topic to obtain a K/A supporting
plant specific SRO objectives and/or 10 CFR 55.43 lAW NUREG 1021
Revision 8, Supplement 1.
NOTE 3: Random generator did not meet the requirement for 2 items in a
category. Chose a system and K/A that would complete the category
requirements.
NOTE 4: K/A moved within topic per NRC request 7/27/2001 to provide
more uniform coverage of K/As
NOTE 5: Movement of K/As per NRC request created a separate question
for SRO. Considered a common question does not meet 10 CFR55.43
criteria.
SRO ONLY QUESTIONS are identified by * BOLD print and underlined.
(
ES-401 Record of Rejected K/As Form ES-410-10
Tier/ Randomly
Group Selected K/A Reason for Rejection
Required an additional question to meet minimum sampling in a tier
category of two (2) questions. Selected 013K2.01 based on random
T2/G1 017A4.02 drawing and within the required category.
Required an additional question to meet minimum sampling in a tier
category of two (2) questions. Selected 012K6.04 based on random
T2/G2 011 K1.01 drawing and within the required category.
Per NRC request for a more uniform coverage of K/As. Selected 061 K5.01
T2/G1 061 K1.01 based on random drawing within the required category.
Per NRC request for a more uniform coverage of K/As. Selected 010K4.03
based on random drawing within the required category. This resulted in an
T2/G2 01OK1.01 SRO only question.
t
I
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NUREG-1021, Rev. 8, Supplement I
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