ML100470905
| ML100470905 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/20/2009 |
| From: | D'Antonio J Operations Branch I |
| To: | Dominion Nuclear Connecticut |
| Hansell S | |
| Shared Package | |
| ML092400035 | List: |
| References | |
| 50-336/10-301, ES-401, ES-401-2, TAC U01799, FOIA/PA-2011-0115 50-336/10-301 | |
| Download: ML100470905 (20) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 2 Date of Exam: 12/18/09 RO KJA Category Points SRO-Only Points Tier Group
~{
K K
K K A A
A A
G r 1
3 4
5 6
1 2
3 4
A2 G*
Total
- 1.
1
'~
V A
6
~
10 Emergency &
Abnormal 2
/'
9 2
2 4
Plant
)<
Evolutions Tier Totals 27 4
6 10
./
1 28 1
4 5
- 2.
Systems 2
10 N/A 1
2 3
Plant L
Tier Totals
~ 2 6
8
- 3. Generic Knowledge and Abilities "1~
~,-~--10 1
2 3
4 Categories
~
2 2
2 1
7 Note:
- 1.
Ensure that at least 2 topics from every KlA category are sampled within each tier of the RO and SRO outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KlA category shall not be less than 2).
- 2.
The point total for each group and tier in the proposed outline must match those 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/evolutions that are included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KlA statements.
- 4.
SEflect 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, 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 KlA categories.
- 7.
The generic KlAs in Tiens 1 and 2 shall be selected from Section 2 of the KlA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.
- 8.
On the following pages, enter the KlA numbens, 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 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-only exams.
- 9.
For Tier 3, s.elect topics form Section 2 of the KIA catalog, and enter the KlA numbers, descriptions, IRs, and point totals (#) on Form ES-40103. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 2 Date of Exam: 12/18/09 RO KJA Category Points SRO-Only Points Tier Group
~ {
K K
K K A A
A A
G r 1
3 4
5 6
1 2
3 4
A2 G*
Total
- 1.
1
'~
V A
6
~
10 Emergency &
Abnormal 2
/'
9 2
2 4
Plant
)<
Evolutions Tier Totals 27 4
6 10
./
1 28 1
4 5
- 2.
Systems 2
10 N/A 1
2 3
Plant L
Tier Totals
~ 2 6
8
- 3. Generic Knowledge and Abilities "1-~
~,-~
--10 1
2 3
4 Categories
~
2 2
2 1
7 Note:
- 1.
Ensure that at least 2 topics from every KlA category are sampled within each tier of the RO and SRO outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KlA category shall not be less than 2).
- 2.
The point total for each group and tier in the proposed outline must match those 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/evolutions that are included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KlA statements.
- 4.
SEflect 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, 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 KlA categories.
- 7.
The generic KlAs in Tiens 1 and 2 shall be selected from Section 2 of the KlA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.
- 8.
On the following pages, enter the KlA numbens, 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 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-only exams.
- 9.
For Tier 3, s.elect topics form Section 2 of the KIA catalog, and enter the KlA numbers, descriptions, IRs, and point totals (#) on Form ES-40103. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES*401 2
Form ES-401-2 ES-401 Emerg E/APE # 1Name 1Safety Function (BW/E02&E10; CE/E02) Reactor
- Recovery 11 000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA I 3 000011 Large Break LOCA 13 000015/17 RCP Malfunctions I 4 000022 Loss of Rx Coolant I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water 18 Pressurizer Pressure Control Malfunction 13 000029 ATWS 11 000038 Steam Gen. Tube Rupture 13 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer I 4
000054 (CE/E06) Loss of Main Feedwater 14 000055 Station Blackout 1 6 000056 Loss of Off-site Power /6 000057 Loss of Vital AC Inst. Bus 1 6 000058 Loss of DC Power I 6 000065 Loss of Instrument Air 18 000077 Generator Voltage and Electric Grid Disturbances I 6 KIA Category Totals:
PWR Examination Outline Form ES-401-2 and Abnormal Plant Evolutions Tier 1/Group 1 KKK A A
G 12312 KIA Topic(s)
IR 2.1.31 - Ability to locate control room 4.6/4.3 switches, controls, and indications, and to determine that they correctly reflect the desired plant EA2.06 - Ability to determine or interpret 3.7*/4.0" the following as they apply to a Large Break LOCA: That fan is in slow speed and dampers are in accident mode LOCA 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2.1.30 - Ability to locate and operate local controls.
4.4/4/7 4.4/4.0 2.4.35 Knowledge oflocal auxiliary 3.8/4.0 operator tasks during an emergency and the resultant erational effects.
2 3
4 5
AA2.06 - Ability to determine and interpret 3.6*/4.2 6
the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing Group Point Total:
ES-401 ES*401 ES-401 Emerg E/APE # 1 Name 1 Safety Function (BW/E02&E10; CE/E02) Reactor
- Recovery 11 000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA I 3 000011 Large Break LOCA 13 000015/17 RCP Malfunctions I 4 000022 Loss of Rx Coolant I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water 18 Pressurizer Pressure Control Malfunction 1 3 000029 ATWS 11 000038 Steam Gen. Tube Rupture 1 3 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer I 4
000054 (CE/E06) Loss of Main Feedwater 14 000055 Station Blackout 1 6 000056 Loss of Off-site Power /6 000057 Loss of Vital AC Inst. Bus 1 6 000058 Loss of DC Power I 6 000065 Loss of Instrument Air 18 000077 Generator Voltage and Electric Grid Disturbances I 6 KIA Category Totals:
2 Form ES-401-2 PWR Examination Outline Form ES-401-2 and Abnormal Plant Evolutions Tier 1/Group 1 KKK A A
G 12312 KIA Topic(s)
IR 2.1.31 - Ability to locate control room 4.6/4.3 switches, controls, and indications, and to determine that they correctly reflect the desired plant lineu.
EA2.06 - Ability to determine or interpret 3.7*/4.0" the following as they apply to a Large Break LOCA: That fan is in slow speed and dampers are in accident mode LOCA 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2.1.30 - Ability to locate and operate cOlnn<me:nts. inelu local controls.
4.4/4/7 4.4/4.0 2.4.35 Knowledge oflocal auxiliary 3.8/4.0 operator tasks during an emergency and the resultant effects.
2 3
4 5
AA2.06 - Ability to determine and interpret 3.6*/4.2 6
the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing Group Point Total:
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline FORM ES-401-2 Emo,rnoni"'\\1 and Abnormal Plant Evolutions - Tier 1/Group 2 (RO 1
============~~========~=====9==91 E/APE # 1Name 1Safety Function 000001 Continuous Rod Withdrawal 1 1 000003 Dropped Control Rod 11 Control Rod / 1 0032 Loss of Source Range NI 17 000033 Loss of Intermediate Ran NI/7 000036 000037 Steam Generator Tube Leak 13 000051 Loss of Condenser Vacuum /4 000059 Accidental Li RadWaste ReI. / 9 000060 Accidental Gaseous Radwaste ReI. / 9 000061 ARM System Alarms /7 000067 Plant Fire On-site I 8 000068 Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity /5 000074 (W/E06&E07) Inad. Core Cooling /4 000076 High Reactor Coolant Activity /9 A13; W/E09&E10 Natural Circ./4
- PTS /4 KKK 123 KIA Topic(s)
IR M2.04 - Ability to determine and 3.4*/3.6*
7 interpret the following as they apply to the Dropped Control Rod: Rod motion stops due to dropped rod 2.4.18 - Knowledge of the specific bases for EOPs.
3.3/4.0 8
2.4.30 - Knowledge of events 2.7/4.1 9
related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
M2.02 - Ability to determine and 2.4/2.7*
10 interpret the following as they apply to the High Reactor Coolant Activity: 'Nhen demlneralizer resin needs to be replaeed.
Does NOT distinguish between a competent and incompetent SRO.
M2.07 - Corrective Actions required 2.8/3.4 for high fission product acti vity in RCS ES-401 ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline FORM ES-401-2 Emo,rnoni"'\\1 and Abnormal Plant Evolutions - Tier 1/Group 2 (RO 1
============~~========~=====9==91 E/APE # 1 Name 1 Safety Function 000001 Continuous Rod Withdrawal 1 1 000003 Dropped Control Rod 1 1 Control Rod / 1 0032 Loss of Source Range NI 17 000033 Loss of Intermediate Ran NI/7 000036 000037 Steam Generator Tube Leak 13 000051 Loss of Condenser Vacuum /4 000059 Accidental Li RadWaste ReI. / 9 000060 Accidental Gaseous Radwaste ReI. / 9 000061 ARM System Alarms /7 000067 Plant Fire On-site I 8 000068 Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity /5 000074 (W/E06&E07) Inad. Core Cooling /4 000076 High Reactor Coolant Activity /9 A13; W/E09&E10 Natural Circ./4
- PTS /4 KKK 123 ES-401 KIA Topic(s)
IR M2.04 - Ability to determine and 3.4*/3.6*
7 interpret the following as they apply to the Dropped Control Rod: Rod motion stops due to dropped rod 2.4.18 - Knowledge of the specific bases for EOPs.
3.3/4.0 8
2.4.30 - Knowledge of events 2.7/4.1 9
related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
M2.02 - Ability to determine and 2.4/2.7*
10 interpret the following as they apply to the High Reactor Coolant Activity: 'Nhen demlneralizer resin needs to be replaeed.
Does NOT distinguish between a competent and incompetent SRO.
M2.07 - Corrective Actions required 2.8/3.4 for high fission product acti vity in RCS
ES*401 4
Form ES-401*2 ES-401 PWR Examination Outli,s;;.--.....
Plant......\\"~r""rns - Tier 2/Grou Form ES-401-2 System # / Name K
1 K
2 KKK 3
4 5
K 6
KIA Topic(s)
IR 003 Reactor Coolant Pump 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of ant "n"ra'C1n" 4.3/4.4 11 004 Chemical and Volume Control A2.15 - Ability to (a) predictthe impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level 3.5/3.7 12 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.5/4.7 13 013 Engineered Safety Features Actuation 022 Containment 026 Containment Spray 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
4.2/4.0 14 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution ES-401 ES*401 ES-401 System # / Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution K K 1
2 4
Form ES-401*2 PWR Examination Outli,s;;.--.....
Form ES-401-2 Plant...... \\"~r""rns - Tier 2/Grou KKK K 3
4 5
6 ES-401 KIA Topic(s)
IR 2.1.23 - Ability to perform specific 4.3/4.4 11 system and integrated plant procedures during all modes of ant "n"ra'C1n" A2.15 - Ability to (a) predictthe 3.5/3.7 12 impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level 2.4.4 - Ability to recognize 4.5/4.7 abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
4.2/4.0 13 14
15 ES-401 5
Form ES-401*2 ES-401 PWR Examination Outli '.... _.....
Form ES-401-2 Plant Systems - Tier 2/Grou 1~==-------======P=r~~==F System # 1 f\\ame KKK K 1 234 KIA Topic(s}
Group Point Total:
IR 3.7/4.1 064 Emergency Diesel Generator 073 Process Radiation ES-401 ES-401 5
ES-401 PWR Examination Outli '.... _.....
Plant Systems - Tier 2/Grou 1~==-------======P=r~~==F System # 1 f\\ame 064 Emergency Diesel Generator 073 Process Radiation KKK K 1 234 KIA Topic(s}
Group Point Total:
ES-401 Form ES-401*2 Form ES-401-2 IR 3.7/4.1 15
ES-401 6
Form ES-401*2 ES-401 PWR Examination Outline s - Tier 2/Group 2 1F=====================T==r~==T==r='==T==
System # 1Name 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine I-<,"n",.,., Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Dis 072 Area Radiation Monitoring 075 Circulati Water 079 Station Air 086 Fire Protection K K 1
2 KKK 345 K
6 KIA Topic(s) 2.1.32 - Ability to explain and apply all system limits and precautions.
Form ES-401-2 IR 3.8/4.0 16 2.2.36 - Ability to analyze the 3.1/4.2 17 effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
A2.03 - Ability to (a) predict 2.7/2.9 the impacts of the following mal-functions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Inadvertent aetuation ofthe FPS due to circuit failure or wellonl!!:
ES-401 PWR Examination Outline s - Tier 2/Group 2 1F=====================T==r~==T==r='==T==
System # 1 Name 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine I-<,"n",.,., Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Dis 072 Area Radiation Monitoring 075 Circulati Water 079 Station Air 086 Fire Protection K K 1
2 KKK 345 K
6 ES-401 Form ES-401*2 KIA Topic(s) 2.1.32 - Ability to explain and apply all system limits and precautions.
Form ES-401-2 IR 3.8/4.0 16 2.2.36 - Ability to analyze the 3.1/4.2 17 effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
A2.03 - Ability to (a) predict 2.7/2.9 the impacts of the following mal-functions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Inadvertent aetuation of the FPS due to circuit failure or wellonl!!:
18
ES-401 7
Form ES-401-2 PWR Examination Outline
- Tier 2/Group 2 p Point Total:
3 ES-401 Form ES-401-2 Plant KKK KIA Topic(s)
IR System # / Name KKK 1 234 5 6 KIA Category Point Totals:
ES-401 ES-401 ES-401 System # / Name KIA Category Point Totals:
7 PWR Examination Outline Plant
- Tier 2/Group 2 KKK KKK 1 234 5 6
ES-401 Form ES-401-2 Form ES-401-2 KIA Topic(s)
IR p Point Total:
3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facili Millstone Unit 2 Date of Exam: 12/18/09 Category KJA#
Topic RO SRO Knowledge of facility requirements for controlling 2.1.13 vital/controlled access.
- 1.
Conduct of Knowledge of the fuel-handling responsibilities of SROs.
2.1.35 Operations Subtotal Knowledge of the process for managing maintenance activities 2.2.17 during power operations, such as risk assessments, work prioritization, and coordination with the transmission system
- 2.
Equipment Control Knowledge of conditions and limitations in the facility license.
2.2.38 Subtotal Ability to approve release permits.
2.3.6
- 3.
Knowledge of radiation or contamination hazards that may 2.3.14 Radiation arise during normal, abnormal, or emergency conditions or Control activities.
Subtotal Ability to prioritize and interpret the significance of each 2.4.45
- 4.
annunciator or alarm.
Emergency Procedures and Plan Subtotal Tier 3 Point Total ES-401 ES-401 Facili Millstone Unit 2 Category
- 1.
Conduct of Operations
- 2.
Equipment Control
- 3.
Radiation Control
- 4.
Emergency Procedures and Plan KJA#
2.1.13 2.1.35 Subtotal 2.2.17 2.2.38 Subtotal 2.3.6 2.3.14 Subtotal 2.4.45 Subtotal Tier 3 Point Total Generic Knowledge and Abilities Outline (Tier 3)
Date of Exam: 12/18/09 Topic Knowledge of facility requirements for controlling vital/controlled access.
Knowledge of the fuel-handling responsibilities of SROs.
Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system Knowledge of conditions and limitations in the facility license.
Ability to approve release permits.
Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
Ability to prioritize and interpret the significance of each annunciator or alarm.
ES-401 Record of Rejected KI As Form ES-401-4 Randomly Reason for Rejection
~
Selected KIA 076-AA2.02 Does NOT distinguish between a competent and incompetent SRO.
1--
ES-401, Page 27 of 33 ES-401 Record of Rejected KI As Form ES-401-4
~
Randomly Reason for Rejection Selected KIA 076-AA2.02 Does NOT distinguish between a competent and incompetent SRO.
1---
ES-401, Page 27 of 33
L Description of the Process Used to Develop the Millstone 2 Exam Outline Obtained copies of Forms ES-40 1-2, PWR Examination Outlines for SRO and RO, and Form ES-401-3 Generic Knowledge and Abilities Outline (Tier 3).
II.
For each Tier and Group, the Example Systematic Sampling Methodology per ES-40 1, and guidance on ES-401-2 were used to select the topics for the SRO exam as follows:
A.
Annotated all systems/topics not applicable to Millstone 2 (Ex. W, BW).
B.
Because each group had more topics than required for a Tier/Group, tokens were randomly drawn to determine which topics would receive question coverage.
III.
Used the Example Systematic Sampling Methodology per ES-401, Attachment 1 to select the KIA categories ("A2" or "G") for the SRO exam for each topic chosen.
IV.
Used the Example Systematic Sampling Methodology per ES-401, Attachment 1 to select the individual KIA statements for the SRO exam as follows:
A.
Any individual KIA statement with an importance rating of<2.5 was eliminated prior to the selection process.
B.
Prior to randomly selecting the individual KIA statements for Tier I and 2 "Generic" categories, non-relevant KIA statements were removed. Only the Generic KIAs listed in ES-40 I, D.l.b were made available for random selection.
C.
Prior to randomly selecting the individual KIA statements for Tier 1 and 2 "A2" categories, non-relevant KIA statements were removed.
V.
Verified each KIA category for the SRO exam had at least 2 points in each tier (as applicable).
Description of the Process Used to Develop the Millstone 2 Exam Outline L
Obtained copies of Forms ES-40 1-2, PWR Examination Outlines for SRO and RO, and Form ES-401-3 Generic Knowledge and Abilities Outline (Tier 3).
II.
For each Tier and Group, the Example Systematic Sampling Methodology per ES-40 1, and guidance on ES-401-2 were used to select the topics for the SRO exam as follows:
A.
Annotated all systems/topics not applicable to Millstone 2 (Ex. W, BW).
B.
Because each group had more topics than required for a Tier/Group, tokens were randomly drawn to determine which topics would receive question coverage.
III.
Used the Example Systematic Sampling Methodology per ES-401, Attachment 1 to select the KIA categories ("A2" or "G") for the SRO exam for each topic chosen.
IV.
Used the Example Systematic Sampling Methodology per ES-401, Attachment 1 to select the individual KIA statements for the SRO exam as follows:
A.
Any individual KIA statement with an importance rating of <2.5 was eliminated prior to the selection process.
B.
Prior to randomly selecting the individual KIA statements for Tier I and 2 "Generic" categories, non-relevant KIA statements were removed. Only the Generic KI As listed in ES-40 I, D.l.b were made available for random selection.
C.
Prior to randomly selecting the individual KIA statements for Tier 1 and 2 "A2" categories, non-relevant KIA statements were removed.
V.
Verified each KIA category for the SRO exam had at least 2 points in each tier (as applicable).
ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 2 Date of Exam: 12/18/09 Tier Group RO KIA Category Points SRO-Only Points
~
1 Ii K
3 i'.
K 4
K 5
K 6
A 1
A 2
A 3
A 4
G
- ~
A2 G*
Total
- 1.
Emergency &
Abnormal Plant Evolutions 1
~
/
~
V 18 2
4 6
2
/'
9 2
2 4
Tier Totals l>""
27 4
6 10
- 2.
Systems Plant 1
/
/'
"'" ~
28 1
4 5
2
/V
~ 10 I\\J/A 1
2 3
Tier Totals 1/
V
~ 2 6
8
- 3. Generic Knowledge and Abilities Categorie!s 1~
3---
l..--4----10 1
2 3
4 7
~
r---
2 2
2 1
Note:
- 1.
Ensure that at least 2 topics from every KlA category are sampled within each tier of the RO and SRO outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KlA category shall not be less than 2).
- 2.
The point total for each group and tier in the proposed outline must match those 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/evolutions that are included on the outline should be added. RefE!r to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KlA 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, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the R,O 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 KlA categories.
- 7.
- The generic KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KlA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.
B.
On the following pages, enter the KlA 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 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-only exams.
- 9.
For Tier 3, sl31ect topics form Section 2 of the KlA catalog, and enter the KlA numbers, descriptions, IRs, and point totals (#) on Form ES-40103. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 2 Date of Exam: 12/18/09 RO KIA Category Points SRO-Only Points Tier Group
~ Ii K
K K
K A A
A A
G ~
1 3
4 5
6 1
2 3
4 A2 G*
Total i'.
- 1.
1
~ ~
V 18 2
4 6
Emergency &
Abnormal 2
/'
9 2
2 4
Plant l>
Evolutions Tier Totals 27 4
6 10
/
1
/
"'" ~
28 1
4 5
- 2.
/'
Systems 2
/V
~ 10 I\\J/A 1
2 3
Plant V
~
Tier Totals 1/
2 6
8
- 3. Generic Knowledge and Abilities 1-~
3 l..--4-----10 1
2 3
4 r----
Categorie!s
~
2 2
2 1
7 Note:
- 1.
Ensure that at least 2 topics from every KlA category are sampled within each tier of the RO and SRO outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KlA category shall not be less than 2).
- 2.
The point total for each group and tier in the proposed outline must match those 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/evolutions that are included on the outline should be added. RefE!r to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KlA 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, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the R,O 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 KlA categories.
- 7.
The generic KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KlA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.
B.
On the following pages, enter the KlA 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 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-only exams.
- 9.
For Tier 3, sl31ect topics form Section 2 of the KlA catalog, and enter the KlA numbers, descriptions, IRs, and point totals (#) on Form ES-40103. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES*401 2
Form ES*401*2 ES-401 PWR Examination Outline rnc.rr,,:.nr'\\I and Abnormal Plant Evolutions - Tier 1 Form ES-401-2 E/APE # 1Name 1Safety Function 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery 11 000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA 1 3 000011 Large Brea~: LOCA 13 000015/17 RCP Malfunctions 1 4 000022 Loss of Rx Coolant Makeup 1 2 000025 Loss of RHR System 14 000026 Loss of Component Cooling Water 18 000027 Pressurizer Pressum Control Malfunction 1 3 000029 ATWS 11 000038 Steam Gen. Tube Rupture 1 3 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer 1 4
000054 (CE/E06) Loss of Main Feedwater 14 000055 Station Blackout 1 6 000056 Loss of O"f-site Power 1 6 000057 Loss of Vital AC Inst. Bus 1 6 000058 Loss of DC Power 1 6 000062 Loss of Nuclear Svc Water 1 4 KKK A A
G 12312 KIA Topic(s) 2.1.J1 Ability toloeate eOHtFol Foam switehes, eOHtFols, aHd iHdieatioHs, aHd to deteFmiHe that they eOFFeetly FeOeet the desiFed plaHt liHeup.
Does not adequately test SRO knowledge or ability.
2.1.20 - Ability to interpret and execute procedure steps.
EA2.06 Ability to deteFmiHe OF iHteFpFet the followiHg as they apply to a LaFge BFeal(
LOCA.I That faH is iH slavi speee aRe eampers are iR aeeieeRt meee el:lriRg bOCA Does not adequately test SRO knowledge or ability.
EA2.10 - Ability to determine or interpret the following as they apply to a Large Break LOCA: Verification of adequate core cooling 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2.1.30 - Ability to locate and operate local controls.
IR 4.6/4.6 d.7*!4.0*
4.5/4/7 4.41417 4.4/4.0 2.4.35 - Knowledge oflocal auxiliary 3.8/4.0 operator tasks during an emergency and the resultant effects.
2 3
4 5
ES-401 ES*401 2
Form ES*401*2 ES-401 PWR Examination Outline rnc.rr,,:.nr'\\I and Abnormal Plant Evolutions - Tier 1 Form ES-401-2 E/APE # 1 Name 1 Safety Function 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery 1 1 000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA 1 3 000011 Large Brea~: LOCA 13 000015/17 RCP Malfunctions 1 4 000022 Loss of Rx Coolant Makeup 1 2 000025 Loss of RHR System 14 000026 Loss of Component Cooling Water 1 8 000027 Pressurizer Pressum Control Malfunction 1 3 000029 ATWS 11 000038 Steam Gen. Tube Rupture 1 3 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer 1 4
000054 (CE/E06) Loss of Main Feedwater 14 000055 Station Blackout 1 6 000056 Loss of O"f-site Power 1 6 000057 Loss of Vital AC Inst. Bus 1 6 000058 Loss of DC Power 1 6 000062 Loss of Nuclear Svc Water 1 4 KKK A A
G 12312 KIA Topic(s) 2.1.J1 Ability toloeate eOHtFol Foam switehes, eOHtFols, aHd iHdieatioHs, aHd to deteFmiHe that they eOFFeetly FeOeet the desiFed plaHt liHeup.
Does not adequately test SRO knowledge or ability.
2.1.20 - Ability to interpret and execute procedure steps.
EA2.06 Ability to deteFmiHe OF iHteFpFet the followiHg as they apply to a LaFge BFeal(
LOCA.I That faH is iH slavi speee aRe eampers are iR aeeieeRt meee el:lriRg bOCA Does not adequately test SRO knowledge or ability.
EA2.10 - Ability to determine or interpret the following as they apply to a Large Break LOCA: Verification of adequate core cooling 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2.1.30 - Ability to locate and operate local controls.
IR 4.6/4.6 d.7*!4.0*
4.5/4/7 4.41417 4.4/4.0 2.4.35 - Knowledge oflocal auxiliary 3.8/4.0 operator tasks during an emergency and the resultant effects.
ES-401 2
3 4
5
ES-401 3
Form ES-401-2 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO KKK A A
G KIA Topic(s)
IR E/APE # I Name I Safety Function 12312 000065 Loss of Instrument Air 18 AA2.06 - Ability to determine and interpret 3.6*/4.2 6
the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing 000077 Generator Voltage and Electric Grid Disturbances I 6 6
KIA Category Totals:
Group Point Total:
PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO E/APE # I Name I Safety Function KKK A A
G 12312 KIA Topic(s)
Form ES-401-2 Form ES-401-2 IR 000065 Loss of Instrument Air 18 AA2.06 - Ability to determine and interpret 3.6*/4.2 6
000077 Generator Voltage and Electric Grid Disturbances I 6 KIA Category Totals:
the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing Group Point Total:
6 ES-401
, ES-401 4
Form ES*401*2 1
PWR Examination Outline mAlrnAn{'\\/ and Abnormal Plant Evolutions - Tier 1 FORM ES-40 1-2 E/APE # 1Name 1Safety Function 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod 1 1 000005 Inoperable/Stuck Control Rod 11 000024 Emergency Boration I 1 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Ra NI/7 000033 Loss of Intmmediate Range Nil 7 000036 BW/A08 Fuel Handling Accident I 8 000037 Steam Generator Tube Leak 13 000051 Loss of Condenser Vacuum 14 000060 Accidental Gaseous Radwast 000061 ARM ""<;!'I"'Tn Alarrns 17 000067 Plant Fire On-site l 8 000068 000069 E14 Loss of CTMT I 15 000074 (W/E06&E07) Inad. Core Cooling 14 000076 High Reactor Coolant Activity 19 BW/E09; CE/A13; W/E09&E10 Natural Circ./4 CEIA 11; W IE08 ReS Overcooling - PTS 14 CE/A16 Excess ReS Leakage 12 CE/E09 Functional KIA Category Point Totals:
KKK 123
==========~~=======T====~==~l KIA Topic(s)
IR AA2.04 - Ability to determine and 3.4*/3.6*
7 interpret the following as they apply to the Dropped Control Rod: Rod motion stops due to dropped rod 2.4.18 - Knowledge of the specific bases for EOPs.
2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system 0 3.3/4.0 8
2.7/4.1 AA2.07 - Ability to determine and 2.4/2.7*
10 interpret the following as they apply to the High Reactor Coolant Activity: \\l/heH demiHeralizer feSiH Heeds te ae feplaeed.
Does NOT distinguish between a competent and incompetent SRO.
AA2.02 - Corrective Actions required 2.8/3.4 for high fission product activity in RCS Group Point Total:
4 ES-401
, ES-401 4
Form ES*401*2 1
PWR Examination Outline mAlrnAn{'\\/ and Abnormal Plant Evolutions - Tier 1 FORM ES-40 1-2 E/APE # 1 Name 1 Safety Function 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod 1 1 000005 Inoperable/Stuck Control Rod 11 000024 Emergency Boration I 1 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Ra NI/7 000033 Loss of Intmmediate Range Nil 7 000036 BW/A08 Fuel Handling Accident I 8 000037 Steam Generator Tube Leak 13 000051 Loss of Condenser Vacuum 14 000060 Accidental Gaseous Radwast 000061 ARM ""<;!'I"'Tn Alarrns 17 000067 Plant Fire On-site l 8 000068 000069 E14 Loss of CTMT I 15 000074 (W/E06&E07) Inad. Core Cooling 14 000076 High Reactor Coolant Activity 19 BW/E09; CE/A13; W/E09&E10 Natural Circ./4 CEI A 11; W IE08 ReS Overcooling - PTS 14 CE/A16 Excess ReS Leakage 12 CE/E09 Functional KIA Category Point Totals:
KKK 123 ES-401
==========~~=======T====~==~l KIA Topic(s)
IR AA2.04 - Ability to determine and 3.4*/3.6*
7 interpret the following as they apply to the Dropped Control Rod: Rod motion stops due to dropped rod 2.4.18 - Knowledge of the specific bases for EOPs.
2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system 0 3.3/4.0 8
2.7/4.1 AA2.07 - Ability to determine and 2.4/2.7*
10 interpret the following as they apply to the High Reactor Coolant Activity: \\l/heH demiHeralizer feSiH Heeds te ae feplaeed.
Does NOT distinguish between a competent and incompetent SRO.
AA2.02 - Corrective Actions required 2.8/3.4 for high fission product activity in RCS Group Point Total:
4
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outli '......__
Tier 2/Grou Form ES-401-2 Plant ",,,,..TP1rTlS System # 1Name K
K K
K K
K A
KIA Topic(s) 1 2
3 4
5 6
1 003 Reactor Coolant Pump 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of 004 Chemical and Volume Control A2.15 - Ability to (a) predict the impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 2.4.4 - Ability to recognize 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cool 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater IR 4.3/4.4 11 3.5/3.7 12 4.5/4.7 13 4,2I4..,G 14 Does not adequately test SRO knowledge or ability for this system.
2.4.9 - Knowledge oflow 3.8/4.2 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating 2.4.50 Ability to "Iel'ify system alal'm setpeints and epeFate eentFels identified in the alaFm FespeRse manual.
ES-401 ES-401 ES-401 System # 1 Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cool 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater K
K K
1 2
3 5
Form ES-401-2 PWR Examination Outli '...... __
Form ES-401-2 Plant ",,,,.. TP1rTlS - Tier 2/Grou K
K K
A 4
5 6
1 ES-401 KIA Topic(s) 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of A2.15 - Ability to (a) predict the impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating 2.4.50 Ability to "Iel'ify system alal'm setpeints and epeFate eentFels identified in the alaFm FespeRse manual.
Does not adequately test SRO knowledge or ability for this system.
IR 4.3/4.4 11 3.5/3.7 12 4.5/4.7 13 4,2I4..,G 14 2.4.9 - Knowledge oflow 3.8/4.2 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
ES*401 6
Form ES*401*2 ES-401 System # / Name 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Moni 076 Service Water 078 Instrument Air 103 Containment KIA VCH,.,YVI Point Totals:
PWR Examination Outl Plant Systems - Tier 2/Gro KKK KKK A 1 234 561 Form ES-401-2 KIA Topic(s)
IR 2.2.12 - Knowledge of surveillance 3.7/4.1 15 procedures.
5 ES-401 ES*401 ES-401 System # / Name 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Moni 076 Service Water 078 Instrument Air 103 Containment KIA VCH,.,YVI Point Totals:
6 PWR Examination Outl Plant Systems - Tier 2/Gro KKK KKK A 1 234 561 ES-401 Form ES*401*2 Form ES-401-2 KIA Topic(s)
IR 2.2.12 - Knowledge of surveillance 3.7/4.1 15 procedures.
5
. ES-401 7
Form ES-401-2 ES-401 System # / Name 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control
. 014 Rod Position Indication I 015 Nuclear Instn.. mentation I 016 Non-nuclear
- Instrumentation I 017 In-core Temperature Monitor 028 Hydrogen ReGombiner I and Purge Control 029 Containment Purge I 033 Spent Fuel Pool Cooling
. 034 Fuel Handli 041 Steam Dump/Turbine I"'IVI:JFI!"S Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Ci Water 079 Station Air K K 1
2 K K 3
4 Form ES-40 1-2 KIA Toplc(s) 2.1.32 - Ability to explain and apply all system limits and precautions.
IR 3.8/4.0 16 2.2.36 Ability to IIRIII~e the
~
17 effeet of mlliRteftllftee lIeth'ities, sueh liS degnoed poweF saUFees, aft the status of limitiftg eoftditiaRs feF apentiofts.
NO Technical Specifications exist for the Main Turbine Generator; therefore, NO Limiting Conditions for Operation exist.
2.4.47 - Ability to diagnose and 4.2/4.2 recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
. ES-401 ES-401 System # / Name 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control
. 014 Rod Position Indication I 015 Nuclear Instn.. mentation I 016 Non-nuclear
- Instrumentation I 017 In-core Temperature Monitor 028 Hydrogen ReGombiner I and Purge Control 029 Containment Purge I 033 Spent Fuel Pool Cooling
. 034 Fuel Handli 041 Steam Dump/Turbine I"'IVI:JFI!"S Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Ci Water 079 Station Air K K 1
2 K K 3
4 7
PWR Examination Outline 2 (
ES-401 Form ES-401-2 Form ES-40 1-2 KIA Topic(s) 2.1.32 - Ability to explain and apply all system limits and precautions.
IR 3.8/4.0 16 2.2.36 Ability to IIRIII~e the
~
17 effed of mlliRteftllftee lIetivities, sueD liS degnded poweF saUFees, aft the status of limitiftg eoftditiaRs feF apentiofts.
NO Technical Specifications exist for the Main Turbine Generator; therefore, NO Limiting Conditions for Operation exist.
2.4.47 - Ability to diagnose and 4.2/4.2 recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
ES-401 8
Form ES-401-2 ES-401 System # 1Name 086 Fire Protection K K 1
2 PWR Examination Outline Plant
- Tier 2/Group 2 (
K K 3
4 K
5 K
6 Form ES-401-2 KIA Topic(s)
IR A2.03 - Ability to (a) predict 2.7/2.9 18 the impacts of the following mal-functions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Inadvertent actuation ofthe FPS due to circuit failure or """"U1l1'"
ES-401 ES-401 ES-401 System # 1 Name 086 Fire Protection K K 1
2 8
PWR Examination Outline Plant
- Tier 2/Group 2 (
K K 3
4 K
5 K
6 ES-401 Form ES-401-2 Form ES-401-2 KIA Topic(s)
IR A2.03 - Ability to (a) predict 2.7/2.9 18 the impacts of the following mal-functions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Inadvertent actuation of the FPS due to circuit failure or """"U1l1'"
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401*3 Date of Exam: 12/18/09 KJA#
Topic RO SRO Category Knowledge of faeility reE)uirements far controlling 2.1.13
'lital/cantrolled aecess.
Rejected by NRC on previous exam. Only General Employee or item.
- 1.
Ability to use procedures to determine the effects on reactivity Conduct of 2.1.43 of plant changes, such as reactor coolant system temperature,
- Operations etc.
Knowledge of the fuel-handling responsibilities of SROs.
2.1.35 Subtotal Knowledge of the process for managing maintenance activities 2.2.17 during power operations, such as risk assessments, work prioritization, and coordination with the transmission system
- 2.
Equipment Control Knowledge of conditions and limitations in the facility license.
2.2.38 Subtotal Ability to approve release permits.
2.3.6
- 3.
Knowledge of radiation or contamination hazards that may 2.3.14 Radiation arise during normal, abnormal, or emergency conditions or Control activities.
Subtotal Ability to prioritize and interpret the significance of each 2.4.45
- 4.
annunciator or alarm.
Emergency Procedures and Plan Subtotal Tier 3 Point Total fuel ES-401 ES-401 Category
- 1.
Conduct of
- Operations
- 2.
Equipment Control
- 3.
Radiation Control
- 4.
Emergency Procedures and Plan KJA#
2.1.13 2.1.43 2.1.35 Subtotal 2.2.17 2.2.38 Subtotal 2.3.6 2.3.14 Subtotal 2.4.45 Subtotal Tier 3 Point Total Generic Knowledge and Abilities Outline (Tier 3)
Date of Exam: 12/18/09 Topic Knowledge of faeility reE)uirements for controlling
'lital/cantrolled aecess.
Rejected by NRC on previous exam. Only General Employee or item.
Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, fuel etc.
Knowledge of the fuel-handling responsibilities of SROs.
Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system Knowledge of conditions and limitations in the facility license.
Ability to approve release permits.
Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
Ability to prioritize and interpret the significance of each annunciator or alarm.
ES-401 Record of Rejected KJAs Form ES-401-4 Tier /
Group Randomly Selected KJA Reason for Rejection 1/1 009 - 2.1.31 Does NOT adequately test SRO knowledge or ability. Unable to develoE a reasonable SRO guestion to test this KIA.
1/1 011 - EA2.06 Does NOT adequately test SRO knowledge or ability. Determining that CAR Fans shift to slow is a basic RO function and there are NO dampers that shift during a LOCA.
1/2 076 - AA2.07 Does NOT distinguish between a competent and incompetent SRO.
2/1 026 - 2.4.50 Does NOT adequately test SRO knowledge or ability for this system.
This system only has one alarm and the response is very basic.
2/2 045 - 2.2.36 No Technical Specifications exist for the Main Turbine Generator; therefore, no Limiting Conditions for Operation exist.
3/0 2.1.13 Rejected by NRC on previous exam. Only General Employee or Security knowledge item.
ES-401, Page 27 of 33 ES-401 Record of Rejected KJAs Form ES-401-4 Tier /
Randomly Reason for Rejection Group Selected KJ A 1/1 009 - 2.1.31 Does NOT adequately test SRO knowledge or ability. Unable to develoE a reasonable SRO guestion to test this KIA.
1/1 011 - EA2.06 Does NOT adequately test SRO knowledge or ability. Determining that CAR Fans shift to slow is a basic RO function and there are NO dampers that shift during a LOCA.
1/2 076 - AA2.07 Does NOT distinguish between a competent and incompetent SRO.
2/1 026 - 2.4.50 Does NOT adequately test SRO knowledge or ability for this system.
This system only has one alarm and the response is very basic.
2/2 045 - 2.2.36 No Technical Specifications exist for the Main Turbine Generator; therefore, no Limiting Conditions for Operation exist.
3/0 2.1.13 Rejected by NRC on previous exam. Only General Employee or Security knowledge item.
ES-401, Page 27 of 33