ML082830421
| ML082830421 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/27/2008 |
| From: | Ryan Lantz Operations Branch IV |
| To: | Keenan J Pacific Gas & Electric Co |
| References | |
| 50-275/08-301, 50-323/08-301, ES-401, ES-401-2 50-275/08-301, 50-323/08-301 | |
| Download: ML082830421 (17) | |
Text
03/05/2008 Printed:
ES-401 Facility:
DCPP PWR Examination Outline Form ES-401-2 3
3 3
3 3
3 2
2 1
2 2
0 5
5 4
5 5
3 3
2 3
3 3
2 3
3 2
3 1
1 1
1 1
1 1
1 1
1 0
1 4
3 4
4 4
3 4
4 3
3 2
2 3
2 3
RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*
- 1.
Emergency Abnormal Plant Evolutions 1
1 2
2 Tier Totals Tier Totals
- 2.
Plant Systems 1
2 3
4
- 3. Generic Knowledge And Abilities Categories
- 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.
- 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.
- 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 not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 5.
Absent a plant-specific priority, only those K/As 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.
Note:
Date Of Exam:
06/13/2008 28 18 9
27 10 38 10
- 1.
Ensure that at least two topics from every applicable K/A 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 K/A category shall not be less than two).
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A 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-only exams.
SRO-Only Points A2 G*
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1
2 3
4 0
0 0
0 0
0 0
- 9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
Limit SRO selections to K/As that are linked to 10 CFR 55.43.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
N/A N/A Total 0
0 1
02/04/2008 12:53:13 pm
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK3.01 - Actions contained in EOP for reactor trip 4.0 1
X 000007 Reactor Trip - Stabilization - Recovery
/ 1 AK1.01 - Thermodynamics and flow characteristics of open or leaking valves 3.2 1
X 000008 Pressurizer Vapor Space Accident / 3 EK2.03 - S/Gs 3.0 1
X 000009 Small Break LOCA / 3 EA2.13 - Difference between overcooling and LOCA indications 3.7*
1 X
000011 Large Break LOCA / 3 AK2.10 - RCP indicators and controls 2.8*
1 X
000015/000017 RCP Malfunctions / 4 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.
4.2 1
X 000022 Loss of Rx Coolant Makeup / 2 AA1.11 - Reactor building sump level indicators 2.9 1
X 000025 Loss of RHR System / 4 AA2.04 - The normal values and upper limits for the temperatures of the components cooled by CCW 2.5 1
X 000026 Loss of Component Cooling Water / 8 AA2.04 - Tech-Spec limits for RCS pressure 3.7 1
X 000027 Pressurizer Pressure Control System Malfunction / 3 EK3.04 - Automatic actions provided by each PRM 3.9 1
X 000038 Steam Gen. Tube Rupture / 3 AK3.01 - Reactor and/or turbine trip, manual and automatic 4.1 1
X 000054 Loss of Main Feedwater / 4 EA1.06 - Restoration of power with one ED/G 4.1 1
X 000055 Station Blackout / 6 2.2.37 - Ability to determine operability and/or availability of safety related equipment.
3.6 1
X 000058 Loss of DC Power / 6 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
4.3 1
X 000065 Loss of Instrument Air / 8 EA1.3 - Desired operating results during abnormal and emergency situations 3.8 1
X W/E04 LOCA Outside Containment / 3 EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.7 1
X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 EK1.2 - Normal, abnormal and emergency operating procedures associated with Loss of Emergency Coolant Recirculation 3.6 1
X W/E11 Loss of Emergency Coolant Recirc. / 4 1
02/04/2008 12:52:37 pm
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the Uncontrolled Depressurization of all Steam Generators 3.4 1
X W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 18 3
3 3
3 3
3 K/A Category Totals:
Group Point Total:
2 02/04/2008
12:52:37 pm 02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AK2.05 - Control rod drive power supplies and logic circuits 2.5 1
X 000003 Dropped Control Rod / 1 AK2.03 - Controllers and positioners 2.6 1
X 000024 Emergency Boration / 1 AA1.05 - Initiation of excess letdown per the CVCS 2.8 1
X 000028 Pressurizer Level Malfunction / 2 AA2.01 - ARM system indications 3.2 1
X 000036 Fuel Handling Accident / 8 AA2.02 - Conditions requiring reactor and/or turbine trip 3.9 1
X 000051 Loss of Condenser Vacuum / 4 AA1.01 - Automatic actuation 3.6 1
X 000061 ARM System Alarms / 7 EK1.1 - Components, capacity, and function of emergency systems 3.2 1
X W/E02 SI Termination / 3 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the Natural Circulation Operations 3.3 1
X W/E09 Natural Circ. / 4 EK3.2 - Normal, abnormal and emergency operating procedures associated with High Containment Radiation 2.9 1
X W/E16 High Containment Radiation / 9 9
2 2
1 2
2 0
K/A Category Totals:
Group Point Total:
1 02/04/2008
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 2.1.27 - Knowledge of system purpose and/or function.
3.9 1
X 003 Reactor Coolant Pump K5.03 - Effects of RCP shutdown on T-ave.,
including the reason for the unreliability of T-ave. in the shutdown loop 3.1 1
X 003 Reactor Coolant Pump K6.04 - Pumps 2.8 1
X 004 Chemical and Volume Control K4.05 - Relation between RHR flowpath and refueling cavity 2.5 1
X 005 Residual Heat Removal A4.01 - Controls and indication for RHR pumps 3.6*
1 X
005 Residual Heat Removal K5.06 - Relationship between ECCS flow and RCS pressure 3.5 1
X 006 Emergency Core Cooling K4.16 - Interlocks between RHR valves and RCS 3.2 1
X 006 Emergency Core Cooling A1.02 - Maintaining quench tank pressure 2.7 1
X 007 Pressurizer Relief/Quench Tank K3.01 - Loads cooled by CCWS 3.4 1
X 008 Component Cooling Water K2.01 - PZR heaters 3.0 1
X 010 Pressurizer Pressure Control K1.08 - MFW 2.9*
1 X
012 Reactor Protection K2.01 - ESFAS/safeguards equipment control 3.6*
1 X
013 Engineered Safety Features Actuation K5.02 - Safety system logic and reliability 2.9 1
X 013 Engineered Safety Features Actuation K4.04 - Cooling of control rod drive motors 2.8 1
X 022 Containment Cooling A1.02 - Containment pressure 3.6 1
X 022 Containment Cooling K1.01 - ECCS 4.2 1
X 026 Containment Spray K1.05 - T/G 2.5*
1 X
039 Main and Reheat Steam A4.12 - Initiation of automatic feedwater isolation 3.4 1
X 059 Main Feedwater K3.02 - S/G 4.2 1
X 061 Auxiliary/Emergency Feedwater A2.04 - pump failure or improper operation 3.4 1
X 061 Auxiliary/Emergency Feedwater A3.04 - Operation of inverter (e.g., precharging synchronizing light, static transfer) 2.7 1
X 062 AC Electrical Distribution A2.01 - Grounds 2.5 1
X 063 DC Electrical Distribution 1
02/04/2008 12:52:53 pm
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.05 - Loading the ED/G 3.1 1
X 064 Emergency Diesel Generator K6.07 - Air receivers 2.7 1
X 064 Emergency Diesel Generator A1.01 - Radiation levels 3.2 1
X 073 Process Radiation Monitoring K3.07 - ESF loads 3.7 1
X 076 Service Water A4.01 - Pressure gauges 3.1 1
X 078 Instrument Air A3.01 - Containment isolation 3.9 1
X 103 Containment 28 3
2 3
3 3
1 K/A Category Totals:
3 3
2 2
3 Group Point Total:
2 02/04/2008 12:52:53 pm
12:52:45m 02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 K3.03 - Containment 4.2 1
X 002 Reactor Coolant 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 1
X 011 Pressurizer Level Control K1.01 - CRDS 3.2*
1 X
014 Rod Position Indication K5.01 - Temperature at which cladding and fuel melt 3.1 1
X 017 In-core Temperature Monitor K2.01 - Fans 3.1*
1 X
027 Containment Iodine Removal K6.01 - Hydrogen recombiners 2.6 1
X 028 Hydrogen Recombiner and Purge Control K4.01 - Maintenance of spent fuel level 2.9 1
X 033 Spent Fuel Pool Cooling A1.01 - S/G wide and narrow range level during startup, shutdown, and normal operations 3.6 1
X 035 Steam Generator A3.04 - T/G trip 3.4 1
X 045 Main Turbine Generator A2.01 - Cross-connection with IAS 2.9 1
X 079 Station Air 10 1
1 1
1 1
1 K/A Category Totals:
1 1
1 1
0 Group Point Total:
1 02/04/2008
12:53:00 pm Facility:
DCPP Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 02/04/2008 Printed:
PWR RO Examination Outline 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.
4.1 1
Conduct of Operations 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
4.3 1
2 Category Total:
2.2.12 Knowledge of surveillance procedures.
3.7 1
Equipment Control 2.2.14 Knowledge of the process for controlling equipment configuration or status.
3.9 1
2.2.43 Knowledge of the process used to track inoperable alarms.
3.2 1
3 Category Total:
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 1
Radiation Control 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.4 1
2 Category Total:
2.4.14 Knowledge of general guidelines for EOP usage.
3.8 1
Emergency Procedures/Plan 2.4.25 Knowledge of fire protection procedures.
3.3 1
2.4.37 Knowledge of the lines of authority during implementation of the emergency plan.
3.0 1
3 Category Total:
10 Generic Total:
1 02/04/2008 12:53:07 pm
03/05/2008 Printed:
ES-401 Facility:
DCPP PWR Examination Outline Form ES-401-2 3
3 3
3 3
3 2
2 1
2 2
0 5
5 4
5 5
3 3
2 3
3 3
2 3
3 2
3 1
1 1
1 1
1 1
1 1
1 0
1 4
3 4
4 4
3 4
4 3
3 2
2 3
2 3
RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*
- 1.
Emergency Abnormal Plant Evolutions 1
1 2
2 Tier Totals Tier Totals
- 2.
Plant Systems 1
2 3
4
- 3. Generic Knowledge And Abilities Categories
- 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.
- 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.
- 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 not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 5.
Absent a plant-specific priority, only those K/As 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.
Note:
Date Of Exam:
06/13/2008 28 18 9
27 10 38 10
- 1.
Ensure that at least two topics from every applicable K/A 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 K/A category shall not be less than two).
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A 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-only exams.
SRO-Only Points A2 G*
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1
2 3
4 0
0 0
0 0
0 0
- 9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
Limit SRO selections to K/As that are linked to 10 CFR 55.43.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
N/A N/A Total 0
0 1
02/04/2008 12:53:13 pm
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK3.01 - Actions contained in EOP for reactor trip 4.0 1
X 000007 Reactor Trip - Stabilization - Recovery
/ 1 AK1.01 - Thermodynamics and flow characteristics of open or leaking valves 3.2 1
X 000008 Pressurizer Vapor Space Accident / 3 EK2.03 - S/Gs 3.0 1
X 000009 Small Break LOCA / 3 EA2.13 - Difference between overcooling and LOCA indications 3.7*
1 X
000011 Large Break LOCA / 3 AK2.10 - RCP indicators and controls 2.8*
1 X
000015/000017 RCP Malfunctions / 4 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.
4.2 1
X 000022 Loss of Rx Coolant Makeup / 2 AA1.11 - Reactor building sump level indicators 2.9 1
X 000025 Loss of RHR System / 4 AA2.04 - The normal values and upper limits for the temperatures of the components cooled by CCW 2.5 1
X 000026 Loss of Component Cooling Water / 8 AA2.04 - Tech-Spec limits for RCS pressure 3.7 1
X 000027 Pressurizer Pressure Control System Malfunction / 3 EK3.04 - Automatic actions provided by each PRM 3.9 1
X 000038 Steam Gen. Tube Rupture / 3 AK3.01 - Reactor and/or turbine trip, manual and automatic 4.1 1
X 000054 Loss of Main Feedwater / 4 EA1.06 - Restoration of power with one ED/G 4.1 1
X 000055 Station Blackout / 6 2.2.37 - Ability to determine operability and/or availability of safety related equipment.
3.6 1
X 000058 Loss of DC Power / 6 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
4.3 1
X 000065 Loss of Instrument Air / 8 EA1.3 - Desired operating results during abnormal and emergency situations 3.8 1
X W/E04 LOCA Outside Containment / 3 EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.7 1
X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 EK1.2 - Normal, abnormal and emergency operating procedures associated with Loss of Emergency Coolant Recirculation 3.6 1
X W/E11 Loss of Emergency Coolant Recirc. / 4 1
02/04/2008 12:52:37 pm
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the Uncontrolled Depressurization of all Steam Generators 3.4 1
X W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 18 3
3 3
3 3
3 K/A Category Totals:
Group Point Total:
2 02/04/2008
12:52:37 pm 02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AK2.05 - Control rod drive power supplies and logic circuits 2.5 1
X 000003 Dropped Control Rod / 1 AK2.03 - Controllers and positioners 2.6 1
X 000024 Emergency Boration / 1 AA1.05 - Initiation of excess letdown per the CVCS 2.8 1
X 000028 Pressurizer Level Malfunction / 2 AA2.01 - ARM system indications 3.2 1
X 000036 Fuel Handling Accident / 8 AA2.02 - Conditions requiring reactor and/or turbine trip 3.9 1
X 000051 Loss of Condenser Vacuum / 4 AA1.01 - Automatic actuation 3.6 1
X 000061 ARM System Alarms / 7 EK1.1 - Components, capacity, and function of emergency systems 3.2 1
X W/E02 SI Termination / 3 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the Natural Circulation Operations 3.3 1
X W/E09 Natural Circ. / 4 EK3.2 - Normal, abnormal and emergency operating procedures associated with High Containment Radiation 2.9 1
X W/E16 High Containment Radiation / 9 9
2 2
1 2
2 0
K/A Category Totals:
Group Point Total:
1 02/04/2008
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 2.1.27 - Knowledge of system purpose and/or function.
3.9 1
X 003 Reactor Coolant Pump K5.03 - Effects of RCP shutdown on T-ave.,
including the reason for the unreliability of T-ave. in the shutdown loop 3.1 1
X 003 Reactor Coolant Pump K6.04 - Pumps 2.8 1
X 004 Chemical and Volume Control K4.05 - Relation between RHR flowpath and refueling cavity 2.5 1
X 005 Residual Heat Removal A4.01 - Controls and indication for RHR pumps 3.6*
1 X
005 Residual Heat Removal K5.06 - Relationship between ECCS flow and RCS pressure 3.5 1
X 006 Emergency Core Cooling K4.16 - Interlocks between RHR valves and RCS 3.2 1
X 006 Emergency Core Cooling A1.02 - Maintaining quench tank pressure 2.7 1
X 007 Pressurizer Relief/Quench Tank K3.01 - Loads cooled by CCWS 3.4 1
X 008 Component Cooling Water K2.01 - PZR heaters 3.0 1
X 010 Pressurizer Pressure Control K1.08 - MFW 2.9*
1 X
012 Reactor Protection K2.01 - ESFAS/safeguards equipment control 3.6*
1 X
013 Engineered Safety Features Actuation K5.02 - Safety system logic and reliability 2.9 1
X 013 Engineered Safety Features Actuation K4.04 - Cooling of control rod drive motors 2.8 1
X 022 Containment Cooling A1.02 - Containment pressure 3.6 1
X 022 Containment Cooling K1.01 - ECCS 4.2 1
X 026 Containment Spray K1.05 - T/G 2.5*
1 X
039 Main and Reheat Steam A4.12 - Initiation of automatic feedwater isolation 3.4 1
X 059 Main Feedwater K3.02 - S/G 4.2 1
X 061 Auxiliary/Emergency Feedwater A2.04 - pump failure or improper operation 3.4 1
X 061 Auxiliary/Emergency Feedwater A3.04 - Operation of inverter (e.g., precharging synchronizing light, static transfer) 2.7 1
X 062 AC Electrical Distribution A2.01 - Grounds 2.5 1
X 063 DC Electrical Distribution 1
02/04/2008 12:52:53 pm
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.05 - Loading the ED/G 3.1 1
X 064 Emergency Diesel Generator K6.07 - Air receivers 2.7 1
X 064 Emergency Diesel Generator A1.01 - Radiation levels 3.2 1
X 073 Process Radiation Monitoring K3.07 - ESF loads 3.7 1
X 076 Service Water A4.01 - Pressure gauges 3.1 1
X 078 Instrument Air A3.01 - Containment isolation 3.9 1
X 103 Containment 28 3
2 3
3 3
1 K/A Category Totals:
3 3
2 2
3 Group Point Total:
2 02/04/2008 12:52:53 pm
12:52:45m 02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 K3.03 - Containment 4.2 1
X 002 Reactor Coolant 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 1
X 011 Pressurizer Level Control K1.01 - CRDS 3.2*
1 X
014 Rod Position Indication K5.01 - Temperature at which cladding and fuel melt 3.1 1
X 017 In-core Temperature Monitor K2.01 - Fans 3.1*
1 X
027 Containment Iodine Removal K6.01 - Hydrogen recombiners 2.6 1
X 028 Hydrogen Recombiner and Purge Control K4.01 - Maintenance of spent fuel level 2.9 1
X 033 Spent Fuel Pool Cooling A1.01 - S/G wide and narrow range level during startup, shutdown, and normal operations 3.6 1
X 035 Steam Generator A3.04 - T/G trip 3.4 1
X 045 Main Turbine Generator A2.01 - Cross-connection with IAS 2.9 1
X 079 Station Air 10 1
1 1
1 1
1 K/A Category Totals:
1 1
1 1
0 Group Point Total:
1 02/04/2008
12:53:00 pm Facility:
DCPP Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 02/04/2008 Printed:
PWR RO Examination Outline 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.
4.1 1
Conduct of Operations 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
4.3 1
2 Category Total:
2.2.12 Knowledge of surveillance procedures.
3.7 1
Equipment Control 2.2.14 Knowledge of the process for controlling equipment configuration or status.
3.9 1
2.2.43 Knowledge of the process used to track inoperable alarms.
3.2 1
3 Category Total:
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 1
Radiation Control 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.4 1
2 Category Total:
2.4.14 Knowledge of general guidelines for EOP usage.
3.8 1
Emergency Procedures/Plan 2.4.25 Knowledge of fire protection procedures.
3.3 1
2.4.37 Knowledge of the lines of authority during implementation of the emergency plan.
3.0 1
3 Category Total:
10 Generic Total:
1 02/04/2008 12:53:07 pm
02/04/2008 Printed:
ES-401 Facility:
DCPP PWR Examination Outline Form ES-401-2 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*
- 1.
Emergency Abnormal Plant Evolutions 1
1 2
2 Tier Totals Tier Totals
- 2.
Plant Systems 1
2 3
4
- 3. Generic Knowledge And Abilities Categories
- 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.
- 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.
- 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 not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 5.
Absent a plant-specific priority, only those K/As 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.
Note:
Date Of Exam:
06/13/2008 0
0 0
0 0
0 0
- 1.
Ensure that at least two topics from every applicable K/A 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 K/A category shall not be less than two).
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A 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-only exams.
SRO-Only Points A2 G*
3 3
2 2
5 5
3 2
2 1
3 2
2 1
2 1
2 3
4 10 4
6 5
3 8
7
- 9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
Limit SRO selections to K/As that are linked to 10 CFR 55.43.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
N/A N/A Total 0
5 1
02/04/2008
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 EA2.14 - Actions to be taken if PTS limits are violated 4.4 1
X 000009 Small Break LOCA / 3 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.7 1
X 000011 Large Break LOCA / 3 2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
4.2 1
X 000026 Loss of Component Cooling Water / 8 AA2.03 - DC loads lost; impact on to operate and monitor plant systems 3.9 1
X 000058 Loss of DC Power / 6 AA2.05 - When to commence plant shutdown if instrument air pressure is decreasing 4.1 1
X 000065 Loss of Instrument Air / 8 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
4.7 1
X W/E11 Loss of Emergency Coolant Recirc. / 4 6
0 0
0 0
3 3
K/A Category Totals:
Group Point Total:
1 02/04/2008 4:19:56 pm
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 AA2.04 - Satisfactory overlap between source-range, intermediate-range and power-range instrumentation 3.6 1
X 000033 Loss of Intermediate Range NI / 7 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
4.4 1
X 000036 Fuel Handling Accident / 8 AA2.05 - Past history of leakage with current problem 3.3 1
X 000037 Steam Generator Tube Leak / 3 2.2.44 - 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.
4.4 1
X W/E02 SI Termination / 3 4
0 0
0 0
2 2
K/A Category Totals:
Group Point Total:
1 02/04/2008 4:20:02 pm
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.18 - High VCT level 3.1 1
X 004 Chemical and Volume Control 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.7 1
X 005 Residual Heat Removal 2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
4.5 1
X 062 AC Electrical Distribution A2.02 - Loss of ventilation during battery charging 3.1 1
X 063 DC Electrical Distribution A2.05 - Emergency containment entry 3.9 1
X 103 Containment 5
0 0
0 0
3 2
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1 02/04/2008 4:20:08 pm
02/04/2008 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A2.02 - Loss of coolant pressure 4.4 1
X 002 Reactor Coolant 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.
4.3 1
X 011 Pressurizer Level Control A2.04 - Loss of condensate pumps 2.8*
1 X
056 Condensate 3
0 0
0 0
2 1
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1 02/04/2008 4:20:14 pm
Facility:
DCPP Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 02/04/2008 Printed:
PWR SRO Examination Outline 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
4.6 1
Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements.
3.9 1
2 Category Total:
2.2.6 Knowledge of the process for making changes to procedures.
3.6 1
Equipment Control 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
4.2 1
2 Category Total:
2.3.6 Ability to approve release permits.
3.8 1
Radiation Control 1
Category Total:
2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
4.4 1
Emergency Procedures/Plan 2.4.32 Knowledge of operator response to loss of all annunciators.
4.0 1
2 Category Total:
7 Generic Total:
1 02/04/2008 4:20:20 pm 4:20:25 pm
ES-401 Record of Rejected K/As DCPP June 2008 Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 54/AK.03 No specific procedure step to deal with manual control of AFW valves on Loss of Main Feedwater, additionally AFW is over sampled. (RO) 1/1 77/AK2.01 No specific procedure to deal with Generator Voltage and Electric Grid Disturbances and the effect on plant motors.
(RO) 1/2 67/AK3.04 No EOP/AOP procedural guidance used by reactor operators to respond plant fire on site, will examine similar knowledge under G.2.4.25. (RO) 2/2 34/A3.03 No automatic actions for High Flux at shutdown at DCPP.
(RO) 1/2 03/2.1.37 Generic item that is not on list of items to be included in ES-401 section D.1.b for Tiers 1 & 2. (SRO) 2/1 22/A2.06 Not applicable for DCPP, no CCS pumps. (SRO) 3 G2.2.25 Same K/A was selected for SRO exam, Item is more appropriate for SROs. (RO)
ES-401 Record of Rejected K/As DCPP June 2008 Form ES-401-4 Description of program used to generate DCPP June 2008 Written Exam K/As Generated the RO and SRO sample plan using the NKEG Database program, version 1.1., developed by Westinghouse Electric Company. This program will automatically produce a Random Sample Plan based on NUREG 1122, Rev. 2, Supplement 1, K/As.
K/As were suppressed prior to the outline generation process as provided for in the examiner standard, the list of suppressed K/As is provided as required by the examiner standard.
Inappropriate and inapplicable K/As were discarded during the outline development process and are included in the record of rejected K/As. The replacement K/As were replaced using the random sample function of the NKEG database program to ensure they were randomly selected.
During development of the test questions, it was determined that one generic K/A was not appropriate for an RO exam, the same K/A was also selected for the SRO exam. The K/A was deleted and another generic K/A from the same area (Equipment Control) was randomly selected by placing into a cup, numbers that corresponded to the K/As in the Equipment Control Area. A number was then drawn out of the cup and that was used for the replacement K/A.