ML080720506

Feb 2008 Exam 05000327 & 05000328-08-301 - Final Outlines

ML080720506
Person / Time
Site:	Sequoyah
Issue date:	02/05/2008
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-327/08-301, 50-328/08-301
Download: ML080720506 (32)

See also: IR 05000328/2008301

Text

Final Submittal

(Blue Paper)

FINAL OUTLINES

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ES-401 PWR Examination Outline Form ES-401-2

Facility: Sequoyah Printed: 01/13/2008

Date Of Exam: 01/28/2008

RO KiA Category Points SRO-Only Points

Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 0 0 0

Emergenc

2 1 2 1 N/A 1 2 2 9 0 0 0

& N/A

Abnormal Tier

Plant

Totals 4 5 4 4 5 5 27 0 0 0

Evolutions

1 2 2 3 3 3 2 2 3 2 3 3 28 0 0 0

2.

2 1 1 1 1 1 1 1 0 1 1 1 10 01 0 0 0

Plant

Systems Tier 0 0 0

3 3 4 4 4 3 3 3 3 4 4 38

Totals

1 2 3 4 1 2 3 4

3. Generic Knowledge And

10 0

Abilities Categories

3 2 3 2 0 0 0 0

Note:

1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO and

SRO-only outlines (Le., except for one category in Tier 3 of the 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 +/-1 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 ES-401 , Attachment 2, for

guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher

shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics 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.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics'

importance ratings (IRs) 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; 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-onlyexams.

( 9. ForTier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions,

IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to

10 CFR 55.43.

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant EVOlutions - Tier I 1 Group I Form ES-401-2

I TCJAPE # 1 Name 1 Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points

(

000007 Reactor Trip - Stabilization - X EAl.08 - AFW System 4.4 1

Recovery 11

000008 Pressurizer Vapor Space Accident 1 X AA2.29 - The effects of bubble in 3.9 1

3 reactor vessel

000009 Small Break LOCA 13 X EA2.24 - RCP temperature setpoints 2.6 1

000011 Large Break LOCA 13 X EK3.13 - Hot-leg injection/recirculation 3.8 1

000015/000017 RCP Malfunctions 14 X AK2.08 - CCWS 2.6 1

000022 Loss of Rx Coolant Makeup 12 X AA2.03 - Failures of flow control valve 3.1 1

or controller

000025 Loss of RHR System 14 X AK2.05 - Reactor building sump 2.6 1

000026 Loss of Component Cooling Water 1 X AK3.03 - Guidance actions contained in 4.0 1

8 EOP for Loss of CCW

000027 Pressurizer Pressure Control System X AAl.02 - SCR-controlled heaters in 3.1 * 1

Malfunction 13 manual mode

000038 Steam Gen. Tube Rupture 13 X 2.1.3 - Knowledge of shift turnover 3.0 1

practices.

000040 Steam Line Rupture - Excessive X AKl.03 - RCS shrink and consequent 3.8 1

Heat Transfer 1 4 depressurization

( )0055 Station Blackout 16 X 2.4.29 - Knowledge of the emergency 2.6 1

plan.

000056 Loss of Off-site Power 16 X AKl.03 - Definition of subcooling: use 3.1* 1

of steam tables to determine it

000058 Loss of DC Power 16 X AKl.Ol - Battery charger equipment 2.8 1

and instrumentation

000062 Loss of Nuclear Svc Water 14 X AAl.Ol - Nuclear service water 3.1 1

temperature indications

W IE04 LOCA Outside Containment 13 X 2.4.48 - Ability to interpret control 3.5 1

room indications to verify the status and

operation of system, and understand

how operator actions and directives

affect plant and system conditions.

W/E05 Inadequate Heat Transfer - Loss of X EK3.1 - Facility operating 3.4 1

Secondary Heat Sink 14 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

I

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2

I

':/APE # / Name / Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points

W/E 11 Loss of Emergency Coolant Recirc. / X EK2.2 - Facility's heat removal systems, 3.9 1

4 including primary coolant, emergency

coolant, the decay heat removal

systems, and relations between the

proper operation of these systems to the

operation of the facility

KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18

(

(

2

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2

I

7,/APE # / Name / Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points

000001 Continuous Rod Withdrawal / 1 X AK2.05 - Rod motion lights 2.9* 1

000033 Loss of Intermediate Range NI /7 X 2.4.21 - Knowledge of the parameters 3.7 1

and logic used to assess the status of

safety functions including: 1. Reactivity

control; 2. Core cooling and heat

removal; 3. Reactor coolant system

integrity; 4. Containment conditions; 5.

Radioactivity release control.

000036 Fuel Handling Accident / 8 X AKl.O 1 - Radiation exposure hazards 3.5 1

000060 Accidental Gaseous Radwaste ReI. / X AA1.02 - Ventilation system 2.9 1

9

000069 Loss of CTMT Integrity / 5 X 2.4.45 - Ability to prioritize and 3.3 1

interpret the significance of each

annunciator or alarm.

000074 Inad. Core Cooling / 4 X EK3.07 - Starting up emergency 4.0 1

feedwater and RCPs

000076 High Reactor Coolant Activity /9 X AK2.01 - Process radiation monitors 2.6 1

W/E09 Natural Circ. /4 X EA2.1 - Facility conditions and 3.1 1

selection of appropriate procedures

during abnormal and emergency

operations

(

W/E 14 Loss of CTMT Integrity / 5 X EA2.2 - Adherence to appropriate 3.3 1

procedures and operation within the

limitations in the facility's license and

amendments

KIA Category Totals: 1 2 1 1 2 2 Group Point Total: 9

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

I

Sys/Evol # / Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points

003 Reactor Coolant Pump X K3.04 - RPS 3.9 1

003 Reactor Coolant Pump X 2.3.10 - Ability to perform 2.9 1

procedures to reduce

excessive levels of radiation

and guard against personnel

exposure.

004 Chemical and Volume Control X K5.3l - Purpose of flow 3.0* 1

path around boric acid

storage tank

004 Chemical and Volume Control X A3.08 - Reactor power 3.9 1

005 Residual Heat Removal X A4.03 - RHR temperature, 2.8* 1

PZR heaters and flow, and

nitrogen

006 Emergency Core Cooling X K1.02 - ESFAS 4.3 1

007 Pressurizer Relief/Quench X K3.0l - Containment 3.3 1

Tank

007 Pressurizer Relief/Quench X 2.1.1 - Knowledge of 3.7 1

Tank conduct of operations

requirements.

008 Component Cooling Water X K4.07 - Operation of the 2.6* 1

CCW swing-bus power

supply and its associated

breakers and controls

( J 10 Pressurizer Pressure Control X K6.03 - PZR sprays and 3.2 1

heaters

012 Reactor Protection X K4.04 - Redundancy 3.1 1

013 Engineered Safety Features X K2.0l - ESFAS/safeguards 3.6* 1

Actuation equipment control

022 Containment Cooling X A2.04 - Loss of service 2.9* 1

water

025 Ice Condenser X K5.02 - Heat transfer 2.6* 1

026 Containment Spray X K4.07 - Adequate level in 3.8* 1

containment sump for

suction (interlock)

026 Containment Spray X 2.4.48 - Ability to interpret 3.5 1

control room indications to

verify the status and

operation of system, and

understand how operator

actions and directives affect

plant and system conditions.

039 Main and Reheat Steam X Al.09 - Main steam line 2.5* 1

radiation monitors

059 Main Feedwater X A2.07 - Tripping ofMFW 3.0* 1

pump turbine

059 Main Feedwater X A4.0l - MFW turbine trip 3.1 * 1

indication

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

I

Sys/Evol # / Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points

061 Auxiliary/Emergency X K5.0l - Relationship 3.6 1

Feedwater between AFW flow and

RCS heat transfer

062 AC Electrical Distribution X Kl.02 - ED/G 4.1 1

063 DC Electrical Distribution X K2.0l - Major DC loads 2.9* 1

064 Emergency Diesel Generator X K6.08 - Fuel oil storage 3.2 1

tanks

073 Process Radiation Monitoring X Al.Ol - Radiation levels 3.2 1

076 Service Water X A2.02 - Service water 2.7 1

header pressure

076 Service Water X A4.02 - SWS valves 2.6 1

078 Instrument Air X K3.0l - Containment air 3.1 * 1

system

103 Containment X A3.0l - Containment 3.9 1

isolation

KIA Category Totals: 2 2 3 3 3 2 2 3 2 3 3 Group Point Total: 28

(

(

2

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 1 Group 2 Form ES-401-2

I

Sys/Evol # 1 Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points

011 Pressurizer Level Control X K6.05 - Function ofPZR 3.1 1

level gauges as postaccident

monitors

015 Nuclear Instrumentation X K2.01 - NIS channels, 3.3 1

components, and

interconnections

016 Non-nuclear Instrumentation X K1.l0 - CCS 3.1 * 1

017 In-core Temperature Monitor X K4.03 - Range of 3.1 1

temperature indication

045 Main Turbine Generator X K5.17 - Relationship 2.5* 1

between moderator

temperature coefficient and

boron concentration in RCS

as T IG load increases

055 Condenser Air Removal X A3.03 - Automatic diversion 2.5* 1

of CARS exhaust

068 Liquid Radwaste X A4.01 - Control board for 2.7* 1

boron recovery

071 Waste Gas Disposal X K3.04 - Ventilation system 2.7 1

075 Circulating Water X 2.2.11 - Knowledge of the 2.5 1

process for controlling

temporary changes.

086 Fire Protection X A1.01 - Fire header pressure 2.9 1

( KIA Category Totals: 1 1 1 1 1 1 1 0 1 1 1 Group Point Total: 10

I

(

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah Form ES-401-3

Generic Catezorv KA KA Topic Points

Conduct of Operations 2.1.3 Knowledge of shift turnover practices. 3.0 I

2.1.27 Knowledge of system purpose and or function. 2.8 I

2.1.28 Knowledge of the purpose and function of major 3.2 I

system components and controls.

Category Total: 3

Equipment Control 2.2.26 Knowledge of refueling administrative 2.5 I

requirements.

2.2.33 Knowledge of control rod programming. 2.5 I

Category Total: 2

Radiation Control 2.3.2 Knowledge of facility ALARA program. 2.5 I

2.3.9 Knowledge of the process for performing a 2.5 I

containment purge.

(

2.3.10 Ability to perform procedures to reduce excessive 2.9 I

levels of radiation and guard against personnel

exposure.

Category Total: 3

Emergency Procedures/Plan 2.4.16 Knowledge of EOP implementation hierarchy and 3.0 I

coordination with other support procedures.

2.4.22 Knowledge of the bases for prioritizing safety 3.0 I

functions during abnormal/emergency operations.

Category Total: 2

Generic Total: 10

(

Form ES-401-2

Printed: 01/13/2008

SRO-Only Points

A2 G* Total

0 0 0

0 0 0

0 0 0

0 0 0

01 0 0 0

0 0 0

1 2 3 4

0

0 0 0 0

1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO and

SRO-only outlines (Le., except for one category in Tier 3 of the 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 +/-1 from that specified in the

table based on NRC revisions. The final RO exam musttotal 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 ES-401, Attachment 2, for

guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher

shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics 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.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics'

importance ratings (IRs) 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; 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-onlyexams.

( 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions,

IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to

10 CFR 55.43.

PWR RO Examina . Outline Printed: 01/13/200

Facility: Sequoyah

ES - 401 E merzency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2

E/APE # / Name / Safety Function KA KA Topic Comment

000007 Reactor Trip - Stabilization - Recovery / 1 EA1.08 AFW System

000008 Pressurizer Vapor Space Accident / 3 AA2.29 The effects of bubble in reactor vessel

000009 Small Break LOCA / 3 EA2.24 RCP temperature setpoints

000011 Large Break LOCA /3 EK3.13 Hot-leg injection/recirculation

000015/000017 RCP Malfunctions / 4 AK2.08 CCWS

000022 Loss of Rx Coolant Makeup / 2 AA2.03 Failures of flow control valve or controller

000025 Loss ofRHR System / 4 AK2.05 Reactor building sump

000026 Loss of Component Cooling Water /8 AK3.03 Guidance actions contained in EOP for Loss of

CCW

000027 Pressurizer Pressure Control System Malfunction /3 AAl.02 SCR-controlled heaters in manual mode

000038 Steam Gen. Tube Rupture /3 2.1.3 Knowledge of shift turnover practices.

000040 Steam Line Rupture - Excessive Heat Transfer / 4 AK1.03 RCS shrink and consequent depressurization

PWRRO Examina . Outline Printed: 01/13/200

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 1 Group 1 Form ES-401-2

E/APE # 1 Name 1 Safety Function KA KA Topic Comment

000055 Station Blackout 16 2.4.29 Knowledge of the emergency plan. KA replaced with 055 G 2.4.18

as directed by Chief Examiner.

12/20/2007

000056 Loss of Off-site Power 16 AKl.03 Definition of subcooling: use of steam tables to

determine it

000058 Loss of DC Power 16 AK1.01 Battery charger equipment and instrumentation

000062 Loss of Nuclear Svc Water 14 AA1.01 Nuclear service water temperature indications

W/E04 LOCA Outside Containment 13 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.

W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink EK3.1 Facility operating characteristics during transient

14 conditions, including coolant chemistry and the

effects of temperature, pressure, and reactivity

changes and operating limitations and reasons for

these operating characteristics

W/Ell Loss of Emergency Coolant Recirc. 14 EK2.2 Facility's heat removal systems, including primary

coolant emerzencv coolant the decav heat

removal systems, and relations between the proper

operation of these systems to the operation of the

facility

2

PWR RO Examim . Outline Printed: 01/13/20l

Facility: Sequoyah

ES - 401 E meraencv and A bnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2

E/APE # I Name I Safety Function KA KA Topic Comment

000001 Continuous Rod Withdrawal 11 AK2.05 Rod motion lights

000033 Loss ofIntermediate Range NI I 7 2.4.21 Knowledge of the parameters and logic used to

assess the status of safety functions including: 1.

Reactivity control; 2. Core cooling and heat

removal; 3. Reactor coolant system integrity; 4.

Containment conditions; 5. Radioactivity release

control.

000036 Fuel Handling Accident I 8 AK1.01 Radiation exposure hazards

000060 Accidental Gaseous Radwaste ReI. I 9 AA1.02 Ventilation system

000069 Loss of CTMT Integrity I 5 2.4.45 Ability to prioritize and interpret the significance

of each annunciator or alarm.

000074 Inad. Core Cooling I 4 EK3.07 Starting up emergency feedwater and RCPs

000076 High Reactor Coolant Activity 19 AK2.01 Process radiation monitors

W/E09 Natural Circ. 14 EA2.1 Facility conditions and selection of appropriate

procedures during abnormal and emergency

operations

W/E14 Loss ofCTMT Integrity 15 EA2.2 Adherence to appropriate procedures and

oneration within the limitations in the facility's

license and amendments

Printed: 01/13 ,-~

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

Sys/Evol # / Name KA KA Topic Comment

003 Reactor Coolant Pump K3.04 RPS

003 Reactor Coolant Pump 2.3.10 Ability to perform procedures to reduce excessive

levels of radiation and guard against personnel

exposure.

004 Chemical and Volume Control K5.3l Purpose of flow path around boric acid storage Plant design does not provide a flow path around

tank the Boric Acid Storage Tank. Replace with

randomly selected KIA 004 K5.26. The selection

was randomly selected within the original KIA 004

K5.

004 Chemical and Volume Control A3.08 Reactor power

005 Residual Heat Removal A4.03 RHR temperature, PZR heaters and flow, and

nitrogen

006 Emergency Core Cooling K1.02 ESFAS

007 Pressurizer Relief/Quench Tank K3.0l Containment

007 Pressurizer Relief/Quench Tank 2.1.1 Knowledge of conduct of operations requirements.

008 Component Cooling Water K4.07 Operation of the CCW swing-bus power supply

and its associated breakers and controls

010 Pressurizer Pressure Control K6.03 PZR sprays and heaters

012 Reactor Protection K4.04 Redundancy

013 Engineered Safety Features Actuation K2.0l ESFAS/safeguards equipment control

PWR RO ,-',mination Outline Printed: 0 1/l3'~"~

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

Sys/Evol # / Name KA KA Topic Comment

022 Containment Cooling A2.04 Loss of service water

025 Ice Condenser K5.02 Heat transfer

026 Containment Spray K4.07 Adequate level in containment sump for suction

(interlock)

026 Containment Spray 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.

039 Main and Reheat Steam Al.09 Main steam line radiation monitors KA replaced with 039 Al.05 as directed by Chief

Examiner. 12/20/2007

059 Main Feedwater A2.07 Tripping ofMFW pump turbine

059 Main Feedwater A4.01 MFW turbine trip indication

061 Auxiliary/Emergency Feedwater K5.01 Relationship between AFW flow and RCS heat

transfer

062 AC Electrical Distribution Kl.02 ED/G

063 DC Electrical Distribution K2.01 Major DC loads

064 Emergency Diesel Generator K6.08 Fuel oil storage tanks

073 Process Radiation Monitoring Al.Ol Radiation levels

076 Service Water A2.02 Service water header pressure

2

PWR RO---'~mination Outline Printed: 01/13 !-~~

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

Sys/Evol # / Name KA KA Topic Comment

076 Service Water A4.02 SWS valves

078 Instrument Air K3.01 Containment air system

103 Containment A3.01 Containment isolation

3

PWR Ro.~'1mination Outline Printed: OlI1Y-'Q

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2

Sys/Evol # / Name KA KA Topic Comment

011 Pressurizer Level Control K6,05 Function of PZR level gauges as postaccident

monitors

015 Nuclear Instrumentation K2,01 NIS channels, components, and interconnections

016 Non-nuclear Instrumentation KUO CCS

017 In-core Temperature Monitor K4.03 Range of temperature indication

045 Main Turbine Generator K5,17 Relationship between moderator temperature

coefficient and boron concentration in RCS as

T/G load increases

055 Condenser Air Removal A3,03 Automatic diversion of CARS exhaust

068 Liquid Radwaste A4,01 Control board for boron recovery The Boron Recovery System has been abandoned at

the Sequoyah Plant Replace with randomly

selected KIA 068 A4,02. The selection was

randomly selected within the original KIA 068 A4,

071 Waste Gas Disposal K3.04 Ventilation system

075 Circulating Water 2.2,11 Knowledge of the process for controlling KA replaced with 075 G 2.2,13 as directed by Chief

temporary changes. Examiner. 12/20/2007

086 Fire Protection ALOI Fire header pressure

Generic Knowledge . Abilities Outline (Tier 3) Printed: 01/13/20

PWR RO Examination Outline

Form ES-401-3

Facility: Sequoyah

Generic Category KA KA Topic Comment

Conduct of Operations Knowledge of shift turnover practices.

Knowledge of system purpose and or function.

Knowledge of the purpose and function of major system components

Category Total: 3

Equipment Control Knowledge of refueling administrative requirements.

2.2.33 IKnowledge of control rod programming.

Category Total: 2

Radiation Control Knowledge of facility ALARA program.

Knowledge of the process for performing a containment purge.

Ability to perform procedures to reduce excessive levels of radiation

Category Total: 3

Emergency Procedures/Plan Knowledge of EOP implementation hierarchy and coordination with

Knowledge of the bases for prioritizing safety functions during

Category Total: 2

Generic Total: 10

ES-401 Record of Rejected KIAs Form ES-401-4

(

Tier / Randomly Reason for Rejection

Group Selected KIA

2/1 004 K5.31 Plant design does not provide a flow path around the Boric

Acid Storage Tank. Replace with randomly selected KJA

004 K5.26

2/2 068 A4.01 The Boron Recovery System has been abandoned at the

Sequoyah plant. Replace with randomly selected KJA 068

A4.02

2/1 039 A1.09 KA replaced with 039 A1.05 during exam review as

directed by Chief Examiner. 12/20/2007

1/1 055 G2.4.29 KA replaced with 055 G 2.4.18 during exam review as

directed by Chief Examiner. 12/20/2007

2/2 075 G2.2.11 KA replaced with 075 G 2.2.13 during exam review as

directed by Chief Examiner. 12/20/2007

(

(

ES-401, Page 27 of 33

HItvJ

ES-401 PWR Examination Outline Form ES-401-2

Facility: Sequoyah Printed: 01/13/2008

Date Of Exam: 01/28/2008

RO KIA Category Points SRO-Only Points

Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 4 3 7

Emergenc

2 0 0 0 N/A 0 0 0 0 3 2 5

& N/A

Abnormal Tier

Plant

Totals 0 0 0 0 0 0 0 7 5 12

Evolutions

1 0 0 0 0 0 0 0 0 0 0 0 0 2 2 4

2.

2 0 0 0 0 0 0 0 0 0 0 0 0 01 1 1 2

Plant

Systems Tier 3 3 6

0 0 0 0 0 0 0 0 0 0 0 0

Totals

1 2 3 4 1 2 3 4

3. Generic Knowledge And

0 7

Abilities Categories

0 0 0 0 2 1 2 2

Note:

1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO and

SRO-only outlines (Le., except for one category in Tier 3 of the 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 +/-1 from that specified in the

table based on NRC revisions. The f nal 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 ES-401, Attachment 2, for

guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher

shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics 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.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics'

importance ratings (IRs) 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; 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-onlyexams.

( 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions,

IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to

10 CFR 55.43.

PWR SRO Examir, In Outline Printed: 0l/13/20C

Facility: Sequoyah

ES - 401 E merzency an dAb normal Plant Evolutions - Tier 1 1 Group 1 Form ES-401-2

EI APE # 1 Name 1 Safety Function KA KA Topic Comment

000008 Pressurizer Vapor Space Accident 13 2.4.49 Ability to perform without reference to procedures KA replaced with 008 G 2.4.41

those actions that require immediate operation of as directed by Chief Examiner.

system components and controls. 12120/2007

000029 ATWS 11 EA2.09 Occurrence of a main turbine/reactor trip

000054 Loss of Main Feedwater 14 AA2.05 Status ofMFW pumps, regulating and stop valves

000057 Loss of Vital AC Inst. Bus 16 AA2.17 System and component status, using local or

remote controls

000065 Loss of Instrument Air 1 8 AA2.01 Cause and effect of low-pressure instrument air

alarm

W/Ell Loss of Emergency Coolant Recirc. 14 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.

W/E12 - Steam Line Rupture - Excessive Heat Transfer 14 2.4.33 Knowledge of the process used track inoperable Unable to write question that tied

alarms. process for tracking INOP

alarms to a Steam Line Rupture -

Excessive Heat Transfer.

Replace with W/E12 G2.1.32-

New KIA supplied by Chief

Examiner 8/23/07

PWR SRO Examin n Outline Printed: 01/13/20(,

Facility: Sequoyah

ES - 401 Emerzencv and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2

E/ APE # / Name / Safety Function KA KA Topic Comment

000003 Dropped Control Rod / 1 2.2.26 Knowledge of refueling administrative Unable to write question that

requirements. connected Refueling

Administrative Requirements to

the Abnormal Plant Evolution of

Dropped Control Rod. Replace

with 003 G2.2.22 - New KIA

supplied by Chief Examiner

8/23/07

000005 Inoperable/Stuck Control Rod / 1 AA2.03 Required actions if more than one rod is stuck or

inoperable

000051 Loss of Condenser Vacuum / 4 AA2.02 Conditions requiring reactor and/or turbine trip

W/E02 SI Termination / 3 EA2.2 Adherence to appropriate procedures and

operation within the limitations in the facility's

license and amendments

W/E16 High Containment Radiation /9 2.2.31 Knowledge of procedures and limitations involved

in initial core loading.

PWR SROC--.lmination Outline Printed: 0 1/1y~~

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

Sys/Evol # / Name KA KA Topic Comment

008 Component Cooling Water A2.09 Results of excessive exit temperature from the

letdown cooler, including the temperature effects

on ion-exchange resins

010 Pressurizer Pressure Contra 1 2.4.38 Ability to take actions called for in the facility

emergency plan, including (if required) supporting

or acting as emergency coordinator.

013 Engineered Safety Features Actuation A2.05 Loss of de control power

103 Containment 2.2.14 Knowledge of the process for making

confizuration chances.

PWR SRO-'Unination Outline Printed: Ol/13r-~~

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 1 Group 2 Form ES-401-2

Sys/Evol # 1 Name KA KA Topic Comment

029 Containment Purge 2.4.38 Ability to take actions called for in the facility Unable to write question related taking actions

emergency plan, including (if required) supporting called for in the Emergency Plan to Containment

or acting as emergency coordinator. Purge.

Replace with 029 G2.4.46 - New KIA supplied by

Chief Examiner 8/23/07

034 Fuel Handling Equipment A2.02 Dropped cask

Generic Knowledge Abilities Outline (Tier 3) Printed: 01/13/20,

PWR SRO Examination Outline

Form E8-401-3

Facility: Sequoyah

Generic Category KA KA Topic Comment

Conduct of Operations Ability to apply teclmical specifications for a system.

Ability to recognize indications for system operating parameters

Category Total: 2

Equipment Control Knowledge of the process for determining if the proposed change,

Category Total: 1

Radiation Control Knowledge of 10 CFR: 20 and related facility radiation control

Knowledge of the requirements for reviewing and approving release

Category Total: 2

Emergency Procedures/Plan Knowledge oflow power /shutdown implications in accident (e.g.

Ability to perform without reference to procedures those actions that

Category Total: 2

Generic Total: 7

ES-401 PWR Examination Outline Form ES-401-2

Facility: Sequoyah Printed: 01/13/2008

Date Of Exam: 01/28/2008

RO KIA Category Points SRO-Only Points

Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 4 3 7

Emergenc

2 0 0 0 0 0 0 0 3 2 5

& N/A N/A

Abnormal Tier

Plant

Totals 0 0 0 0 0 0 0 7 5 12

Evolutions

1 0 0 0 0 0 0 0 0 0 0 0 0 2 2 4

2.

Plant

2 0 0 0 0 0 0 0 0 0 0 0 0 01 1 1 2

Systems Tier

0 0 0 0 0 0 0 0 0 0 0 0 3 3 6

Totals

1 2 3 4 1 2 3 4

3. Generic Knowledge And

0 7

Abilities Categories

0 0 0 0 2 1 2 2

Note:

1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO and

SRO-only outlines (i.e., except for one category in Tier 3 of the 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 +/-1 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 ES-401 , Attachment 2, for

guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher

shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics 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.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics'

importance ratings (IRs) 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; 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-onlyexams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions,

IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to

10 CFR 55.43.

PWR SRO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant Evolutions - Tier I / Group I Form ES-401-2

I ~/APE # / Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points

000008 Pressurizer Vapor Space Accident / X 2.4.49 - Ability to perform without 4.0 1

3 reference to procedures those actions

that require immediate operation of

system components and controls.

000029 ATWS / 1 X EA2.09 - Occurrence of a main 4.5 1

turbine/reactor trip

000054 Loss of Main Feedwater /4 X AA2.05 - Status ofMFW pumps, 3.7 1

regulating and stop valves

000057 Loss of Vital AC Inst. Bus / 6 X AA2.17 - System and component status, 3.4 1

using local or remote controls

000065 Loss of Instrument Air / 8 X AA2.01 - Cause and effect of 3.2 1

low-pressure instrument air alarm

W/E 11 Loss of Emergency Coolant Recirc. / X 2.4.48 - Ability to interpret control 3.8 1

4 room indications to verify the status and

operation of system, and understand

how operator actions and directives

affect plant and system conditions.

W/EI2 - Steam Line Rupture - Excessive X 2.4.33 - Knowledge of the process used 2.8 1

Heat Transfer / 4 track inoperable alarms.

KIA Category Totals: 0 0 0 0 4 3 Group Point Total: 7

('

PWR SRO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2

I ~/APE # / Name / Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points

(

000003 Dropped Control Rod / 1 X 2.2.26 - Knowledge of refueling 3.7 1

administrative requirements.

000005 Inoperable/Stuck Control Rod / 1 X AA2.03 - Required actions if more than 4.4 1

one rod is stuck or inoperable

000051 Loss of Condenser Vacuum /4 X AA2.02 - Conditions requiring reactor 4.1 1

and/or turbine trip

W/E02 SI Termination /3 X EA2.2 - Adherence to appropriate 4.0 1

procedures and operation within the

limitations in the facility's license and

amendments

W/E 16 High Containment Radiation / 9 X 2.2.31 - Knowledge of procedures and 2.9* 1

limitations involved in initial core

loading.

KIA Category Totals: 0 0 0 0 3 2 Group Point Total: 5

(

(

PWR SRO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 1 Group 1 Form ES-401-2

I

Sys/Evol # 1 Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points

008 Component Cooling Water X A2.09 - Results of excessive 2.8 1

exit temperature from the

letdown cooler, including

the temperature effects on

ion-exchange resins

010 Pressurizer Pressure Control X 2.4.38 - Ability to take 4.0 1

actions called for in the

facility emergency plan,

including (if required)

supporting or acting as

emergency coordinator.

013 Engineered Safety Features X A2.05 - Loss of de control 4.2 1

Actuation power

103 Containment X 2.2.14 - Knowledge of the 3.0 1

process for making

configuration changes.

KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 2 Group Point Total: 4

(

(

PWR SRO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 1 Group 2 Form ES-401-2

I

f Sys/Evol # 1 Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points

\

029 Containment Purge X 2.4.38 - Ability to take 4.0 1

actions called for in the

facility emergency plan,

including (if required)

supporting or acting as

emergency coordinator.

034 Fuel Handling Equipment X A2.02 - Dropped cask 3.9 1

KIA Category Totals: 0 0 0 0 0 0 0 I 0 0 I Group Point Total: 2

(

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 01/13/2008

Facility: Sequoyah Form ES-401-3

Generic Category KA Topic

Conduct of Operations 2.1.12 Ability to apply technical specifications for a 4.0 1

system.

2.1.33 Ability to recognize indications for system 4.0 1

operating parameters which are entry-level

conditions for technical specifications.

Category Total: 2

Equipment Control 2.2.8 Knowledge of the process for determining if the 3.3 I

proposed change, test, or experiment involves an

unreviewed safety question.

Category Total: 1

Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility 3.0 I

radiation control requirements.

2.3.6 Knowledge of the requirements for reviewing and 3.1 I

approving release permits.

Category Total: 2

( Emergency Procedures/Plan 2.4.9 Knowledge of low power /shutdown implications 3.9 I

in accident (e.g. LOCA or loss ofRHR)

mitigation strategies.

2.4.49 Ability to perform without reference to 4.0 I

procedures those actions that require immediate

operation of system components and controls.

Category Total: 2

Generic Total: 7

ES-401 Record of Rejected KlAs Form ES-401-4

Tier / Randomly Reason for Rejection

Group Selected KJA

1/2 003,G2.2.26 Unable to write question that connected Refueling

Administrative Requirements to the Abnormal Plant

Evolution of Dropped Control Rod. Replace with 003

G2.2.22 - New KiA supplied by Chief Examiner 8/23/07

1/1 008 G2.4.49 KA replaced with 008 G 2.4.41 during exam review as

directed by Chief Examiner. 12/20/2007

2/2 029 G2.4.38 Unable to write question related taking actions called for in

the Emergency Plan to Containment Purge.

Replace with 029 G2.4.46 - New KiA supplied by Chief

Examiner 8/23/07

1/1 E12 G2.4.33 Unable to write question that tied process for tracking

INOP alarms to a Stearn Line Rupture - Excessive Heat

Transfer. Replace with W/EI2 G2.1.32 - New KiA

supplied by Chief Examiner 8/23/07

3 G2.4.49 KA replaced with G 2.4.40 during exam review as directed

by Chief Examiner. 12/20/2007

(

ES-401, Page 27 of 33