ML14111A352

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2014-03-Final Outlines
ML14111A352
Person / Time
Site: River Bend Entergy icon.png
Issue date: 03/27/2014
From: Vincent Gaddy
Operations Branch IV
To:
Entergy Operations
laura hurley
References
50-458/14-003
Download: ML14111A352 (31)
v • d • e


Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: River Bend Station Date of Exam: March 2014 RO K/A Category Points SRO-Only Points Tier Group 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 3 4 7 Emergency &

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

Plant 2 2 1 1 1 1 1 1 1 1 1 1 12 2 1 3 Systems Tier Totals 5 3 3 3 3 3 4 3 3 4 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 1 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).
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/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 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.

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 A G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced X Ability to operate and/or monitor the following 3.3 1 Core Flow Circulation / 1 & 4 as they apply to Partial or Complete Loss of Forced Core Flow Circulation:

AA1.05 Recirculation flow control system CFR: 41.7 295003 Partial or Complete Loss of AC / 6 X 2.1.20 Ability to interpret and execute 4.6 2 procedure steps.

CFR: 41.10 295004 Partial or Total Loss of DC Pwr / 6 X Ability to operate and/or monitor the following 3.8 3 as they apply to Partial or Complete Loss of D.C. Power:

AA1.02 Systems necessary to assure safe plant shutdown CFR: 41.7 295005 Main Turbine Generator Trip / 3 X Knowledge of the interrelations between Main 3.2 4 Turbine Generator Trip and the following:

AK2.08 A.C. electrical distribution 295006 SCRAM / 1 X Knowledge of the following concepts as they 3.7 5 apply to SCRAM:

AK1.03 Reactivity control CFR: 41.8-41.10 295016 Control Room Abandonment / 7 X 2.4.34 Knowledge of RO tasks performed 4.2 6 outside the main control room during an emergency and the resultant operational effects.

CFR: 41.10 295018 Partial or Total Loss of CCW / 8 X Ability to determine and/or interpret the 3.2 7 following as they apply to Partial or Complete Loss of Component Cooling Water:

AA2.03 Cause for partial or complete loss CFR: 41.10 295019 Partial or Total Loss of Inst. Air / 8 X Knowledge of the interrelations between Partial 2.9 8 or Complete Loss of Instrument Air and the following:

AK2.02 Component cooling water CFR: 41.7

295021 Loss of Shutdown Cooling / 4 X Knowledge of the reasons for the following 3.6 9 responses as they apply to Loss of Shutdown Cooling:

AK3.05 Establishing alternate heat removal flowpaths.

CFR: 41.5 295023 Refueling Acc / 8 X Knowledge of the operational implications of 3.7 10 the following concepts as they apply to Refueling Accidents:

AK1.03 Inadvertent criticality CFR: 41.8-41.10 295024 High Drywell Pressure / 5 X Knowledge of the reasons for the following 3.6 11 responses as they apply to High Drywell Pressure:

EK3.03 Containment venting: Mark III CFR: 41.5 295025 High Reactor Pressure / 3 X Ability to determine and/or interpret the 4.2* 12 following as they apply to High Reactor Pressure:

EA2.02 Reactor power CFR: 41.7 295026 Suppression Pool High Water X Ability to operate and/or monitor the following 4.1 13 Temp. / 5 as they apply to Suppression Pool High Water Temperature:

EA1.01 Suppression pool cooling CFR: 41.7 295027 High Containment Temperature / 5 X 2.4.4 Ability to recognize abnormal indications 4.5 14 for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

CFR: 41.10 295028 High Drywell Temperature / 5 X Knowledge of the operational implications of 3.5 15 the following concepts as they apply to High Drywell Temperature:

EK1.01 Reactor water level measurement CFR: 41.8-41.10 295030 Low Suppression Pool Wtr Lvl / 5 295031 Reactor Low Water Level / 2 X Knowledge of the reasons for the following 3.9 16 responses as they apply to Reactor Low Water Level:

EK3.01 Automatic depressurization system actuation CFR: 41.5

295037 SCRAM Condition Present X Ability to determine and/or interpret the 4.3* 17 and Reactor Power Above APRM following as they apply to Scram Condition Downscale or Unknown / 1 Present and Reactor Power above APRM Downscale or Unknown:

EA2.03 SBLC tank level CFR: 41.10 295038 High Off-site Release Rate / 9 X Knowledge of the interrelations between High 3.9 18 Off-Site Release Rate and the following:

EK2.04 Stack-gas monitoring system: Plant-specific CFR: 41.7 600000 Plant Fire On Site / 8 X Ability to operate and/or monitor the following 3.0 19 as they apply to Plant Fire On Site:

AA1.06 Fire Alarm 700000 Generator Voltage and Electric Grid X Knowledge of the reasons for the following 3.9 20 Disturbances / 6 responses as they apply to Generator Voltage and Electric Grid Disturbances:

AK3.01 Reactor and turbine trip criteria CFR: 41.4, 41.5, 41.7, 41.10 K/A Category Totals: 3 3 4 4 3 3 Group Point Total: 20/7

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 A G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced X 2.1.23 Ability to perform specific system and 4.4 76 Core Flow Circulation / 1 & 4 integrated plant procedures during all modes of plant operation.

CFR: 43.5 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 X Ability to determine and/or interpret the 4.6* 77 following as they apply to SCRAM:

AA2.01 Reactor power CFR: 43.5 295016 Control Room Abandonment / 7 X Ability to determine and/or interpret the 4.1 79 following as they apply to CONTROL ROOM ABANDONMENT:

AA 2.01 Reactor Power CFR 43.5 295018 Partial or Total Loss of CCW / 8 X 2.4.45 Ability to prioritize and interpret the 4.3 78 significance of each annunciator or alarm.

CFR: 43.5 295019 Partial or Total Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 X 2.4.21 Knowledge of the parameters and logic 4.6 80 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: 43.5 295026 Suppression Pool High Water Temp. / 5 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 295030 Low Suppression Pool Wtr Lvl / 5 X 2.4.50 Ability to verify system alarm setpoints 4.0 81 and operate controls identified in the alarm response manual.

295031 Reactor Low Water Level / 2 X Ability to determine and/or interpret the 4.2* 82 following as they apply to Reactor Low Water Level:

EA2.03 Reactor pressure 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 700000 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals: 3 4 Group Point Total: 20/7

ES-401 3 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 295002 Loss of Main Condenser Vac / 3 X Knowledge of the reasons for the following 3.2 21 responses as they apply to Loss of Main Condenser Vacuum:

AK3.09 Reactor power reduction CFR: 41.5 295007 High Reactor Pressure / 3 X 2.2.44 Ability to interpret control room 4.2 22 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 295008 High Reactor Water Level / 2 X Knowledge of the operational implications of the 4.0* 23 following concepts as they apply to High Containment Temperature (Mark III Containment Only):

AK1.01 Containment pressure: Mark III CFR: 41.8-141.10 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 X Ability to determine and/or interpret the 4.1* 24 following as they apply to Incomplete Scram:

AA2.02 Control rod position CFR: 41.10 295017 High Off-site Release Rate / 9 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 3.4 25 Suppression Pool Water Level and the following:

EK 2.06 SRVs and discharge piping CFR: 41.7 295032 High Secondary Containment Area Temperature / 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 X Ability to operate and/or monitor the following 2.8 26 Sump/Area Water Level / 5 as they apply to Secondary Containment High Sump/Area Water Level:

EA1.03 Radwaste CFR: 41.7 500000 High CTMT Hydrogen Conc. / 5 X Knowledge of the reasons for the following 3.0 27 responses as they apply to High Primary Containment Hydrogen Concentrations:

EK3.03 Operation of hydrogen and oxygen recombiners CFR: 41.5 K/A Category Point Totals: 1 1 2 1 1 1 Group Point Total: 7/3

ES-401 3 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 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X 2.4.6 Knowledge of EOP mitigation strategies. 4.7 83 CFR: 43.5 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 X Ability to determine and/or interpret the following 3.4 84 as they apply to Inadvertent Containment Isolation:

AA2.02 Drywell/containment temperature CFR: 43.5 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment X Ability to determine and/or interpret the following 4.2 85 Ventilation High Radiation / 9 as they apply to Secondary Containment Ventilation High Radiation:

EA2.01 Ventilation radiation levels CFR: 43.5 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 2 1 Group Point Total: 7/3

ES-401 4 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 A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection X Knowledge of the operational 3.5 28 Mode implications of the following concepts as they apply to RHR/LPCI: Injection Mode (Plant Specific):

K5.02 Core cooling methods CFR: 41.5 205000 Shutdown Cooling X Knowledge of the electrical power 3.1* 29 supplies to the following:

K2.01 Pump motors CFR: 41.7 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS X X Ability to (a) predict the impacts of the 3.2 30 following on the Low Pressure Core Spray System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.06 Inadequate system flow CFR: 41.5 Ability to manually operate and/or 2.7 31 monitor in the control room:

A4.07 Fill pump CFR: 41.7 209002 HPCS X Knowledge of the physical connections 3.8 32 and/or cause-effect relationships between High Pressure Core Spray System (HPCS) and the following:

K1.04 HPCS diesel generator: BWR-5,6 CFR: 41.2-41.9 211000 SLC X Ability to predict and/or monitor changes 4.0* 33 in parameters associated with operating the Standby Liquid Control System controls including:

A1.09 SBLC system lineup CFR: 41.5

212000 RPS X X Knowledge of the effect that a loss or 4.0 34 malfunction of the Reactor Protection System will have on the following:

K3.06 Scram air header solenoid operated valves CFR: 41.7 2.1.28 Knowledge of the purpose and 4.1 35 function of major system components and controls.

CFR: 41.7 215003 IRM X Knowledge of the operational 2.6 36 implications of the following concepts as they apply to Intermediate Range Monitor (IRM) System:

K5.01 Detector operation CFR: 41.5 215004 Source Range Monitor X Knowledge of the effect that a loss or 3.2 37 malfunction of the following will have on the Source Range Monitor (SRM) System:

K6.01 RPS CFR: 41.7 215005 APRM / LPRM X Knowledge of the physical connections 3.6 38 and/or cause-effect relationships between Average Power Range Monitor/Local Power Range Monitor System and the following:

K1.09 Reactor recirculation system:

BWR-5,6 CFR: 41.2-41.9 217000 RCIC X Ability to monitor automatic operations 3.7 39 of the Reactor Core Isolation Cooling System (RCIC) including:

A3.03 System pressure CFR: 41.7 218000 ADS X Knowledge of the effect that a loss or 3.4 40 malfunction of the following will have on the Automatic Depressurization System:

K6.07 Primary containment instrumentation CFR: 41.7 223002 PCIS/Nuclear Steam X Knowledge of Primary Containment 3.3 41 Supply Shutoff Isolation System/Nuclear Steam Supply Shut-Off design feature(s) and/or interlocks which provide for the following:

K4.08 Manual defeating of selected isolations during specified emergency conditions.

CFR: 41.7

239002 SRVs X Ability to manually operate and/or 3.6 42 monitor in the control room:

A4.02 Tail pipe temperatures CFR: 41.7 259002 Reactor Water Level X X Knowledge of Reactor Water Level 3.4 43 Control Control System design feature(s) and/or interlocks which provide for the following:

K4.10 Three element control (main steam flow, reactor feedwater flow, and reactor water level provide input)

CFR: 41.7 2.1.32 Ability to explain and apply system 3.8 44 limits and precautions.

CFR: 41.10 261000 SGTS X Ability to predict and/or monitor changes 3.1 45 in parameters associated with operating the Standby Gas Treatment System controls including:

A1.02 Primary containment pressure CFR: 41.5 262001 AC Electrical X Knowledge of the effect that a loss or 3.5 46 Distribution malfunction of the A.C. Electrical Distribution will have on the following:

K3.01 Major system loads CFR: 41.7 262002 UPS (AC/DC) X Ability to monitor automatic operations 2.8 47 of the Uninterruptable Power Supply (A.C./D.C.) including:

A3.01 Transfer from preferred to alternate source.

CFR: 41.7 263000 DC Electrical X X Ability to predict and/or monitor changes 2.5 48 Distribution in parameters associated with operating the D.C. Electrical Distribution controls including:

A1.01 Battery charging/discharging rate CFR: 41.5 2.4.31 Knowledge of annunciator alarms, 4.2 49 indications, or response procedures.

CFR: 41.10

264000 EDGs X X Knowledge of the physical connections 3.2 50 and/or cause-effect relationships between Emergency Generators (Diesel/Jet) and the following:

K1.04 Emergency generator cooling water system.

CFR: 41.2-41.9 Ability to (a) predict the impacts of the following on the Emergency Generators 3.4 51 (Diesel/Jet); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.06 Opening normal and/or alternate power to emergency bus.

CFR: 41.5 300000 Instrument Air X Knowledge of the electrical power 3.0 52 supplies to the following:

K2.02 Emergency air compressor CFR: 41.7 400000 Component Cooling X Ability to manually operate and/or 3.1 53 Water monitor in the control room:

A4.01 CCW indications and control CFR: 41.7 K/A Category Point Totals: 3 2 2 2 2 2 3 2 2 3 3 Group Point Total: 26/5

ES-401 4 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 A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS 209002 HPCS 211000 SLC X Ability to (a) predict the impacts of the 3.4* 86 following on the Standby Liquid Control System; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations:

A2.03 A.C. power failures 212000 RPS 215003 IRM 215004 Source Range Monitor 215005 APRM / LPRM 217000 RCIC 218000 ADS X 2.2.40 Ability to apply Technical 4.7 87 Specifications for a system.

CFR: 43.2, 43.5 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs X Ability to (a) predict the impacts of the 4.3* 88 following on the Relief/Safety Valves; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations:

A2.06 Reactor high pressure 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution

262002 UPS (AC/DC) X Ability to (a) predict the impacts of the 2.7 89 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:

A2.02 Over voltage 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling X 2.4.11 Knowledge of abnormal condition 4.2 90 Water procedures.

CFR: 43.5 K/A Category Point Totals: 3 2 Group Point Total: 26/5

ES-401 5 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 A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic X Knowledge of electrical power 4.5* 54 supplies to the following:

K2.05 Alternate rod insertion valve solenoids: Plant-Specific CFR: 41.7 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS X Ability to (a) predict the impacts of 3.7 55 the following on the Rod Control and Information System (RCIS); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.12 Rod uncoupled: BWR-6 CFR: 41.5 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control X Ability to predict and/or monitor 3.4 56 changes in parameters associated with operating the Recirculation Flow Control System controls including:

A1.08 Recirculation FCV position 204000 RWCU X Ability to manually operate and/or 2.8 57 monitor in the control room:

A4.04 Heat exchanger operation CFR: 41.7 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling X Ability to monitor automatic 3.3 58 Mode operations of the RHR/LPCI:

Torus/Suppression Pool Cooling Mode including:

A3.01 Valve operation CFR: 41.7 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode

233000 Fuel Pool Cooling/Cleanup X Knowledge of Fuel Pool Cooling and 2.9 59 Clean-Up design feature(s) and/or interlocks which provide for the following:

K4.06 Maintenance of adequate pool level.

CFR: 41.7 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate X Knowledge of the effect that a loss 3.2 60 or malfunction of the Reactor Condensate System will have on the following:

K3.02 CRD hydraulics system CFR: 41.7 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas X Knowledge of the operational 2.7 61 implications of the following concepts as they apply to Offgas System:

K5.07 Radioactive decay CFR: 41.7 272000 Radiation Monitoring 286000 Fire Protection X Knowledge of the physical 2.9 62 connections and/or cause-effect relationships between Fire Protection System and the following:

K1.03 Reactor water level CFR: 41.2-41.9 288000 Plant Ventilation X 2.1.30 Ability to locate and operate 4.4 63 components, including local controls.

CFR: 41.7 290001 Secondary CTMT X Knowledge of the effect that a loss 3.9 64 or malfunction of the following will have on the Secondary Containment:

K6.04 Primary containment system CFR: 41.7 290003 Control Room HVAC 290002 Reactor Vessel Internals X Knowledge of the physical 3.1 65 connections and/or cause-effect relationships between Reactor Vessel Internals and the following:

K1.06 HPCS: Plant-Specific CFR: 41.2-41.9

K/A Category Point Totals: 2 1 1 1 1 1 1 1 1 1 1 Group Point Total: 12/3 ES-401 5 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 A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive X Ability to (a) predict the impacts of 3.4 91 Mechanism the following on the Control Rod and Drive Mechanism; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations:

A2.09 Low reactor pressure 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux. X Ability to (a) predict the impacts of 4.1* 92 the following on the Primary Containment System and Auxiliaries; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.06 High containment pressure:

Mark-III 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate

259001 Reactor Feedwater X 2.4.46 Ability to verify that the 4.2 93 alarms are consistent with the plant conditions.

CFR: 43.5 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals: 2 1 Group Point Total: 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.2 Knowledge of operator responsibilities during all modes of 4.1 66 plant operation.

1.

CFR: 41.10 Conduct of Operations 2.1.15 Knowledge of administrative requirements for temporary 2.7 67 management directives, such as standing orders, night orders, operations memos, etc.

CFR: 41.10 2.1.44 Knowledge of RO duties in the control room during fuel 3.9 68 handling such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

CFR: 41.10 2.1.4 Knowledge of individual licensed operator 3.8 94 responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

CFR: 43.2 2.1.41 Knowledge of the refueling process. 3.7 95 CFR: 43.6 Subtotal 3 2 2.2.6 Knowledge of the process for making changes to 3.0 69 procedures.

CFR: 41.10 2.

Equipment 2.2.14 Knowledge of the process for controlling equipment 3.9 70 Control configuration or status.

CFR: 41.10 2.2.7 Knowledge of the process for conducting special or 3.6 96 infrequent tests.

CFR: 43.3 2.2.20 Knowledge of the process for managing 3.8 97 troubleshooting activities.

CFR: 43.5 Subtotal 2 2 2.3.12 Knowledge of radiological safety principles pertaining to 3.2 71 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to

3. locked high-radiation areas, aligning filters, etc.

Radiation CFR: 41.12

Control 2.3.14 Knowledge of radiation or contamination hazards that 3.4 72 may arise during normal, abnormal, or emergency conditions or activities.

CFR: 41.12 2.3.11 Ability to control radiation releases. 4.3 98 CFR: 43.4 Subtotal 2 1 2.4.5 Knowledge of the organization of the operating 3.7 73 procedures network for normal, abnormal, and

4. emergency evolutions.

Emergency CFR: 41.10 Procedures /

Plan 2.4.13 Knowledge of crew roles and responsibilities during EOP 4.0 74 usage.

CFR: 41.10 2.4.37 Knowledge of the lines of authority during implementation 3.0 75 of the emergency plan.

CFR: 41.10 2.4.22 Knowledge of the bases for prioritizing safety 4.4 99 functions during abnormal/emergency operations.

CFR: 43.5 2.4.42 Knowledge of emergency response facilities. 3.8 100 Subtotal 3 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 1/1 RO 295021 AK3.04 This function is not performed in the off-normal procedure.

Randomly reselected KA 295021 AK3.05 1/2 RO 295029 EK2.05 This KA is rejected because it refers to a component not used in the River Bend Station design. Randomly reselected KA 295029 EK2.06 1/2 RO 500000 EK3.05 This KA is rejected because it refers to a component not used in the River Bend Station design. Randomly reselected KA 500000 EK3.03 2/2 RO 202002 A1.01 This KA is rejected because no credible tie for this KA exists for the system. Randomly reselected KA 202002 A1.08 2/2 RO 286000 K1.05 This KA is rejected because no credible tie for this KA exists for the system. Randomly reselected KA 286000 K1.03 1/1 SRO 295030 G.2.4.2 This KA rejected due to inability to write an SRO-only question for this RO level knowledge KA (EOP entry conditions). Randomly reselected KA 295030 G.2.4.50 2/1 SRO 400000 G.2.2.37 This KA rejected because no credible tie for this KA exists for the system. (CCW is not safety related, therefore no operability requirements).Randomly reselected 400000 G.2.4.11.

1/1 SRO 295025 EA 2.06 This KA rejected due to oversampling (compare with Q80).

Randomly reselected 296016 AA2.01

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 3/24/2014 Examination Level: RO SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

(A1) Perform Jet Pump Operability (STP-053-3001)

Conduct of Operations R, M KA 2.1.20, 2.1.25 (A2) Verify Thermal Power and Loop Flow for Single R, N Loop Ops per GOP-0004 Steps 4.1-4.3 Conduct of Operations KA 2.1.7 (A3) Perform Hand Written Tagout for HVT-UC12 R, N Turbine Building Unit Cooler Equipment Control KA 2.2.13 (A4) Determine Radiological Brief and Protective R, N Clothing Requirements Radiation Control KA 2.3.7 Emergency Procedures/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)

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 3/24/2014 Examination Level: RO SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

(A5) Determine the Heat Up Rate and the Time to Top Conduct of Operations R, N of Active Fuel during a Loss of Shutdown Cooling KA 2.1.25 (A6) Determine personnel callout availability R, M Conduct of Operations KA 2.1.5 (A7) Review manual Tagout of HVT-UC12.

R, N Equipment Control KA 2.2.13 (A8) Determine if a worker is allowed to perform work R, N without exceeding administrative dose limit Radiation Control KA 2.3.7 (A9) Classify an Emergency R, N Emergency Procedures/Plan KA 2.4.30 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)

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 3/24/2014 Exam Level: RO SRO-I SRO-U Operating Test No.: ______________

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. (S1) Initiate RCIC for level control A,E,L,N,S 4
b. (S2) Perform STP to Slow Stroke the MSIVs N,S 3
c. (S3) Alternate Feedwater Level Control channels A,N,S 2
d. (S4) Parallel offsite power source to standby diesel generator D,S 6
e. (S5) Initiate Standby Liquid Control A,E,L,N,S 1
f. (S6) Emergency operation of containment coolers with Service water D,E,S,EN 5
g. (C1) Defeating Offgas high radiation isolation interlock C,D,E,L 9
h. (C2) Bypass an LPRM C,D 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. (P1) Alternating Control Building chilled water pump and chiller within D,EN 9 the standby division
j. (P2) Cross connecting DG air receivers within a single division N 6
k. (P3) Align Instrument Air diesel air compressor backup to safety A,D,E,L,R 8 relief valve header

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 4 (C)ontrol room (D)irect from bank 9/ 8/ 46 (E)mergency or abnormal in-plant 1/ 1/ 15 (EN)gineered safety feature - / - / 1 (control room system) -

(L)ow-Power / Shutdown 1/ 1/ 14 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 15 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1/ 1/ 11 (S)imulator

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 3/24/2014 Exam Level: RO SRO-I SRO-U Operating Test No.: ______________

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. (S1) Initiate RCIC for level control A.E,L,N,S 4
b. (S2) Perform STP to Slow Stroke the MSIVs N,S 3
c. (S3) Alternate Feedwater Level Control channels A,N,S 2 Instant does not perform S4
e. (S5) Initiate Standby Liquid Control A,E,L,N,S 1
f. (S6) Emergency operation of containment coolers with Service water D,E,S,EN 5
g. (C1) Defeating Offgas high radiation isolation interlock C,D,E,L 9
h. (C2) Bypass an LPRM C,D 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. (P1) Alternating Control Building chilled water pump and chiller within D,EN 9 the standby division
j. (P2) Cross connecting DG air receivers within a single division N 6
k. (P3)Align Instrument Air diesel air compressor backup to safety A,D,E,L,R 8 relief valve header

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 4 (C)ontrol room (D)irect from bank 9/ 8/ 45 (E)mergency or abnormal in-plant 1/ 1/ 15 (EN)gineered safety feature - / - / 1 (control room system) -

(L)ow-Power / Shutdown 1/ 1/ 14 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 5 (3 AP)

(P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1/ 1/ 11 (S)imulator

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 3/24/2014 Exam Level: RO SRO-I SRO-U Operating Test No.: ______________

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function (S1) Initiate RCIC for level control A.E,L,N,S 4 (S6) Emergency operation of containment coolers with Service water D,E,S,EN 5 (C1) Defeating Offgas high radiation isolation interlock C,D,E,L 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

(P2) Cross connecting DG air receivers within a single division N 6 (P3) Align Instrument Air diesel air compressor backup to safety relief A,D,E,L,R 8 valve header

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 2 (C)ontrol room (D)irect from bank 9/ 8/ 4 3 (E)mergency or abnormal in-plant 1/ 1/ 1 4 (EN)gineered safety feature - / - / 1 (control room system) 1 (L)ow-Power / Shutdown 1/ 1/ 1 3 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 2 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1/ 1/ 1 1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 IC No.: 210 Examiners: Theresa Buchanan Operators: _____________________________

Steve Garchow _____________________________

Mike Bloodgood _____________________________

Initial Conditions: 100% reactor power.

APRM B is bypassed to support I&C testing Turnover Shift priorities: 1) Perform STP-257-0201 Event Malf. Event Event No. No. Type* Description 1 NA N (SRO, BOP) Perform STP-257-0201, SBGT Operability Test 2 CRDM2045 C (SRO, ATC) Control Rod Drift Out, rod 20-45 (Tech Spec) 3 NMS011F I (SRO, ATC) APRM F fails upscale (Tech Spec)

GMC002A I (BOP) Stator Cooling Water Pump A trips, B fails to auto start 4

GMC001B 5 MSS005N C (SRO, BOP) Safety Relief Valve 51G fails open R (ATC) 6 NA M (ALL) Reactor scram with uncontrolled pressure drop 7 FWS004B C (ATC) FW master controller output fails high (triggered 1 minute after Mode Switch) 8 MSS018 C (SRO, BOP) B21-AOVF022A & B21-F028A fail to close MSS019 with MSS004 Steam Leak outside primary containment

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) Rod Drift, APRM F, Stator Cooling, SRV open, FW Master controller failure, MSIV failure Malfunctions after EOP entry (1-2) (2) FW Master controller, B21-AOVF022A & B21-AOVF028A Abnormal Events (2-4) (4) SOP-0061, AOP-0035, AOP-0001, AOP-0003 Major Transients (1-2) (1) Reactor scram with uncontrolled pressure drop EOPs entered (1-2) (2) EOP-0001, EOP-0002 EOP contingencies (0-2) (1) Enter EOP-0002 Critical Tasks (2-3) (2) Mode switch to Shutdown by 110°F; Close Main Steam Stop Valve, B21-F098A

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 2 IC No.: 207 Examiners: Theresa Buchanan Operators: _____________________________

Steve Garchow _____________________________

Mike Bloodgood _____________________________

Initial Conditions: Reactor power 70%, RCIC tagged out FWS-P1A tagged out, Feed Reg Valves B & C in service, CRD-P1A tagged out Fuel shuffle in Spent Fuel Pool ongoing Turnover Shift priorities: 1) Place 3rd Feedwater Reg Valve in service.

2) Raise power with control rods.

Event Malf. Event Type* Event No. No. Description rd 1 NA N (SRO, BOP) Place 3 Feedwater Regulating Valve in service.

2 NA R (ATC) Raise power with control rods.

3 p601_16a:h-5 I (SRO, BOP) E22-N654C fails upscale (CST High Level) - (Tech Spec)

LO_E22-D2-A Manual action to align HPCS Suction to Supp Pool 4 RCS002B C (SRO,ATC) Trip of Recirc Pump B (Tech Spec) 5 RPS003A C(ALL) Loss of RPS A 6 ED002B M (ALL) Loss of NPS-SWG1B/Loss of Feedwater RPS001A Failure to Scram-All Signals ARI effective 7 CRD001B C (SRO) CRD Pump B trip 8 HPCS005 C (SRO, BOP) HPCS suction strainer blockage HPCS001 HPCS pump trip (delay 1:10)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (7) CST Level Instrument Failure, Recirc Pump trip, Loss of RPS, Loss of NPS SWG1B, Failure to Scram, CRD, HPCS Malfunctions after EOP entry (1-2) (2) CRD, HPCS Abnormal Events (2-4) (4) AOP-0024, AOP-0010, AOP-0001, AOP-0002 Major Transients (1-2) (1) Loss of NPS-SWGR1B/Loss of Feed EOPs entered (1-2) (1) EOP-0001 EOP contingencies (0-2) (1) Alternate Level Control Critical Tasks (2-3) (2) Initiate ARI, Emergency Depressurize

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 3 IC No.: 208 Examiners: Theresa Buchanan Operators: _____________________________

Steve Garchow _____________________________

Mike Bloodgood _____________________________

Initial Conditions: Reactor power 70%.

CRD-A, HDL-P1B & C, CCP-P1A & B running Accumulator Fault on Control Rod 28 Maintenance package in progress Turnover Shift priorities 1) Rotate RPCCW pumps,

2) Lower Reactor Power Event Malf. Event Type* Event No. No. Description 1 NA N (SRO, BOP) Rotate RPCCW pumps.

2 NA R (ATC) Lower reactor power with control rods to 65%.

3 CCP001C C (BOP) CCP-P1C trips; P1B fails to auto start CCP004B 4 ED003A Loss of NNS-SWGR1A C (ALL)

DG002C Div 3 EDG fails to start (Tech Spec) 5 CRD016 C (SRO, ATC) CRD suction filter clogging and pump trip (Tech Spec) trigger initiated on CRD-P1B pump start (ramped to 97% over 2 min, 30sec)

{Remove Malfunction after ATWS - role play}

6 CRD014 M (ALL) Anticipated Transient without Scram (Hydraulic Lock) [83%]

7 TMS003 C (SRO, ATC) Main Turbine High Vibration requiring a manual Turbine Trip 8 AI_E51-R600- C (SRO, BOP) RCIC Flow Controller Fails Low - requires manual operation.

CTW

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