ML18240A427
| ML18240A427 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/28/2018 |
| From: | Southern Nuclear Company |
| To: | NRC/RGN-II |
| References | |
| Download: ML18240A427 (15) | |
Text
ES-401N, Rev. 10 PWR Examination Outline Form ES-401N-2 Facility:
Date of Exam:
Tier Group RO K/A Category Points SRO-Only Points K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total
- 1.
Emergency &
Abnormal Plant Evolutions 1
N/A N/A 18 6
2 9
4 Tier Totals 27 10
- 2.
Plant Systems 1
28 5
2 10 3
Tier Totals 38 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
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, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).
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 section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 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.
6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
- 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 KAs.
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.
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.
3 3
3 2
3 3
2 1
2 1
2 1
5 4
5 3
5 4
3 3
2 2
3 3
3 2
2 3
2 1
1 1
1 1
1 1
0 1
1 1
4 4
3 3
4 4
4 2
3 4
3 2
3 2
1 3
2 2
2 3
3 6
2 2
5 5
10 2
3 1
2 5
18 27 38 9
28 10 4
3 5
8 Vogtle February 2017
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 Rapid Power Reduction Reactor Coolant System boron addition volume and rate A-301AA2.02 3
3.1 Uncontrolled Cooldown SG PORVs A-313AA1.03 3.5 Loss of 6.9KV, 4160 Volt, or 480 Volt Bus Power Main Control Room Emergency Habitability System A-323AK1.08 3.2 Malfunction of Protection and Safety Monitoring System Ability to use integrated control systems to operate plant systems or components.
A-336AG2.1.14 4
3.3 Passive Residual Heat Removal Heat Exchanger Leak Trending Passive Residual Heat Removal System inlet temperatures and pressures A-337AK3.06 2.7 Reactor Coolant Pump Malfunctions Ability to prioritize and interpret the significance of each annunciator or alarm.
A-342AG2.4.36 4.1 4.3 Loss of Normal Residual Heat Removal Transferring Reactor Coolant System heat load to the Passive Residual Heat Removal System heat exchanger A-343AK2.02 3.5 Loss of Reactor or Secondary Coolant Automatic Depressurization System E-1EK1.01 4.3 Faulted Steam Generator Isolation Checking Passive Residual Heat Removal System is available prior to isolating the startup feedwater lines to the faulted steam generators E-2EK3.04 3.4 Loss of Coolant Accident Outside Containment Diverse Actuation System ECA-1.1EA1.02 3.6 Reactor Trip Response Inability to stabilize Reactor Coolant System at no load Tcold temperature ES-0.1EK2.10 3.3 Page 1 of 2 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 Passive Safety System Termination Pressurizer Pressure Control System ES-1.1EK1.12 2.8 ADS Stage 1-3 Actuation Response ADS Stage 4 ES-1.3EA1.14 3.6 0
ADS Stage 4 Actuation Response ADS Stage 4 proper alignment ES-1.4EA2.01 3.6 3.8 Response to Inadequate Core Cooling Knowledge of Emergency/Abnormal Operating Procedure entry conditions.
FR-C.1EG2.4.1 4.6 4.8 Response to Loss of Heat Sink Automatic Depressurization System Actuation FR-H.1EK3.14 4.4 Response to Nuclear Power Generation - ATWS Failure to recognize the need and failure to manually trip the reactor through the Protection and Safety Monitoring System, given anticipated transient without scram (PRA related)
FR-S.1EK2.03 4.1 Response to Loss of RCS Inventory During Shutdown Core exit temperature SDP-1EA2.03 3.6 3.6 Page 2 of 2 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T1G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 Steam Generator Tube Leak Using Passive Residual Heat Removal System for Reactor Coolant System cooldown A-304AK2.08 3.2 Rod Control System Malfunctions Checking On-line Power Distribution Monitoring System is operable A-311AK3.02 3.3 Loss of Circulating Water Circulating Water trash screens A-320AK1.09 2.6 Startup Feedwater System Malfunctions Steam generator level A-327AA2.01 2.8 3.5 Malfunction of Feedwater Heaters and Extraction Steam Main and Startup Feedwater System A-328AK1.03 2.6 Main Turbine Malfunctions Main turbine load and trip controls A-333AA1.01 3.4 Response to High Containment Pressure Main Steam Isolation Actuation FR-Z.1EK3.06 3.4 Response to Containment Flooding Knowledge of operator response to a loss of all annunciators.
FR-Z.2EG2.4.25 3.6 4
Low Containment Pressure Containment pressure FR-Z.4EA2.01 2.8 3
Page 1 of 1 7:41 AM 01/11/2016
NAME / SAFETY FUNCTION K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 Automatic Depressurization System Reactor Cooling System pressure ADSA4.04 4.1 Automatic Depressurization System Diverse Actuation System ADSK6.01 4.2 Compressed Air System Instrument air compressor package parameters CASA1.01 2.6 Component Cooling Water System Normal Reactor Coolant System cooldown CCSK4.02 3
Containment System Steam Generator System CNSK1.20 3.3 Containment System Containment integrity CNSK3.01 4
Chemical and Volume Control System Containment isolation valves CVSK2.04 3.7 Diverse Actuation System Containment isolation DASA2.05 3.4 3.3 AC Electrical Distribution Systems Knowledge of limiting conditions for operations and safety limits.
ECSG2.2.17 4
4.7 Engineered Safeguards Actuation System P-12, Pressurizer Level ESASK6.23 3.6 Main and Startup Feedwater System Main feedwater control valve FWSA4.05 3.3 Page 1 of 3 7:41 AM 01/11/2016
NAME / SAFETY FUNCTION K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 Class 1E and Non 1E DC and UPS Systems Non class 1E instrument bus inverters (OE-related)
IDSK2.09 2.5 Class 1E and Non 1E DC and UPS Systems System ground detection IDSK4.06 2.6 Main Steam System Steam Line Isolation Actuation MSSA3.05 3.5 Passive Containment Cooling System Loss of coolant accident PCSA2.13 3.8 4.1 Passive Containment Cooling System Heat transfer via radiation PCSK5.03 2.5 Pressurizer Pressure Control System Ability to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.
PPCSG2.4.39 4.2 4
Passive Residual Heat Removal System Passive Residual Heat Removal System heat exchanger temperature PRHRA1.03 3.5 Passive Core Cooling System Normal Residual Heat Removal System PXSK3.02 3.2 Reactor Coolant Pump System Reactor coolant pump start effect on reactivity/boron (OE-related)
RCPK5.04 3.2 Reactor Coolant System Reactor Coolant System Automatic Depressurization System discharge temperature RCSA1.17 3.9 Reactor Coolant System Normal Residual Heat Removal System RCSK1.18 3.6 Page 2 of 3 7:41 AM 01/11/2016
NAME / SAFETY FUNCTION K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 Normal Residual Heat Removal System Post loss of coolant accident containment makeup RNSA4.07 3.5 Normal Residual Heat Removal System Pump flow rate instrument RNSK6.04 2.7 Reactor Trip System Reactor Trip System Instrumentation RTSK2.02 3.6 Steam Generator System Chemistry and corrosion control SGSK5.14 2.6 Service Water System Circulating Water System SWSK1.03 2.7 Onsite Standby Power System Standby Diesel Generator starting and loading ZOSA3.01 3.2 Page 3 of 3 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 Condensate System Feedwater heater automatic isolation and bypass CDSK4.07 2.6 Digital Rod Control System Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
DRCSG2.2.28 3.9 4.6 Fuel Handling System Loss of Containment Air Filtration System FHSK5.06 2.7 3.0 Incore Instrumentation System Special Monitoring System IISK1.07 2.5 Nuclear Instrumentation System P-17, Negative Flux Rate Alert NISA3.03 3.6 Pressurizer Level Control System Code safety tailpipe temperature PLCSA1.08 3.1 Radiation Monitoring System Radiation monitors that provide Engineered Safeguards Actuation System Actuations RMSK2.01 3.1 Containment Air Filtration System Compressed Air System VFSK6.01 2.5 Containment Hydrogen Control System Containment hydrogen igniter VLSA4.02 3.6 Gaseous Radwaste System Plant Gas Systems WGSK3.01 2.6 Page 1 of 1 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401N-3 Radiation Control Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.
G.2.3.9 2.9 3.1 Conduct of operations Ability to use procedures related to shift staffing, such as minimum crew complement, or overtime limitations.
G2.1.5 2.9 3.9 Conduct of operations Ability to coordinate personnel activities outside the control room.
G2.1.8 3.4 4.1 Equipment Control Knowledge of the process for managing troubleshooting activities.
G2.2.15 2.6 3.8 Equipment Control Ability to determine operability or availability of safety related equipment.
G2.2.22 4.6 Equipment Control Knowledge of less than or equal to one hour Technical Specification action statements. (This K/A does not include Action Statements of one hour or less that follow the expiration of a completion time for a Technical Specification condition for which an A G2.2.24 3.9 4.5 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions.
G2.3.4 3.5 3.6 Emergency Procedures/Plans Knowledge of the parameters and logic used to assess the status of Emergency Operating Procedures Critical Safety Functions or Shutdown Critical Safety Functions.
G2.4.16 4
4.6 Emergency Procedures/Plans Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material G2.4.38 4.2 4.2 Emergency Procedures/Plans Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
G2.4.8 3.8 4.2 Page 1 of 1 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 Loss of 6.9KV, 4160 Volt, or 480 Volt Bus Power Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
A-323AG2.2.21 3.1 4.2 Loss of Instrument Air Ability to use integrated control systems to operate plant systems or components.
A-329AG2.1.14 4
3.3 Malfunction of Protection and Safety Monitoring System Diverse Actuation System indications A-336AA2.02 4
3.7 Loss of Reactor or Secondary Coolant Passive Residual Heat Removal System flow E-1EA2.04 3.4 3.4 Response to Inadequate Core Cooling Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
FR-C.1EG2.2.19 0
4.2 Response to Loss of Heat Sink Reactor Coolant System pressure and/or temperature FR-H.1EA2.02 3.8 3.7 Page 1 of 1 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 Loss of Control Room Air Conditioning Nuclear Island Nonradioactive Ventilation System flow A-308AA2.02 2.3 2.8 Condensate System Malfunctions Ability to determine operability or availability of safety related equipment.
A-318AG2.2.22 0
4.6 Post Loss of Coolant Accident Cool Down and Depressurization Containment pressure ES-1.2EA2.07 3.2 3.7 Response to Saturated Core Cooling Knowledge of Emergency/Abnormal Operating Procedures layout, symbols, and icons.
FR-C.3EG2.4.14 3.4 4.1 Page 1 of 1 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 Compressed Air System Loss of instrument air supply pressure CASA2.06 3
2.7 Containment System Normal Residual Heat Removal System containment isolation CNSA2.03 3.7 3.6 Engineered Safeguards Actuation System Ability to identify post-accident instrumentation.
ESASG2.4.3 3.7 3.9 Main and Startup Feedwater System Ability to perform general and/or normal operating procedures during any plant condition.
FWSG2.1.21 4.3 4.4 Reactor Trip System Knowledge of Emergency/Abnormal Operating Procedure entry conditions.
RTSG2.4.1 4.6 4.8 Page 1 of 1 7:41 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 Fire Protection System Ability to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.
FPSG2.4.39 4.2 4
Steam Dump Control System Main steam header pressure SDCSA2.08 2.7 2.9 Main Control Room HVAC Knowledge of annunciator alarms, indications, or response procedures.
VESG2.4.24 4.2 4.1 Page 1 of 1 7:42 AM 01/11/2016
NAME / SAFETY FUNCTIO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
KA RO SRO IR ES-401N, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401N-3 Radiation Control Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.
G.2.3.9 2.9 3.1 Conduct of operations Knowledge of the fuel-handling responsibilities of SROs.
G2.1.30 3
Equipment Control Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, or tag-outs.
G2.2.11 3.9 4.3 Equipment Control Ability to obtain and/or interpret station electrical and mechanical drawings.
G2.2.27 3.5 3.9 Radiation Control Ability to control radiation releases.
G2.3.5 3.8 4.3 Emergency Procedures/Plans Ability to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.
G2.4.39 4.2 4
Emergency Procedures/Plans Knowledge of Emergency/Abnormal Operating Procedures major action categories.
G2.4.6 3.7 4.7 Page 1 of 1 7:42 AM 01/11/2016
Draft ES-301-1, ES-301-2, RO Written Exam, SRO Written Exam, Simulator Scenarios, Simulator JPMs, In-Plant JPMs, and Administrative JPMs are located in Non-Public ADAMS due to being Proprietary information.