ML15007A173

2014-12 Draft Outlines

ML15007A173
Person / Time
Site:	River Bend
Issue date:	12/12/2014
From:	Vincent Gaddy Operations Branch IV
To:
laura hurley
References
Download: ML15007A173 (27)

Text

SUPPRESSED KAs AND JUSTIFICATION 2.0 GENERIC KAs:

2.2.3 & 2.2.4 Multi-unit KAs not applicable to the single unit RBS facility.

3.1 REACTIVITY CONTROL SYSTEMS KAs:

201002 Reactor Manual Control System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at River Bend.

3.2 INVENTORY CONTROL SYSTEMS KAs:

206000 High Pressure Core Injection (HPCI) - All KAs in this section were suppressed. This system is not part of the RBS GE BWR-6 design. HPCS provides this function at River Bend.

3.4 HEAT REMOVAL SYSTEMS KAs:

206000 High Pressure Core Injection (HPCI) - All KAs in this section were suppressed. This system is not part of the RBS GE BWR-6 design. HPCS provides this function at River Bend.

207000 Isolation (Emergency) Condenser - All KAs in this section were suppressed. This system is not part of the RBS GE BWR-6 design. RCIC provides this function at River Bend.

3.5 CONTAINMENT INTEGRITY SYSTEMS KAs:

226001 RHR/LPCI: Containment Spray Mode - All KAs in this section were suppressed. This system is not part of the RBS GE BWR-6 Mark III Containment design.

230000 RHR/LPCI: Torus/Pool Spray Mode - All KAs in this section were suppressed. This system is not part of the RBS GE BWR-6 Mark III Containment design.

3.7 INSTRUMENTATION SYSTEMS KAs SUPPRESSED:

215002 Rod Block Monitor System - All KAs in this section were suppressed.

The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

214000 Rod Position Information System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

201004 Rod Sequence Control System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

201006 Rod Worth Minimizer System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

ES-401 BWR Examination Outline Form ES-401-1 Facility: River Bend Station Date of Exam: December 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 4 4 3 3 3 3 20 3 4 7 Emergency & N/A N/A Abnormal Plant 2 1 2 1 1 1 1 7 2 1 3 Evolutions Tier Totals 5 6 4 4 4 4 27 5 5 10 1 2 3 2 2 3 2 2 2 3 3 2 26 3 2 5 2.

Plant 2 1 1 1 2 1 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 3 4 3 4 4 3 3 3 4 4 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 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 AK2.02 Knowledge of the interrelations between 295001 Partial or Complete Loss of Forced R PARTIAL OR COMPLETE LOSS OF FORCED 3.2 1 Core Flow Circulation / 1 & 4 CORE FLOW CIRCULATION and the following:

Nuclear boiler instrumentation 295003 Partial or Complete Loss of AC / 6 AK1.04 Knowledge of the operational implications 295004 Partial or Total Loss of DC Pwr / 6 R of the following concepts as they apply to PARTIAL 2.8 2 OR COMPLETE LOSS OF DC POWER : Effect of battery discharge rate on capacity G2.2.44 Ability to interpret control room indications S to verify the status and operation of a system, and 4.4 76 understand how operator actions and directives affect plant and system conditions.

AK2.07 Knowledge of the interrelations between 295005 Main Turbine Generator Trip / 3 R MAIN TURBINE GENERATOR TRIP and the 3.6 3 following: Reactor pressure control AK3.03 Knowledge of the operational implications 295006 SCRAM / 1 R of the following concepts as they apply to SCRAM: 3.8 4 Reactor pressure response S G2.4.2 Knowledge of system set points, interlocks 4.6 77 and automatic actions associated with EOP entry conditions.

A1.06 Knowledge of the operational implications of 295016 Control Room Abandonment / 7 R the following concepts as they apply to CONTROL 4.0 5 ROOM ABANDONMENT : Reactor water level A2.04 Ability to determine and/or interpret the 295018 Partial or Total Loss of CCW / 8 R following as they apply to PARTIAL OR 2.9 6 COMPLETE LOSS OF COMPONENT COOLING WATER : System flow G2.4.47 Ability to diagnose and recognize trends in 295019 Partial or Total Loss of Inst. Air / 8 R an accurate and timely manner utilizing the 4.2 7 appropriate control room reference material.

AK1.03 Knowledge of the operational implications 295021 Loss of Shutdown Cooling / 4 R of the following concepts as they apply to LOSS 3.9 8 OF SHUTDOWN COOLING : Adequate core cooling S 3.6 78 AA2.04 Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING : Reactor water temperature AK2.05 Knowledge of the interrelations between 295023 Refueling Acc / 8 R REFUELING ACCIDENTS and the following: 3.5 9 Secondary containment ventilation EK3.04 Knowledge of the reasons for the following 295024 High Drywell Pressure / 5 R responses as they apply to HIGH DRYWELL 3.7 10 PRESSURE: Emergency depressurization EA1.05 Ability to operate and/or monitor the 295025 High Reactor Pressure / 3 R following as they apply to HIGH REACTOR 3.7 11 PRESSURE: RCIC: Plant-Specific EA2.03 Ability to determine and/or interpret the 295026 Suppression Pool High Water R following as they apply to SUPPRESSION POOL 3.9 12 Temp. / 5 HIGH WATER TEMPERATURE: Reactor pressure G2.4.20 Knowledge of the operational implications 295027 High Containment Temperature / 5 R of EOP warnings, cautions, and notes. 3.8 13

EK1.01 Knowledge of the operational implications 295028 High Drywell Temperature / 5 R of the following concepts as they apply to HIGH 3.5 14 DRYWELL TEMPERATURE: Reactor water level measurement G2.4.21 Knowledge of the parameters and logic S used to assess the status of safety functions, such 4.6 79 as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

EK2.08 Knowledge of the interrelations between 295030 Low Suppression Pool Wtr Lvl / 5 R LOW SUPPRESSION POOL WATER LEVEL and 3.5 15 the following: SRV discharge submergence EK2.03 Knowledge of the interrelations between 295031 Reactor Low Water Level / 2 R REACTOR LOW WATER LEVEL and the 4.2 16 following: Low pressure core spray S EA2.04 Ability to determine and/or interpret the 4.8 80 following as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling EA1.06 Ability to operate and/or monitor the 295037 SCRAM Condition Present R following as they apply to SCRAM CONDITION 4.1 17 and Reactor Power Above APRM PRESENT AND REACTOR POWER ABOVE Downscale or Unknown / 1 APRM DOWNSCALE OR UNKNOWN: Neutron monitoring system EA2.03 Ability to determine and/or interpret the 295038 High Off-site Release Rate / 9 R following as they apply to HIGH OFF-SITE 3.5 18 RELEASE RATE: Radiation levels AA2.16 Ability to determine and interpret the 600000 Plant Fire On Site / 8 S following as they apply to PLANT FIRE ON SITE: 3.5 81 Vital equipment and control systems to be maintained and operated during a fire R G2.4.11 Knowledge of abnormal condition 4.0 19 procedures AK1.03 Knowledge of the operational implications 700000 Generator Voltage and Electric Grid R of the following concepts as they apply to 3.3 20 Disturbances / 6 GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Under-excitation G2.2.37 Ability to determine operability and/or S availability of safety related equipment. 4.6 82 K/A Category Totals (RO): 4 4 3 3 3 3 Group Point Total: 20 K/A Category Totals (SRO): 3 4 Group Point Total: 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 AK2.01 Knowledge of the interrelations between 295007 High Reactor Pressure / 3 R HIGH REACTOR PRESSURE and the following: 3.5 21 Reactor/turbine pressure regulating system AA2.05 Ability to determine and/or interpret the 295008 High Reactor Water Level / 2 R following as they apply to HIGH REACTOR WATER 2.9 22 LEVEL: Swell 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 G2.4.50 Ability to verify system alarm setpoints and 295011 High Containment Temp / 5 R operate controls identified in the alarm response 4.2 23 manual.

AK1.02 Knowledge of the operational implications of 295012 High Drywell Temperature / 5 R the following concepts as they apply to HIGH 3.1 24 DRYWELL TEMPERATURE : Reactor power level control AK2.01 Knowledge of the interrelations between 295013 High Suppression Pool Temp. / 5 R HIGH SUPPRESSION POOL TEMPERATURE and 3.6 25 the following: Suppression pool cooling 295014 Inadvertent Reactivity Addition / 1 AA2.02 Ability to determine and/or interpret the 295015 Incomplete SCRAM / 1 S following as they apply to INCOMPLETE SCRAM : 4.2 83 Control rod position 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 EK3.03 Knowledge of the reasons for the following 295029 High Suppression Pool Wtr Lvl / 5 R responses as they apply to HIGH SUPPRESSION 3.4 26 POOL WATER LEVEL : Reactor SCRAM S G2.2.25 Knowledge of the bases in Technical 4.2 84 Specifications for limiting conditions for operations and safety limits.

EA1.01 Ability to operate and/or monitor the 295032 High Secondary Containment R following as they apply to HIGH SECONDARY 3.6 27 Area Temperature / 5 CONTAINMENT AREA TEMPERATURE : Area temperature monitoring system 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 EA2.03 Ability to determine and / or interpret the 500000 High CTMT Hydrogen Conc. / 5 S following as they apply to HIGH PRIMARY 3.8 85 CONTAINMENT HYDROGEN CONCENTRATIONS: Combustible limits for drywell K/A Category Point Totals (RO): 1 2 1 1 1 1 Group Point Total: 7 K/A Category Point Totals (SRO): 2 1 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 K4.09 Knowledge of RHR/LPCI: INJECTION 203000 RHR/LPCI: Injection R MODE (PLANT SPECIFIC) design feature(s) 3.1 28 Mode and/or interlocks which provide for the following: Surveillance for all operable components K5.02 Knowledge of the operational 205000 Shutdown Cooling R implications of the following concepts as 2.8 29 they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) : Valve operation S A2.03 Ability to (a) predict the impacts of the 3.2 86 following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C.

failure 206000 HPCI N/A for RBS 207000 Isolation (Emergency) N/A for RBS Condenser K6.03 Knowledge of the effect that a loss or 209001 LPCS R malfunction of the following will have on the 3.3 30 LOW PRESSURE CORE SPRAY SYSTEM :

Torus/suppression pool water level A3.03 Ability to monitor automatic R operations of the LOW PRESSURE CORE 3.5 31 SPRAY SYSTEM including: System pressure A1.08 Ability to predict and/or monitor 209002 HPCS R changes in parameters associated with 3.1 32 operating the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) controls including:

System lineup: BWR-5,6 K5.06 Knowledge of the operational 211000 SLC R implications of the following concepts as 3.0 33 they apply to STANDBY LIQUID CONTROL SYSTEM: Tank level measurement A2.03 Ability to (a) predict the impacts of the R following on the STANDBY LIQUID 3.2 34 CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A.C. power failures 212000 RPS R A3.06 Ability to monitor automatic 4.2 35 operations of the REACTOR PROTECTION SYSTEM including: Main turbine trip: Plant-Specific G2.2.12 Knowledge of surveillance S 4.1 87 procedures.

215003 IRM R A4.05 Ability to manually operate and/or 3.4 36 monitor in the control room: Trip bypasses

215004 Source Range Monitor R K2.01 Knowledge of electrical power 2.6 37 supplies to the following: SRM channels/detectors G2.4.4 Ability to recognize abnormal indications for system operating parameters R that are entry-level conditions for emergency 4.5 38 and abnormal operating procedures.

215005 APRM / LPRM R K1.09 Knowledge of the physical 3.6 39 connections and/or cause-effect relationships between AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: Reactor recirculation system:

BWR-5,6 A2.02 Ability to (a) predict the impacts of the S following on the AVERAGE POWER 3.7 88 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: Upscale or downscale trips 217000 RCIC R K2.01 Knowledge of electrical power 2.8 40 supplies to the following: Motor operated valves 218000 ADS R K3.02 Knowledge of the effect that a loss or 4.5 41 malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following: Ability to rapidly depressurize the reactor A4.02 Ability to manually operate and/or R monitor in the control room: ADS logic 4.2 42 initiation 223002 PCIS/Nuclear Steam R K4.01 Knowledge of PRIMARY 3.0 43 Supply Shutoff CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design feature(s) and/or interlocks which provide for the following:

Redundancy 239002 SRVs R K5.04 Knowledge of the operational 3.3 44 implications of the following concepts as they apply to RELIEF/SAFETY VALVES :

Tail pipe temperature monitoring A2.06 Ability to (a) predict the impacts of the S following on the RELIEF/SAFETY VALVES ; 4.3 89 and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Reactor high pressure 259002 Reactor Water Level R K6.03 Knowledge of the effect that a loss or 3.1 45 Control malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM : Main steam flow input 261000 SGTS R A1.01 Ability to predict and/or monitor 2.9 46 changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including: System flow

262001 AC Electrical R A2.11 Ability to (a) predict the impacts of the 3.2 47 Distribution following on the A.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Degraded system voltages G2.2.25 Knowledge of the bases in S Technical Specifications for limiting 4.2 90 conditions for operations and safety limits.

262002 UPS (AC/DC) R A3.01 Ability to monitor automatic 2.8 48 operations of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) including:

Transfer from preferred to alternate source 263000 DC Electrical R A4.01 Ability to manually operate and/or 3.3 49 Distribution monitor in the control room: Major breakers and control power fuses: Plant- Specific 264000 EDGs R K1.05 Knowledge of the physical 3.2 50 connections and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEL/JET) and the following: Emergency generator fuel oil supply system R G2.1.31 Ability to locate control room 4.6 51 switches, controls, and indications, and to l determine that they correctly reflect the desired plant lineup.

300000 Instrument Air R K2.02 Knowledge of electrical power 3.0 52 supplies to the following: Emergency air compressor 400000 Component Cooling R K3.01 Knowledge of the effect that a loss or 2.9 53 Water malfunction of the CCWS will have on the following: Loads cooled by CCWS K/A Category Point Totals (RO): 2 3 2 2 3 2 2 2 3 3 2 Group Point Total: 26 K/A Category Point Totals 3 2 Group Point Total: 5 (SRO):

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 N/A for RBS 201003 Control Rod and Drive R A4.02 Ability to manually operate 3.5 54 Mechanism and/or monitor in the control room:

CRD mechanism position: Plant-Specific 201004 RSCS N/A for RBS 201005 RCIS R A1.01 Ability to predict and/or monitor 3.2 55 changes in parameters associated with operating the ROD CONTROL AND INFORMATION SYSTEM (RCIS) controls including: First stage shell pressure/turbine load: BWR-6 G2.1.23 Ability to perform specific system and integrated plant procedures S 4.4 91 during all modes of plant operation.

201006 RWM 202001 Recirculation R K4.02 Knowledge of RECIRCULATION 3.1 56 System design feature(s) and/or interlocks which provide for the following: Adequate recirculation pump NPSH 202002 Recirculation Flow Control R K1.09 Knowledge of the physical 3.1 57 connections and/or cause-effect relationships between RECIRCULATION FLOW CONTROL SYSTEM and the following: Reactor water level 204000 RWCU S A2.02 Ability to (a) predict the impacts 3.2 92 of the following on the REACTOR WATER CLEANUP SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Pressure control valve failure: LP-RWCU 214000 RPIS N/A for RBS 215001 Traversing In-core Probe 215002 RBM N/A for RBS 216000 Nuclear Boiler Inst. R K6.01 Knowledge of the effect that a 3.1 58 loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION: A.C. electrical distribution 219000 RHR/LPCI: Torus/Pool Cooling R K2.02 Knowledge of electrical power 3.1 59 Mode supplies to the following: Pumps 223001 Primary CTMT and Aux. R G2.1.28 Knowledge of the purpose and 4.1 60 function of major system components and controls.

226001 RHR/LPCI: CTMT Spray Mode N/A for RBS 230000 RHR/LPCI: Torus/Pool Spray N/A for RBS Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam R K3.15 Knowledge of the effect that a 3.5 61 loss or malfunction of the MAIN AND REHEAT STEAM SYSTEM will have on following: Reactor water level control 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure R A2.01 Ability to (a) predict the impacts 3.5 62 Regulator of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of turbine inlet pressure signal 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring R K4.02 Knowledge of RADIATION 3.7 63 MONITORING System design feature(s) and/or interlocks which provide for the following: Automatic actions to contain the radioactive release in the event that the predetermined release rates are exceeded 286000 Fire Protection 288000 Plant Ventilation R A3.01 Ability to monitor automatic 3.8 64 operations of the PLANT VENTILATION SYSTEMS including:

Isolation/initiation signals 290001 Secondary CTMT S A2.04 Ability to (a) predict the impacts 3.7 93 of the following on the SECONDARY CONTAINMENT ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High airborne radiation 290003 Control Room HVAC R K5.01 Knowledge of the operational 3.2 65 implications of the following concepts as they apply to CONTROL ROOM HVAC: Airborne contamination (e.g.,

radiological, toxic gas, smoke) control 290002 Reactor Vessel Internals K/A Category Point Totals (RO): Group Point Total: 12 K/A Category Point Totals (SRO): Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: River Bend Station Date of Exam: December 2014 Category K/A # Topic RO SRO-Only IR # IR #

2.1.7 Ability to evaluate plant performance and make 4.4 66 operational judgments based on operating characteristics,

1. reactor behavior, and instrument interpretation.

Conduct 2.1.31 Ability to locate control room switches, controls, and 4.6 67 of Operations indications, and to determine that they correctly reflect the desired plant lineup.

2.1.40 Knowledge of refueling administrative requirements. 2.8 68 2.1.20 Ability to interpret and execute procedure steps. 4.6 94 2.1.36 Knowledge of procedures and limitations involved in core 4.1 95 alterations.

2.2.6 Knowledge of the process for making changes to 3.0 69 procedures.

2.2.14 Knowledge of the process for controlling equipment 3.9 70 2.

Equipment configuration or status.

Control 2.2.35 Ability to determine Technical Specification Mode of 3.6 71 Operation.

2.2.11 Knowledge of the process for controlling temporary 3.3 96 design changes.

2.2.38 Knowledge of conditions and limitations in the facility 4.5 97 license.

2.3.11 Ability to control radiation releases. 3.8 72 2.3.13 Knowledge of radiological safety procedures pertaining to 3.4 73 licensed operator duties, such as response to radiation 3.

Radiation monitor alarms, containment entry requirements, fuel Control handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.14 Knowledge of radiation or contamination hazards that 3.8 98 may arise during normal, abnormal, or emergency conditions or activities.

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

4.

2.4.26 Knowledge of facility protection requirements, including 3.1 75 Emergency fire brigade and portable fire fighting equipment usage.

Procedures /

Plan 2.4.16 Knowledge of EOP implementation hierarchy and 4.4 99 coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

2.4.44 Knowledge of emergency plan protective action 4.4 100 recommendations.

Subtotal Tier 3 Point Total

Note for Adams package:

There was no ES-401-4 form submitted with the Draft outline submittal because the NRC generated the initial outlines and the licensee made no changes to the outlines prior to outline submittal. There are changes documented in the draft and final exam submittals with the appropriate ES-401-4 form.

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 12/8/2014 Examination Level: RO SRO Operating Test Number: __________

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

(A1) Determine the amount of Decay Heat in the Core Conduct of Operations R, D per OSP-0041 KA 2.1.20 (4.6) Ability to interpret and execute procedure steps (A2) Determine corrected Fuel Zone Level Indication Conduct of Operations R, D KA 2.1.23 (4.3) Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(A3) Use plant drawings to determine effect(s) of fuse R, N removal Equipment Control KA 2.2.15 (3.9) Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.

(A4) Calculate dose/Determine DAC hours Radiation Control R, M KA 2.3.12 (3.2) 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.

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: 12/8/2014 Examination Level: RO SRO Operating Test Number: __________

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

(A5) Determine stay time for a hot environment Conduct of Operations R, M KA 2.1.26 (3.4) Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen, and hydrogen).

R, M (A6) Determine Actions for Reactor Water Chemistry Conduct of Operations KA 2.1.34 (3.5) Knowledge of primary and secondary plant chemistry limits.

R, N (A7) Determine Secondary Containment Operability Equipment Control KA 2.2.12 (4.1) Knowledge of surveillance procedures.

(A8) Determine required actions upon Radioactive Radiation Control R, D Effluent Monitor Failure KA 2.3.11 (4.3) Ability to control radiation releases.

(A9) Determine PAR Emergency Procedures/Plan R, M KA 2.4.44 (4.4) Knowledge of emergency plan protective action recommendations.

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: 12/8/2014 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) Pull Rods to Achieve Criticality - w/ trip of CRD pumps S,A,E,L,N 1

b. (S2) Start ARC Pump - w/ Separator Level Alarm S,A,D,L 2

c. (S3) Adjust Pressure Regulator to Minimize Recirc Pump Seal S,M 3 Thrust Reversal (GOP-0001)

d. (S4) Place Turbine on the Turning Gear (SOP-80 sect 4.2) S,A,L,N 4

e. (S5) Start DW High Volume Purge - after Low Volume Fan trips S,A,D,EN,L 9

f. (S6) Place Suppression Pool Cooling System in Service (SOP-140) S,D,L 5

g. (C1) Shed DC Loads for Station Blackout (AOP-50, Attach 3) C,D,E,L 6

h. (C2) Bypass Control Rod in RACS (STP-500-0705) C,D 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Vent Scram Air Header (Encl 11) R,D,E,EN 1

j. (P2) Supply Fire Protection Water for CB via SSW (SOP-37, sect 5.3) E,N 8

k. (P3) Transfer Div 3 125 VDC to Backup Charger A,E,L,N 6 (AOP-14, Sect 5.3 and SOP-49, Sect 5.11)

@ 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 5 (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) 2 (L)ow-Power / Shutdown 1/1/17 (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: 12/8/2014 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)

b. (S2) Start ARC Pump - w/ Separator Level Alarm S,A,D,L 2

c. (S3) Adjust Pressure Regulator to Minimize Recirc Pump Seal S,M 3 Thrust Reversal (GOP-0001)

d. (S4) Place Turbine on the Turning Gear (SOP-80 sect 4.2) S,A,L,N 4

e. (S5) Start DW High Volume Purge - after Low Volume Fan trips S,A,D,EN,L 9

f. (S6) Place Suppression Pool Cooling System in Service (SOP-140) S,D,L 5

g. (C1) Shed DC Loads for Station Blackout (AOP-50, Attach 3) C,D,E,L 6

h. (C2) Bypass Control Rod in RACS (STP-500-0705) C,D 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Vent Scram Air Header (Encl 11) R,D,E,EN 1

j. (P2) Supply Fire Protection Water for CB via SSW (SOP-37, sect 5.3) E,N 8

k. (P3) Transfer Div 3 125 VDC to Backup Charger A,E,L,N 6 (AOP-14, Sect 5.3 and SOP-49, Sect 5.11)

@ 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 1/1/14 (EN)gineered safety feature - / - / 1 (control room system) 2 (L)ow-Power / Shutdown 1/1/16 (N)ew or (M)odified from bank including 1(A) 2/2/14 (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: 12/8/2014 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)

b. (S2)

c. (S3) Adjust Pressure Regulator to Minimize Recirc Pump Seal S,M 3 Thrust Reversal (GOP-0001)

d. (S4)

e. (S5) Start DW High Volume Purge - after Low Volume Fan trips S,A,D,EN,L 9

f. (S6)

g. (C1) Shed DC Loads for Station Blackout (AOP-50, Attach 3) C,D,E,L 6

h. (C2)

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Vent Scram Air Header (Encl 11) R,D,E,EN 1

j. (P2)

k. (P3) Transfer Div 3 125 VDC to Backup Charger A,E,L,N 6 (AOP-14, Sect 5.3 and SOP-49, Sect 5.11)

@ 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 9/8/43 (E)mergency or abnormal in-plant 1/1/13 (EN)gineered safety feature - / - / 1 (control room system) 2 (L)ow-Power / Shutdown 1/1/13 (N)ew or (M)odified from bank including 1(A) 2/2/12 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1/1/11 (S)imulator

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-1 IC No.: 251 Examiners: ________________ Operators: _____________________________

Initial Conditions: 84% reactor power B21-SRV51C is leaking - resulting in slowly rising suppression pool level ADS-SRV Leaking Alarm is in Turnover Shift priorities: 1) Plant Shutdown in-progress due to leaking SRV; Reactor Engineering directs perform Step 2 of the RMP and then contact RE further guidance. 2) Perform SOP-0031, Section 4.8, Suppression Pool Reject to Radwaste Event Malf. Event Event No. No. Type* Description 0 MSS007K NA SRV 51C is leaking 1 NA R (ATC) Insert Control Rods per RMP step 2 2 NA N (SRO, BOP) Perform SOP-0031 Section 4.8, Suppression Pool Reject to Radwaste 3 RHR002A C (SRO, BOP) RHR A Pump Trip (Tech Spec) 4 FWS017A I (SRO, ATC) Steam Line Flow Transmitter A fails downscale (AOP-0006) 5 NA N (SRO,ATC) Perform SOP-0009 Section 6.3, Three Element to Single Element Control Transfer 6 ED003D C (SRO, ATC) Loss of NNS-SWG2A (AOP-0005) 7 CRDM2017 M (ALL) Reactor scram with turbine trip due to loss of vacuum CRDM3641 ATWS - 3 Control Rods CRDM4425 8 MSS005K C (SRO, BOP) Safety Relief Valve 51C fails open (AOP-0035) 9 RHS- C (BOP) RHS-AOV64 Fails to isolate.

AOV64P

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) RHR A Trip, MSL A Flow XMT, Loss NNS-SWG2A, SRV open, ATWS, RHS-AOV64 failure Malfunctions after EOP entry (1-2) (2) SRV open, failure to isolate Abnormal Events (2-4) (4), AOP-0006, AOP-0005, AOP-0035, AOP-0003 Major Transients (1-2) (1) Reactor scram with turbine trip due to loss of vacuum / 3 Control Rod ATWS EOPs entered (1-2) (2) EOP-0001/ EOP-0001A EOP contingencies (0-2) (1) Enter EOP-0001A Critical Tasks (2-3) (2) SRV closed; All control rods inserted

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-2 IC No.: 252 Examiners: ________________ Operators: _____________________________

Initial Conditions: 100% reactor power.

Turnover Shift priorities: 1) STP-309-0203 in progress; ready to unload and shutdown the HPCS DG per step 7.3 Event Malf. Event Type* Event No. No. Description 1 NA N (SRO, BOP) Unload the HPCS DG per STP-309-0203 Steps 7.3.1 through 7.3.4 2 DG001C C (SRO) HPCS DG trips 3 minutes after output breaker opens (T.S.)

zdi5(497)!=0 3 CCS001B C (SRO, BOP) CCS-P1B trips CCS-P1C fails to auto start (AOP-0012)

CCS003C 4 CNM004B C (SRO,ATC) CNM-P1B trips (RX) (AOP-0006)

R (ATC) 5 ED010 M (ALL) Loss RSS#1 result in loss of normal feedwater 6 RCIC002 C (SRO, BOP) RCIC fails to auto start and must be manually started E51MOVF013P RCIC Injection Valve limited to 2% open 7 MSS001 C (ALL) Steam Leak in Drywell leading to ED on lowering water level and restoration of level with low pressure ECCS

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) HPCS DG, CCS-P1B, CNM-P1B, Loss RSS#1, RCIC S/U, DW Leak, Malfunctions after EOP entry (1-2) (2) RCIC S/U, DW Leak, Abnormal Events (2-4) (2), AOP-0012, AOP-0006 Major Transients (1-2) (1) Reactor scram due to loss of normal feedwater EOPs entered (1-2) (2) EOP-0001, EOP-0002.

EOP contingencies (0-2) (1) Alternate level control Critical Tasks (2-3) (2) ED prior to -186; Restore RPV water level to -186

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-3 IC No.: 253 Examiners: ________________ Operators: _____________________________

Initial Conditions: 93% reactor power. HPCS tagged out for Line Fill Pump Maintenance.

Turnover Shift priorities: (1) Swap Stator Water Cooling Pumps (for tagout of GMC-P1A);

(2) Raise Reactor Power IAW RMP (using flow)

Event Malf. Event Event No. No. Type* Description 1 NA N (SRO, BOP) Swap Stator Water Cooling Pumps (from A to B) 2 NA R (ATC) Raise Reactor Power with Flow 3 B21003B I (SRO) RPV pressure transmitter N005, fails high (TS) 4 GMC002B C (SRO, BOP) Trip of Stator Water Cooling Pump B 5 RPS003B C (SRO,BOP) Loss of RPS-B 6 SWPMOV5AP C (SRO, BOP) Failure to isolate (SWP-MOV 5A) (TS) 7 GMC002A M (ALL) Trip of Stator Water Cooling Pump A - Requires Scram 8 MGEN003 C (ATC) Main Generator Reverse Power Relay Failure 9 CNM006 Condensate Filter High D/P - Loss of Feed C (SRO,BOP)

RCIC001 RCIC Turbine Trip (recoverable)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) GMC-B Trip, Press Xmitter, RPS-B, SWPMOV5A failure to isolate, GMC-A trip, Reverse Power Failure, Loss of Feed Malfunctions after EOP entry (1-2) (2) Reverse Power, RCIC Isolation Abnormal Events (2-4) (3), AOP-0010, AOP-0001, AOP-0002 Major Transients (1-2) (1) Reactor scram with Loss of Stator Water Cooling EOPs entered (1-2) (2) EOP-0001 EOP contingencies (0-2) (1) EOP-0001, Alternate Level Control Critical Tasks (2-3) (2) Inhibit ADS when RPV Level drops below -143 before level reaches -162 ;

Restore and maintain RPV level when RCIC is restored before RPV level reaches -186

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-4 IC No.: 254 Examiners: ________________ Operators: _____________________________

Initial Conditions: 80% reactor power. Performing Sequence Exchange; RHR-B is in Supp Pool Cooling and Containment Purge is in service for post-maintenance RCIC testing; Turnover Shift priorities: Start RCIC for testing Adjust MVARs Raise Reactor power in accordance with the RMP for sequence exchange; Event Malf. Event Event No. No. Type* Description 1 NA N (BOP) Start RCIC IAW SOP-0035, Section 4.2 2 NA N (SRO,ATC) Adjust MVAR on Main Generator to +100 IAW SOP-0080, section 5.9 3 NA R (ATC) Raise Power IAW RMP for sequence exchange 4 NMS011F I (SRO,ATC) APRM F fails upscale (TS) 5 CNM005H I (SRO,ATC) Condenser Hotwell Emergency Makeup Fails High 6 RCIC009 C (SRO,BOP) Spurious RCIC Isolation (TS) 7 RCIC004 M (ALL) Steam Leak in RCIC Room - Spreads to RHR-C (10 gpm ramped 5 min)

RMS215 RMS-RE213 or 214 or 215 Equipment Room Monitor 8 EHC002A C (SRO,ATC) Main Turbine Bypass Valves Fail Open 9 RCIC007 C (SRO,BOP) RCIC Steam Supply Isol Valves (F063 & 64) fail to shut RCIC008

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) APRM upscale, Hotwell Level, RCIC Trip, Steam Leak, BPV Failure, RCIC Isolation Failure Malfunctions after EOP entry (1-2) (2) BPVs, RCIC Isol Valves Abnormal Events (2-4) (3) AOP-0001, AOP-0002, RCIC Testing Failure Major Transients (1-2) (1) Steam Leak in RCIC Room - Spreading EOPs entered (1-2) (2) EOP-0001, EOP-0003 EOP contingencies (0-2) (1) EOP-0003 Critical Tasks (2-3) (2) BPVs closed before exceeding cooldown rate, ED before exceeding max safe Table H

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I IC #251 IC #252 IC #253 IC#254 L N T N I T CREW CREW CREW CREW I A

M C POSITION POSITION POSITION POSITION L U A T S A B S A B S A B S A B M(*)

N Y R T O R T O R T O R T O R I U T P O C P O C P O C P O C P E

RO RX - 0 1 1 0 NOR 2,5 2 1 1 1 SRO-I I/C 3,4,6 4 4 4 2 8

SRO-U MAJ 7 1 2 2 1

TS 3 1 0 2 2 RO RX 1 1 1 1 0 ATC NOR 5 1 1 1 1 SRO-I I/C 4,6 2 4 4 2 MAJ 7 1 2 2 1 SRO-U TS 0 0 2 2 RO RX - 0 1 1 0 BOP NOR 2 1 1 1 1 SRO-I I/C 3, 8, 3 4 4 2 9

SRO-U MAJ 7 1 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I IC #251 IC #252 IC #253 IC#254 L N T N I T CREW CREW CREW CREW I A

M C POSITION POSITION POSITION POSITION L U A T S A B S A B S A B S A B M(*)

N Y R T O R T O R T O R T O R I U T P O C P O C P O C P O C P E

RO RX - 0 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2,3, 5 4 4 2 4,6, SRO-U 7 MAJ 5 1 2 2 1 TS 2 1 0 2 2 RO RX 4 1 1 1 0 ATC NOR - 0 1 1 1 SRO-I I/C 4,7 2 4 4 2 MAJ 5 1 2 2 1 SRO-U TS - 0 0 2 2 RO RX - 0 1 1 0 BOP NOR 1 1 1 1 1 SRO-I I/C 3,6,7 3 4 4 2 SRO-U MAJ 5 1 2 2 1 TS - 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I IC #251 IC #252 IC #253 IC#254 L N T N I T CREW CREW CREW CREW I A

M C POSITION POSITION POSITION POSITION L U A T S A B S A B S A B S A B M(*)

N Y R T O R T O R T O R T O R I U T P O C P O C P O C P O C P E

RO RX - 0 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 3,4,5 5 4 4 2 6,9 SRO-U MAJ 7 1 2 2 1

TS 3,6 2 0 2 2 RO RX 2 1 1 1 0 ATC NOR - 0 1 1 1 SRO-I I/C 8 1 4 4 2 MAJ 7 1 2 2 1 SRO-U TS - 0 0 2 2 RO RX - 0 1 1 0 BOP NOR 1 1 1 1 1 SRO-I I/C 4,5,6 4 4 4 2 9

SRO-U MAJ 7 1 2 2 1 TS - 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I IC #251 IC #252 IC #253 IC#254 L N T N I T CREW CREW CREW CREW I A

M C POSITION POSITION POSITION POSITION L U A T S A B S A B S A B S A B M(*)

N Y R T O R T O R T O R T O R I U T P O C P O C P O C P O C P E

RO RX - - - - 0 1 1 0 NOR 2,5 1 1 2 1 1 1 1 SRO-I I/C 3,4,6 2,3, 3,4,5 4,5,6 5 4 4 2 8 4,6, 6,9 8,9 SRO-U 7 MAJ 7 5 7 7 1 2 2 1 TS 3 2 3,6 4,6 2 0 2 2 RO RX 1 4 2 3 1 1 1 0 ATC NOR 5 - - 2 1 1 1 1 SRO-I I/C 4,6 4,7 8 4,5,8 3 4 4 2 MAJ 7 5 7 7 1 2 2 1 SRO-U TS - - - 0 0 2 2 RO RX - - - - 0 1 1 0 BOP NOR 2 1 1 1 1 1 1 1 SRO-I I/C 3, 8, 3,6,7 4,5,6 69 2 4 4 2 9 9 SRO-U MAJ 7 5 7 7 1 2 2 1 TS - - - 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.