ML16280A465

2016-09 Final Outlines

ML16280A465
Person / Time
Site:	River Bend
Issue date:	09/30/2016
From:	Vincent Gaddy Operations Branch IV
To:
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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 K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 3 3 4 4 3 3 20 4 3 7 Emergency & N/A N/A 2 1 1 2 1 1 1 7 1 2 3 Abnormal Plant Evolutions Tier Totals 4 4 6 5 4 4 27 5 5 10 1 2 3 3 3 3 2 2 2 2 2 2 26 2 3 5 2.

Plant 2 1 1 1 1 1 1 1 1 1 1 2 12 0 1 2 3 Systems Tier Totals 3 4 4 4 4 3 3 3 3 3 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 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 - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G* K/A Topic(s) IR #

1 2 3 1 Knowledge of the reasons for the following responses as they apply to partial or complete loss 3.7 39 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X of forced core flow circulation: (CFR: 41.5 / 45.6)

AK3.02 Reactor power response Ability to operate and/or monitor the following as they apply to partial or complete loss of A.C. power: 3.6 40 295003 Partial or Complete Loss of AC / 6 X (CFR: 41.7 / 45.6)

AA1.04 D.C. electrical distribution system Ability to determine and/or interpret the following as they apply to partial or complete loss of D.C. power: 3.2 41 295004 Partial or Total Loss of DC Pwr / 6 (CFR: 41.10 / 43.5 / 45.13)

X AA2.01 Cause of partial or complete loss of D.C.

power 2.1.19 Ability to use plant computers to evaluate 3.9 42 295005 Main Turbine Generator Trip / 3 X system or component status. (CFR: 41.10 / 45.12)

Knowledge of the operational implications of the following concepts as they apply to SCRAM: (CFR: 3.7 43 295006 SCRAM / 1 X 41.8 to 41.10)

AK1.01 Decay heat generation and removal Knowledge of the interrelations between control room abandonment and the following: (CFR: 41.7 / 4.0 44 295016 Control Room Abandonment / 7 X 45.8)

AK2.02 Local control stations: Plant-Specific Knowledge of the reasons for the following responses as they apply to partial or complete loss 3.3 45 295018 Partial or Total Loss of CCW / 8 X of component cooling water: (CFR: 41.5 / 45.6)

AK3.04 Starting standby pump Ability to operate and/or monitor the following as they apply to partial or complete loss of instrument 3.5 46 295019 Partial or Total Loss of Inst. Air / 8 X air: (CFR: 41.7 / 45.6)

AA1.01 Backup air supply 295021 Loss of Shutdown Cooling / 4 Ability to determine and/or interpret the following as they apply to refueling accidents: (CFR: 41.10 / 43.5 3.4 47 295023 Refueling Acc / 8 X / 45.13)

AA2.02 Fuel Pool Level 2.2.44 Ability to interpret control room indications to verify status and operation of a system, and 4.2 48 295024 High Drywell Pressure / 5 understand how operator actions and directives X affect plant and system conditions. (CFR: 41.5 / 43.5

/ 45.12)

Knowledge of the operational implications of the following concepts as they apply to high reactor 3.9 49 295025 High Reactor Pressure / 3 X pressure: (CFR: 41.8 to 41.10)

EK1.01 Pressure effects on reactor power Knowledge of the interrelations between suppression pool high water temperature and the 3.0 50 295026 Suppression Pool High Water Temp.

/5 X following: (CFR: 41.7 / 45.8)

EK2.05 Containment pressure: Mark-III Knowledge of the reasons for the following responses as they apply to high containment 3.7 51 295027 High Containment Temperature / 5 temperature (Mark III containment only): (CFR: 41.5 X / 45.6)

EK3.01 Emergency depressurization: Mark-III Ability to operate and/or monitor the following as they apply to high drywell temperature: (CFR: 41.7 / 3.9 52 295028 High Drywell Temperature / 5 X 45.6)

EA1.02 Drywell ventilation system

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G* K/A Topic(s) IR #

1 2 3 1 Ability to determine and/or interpret the following as they apply to low suppression pool water level: 3.7 53 295030 Low Suppression Pool Wtr Lvl / 5 X (CFR: 41.10 / 43.5 / 45.13)

EA2.03 Reactor pressure 2.2.37 Ability to determine operability and/or availability of safety related equipment. (CFR: 41.7 / 3.6 54 295031 Reactor Low Water Level / 2 X 43.5 / 45.12)

Knowledge of the operational implications of the following concepts as they apply to SCRAM 3.4 55 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or condition present and reactor power above APRM X downscale or unknown: (CFR: 41.8 to 41.10)

Unknown / 1 EK1.07 Shutdown margin Knowledge of the interrelations between high off-site release rate and the following: (CFR: 41.7 / 45.8) 3.7 56 295038 High Off-site Release Rate / 9 X EK2.05 Site emergency plan Knowledge of the reasons for the following responses as they apply to plant fire on site: (CFR 2.8 57 600000 Plant Fire On Site / 8 41.5,41.10 / 45.6 / 45.13)

X AK3.04 Actions contained in the abnormal procedure for plant fire on site Ability to operate and/or monitor the following as they apply to generator voltage and electric grid 3.8 58 700000 Generator Voltage and Electric Grid Disturbances / 6 disturbances: (CFR: 41.5 and 41.10 / 45.5, 45.7, X and 45.8 )

AA1.02 Turbine/generator controls Ability to determine and/or interpret the following as they apply to Suppression pool high water temp: 4.2 84 295026 Suppression Pool High Water Temp X

/5 (CFR:43.2) EA2.01 SP water temp 2.2.40 Ability to apply Technical Specifications for a system. (CFR:43.5) 4.7 85 295004 Partial or Total Loss of DC Pwr / 6 X Ability to determine and/or interpret the following as they apply to main turbine generator trip: (CFR:43.5) 3.9 86 295005 Main Turbine Generator Trip / 3 X AA2.05 Reactor Power 2.4.11 Knowledge of abnormal condition procedures (43.5) 4.2 87 295016 Control Room Abandonment / 7 X Ability to determine and/or interpret the following as they apply to loss of shutdown cooling: (CFR: 43.5) 3.4 88 295021 Loss of Shutdown Cooling / 4 X AA2.02 RHR/shutdown cooling system flow 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the 4.2 89 295024 High Drywell Pressure / 5 X status of limiting conditions for operations.

(CFR:43.2)

Ability to determine and/or interpret the following as they apply to high drywell temperature: (CFR:43.5) 4.1 90 295028 High Drywell Temperature / 5 X A2.01 Drywell temp K/A Category Totals: 3 3 4 4 3/4 3/3 Group Point Total: 20/7

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G* K/A Topic(s) IR #

1 2 3 1 2 Knowledge of the reasons for the following 3.4 59 295002 Loss of Main Condenser Vac / 3 responses as they apply to loss of main condenser X vacuum: (CFR: 41.5 / 45.6)

AK3.05 Main steam isolation valve: Plant-Specific Ability to operate and/or monitor the following as 3.9 60 295007 High Reactor Pressure / 3 they apply to high reactor pressure: (CFR: 41.7 /

X 45.6)

AA1.04 Safety/relief valve operation: Plant-Specific 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 Ability to determine and/or interpret the following 3.9 61 295012 High Drywell Temperature / 5 as they apply to high drywell temperature: (CFR:

X 41.10 / 43.5 / 45.13)

AA2.02 Drywell pressure 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 2.4.3 Ability to identify post-accident 3.7 62 295015 Incomplete SCRAM / 1 X instrumentation.

Knowledge of the operational implications of the 3.8 63 295017 High Off-site Release Rate / 9 following concepts as they apply to high off-site X release rate: (CFR: 41.8) AK1.02 Protection of general public 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 Knowledge of the interrelations between high 2.6 64 295029 High Suppression Pool Wtr Lvl / 5 suppression pool water level and the following:

X (CFR: 41.7 / 45.8)

EK2.08 Drywell/suppression chamber ventilation Knowledge of the reasons for the following 3.8 65 295032 High Secondary Containment Area responses as they apply to high secondary Temperature / 5 X containment area temperature: (CFR: 41.5 / 45.6)

EK3.03 Isolating affected systems 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 2.1.20 Ability to interpret and execute procedure 4.6 91 295020 Inadvertent Cont. Isolation / 5 & 7 X steps. (CFR: 41.10 / 43.5 / 45.12)

Ability to determine and/or interpret the following 4.2 92 295033 High Secondary Containment Area X as they apply to high secondary containment area Radiation Levels / 9 radiation levels: (CFR: 41.10 / 43.5 / 45.13)

EA2.03 Cause of high area radiation 2.4.6 Knowledge of EOP mitigation strategies. 4.7 93 500000 High CTMT Hydrogen Conc. / 5 X (CFR: 41.10 / 43.5 / 45.13)

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 K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 Knowledge of electrical power supplies to 3.5 1 203000 RHR/LPCI: Injection X the following: (CFR: 41.7)

Mode K2.01 Pumps Knowledge of the effect that a loss or 4.6 malfunction of the RHR/LPCI: injection 24 203000 RHR/LPCI: Injection X mode (plant specific) will have on following:

Mode (CFR: 41.7 / 45.4)

K3.04 Adequate core cooling Knowledge of shutdown cooling system 2.6 (RHR shutdown cooling mode) design 3 205000 Shutdown Cooling X feature(s) and/or interlocks which provide for the following: (CFR: 41.7)

K4.04 Adequate pump NPSH K5. Knowledge of the operational 2.8 implications of the following concepts as 4 209001 LPCS X they apply to LOW PRESSURE CORE SPRAY SYSTEM: (CFR: 41.5 / 45.3)

K5.04 Heat removal (transfer) mechanisms Knowledge of the effect that a loss or 3.4 malfunction of the following will have on the 5 209002 HPCS X HIGH PRESSURE CORE SPRAY SYSTEM (HPCS): (CFR: 41.7 / 45.7)

K6.02 Condensate Storage Tank Level Ability to predict and/or monitor changes in 4.0 parameters associated with operating the 6 211000 SLC X STANDBY LIQUID CONTROL SYSTEM controls including: (CFR: 41.5 / 45.5)

A1.09 SBLC system lineup Ability to (a) predict the impacts of the 4.0 following on the REACTOR PROTECTION 7 SYSTEM ; and (b) based on those predictions, use procedures to correct, 212000 RPS X control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.16 Changing mode switch position Ability to monitor automatic operations of 3.3 the INTERMEDIATE RANGE MONITOR 8 215003 IRM X (IRM) SYSTEM including: (CFR: 41.7 /

45.7)

A3.02 Annunciator and alarm signals Ability to manually operate and/or monitor 3.4 in the control room: (CFR: 41.7 / 45.5 to 9 215004 Source Range Monitor X 45.8)

A4.07 Verification of proper functioning/

operability 2.4.34 Knowledge of RO tasks performed 4.2 outside the main control room during an 10 215005 APRM / LPRM X emergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13)

Knowledge of the physical connections 2.6 and/or cause/effect relationships between 11 REACTOR CORE ISOLATION COOLING 217000 RCIC X SYSTEM (RCIC) and the following: (CFR:

41.2 to 41.9 / 45.7 to 45.8)

K1.04 Main condenser Knowledge of ADS design features and/or 3.8 interlocks which provide for the following: 12 218000 ADS X (CFR: 41.7)

K4.03:ADS logic control

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 K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 Knowledge of the effect that a loss or 2.8 malfunction of the PRIMARY 13 CONTAINMENT ISOLATION 223002 PCIS/Nuclear Steam X SYSTEM/NUCLEAR STEAM SUPPLY Supply Shutoff SHUT-OFF will have on following: (CFR:

41.7 / 45.4)

K3.06 Turbine building radiation Knowledge of RELIEF/SAFETY VALVES 3.9 design feature(s) and/or interlocks which 14 provide for the following: (CFR: 41.7) 239002 SRVs X 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 Knowledge of the operational implications 2.6 of the following concepts as they apply to 15 239002 SRVs X RELIEF/SAFETY VALVES: (CFR: 41.5 /

45.3)

K5.05 Discharge line quencher operation Knowledge of the effect that a loss or 3.3 malfunction of the following will have on the 16 259002 Reactor Water Level X REACTOR WATER LEVEL CONTROL Control SYSTEM: (CFR: 41.7 / 45.7)

K6.02 A.C. power Ability to predict and/or monitor changes in 3.8 parameters associated with operating the 17 259002 Reactor Water Level REACTOR WATER LEVEL CONTROL X

Control SYSTEM controls including: (CFR: 41.5 /

45.5)

A1.03 Reactor power Ability to (a) predict the impacts of the 2.9 following on the STANDBY GAS 18 TREATMENT SYSTEM ; and (b) based on those predictions, use procedures to 261000 SGTS X correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6)

A2.01 Low system flow Ability to monitor automatic operations of 3.0 the STANDBY GAS TREATMENT 19 261000 SGTS X SYSTEM including: (CFR: 41.7 / 45.7)

A3.04 System Temperature Ability to manually operate and/or monitor 3.2 262001 AC Electrical in the control room: (CFR: 41.7 / 45.5 to 20 X

Distribution 45.8)

A4.03 Local operation of breakers 2.4.31 Knowledge of annunciator alarms, 4.2 262002 UPS (AC/DC) X indications, or response procedures. 21 (CFR: 41.10 )

Knowledge of the physical connections 3.3 and/or cause/effect relationships between 22 263000 DC Electrical D.C. ELECTRICAL DISTRIBUTION and X

Distribution the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 A.C. electrical distribution Knowledge of the effect that a loss or 4.2 malfunction of the EMERGENCY 23 264000 EDGs X GENERATORS (DIESEL/JET) will have on following: (CFR: 41.7 / 45.4)

K3.01 Emergency core cooling systems Knowledge of electrical power supplies to 2.8 300000 Instrument Air X the following: (CFR: 41.7) 24 K2.01 Instrument air compressor

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 K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 Knowledge of the operational implications 2.5 of the following concepts as they apply to 25 300000 Instrument Air X the INSTRUMENT AIR SYSTEM: (CFR:

41.5 / 45.3)

K5.01 Air compressors Knowledge of electrical power supplies for 2.9 400000 Component Cooling X the following: (CFR: 41.7) 26 Water K2.01 CCW Pumps Ability to (a) predict the impacts of the 3.4 following on the AVERAGE POWER 76 RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ; and (b) based on those predictions, use 215005 APRM / LPRM X 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 2.2.25 Knowledge of bases for Tech Specs 4.2 239002 SRVs X for LCOs and safety limits (CFR: 43.2) 77 Ability to (a) predict the impacts of the 2.5 following on the UNINTERRUPTABLE 78 POWER SUPPLY (A.C./D.C.) ; and (b) based on those predictions, use 262002 UPS (AC/DC) X procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6)

A2.02 Over voltage 2.4.20 Knowledge of the operational 4.3 264000 EDGs X implications of EOP warnings, cautions, 79 and notes. (CFR: 41.10 / 43.5 / 45.13) 2.2.25 Knowledge of the bases in Tech 4.2 212000 RPS X Specs for LCOs and Safety limits 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 - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 2.2.44 Ability to interpret control room 201001 CRD Hydraulic X indications to verify the status and 4.2 operation of a system, and understand 27 how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12) 2.2.42 Ability to recognize system 201002 RMCS X parameters that are entry-level 4.6 conditions for Technical Specifications. 81 (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3) 201003 Control Rod and Drive Mechanism 201004 RSCS Knowledge of the operational 201005 RCIS X implications of the following concepts 3.5 as they apply to ROD CONTROL AND 28 INFORMATION SYSTEM (RCIS):

(CFR: 41.5 / 45.3)

K5.09 High power setpoints BWR-6 201006 RWM 202001 Recirculation Knowledge of the effect that a loss or 202002 Recirculation Flow Control X malfunction of the RECIRCULATION 3.2 FLOW CONTROL SYSTEM will have 29 on following: (CFR: 41.7 / 45.4)

K3.05 Recirculation pump speed:

Plant-Specific Knowledge of REACTOR WATER 204000 RWCU X CLEANUP SYSTEM design feature(s) 2.9 and/or interlocks which provide for the 30 following: (CFR: 41.7)

K4.03 Over temperature protection for system components 214000 RPIS 215001 Traversing In-Core Probe 215002 RBM Knowledge of the physical connections 216000 Nuclear Boiler Inst. X and/or cause/effect relationships 3.9 between NUCLEAR BOILER 31 INSTRUMENTATION and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.06 Low pressure core spray Knowledge of electrical power supplies 219000 RHR/LPCI: Torus/Pool X to the following: (CFR: 41.7) 2.5 Cooling Mode K2.01 Valves 32 Knowledge of the effect that a loss or 223001 Primary CTMT and Aux. X malfunction of the following will have 3.5 on the PRIMARY CONTAINMENT 33 SYSTEM AND AUXILIARIES: (CFR:

41.7 / 45.7)

K6.02 Containment cooling: Mark-III 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 - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control Ability to (a) predict the impacts of the 241000 Reactor/Turbine Pressure X following on the REACTOR/TURBINE 3.7 Regulator PRESSURE REGULATING 34 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 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater Ability to predict and/or monitor 268000 Radwaste X changes in parameters associated with 2.7 operating the RADWASTE controls 35 including: (CFR: 41.5 / 45.5)

A1.01 Radiation level Ability to monitor automatic operations 271000 Offgas X of the OFFGAS SYSTEM including: 3.4 (CFR: 41.7 / 45.7) 36 A3.07 Process radiation monitoring system indications 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation Ability to manually operate and/or 290001 Secondary CTMT X monitor in the control room: (CFR: 3.2 41.7 / 45.5 to 45.8) 37 A4.09 System status lights and alarms:

Plant-Specific 290003 Control Room HVAC 2.1.32 Ability to explain and apply 290002 Reactor Vessel Internals X system limits and precautions. (CFR: 3.8 41.10 / 43.2 / 45.12) 38 204000 RWCU Ability to (a) predict the impacts of the 234000 Fuel Handling Equipment X following on the FUEL HANDLING 3.7 EQUIPMENT; and (b) based on those 82 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 2.2.22 Knowledge of limiting conditions 290003 Control Room HVAC X 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 #

2.1.3 Knowledge of shift or short-term relief turnover practices. 3.7 66 (CFR: 41.10 / 45.13) 2.1.39 Knowledge of conservative decision making practices. 3.6 67 (CFR: 41.10 / 43.5 / 45.12) 2.1.45 Ability to identify and interpret diverse indications to 4.1 68

1. validate the response of another indication. (CFR: 41.7 /

Conduct of 43.5 / 45.4)

Operations 2.1.5 Ability to use procedures related to shift staffing, such as 3.9 94 minimum crew complement, overtime limitations, etc.

(CFR: 41.10 / 43.5 / 45.12) 2.1.42 Knowledge of new and spent fuel movement procedures. 3.4 95 (CFR: 41.10 / 43.7 / 45.13)

Subtotal 3 2 2.2.2 Ability to manipulate the controls as required to operate 4.6 69 the facility between shutdown and power levels 2.2.43 Knowledge of the process used to track inoperable 3.0 70

2. alarms. (CFR: 41.10 / 43.5)

Equipment 2.2.14 Knowledge of the process for controlling equipment 3.9 71 Control configuration or status. (CFR: 41.10 / 43.3 / 45.13) 2.2.38 Knowledge of conditions and limitations in the facility 4.5 96 license. (CFR: 41.7 / 41.10 / 43.1 / 45.13)

Subtotal 3 1 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 72 emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 2.3.12 Knowledge of radiological safety principles pertaining to 3.2 73 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3. 2.3.5 Ability to use radiation monitoring systems, such as fixed 2.9 97 Radiation radiation monitors and alarms, portable survey Control instruments, personnel monitoring equipment, etc. (CFR:

41.11 / 41.12 / 43.4 / 45.9) 2.3.15 Knowledge of radiation monitoring systems, such as fixed 3.1 98 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR:

41.12 / 43.4 / 45.9)

Subtotal 2 2 2.4.12 Knowledge of general operating crew responsibilities 4.0 74 during emergency operations

4. 2.4.21 Knowledge of the parameters and logic used to assess 4.0 75 Emergency the status of safety functions, such as reactivity control, Procedures / core cooling and heat removal, reactor coolant system Plan integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 / 43.5 / 45.12) 2.4.32 Knowledge of operator response to loss of all 4.0 99 annunciators. (CFR: 41.10 / 43.5 / 45.13)

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 4.4 100 plan, including supporting or acting as emergency coordinator if required. (CFR: 41.10 / 43.5 / 45.11)

Subtotal 2 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 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 licensees bank.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Bend Nuclear Station Date of Examination: 9/12/2016 Examination Level: RO SRO Operating Test Number: LOT-2016 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations R-N CRD pump clearance Conduct of Operations R-N Calculation for leakage Electrical Print Reading (Determine effect of Equipment Control R-N removing fuses in RPS system)

Determine emergency entry requirements for high Radiation Control R-N 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 bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Ben Nuclear Station Date of Examination: 9/12/2016 Examination Level: RO SRO Operating Test Number: LOT-2016 Administrative Topic Type Describe activity to be performed (see Note) Code*

Print Reading (RPS fuse removal)

Conduct of Operations R-N Leakage calculation and TS call associated with Conduct of Operations R-N leakage.

Evaluate a CRD pump clearance Equipment Control R-N Emergency entry for high dose and who authorizes Radiation Control R-N the entry.

Emergency Classification Emergency Plan R-N 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 bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND NUCLEAR STATION Date of Examination: 9/12/2016 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 2016 Control Room Systems* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U Safety System / JPM Title Type Code*

Function S1. Perform Rod Withdrawal Limiter Test with a MSIV 1 A-N-S inadvertent closure.

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 A-D-5 pump amps. S-L In-Plant Systems* (3 for RO); (3 for SRO-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 N-E-L 2 1.1.4-1.1.6 P3. Place Inverter ENB-IV01B in Service M 6

• All RO and SRO-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.

• Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1 / 1 / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator