ML16280A465
| ML16280A465 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/30/2016 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | |
| References | |
| Download: ML16280A465 (40) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 Facility: River Bend Station Date of Exam:
2016 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 3 3 4 N/A 4 3 N/A 3 20 4 3 7 2 1 1 2 1 1 1 7 1 2 3 Tier Totals 4 4 6 5 4 4 27 5 5 10 2. Plant Systems 1 2 3 3 3 3 2 2 2 2 2 2 26 2 3 5 2 1 1 1 1 1 1 1 1 1 1 2 12 0 1 2 3 Tier Totals 3 4 4 4 4 3 3 3 3 3 4 38 4 4 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 3 3 2 2 2 1 2 2 Note: 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). (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 with justification; 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.
- 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 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 a category 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. G* Generic K/As
ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions
E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A2 G* K/A Topic(s)
IR # 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X Knowledge of the reasons for the following responses as they apply to partial or complete loss of forced core flow circulation:
(CFR: 41.5 / 45.6)
AK3.02 Reactor power response 3.7 39 295003 Partial or Complete Loss of AC / 6 X Ability to operate and/or monitor the following as they apply to partial or complete loss of A.C. power:
(CFR: 41.7 / 45.6)
AA1.04 D.C. electrical distribution system 3.6 40 295004 Partial or Total Loss of DC Pwr / 6 X Ability to determine and/or interpret the following as they apply to partial or complete loss of D.C. power:
(CFR: 41.10 / 43.5 / 45.13)
AA2.01 Cause of partial or complete loss of D.C. power 3.2 41 295005 Main Turbine Generator Trip / 3 X 2.1.19 Ability to use plant computers to evaluate system or component status.
(CFR: 41.10 / 45.12) 3.9 42 295006 SCRAM / 1 X Knowledge of the operational implications of the following concepts as they apply to SCRAM: (CFR: 41.8 to 41.10)
AK1.01 Decay heat generation and removal 3.7 43 295016 Control Room Abandonment / 7 X Knowledge of the interrelations between control room abandonment and the following:
(CFR: 41.7 / 45.8) AK2.02 Local control stations: Plant-Specific 4.0 44 295018 Partial or Total Loss of CCW / 8 X Knowledge of the reasons for the following responses as they apply to partial or complete loss of component cooling water:
(CFR: 41.5 / 45.6)
AK3.04 Starting standby pump 3.3 45 295019 Partial or Total Loss of Inst. Air / 8 X Ability to operate and/or monitor the following as they apply to partial or complete loss of instrument air: (CFR: 41.7 / 45.6)
AA1.01 Backup air supply 3.5 46 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 X Ability to determine and/or interpret the following as they apply to refueling accidents:
(CFR: 41.10 / 43.5 / 45.13) AA2.0 2 Fuel Pool Level 3.4 47 295024 High Drywell Pressure / 5 X 2.2.44 Ability to interpret control room indications to verify status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12) 4.2 48 295025 High Reactor Pressure / 3 X Knowledge of the operational implications of the following concepts as they apply to high reactor pressure: (CFR: 41.8 to 41.10)
EK1.01 Pressure effects on reactor power 3.9 49 295026 Suppression Pool High Water Temp. / 5 X Knowledge of the interrelations between suppression pool high water temperature and the following:
(CFR: 41.7 / 45.8)
EK2.05 Containment pressure: Mark
-III 3.0 50 295027 High Containment Temperature / 5 X Knowledge of the reasons for the following responses as they apply to high containment temperature (Mark III containment only):
(CFR: 41.5 / 45.6) EK3.01 Emergency depressurization: Mark
-III 3.7 51 295028 High Drywell Temperature / 5 X Ability to operate and/or monitor the following as they apply to high drywell temperature:
(CFR: 41.7
/ 45.6) EA1.02 Drywell ventilation system 3.9 52 ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions
E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A2 G* K/A Topic(s)
IR # 295030 Low Suppression Pool Wtr Lvl / 5 X Ability to determine and/or interpret the following as they apply to low suppression pool water level:
(CFR: 41.10 / 43.5 / 45.13)
EA2.03 Reactor pressure 3.7 53 295031 Reactor Low Water Level / 2 X 2.2.37 Ability to determine operability and/or availability of safety related equipment.
(CFR: 41.7 / 43.5 / 45.12) 3.6 54 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X Knowledge of the operational implications of the following concepts as they apply to SCRAM condition present and reactor power above APRM downscale or unknown:
(CFR: 41.8 to 41.10)
EK1.07 Shutdown margin 3.4 55 295038 High Off
-site Release Rate / 9 X Knowledge of the interrelations between high off
-site release rate and the following:
(CFR: 41.7 / 45.8)
EK2.05 Site emergency plan 3.7 56 600000 Plant Fire On Site / 8 X Knowledge of the reasons for the following responses as they apply to plant fire on site:
(CFR 41.5,41.10 / 45.6 / 45.13)
AK3.04 Actions contained in the abnormal procedure for plant fire on site 2.8 57 700000 Generator Voltage and Electric Grid Disturbances / 6 X Ability to operate and/or monitor the following as they apply to generator voltage and electric grid disturbances:
(CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8 )
AA1.02 Turbine/generator controls 3.8 58 295026 Suppression Pool High Water Temp
/ 5 X Ability to determine and/or interpret the following as they apply to Suppression pool high water temp
- (CFR:43.2) EA2.01 SP water temp 4.2 84 295004 Partial or Total Loss of DC Pwr / 6 X 2.2.40 Ability to apply Technical Specifications for a system. (CFR:43.5) 4.7 85 295005 Main Turbine Generator Trip / 3 X Ability to determine and/or interpret the following as they apply to main turbine generator trip:
(CFR:43.5) AA2.05 Reactor Power 3.9 86 295016 Control Room Abandonment / 7 X 2.4.11 Knowledge of abnormal condition procedures (43.5) 4.2 87 295021 Loss of Shutdown Cooling / 4 X Ability to determine and/or interpret the following as they apply to loss of shutdown cooling:
(CFR: 43.5
) AA2.02 RHR/shutdown cooling system flow 3.4 88 295024 High Drywell Pressure / 5 X 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
(CFR:43.2) 4.2 89 295028 High Drywell Temperature / 5 X Ability to determine and/or interpret the following as they apply to high drywell temperature:
(CFR:43.5) A2.01 Drywell temp 4.1 90 K/A Category Totals:
3 3 4 4 3/4 3/3 Group Point Total:
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions
E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G* K/A Topic(s)
IR # 295002 Loss of Main Condenser Vac / 3 X Knowledge of the reasons for the following responses as they apply to loss of main condenser vacuum: (CFR: 41.5 / 45.6)
AK3.05 Main steam isolation valve: Plant
-Specific 3.4 59 295007 High Reactor Pressure / 3 X Ability to operate and/or monitor the following as they apply to high reactor pressure:
(CFR: 41.7 / 45.6) AA1.04 Safety/relief valve operation: Plant-Specific 3.9 60 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 X Ability to determine and/or interpret the following as they apply to high drywell temperature:
(CFR: 41.10 / 43.5 / 45.13)
AA2.02 Drywell pressure 3.9 61 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 X 2.4.3 Ability to identify post
-accident instrumentation.
3.7 62 295017 High Off
-site Release Rate / 9 X Knowledge of the operational implications of the following concepts as they apply to high off
-site release rate:
(CFR: 41.8
) AK1.02 Protection of general public 3.8 63 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 X Knowledge of the interrelations between high suppression pool water level and the following:
(CFR: 41.7 / 45.8)
EK2.08 Drywell/suppression chamber ventilation 2.6 64 295032 High Secondary Containment Area Temperature / 5 X Knowledge of the reasons for the following responses as they apply to high secondary containment area temperature:
(CFR: 41.5 / 45.6)
EK3.03 Isolating affected systems 3.8 6 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 295020 Inadvertent Cont. Isolation / 5 & 7 X 2.1.20 Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12) 4.6 91 295033 High Secondary Containment Area Radiation Levels / 9 X Ability to determine and/or interpret the following as they apply to high secondary containment area radiation levels:
(CFR: 41.10 / 43.5 / 45.13)
EA2.03 Cause of high area radiation 4.2 92 500000 High CTMT Hydrogen Conc. / 5 X 2.4.6 Knowledge of EOP mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 4.7 93 K/A Category Point Totals:
1 1 2 1 1/1 1/2 Group Point Total:
7/3 ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems
- Tier 2/Group 1 (RO / SRO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G* K/A Topic(s)
IR # 203000 RHR/LPCI: Injection Mode X Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 Pumps 3.5 1 203000 RHR/LPCI: Injection Mode X Knowledge of the effect that a loss or malfunction of the RHR/LPCI: injection mode (plant specific) will have on following:
(CFR: 41.7 / 45.4)
K3.04 Adequate core cooling 4.6 2 4 205000 Shutdown Cooling X Knowledge of shutdown cooling system (RHR shutdown cooling mode) design feature(s) and/or interlocks which provide for the following:
(CFR: 41.7)
K4.04 Adequate pump NPSH 2.6 3 209001 LPCS X K5. Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: (CFR: 41.5 / 45.3)
K5.04 Heat removal (transfer) mechanisms 2.8 4 209002 HPCS X Knowledge of the effect that a loss or malfunction of the following will have on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS):
(CFR: 41.7 / 45.7)
K6.02 Condensate Storage Tank Level 3.4 5 211000 SLC X Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including:
(CFR: 41.5 / 45.5)
A1.09 SBLC system lineup 4.0 6 212000 RPS X Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 / 45.6)
A2.16 Changing mode switch position 4.0 7 215003 IRM X Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including:
(CFR: 41.7 / 45.7) A3.02 Annunciator and alarm signals 3.3 8 215004 Source Range Monitor X Ability to manually operate and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8) A4.07 Verification of proper functioning/ operability 3.4 9 215005 APRM / LPRM X 2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13) 4.2 10 217000 RCIC X Knowledge of the physical connections and/or cause/effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.04 Main condenser 2.6 11 218000 ADS X Knowledge of ADS design features and/or interlocks which provide for the following
- (CFR: 41.7)
K4.03:ADS logic control 3.8 12 ES-401 6 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems
- Tier 2/Group 1 (RO / SRO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G* K/A Topic(s)
IR # 223002 PCIS/Nuclear Steam Supply Shutoff X Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:
(CFR: 41.7 / 45.4)
K3.06 Turbine building radiation 2.8 13 239002 SRVs X Knowledge of RELIEF/SAFETY VALVES design feature(s) and/or interlocks which provide for the following:
(CFR: 41.7)
K4.01 Insures that only one or two safety/relief valves reopen following the initial portion of a reactor isolation event (LLS logic): Plant
-Specific 3.9 14 239002 SRVs X Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES: (CFR: 41.5 / 45.3) K5.05 Discharge line quencher operation 2.6 15 259002 Reactor Water Level Control X Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM: (CFR: 41.7 / 45.7)
K6.02 A.C. power 3.3 16 259002 Reactor Water Level Control X Ability to predict and/or monitor changes in parameters associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including:
(CFR: 41.5 / 45.5) A1.03 Reactor power 3.8 17 261000 SGTS X Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 / 45.6)
A2.01 Low system flow 2.9 18 261000 SGTS X Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including:
(CFR: 41.7 / 45.7)
A3.04 System Temperature 3.0 19 262001 AC Electrical Distribution X Ability to manually operate and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8) A4.0 3 Local operation of breakers 3.2 20 262002 UPS (AC/DC)
X 2.4.31 Knowledge of annunciator alarms, indications, or response procedures
. (CFR: 41.10
) 4.2 21 263000 DC Electrical Distribution X Knowledge of the physical connections and/or cause/effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following:
(CFR: 41.2 to 41.9 / 45.7 to 45.8) K1.01 A.C. electrical distribution 3.3 22 264000 EDGs X Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following:
(CFR: 41.7 / 45.4)
K3.01 Emergency core cooling systems 4.2 23 300000 Instrument Air X Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 Instrument air compressor 2.8 24 ES-401 7 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems
- Tier 2/Group 1 (RO / SRO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G* K/A Topic(s)
IR # 300000 Instrument Air X Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM:
(CFR: 41.5 / 45.3)
K5.01 Air compressors 2.5 25 400000 Component Cooling Water X Knowledge of electrical power supplies for the following:
(CFR: 41.7)
K2.01 CCW Pumps 2.9 26 215005 APRM / LPRM X Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 / 45.6)
A2.07 Recirculation flow channels flow mismatch 3.4 76 239002 SRVs X 2.2.25 Knowledge of bases for Tech Specs for LCOs and safety limits (CFR: 43.2) 4.2 77 262002 UPS (AC/DC)
X Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 / 45.6)
A2.02 Over voltage 2.5 78 264000 EDGs X 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.
(CFR: 41.10 / 43.5 / 45.13) 4.3 79 212000 RPS X 2.2.25 Knowledge of the bases in Tech Specs for LCOs and Safety limits 4.2 80 K/A Category Point Totals:
2 3 3 3 3 2 2 2/2 2 2 2/3 Group Point Total:
26/5 ES-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems
System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G* K/A Topic(s)
IR # 201001 CRD Hydraulic X 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5 / 43.5 / 45.12) 4.2 27 201002 RMCS X 2.2.42 Ability to recognize system parameters that are entry
-level conditions for Technical Specifications.
(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3) 4.6 81 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS X Knowledge of the operational implications of the following concepts as they apply to ROD CONTROL AND INFORMATION SYSTEM (RCIS)
- (CFR: 41.5 / 45.3)
K5.09 High power setpoints BWR
-6 3.5 28 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control X Knowledge of the effect that a loss or malfunction of the RECIRCULATION FLOW CONTROL SYSTEM will have on following:
(CFR: 41.7 / 45.4)
K3.05 Recirculation pump speed: Plant-Specific 3.2 29 204000 RWCU X Knowledge of REACTOR WATER CLEANUP SYSTEM design feature(s) and/or interlocks which provide for the following:
(CFR: 41.7)
K4.03 Over temperature protection for system components 2.9 30 214000 RPIS 215001 Traversing In
-Core Probe 215002 RBM 216000 Nuclear Boiler Inst.
X Knowledge of the physical connections and/or cause/effect relationships between NUCLEAR BOILER INSTRUMENTATION and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) K1.06 Low pressure core spray 3.9 31 219000 RHR/LPCI: Torus/Pool Cooling Mode X Knowledge of electrical power supplies to the following: (CFR: 41.7)
K2.01 Valves 2.5 32 223001 Primary CTMT and Aux.
X Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES: (CFR: 41.7 / 45.7)
K6.02 Containment cooling: Mark
-III 3.5 33 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode
ES-401 9 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems
System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G* K/A Topic(s)
IR # 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator X Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEMSYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5)
A2.02 High Reactor Pressure 3.7 34 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste X Ability to predict and/or monitor changes in parameters associated with operating the RADWASTE controls including:
(CFR: 41.5 / 45.5)
A1.01 Radiation level 2.7 35 271000 Offgas X Ability to monitor automatic operations of the OFFGAS SYSTEM including:
(CFR: 41.7 / 45.7)
A3.07 Process radiation monitoring system indications 3.4 36 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT X Ability to manually operate and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.09 System status lights and alarms: Plant-Specific 3.2 37 290003 Control Room HVAC 290002 Reactor Vessel Internals X 2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 3.8 38 204000 RWCU 234 000 Fuel Handling Equipment X Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 / 45.6)
A2.01 Interlock Failure 3.7 82 290003 Control Room HVAC X 2.2.22 Knowledge of limiting conditions for operations and safety limits 4.7 83 K/A Category Point Totals:
1 1 1 1 1 1 1 1/1 1 1 2/2 Group Point Total:
12/3 ES-401 10 Form ES-401-3 Facility: River Bend Station Date of Exam:
2016 Category K/A # Topic RO SRO-Only IR # IR # 1. Conduct of Operations
2.1.3 Knowledge
of shift or short
-term relief turnover practices. (CFR: 41.10 / 45.13) 3.7 66 2.1.39 Knowledge of conservative decision making practices. (CFR: 41.10 / 43.5 / 45.12) 3.6 67 2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 / 43.5 / 45.4) 4.1 68 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (CFR: 41.10 / 43.5 / 45.12) 3.9 94 2.1.42 Knowledge of new and spent fuel movement procedures. (CFR: 41.10 / 43.7 / 45.13) 3.4 95 Subtotal 3 2 2. Equipment Control 2.2.2 Ability to manipulate the controls as required to operate the facility between shutdown and power levels 4.6 69 2.2.43 Knowledge of the process used to track inoperable alarms. (CFR: 41.10 / 43.5
) 3.0 70 2.2.14 Knowledge of the process for controlling equipment configuration or status. (CFR: 41.10 / 43.3 / 45.13) 3.9 71 2.2.38 Knowledge of conditions and limitations in the facility license. (CFR: 41.7 / 41.10 / 43.1 / 45.13) 4.5 96 Subtotal 3 1 3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 3.2 72 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high
-radiation areas, aligning filters, etc.
3.2 73 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11 / 41.12 / 43.4 / 45.9) 2.9 97 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9) 3.1 98 Subtotal 2 2 4. Emergency Procedures / Plan 2.4.12 Knowledge of general operating crew responsibilities during emergency operations 4.0 74 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 / 43.5 / 45.12) 4.0 75 2.4.32 Knowledge of operator response to loss of all annunciators. (CFR: 41.10 / 43.5 / 45.13) 4.0 99 ES-401 11 Form ES-401-3 Facility: River Bend Station Date of Exam:
2016 Category K/A # Topic RO SRO-Only IR # IR # 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (CFR: 41.10 / 43.5 / 45.11) 4.4 100 Subtotal 2 2 Tier 3 Point Total 10 7 ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection Rejected KAs were not tracked since this was NRC written and the majority of the exam required new questions to be written for the randomly selected KAs because they did not have previously written questions in the facility licensee's bank.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Bend Nuclear Station Date of Examination: 9/12/201 6 Examination Level: RO SRO Operating Test Number: LOT-201 6 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - N CRD pump clearance Conduct of Operations R - N Calculation for leakage Equipment Control R - N Electrical Print Reading (Determine effect of removing fuses in RPS system)
Radiation Control R - N Determine emergency entry requirements for high dose Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from
ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Ben Nuclear Station Date of Examination:
9/12/201 6 Examination Level: RO SRO Operating Test Number: LOT-201 6 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - N Print Reading (RPS fuse removal)
Conduct of Operations R - N Leakage calculation and TS call associated with leakage.
Equipment Control R - N Evaluate a CRD pump clearance
Radiation Control R - N Emergency entry for high dose and who authorizes the entry.
Emergency Plan R - N Emergency Classification NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from
ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND NUCLEAR STATION Date of Examination:
9/12/201 6 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 201 6 Control Room Systems
-I; 2 or 3 for SRO
-U System / JPM Title Type Code*
Safety Function S1. Perform Rod Withdrawal Limiter Test with a MSIV inadvertent closure. A - N - S 1 S2. Align SU FRV and controller drifts open.
A - N - S - L 2 S3. Open MSIVs per SOP
-011. M - S - L 3 S4. Align Division 3 DG to power ENS
-SWGR1A E - N - S - L 4 ** S5. SBGT fails to start with dampers fail to open.
A - EN - N - S 9 ** S6. Swap electrical bus power supplies N - S 6 S7. Drive In IRM/SRM Detectors Following a SCRAM D - S - L 7 ** S8. Start RHR in Suppression Pool Cooling Mode with high pump amps.
A - D - S - L 5 In-Plant Systems
-I); (3 or 2 for SRO
-U) ** P1. CRD filter swap with new filter clogged (CR-2016-1724) A - N - R 1 ** P2. ATC actions to Man the RSP. AOP 31 Att 12 Section 1.1.4-1.1.6 N - E - L 2 P3. Place Inverter ENB
-IV01B in Service M 6
-I control room (and in
-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in
-plant systems and functions may overlap those tested in the control room.
- and bolded indicates SRO
-U selected JPMs
. Shaded JPM indicates RO only JPM.
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in
-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /