IR 05000328/2008301
| 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) | |
Text
Final Submittal (Blue Paper)
FINAL OUTLINES
£5 -1.j()/-cJ.-
SctyLltJyAI-f 02 CJD&-cl 0/
Printed: 01/13/2008 SRO-Only Points A2 G*
Total
0
0
0
0
0
0
0
0
0
1
3
0
0
0 ES-401 PWR Examination Outline Facility:
Sequoyah Date Of Exam:
01/28/2008 RO KiA Category Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total 1.
3
3
3
18 Emergenc
1
1
2
9
&
N/A N/A Abnormal Tier Plant Totals
5
4
5
Evolutions 2.
2
3
3
2
2
3
Plant
1
1
1
1
1
1
Systems Tier
3
4
3
3
4
38 Totals 3. Generic Knowledge And
2
4
Abilities Categories
2
2 Note:
~\\fJ
Form ES-401-2 (
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 55.4 Facility:
Sequoyah ES - 401 PWR RO Examination Outline Emergency and Abnormal Plant EVOlutions - Tier I 1Group I Printed:
01/13/2008 Form ES-401-2 (
(
I TCJAPE # 1Name 1Safety Function KI K2 K3 Al A2 G
KA Topic Imp.
Points 000007 Reactor Trip - Stabilization -
X EAl.08 - AFW System 4.4
Recovery 11 000008 Pressurizer Vapor Space Accident 1 X
AA2.29 - The effects ofbubble in 3.9
3 reactor vessel 000009 Small Break LOCA 13 X
EA2.24 - RCP temperature setpoints 2.6
000011 Large Break LOCA 13 X
EK3.13 - Hot-leg injection/recirculation 3.8
000015/000017 RCP Malfunctions 14 X
AK2.08 - CCWS 2.6
000022 Loss of Rx Coolant Makeup 12 X
AA2.03 - Failures of flow control valve 3.1
or controller 000025 Loss of RHR System 14 X
AK2.05 - Reactor building sump 2.6
000026 Loss of Component Cooling Water 1 X
AK3.03 - Guidance actions contained in 4.0
8 EOP for Loss of CCW 000027 Pressurizer Pressure Control System X
AAl.02 - SCR-controlled heaters in 3.1*
Malfunction 13 manual mode 000038 Steam Gen. Tube Rupture 13 X
2.1.3 - Knowledge of shift turnover 3.0
practices.
000040 Steam Line Rupture - Excessive X
AKl.03 - RCS shrink and consequent 3.8
Heat Transfer 14 depressurization
)0055 Station Blackout 16 X
2.4.29 - Knowledge of the emergency 2.6
plan.
000056 Loss of Off-site Power 16 X
AKl.03 - Definition of subcooling: use 3.1*
of steam tables to determine it 000058 Loss of DC Power 16 X
AKl.Ol - Battery charger equipment 2.8
and instrumentation 000062 Loss of Nuclear Svc Water 14 X
AAl.Ol - Nuclear service water 3.1
temperature indications WIE04 LOCA Outside Containment 13 X
2.4.48 - Ability to interpret control 3.5
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
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
Facility:
Sequoyah ES - 401 PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Printed:
01/13/2008 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
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 Group Point Total:
2
Facility:
Sequoyah ES - 401 PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Printed:
01/13/2008 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*
000033 Loss of Intermediate Range NI /7 X
2.4.21 - Knowledge of the parameters 3.7
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
000060 Accidental Gaseous Radwaste ReI. /
X AA1.02 - Ventilation system 2.9
9 000069 Loss of CTMT Integrity / 5 X
2.4.45 - Ability to prioritize and 3.3
interpret the significance of each annunciator or alarm.
000074 Inad. Core Cooling / 4 X
EK3.07 - Starting up emergency 4.0
feedwater and RCPs 000076 High Reactor Coolant Activity /9 X
AK2.01 - Process radiation monitors 2.6
W/E09 Natural Circ. /4 X
EA2.1 - Facility conditions and 3.1
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
procedures and operation within the limitations in the facility's license and amendments KIA Category Totals:
2
1
2 Group Point Total:
Facility:
Sequoyah ES - 401 PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Printed:
01/13/2008 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
003 Reactor Coolant Pump X
2.3.10 - Ability to perform 2.9
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*
path around boric acid storage tank 004 Chemical and Volume Control X
A3.08 - Reactor power 3.9
005 Residual Heat Removal X
A4.03 - RHR temperature, 2.8*
PZR heaters and flow, and nitrogen 006 Emergency Core Cooling X
K1.02 - ESFAS 4.3
007 Pressurizer Relief/Quench X
K3.0l - Containment 3.3
Tank 007 Pressurizer Relief/Quench X
2.1.1 - Knowledge of 3.7
Tank conduct of operations requirements.
008 Component Cooling Water X
K4.07 - Operation of the 2.6*
CCW swing-bus power supply and its associated breakers and controls J10 Pressurizer Pressure Control X
K6.03 - PZR sprays and 3.2
heaters 012 Reactor Protection X
K4.04 - Redundancy 3.1
013 Engineered Safety Features X
K2.0l - ESFAS/safeguards 3.6*
Actuation equipment control 022 Containment Cooling X
A2.04 - Loss of service 2.9*
water 025 Ice Condenser X
K5.02 - Heat transfer 2.6*
026 Containment Spray X
K4.07 - Adequate level in 3.8*
containment sump for suction (interlock)
026 Containment Spray X
2.4.48 - Ability to interpret 3.5
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*
radiation monitors 059 Main Feedwater X
A2.07 - Tripping ofMFW 3.0*
pump turbine 059 Main Feedwater X
A4.0l - MFW turbine trip 3.1*
indication
Facility:
Sequoyah ES - 401 PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Printed:
01/13/2008 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
Feedwater between AFW flow and RCS heat transfer 062 AC Electrical Distribution X
Kl.02 - ED/G 4.1
063 DC Electrical Distribution X
K2.0l - Major DC loads 2.9*
064 Emergency Diesel Generator X
K6.08 - Fuel oil storage 3.2
tanks 073 Process Radiation Monitoring X
Al.Ol - Radiation levels 3.2
076 Service Water X
A2.02 - Service water 2.7
header pressure 076 Service Water X
A4.02 - SWS valves 2.6
078 Instrument Air X
K3.0l - Containment air 3.1*
system 103 Containment X
A3.0l - Containment 3.9
isolation KIA Category Totals:
2
3
2
3
3
Group Point Total:
2
Facility:
Sequoyah ES - 401 PWR RO Examination Outline Plant Systems - Tier 2 1Group 2 Printed:
01/13/2008 Form ES-401-2 (
(
I Sys/Evol # 1Name 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
level gauges as postaccident monitors 015 Nuclear Instrumentation X
K2.01 - NIS channels, 3.3
components, and interconnections 016 Non-nuclear Instrumentation X
K1.l0 - CCS 3.1*
017 In-core Temperature Monitor X
K4.03 - Range of 3.1
temperature indication 045 Main Turbine Generator X
K5.17 - Relationship 2.5*
between moderator temperature coefficient and boron concentration in RCS as TIG load increases 055 Condenser Air Removal X
A3.03 - Automatic diversion 2.5*
of CARS exhaust 068 Liquid Radwaste X
A4.01 - Control board for 2.7*
boron recovery 071 Waste Gas Disposal X
K3.04 - Ventilation system 2.7
075 Circulating Water X
2.2.11 - Knowledge of the 2.5
process for controlling temporary changes.
086 Fire Protection X
A1.01 - Fire header pressure 2.9
I KIA Category Totals:
1
1
1
0
1
Group Point Total:
Facility:
Sequoyah Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline Printed:
01/13/2008 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:
Equipment Control 2.2.26 Knowledge ofrefueling administrative 2.5 I
requirements.
2.2.33 Knowledge of control rod programming.
2.5 I
Category Total:
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:
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:
(
Generic Total:
(
Form ES-401-2 Printed: 01/13/2008 SRO-Only Points A2 G*
Total
0
0
0
0
0
0
0
0
0
1
3
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 55.4 Facility:
. Outline Printed:
01/13/200 E
ES 401
-
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 ofbubble 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
Facility:
Sequoyah PWRRO Examina
. Outline Printed:
01/13/200 ES 401
-
Emergency and Abnormal Plant Evolutions - Tier 1 1Group 1 Form ES-401-2 E/APE # 1Name 1Safety 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 ofsteam tables to determine it 000058 Loss ofDC Power 16 AK1.01 Battery charger equipment and instrumentation 000062 Loss ofNuclear 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 ofsystem, 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
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
Facility:
. Outline Printed:
01/13/20l license and amendments A
E ES 401
-
meraencv and 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 ofeach 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
Facility:
Sequoyah ES - 401 Plant Systems - Tier 2 / Group 1 Printed: 01/13,-~
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 Form ES-401-2 Plant Systems - Tier 2 / Group 1 ES - 401 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
PWR RO---'~mination Outline Printed: 01/13!-~~
Facility:
Sequoyah Form ES-401-2 Plant Systems - Tier 2 / Group 1 ES - 401 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
PWR Ro.~'1mination Outline Printed: OlI1Y-'Q Facility:
Sequoyah Form ES-401-2 Plant Systems - Tier 2 / Group 2 ES - 401 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
Facility:
Sequoyah Generic Category Conduct of Operations KA Generic Knowledge
. Abilities Outline (Tier 3)
PWR RO Examination Outline KA Topic Knowledge of shift turnover practices.
Knowledge of system purpose and or function.
Knowledge of the purpose and function of major system components Printed:
01/13/20 Form ES-401-3 Comment Category Total:
Equipment Control Radiation Control Emergency Procedures/Plan Knowledge of refueling administrative requirements.
2.2.33 IKnowledge of control rod programming.
Knowledge of facility ALARA program.
Knowledge of the process for performing a containment purge.
Ability to perform procedures to reduce excessive levels of radiation Knowledge of EOP implementation hierarchy and coordination with Knowledge of the bases for prioritizing safety functions during Category Total:
Category Total:
Category Total:
Generic Total:
(
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 ChiefExaminer. 12/20/2007 1/1 055 G2.4.29 KA replaced with 055 G 2.4.18 during exam review as directed by ChiefExaminer. 12/20/2007 2/2 075 G2.2.11 KA replaced with 075 G 2.2.13 during exam review as directed by ChiefExaminer. 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.
0
0
0
0
3
Emergenc
0
0
0
0
2
&
N/A N/A Abnormal Tier Plant Totals
0
0
0
7
12 Evolutions 2.
0
0
0
0
0
0
2
4
0
0
0
0
0
0
01
1
Plant Systems Tier
0
0
0
0
0
0
3
Totals 3. Generic Knowledge And
2
4
2
4
7 Abilities Categories
0
0
1
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 55.4 Facility:
Sequoyah PWR SRO Examir, In Outline Printed:
0l/13/20C 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 dAb E
ES 401
-
merzency an normal Plant Evolutions - Tier 1 1Group 1 Form ES-401-2 EIAPE # 1Name 1Safety 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 18 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
Facility:
Sequoyah PWR SRO Examin n Outline Printed:
01/13/20(,
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 ofrefueling 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 ChiefExaminer 8/23/07 000005 Inoperable/Stuck Control Rod / 1 AA2.03 Required actions ifmore 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 ofprocedures and limitations involved in initial core loadin PWR SROC--.lmination Outline Printed: 01/1y~~
Facility:
Sequoyah Form ES-401-2 Plant Systems - Tier 2 / Group 1 ES - 401 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 Contra1 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 chance Facility:
Sequoyah ES - 401 PWR SRO-'Unination Outline Plant Systems - Tier 2 1Group 2 Printed: Ol/13r-~~
Form ES-401-2 Sys/Evol # 1Name 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 (ifrequired) 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
Facility:
Sequoyah Generic Category Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan KA Generic Knowledge Abilities Outline (Tier 3)
PWR SRO Examination Outline KA Topic Ability to apply teclmical specifications for a system.
Ability to recognize indications for system operating parameters Knowledge of the process for determining if the proposed change, Knowledge of 10 CFR: 20 and related facility radiation control Knowledge of the requirements for reviewing and approving release Knowledge oflow power /shutdown implications in accident (e.g.
Ability to perform without reference to procedures those actions that Printed:
01/13/20, Form E8-401-3 Comment Category Total:
Category Total:
Category Total:
Category Total:
Generic Total:
ES-401 PWR Examination Outline Facility:
Sequoyah Date Of Exam:
01/28/2008 RO KIA Category Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total 1.
0
0
0
0 Emergenc
0
0
0
0
&
N/A N/A Abnormal Tier Plant Totals
0
0
0
Evolutions 2.
0
0
0
0
0
0
2
0
0
0
0
0
0 Plant Systems Tier
0
0
0
0
0
0 Totals 3. Generic Knowledge And
2
4
Abilities Categories
0
0 Note:
Form ES-401-2 Printed: 01/13/2008 SRO-Only Points A2 G*
Total
3
3
5
5
2
4
1
2
3
1
3
7
1
2 (
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 55.4 Facility:
Sequoyah ES - 401 PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier I / Group I Printed:
01/13/2008 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
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
turbine/reactor trip 000054 Loss of Main Feedwater /4 X
AA2.05 - Status ofMFW pumps, 3.7
regulating and stop valves 000057 Loss of Vital AC Inst. Bus / 6 X
AA2.17 - System and component status, 3.4
using local or remote controls 000065 Loss of Instrument Air / 8 X
AA2.01 - Cause and effect of 3.2
low-pressure instrument air alarm W/E 11 Loss of Emergency Coolant Recirc. /
X 2.4.48 - Ability to interpret control 3.8
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
Heat Transfer / 4 track inoperable alarms.
KIA Category Totals:
0
0
3 Group Point Total:
Facility:
Sequoyah ES - 401 PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Printed:
01/13/2008 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
administrative requirements.
000005 Inoperable/Stuck Control Rod / 1 X
AA2.03 - Required actions if more than 4.4
one rod is stuck or inoperable 000051 Loss of Condenser Vacuum /4 X
AA2.02 - Conditions requiring reactor 4.1
and/or turbine trip W/E02 SI Termination /3 X
EA2.2 - Adherence to appropriate 4.0
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 ofprocedures and 2.9*
limitations involved in initial core loading.
KIA Category Totals:
0
0
2 Group Point Total:
Facility:
Sequoyah ES - 401 PWR SRO Examination Outline Plant Systems - Tier 2 1Group 1 Printed:
01/13/2008 Form ES-401-2 (
(
I Sys/Evol # 1Name 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
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
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
Actuation power 103 Containment X
2.2.14 - Knowledge of the 3.0
process for making configuration changes.
KIA Category Totals:
0
0
0
2
0
Group Point Total:
Facility:
Sequoyah ES - 401 PWR SRO Examination Outline Plant Systems - Tier 2 1Group 2 Printed:
01/13/2008 Form ES-401-2 f
\\
(
I Sys/Evol # 1Name 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
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
KIA Category Totals:
0
0
0
I
0 I
Group Point Total:
Facility:
Sequoyah Generic Category Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline KA Topic Printed:
01/13/2008 Form ES-401-3 (
Conduct of Operations 2.1.12 Ability to apply technical specifications for a 4.0
system.
2.1.33 Ability to recognize indications for system 4.0
operating parameters which are entry-level conditions for technical specifications.
Category Total:
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:
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:
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 ofsystem components and controls.
Category Total:
Generic Total:
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 ofDropped Control Rod. Replace with 003 G2.2.22 - New KiA supplied by ChiefExaminer 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 ChiefExaminer 8/23/07
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