Text

2015-05-DRAFT Outline
	ML16043A001
Person / Time
Site:	River Bend
Issue date:	06/19/2015
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16043A001 (13)
	v • d • e

ES-401 BWR Examination Outline Form ES-401-1 Rev. 01 Facility: Date of Exam:

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 3 4 4 3 20 7 Emergency &

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

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

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

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 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Rev. 01 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 2.1.20 Ability to interpret and execute procedure steps. l 295001 Partial or Complete Loss of Forced X (CFR: 41.10 / 43.5 / 45.12) l 4.6 39 Core Flow Circulation / 1 & 4 AA2. Ability to determine and/or interpret the following 295003 Partial or Complete Loss of AC / 6 X as they apply to PARTIAL OR COMPLETE LOSS OF 3.2 40 A.C. POWER :

(CFR: 41.10 / 43.5 / 45.13)

AA2.03 Battery status: Plant-Specific 295004 Partial or Total Loss of DC Pwr / 6 AA1. Ability to operate and/or monitor the following as 295005 Main Turbine Generator Trip / 3 X they apply to MAIN TURBINE GENERATOR TRIP : 3.1 41 (CFR: 41.7 / 45.6)

AA1.01 Recirculation system: Plant-Specific 2.4.4 Ability to recognize abnormal indications for 295006 SCRAM / 1 X system operating parameters that are entry-level 4.5 42 conditions for emergency and abnormal operating procedures. l (CFR: 41.10 / 43.2 / 45.6)

AK2. Knowledge of the interrelations between 295016 Control Room Abandonment / 7 X CONTROL ROOM ABANDONMENT and the 4.4 43 following:

(CFR: 41.7 / 45.8)

AK2.01 Remote shutdown panel: Plant-Specific AK1. Knowledge of the operational implications of the 295018 Partial or Total Loss of CCW / 8 X following concepts as they apply to PARTIAL OR 3.5 44 COMPLETE LOSS OF COMPONENT COOLING WATER :

(CFR: 41.8 to 41.10)

AK1.01 Effects on component/system operations 295019 Partial or Total Loss of Inst. Air / 8 X AK2. Knowledge of the interrelations between PARTIAL 3.4 45 OR COMPLETE LOSS OF INSTRUMENT AIR and the following:

(CFR: 41.7 / 45.8)

AK2.05 Main steam system AK3. Knowledge of the reasons for the following 295021 Loss of Shutdown Cooling / 4 X responses as they apply to LOSS OF SHUTDOWN 3.6 46 COOLING :

(CFR: 41.5 / 45.6)

AK3.05 Establishing alternate heat removal flow paths AA1. Ability to operate and/or monitor the following as 295023 Refueling Acc / 8 X they apply to REFUELING ACCIDENTS : 3.4 47 (CFR: 41.7 / 45.6)

AA1.04 Radiation monitoring equipment EA2. Ability to determine and/or interpret the following 295024 High Drywell Pressure / 5 X as they apply to HIGH DRYWELL PRESSURE: 4.1 48 (CFR: 41.10 / 43.5 / 45.13)

EA2.06 Suppression pool temperature 2.1.27 Knowledge of system purpose and/or function.

295025 High Reactor Pressure / 3 X (CFR: 41.7) 3.9 49 EA2. Ability to determine and/or interpret the following 295026 Suppression Pool High Water X as they apply to SUPPRESSION POOL HIGH WATER 3.9 50 Temp. / 5 TEMPERATURE:

(CFR: 41.10 / 43.5 / 45.13)

EA2.03 Reactor pressure EA1. Ability to operate and/or monitor the following as 295027 High Containment Temperature / 5 X they apply to HIGH CONTAINMENT TEMPERATURE 3.5 51 (MARK III CONTAINMENT ONLY) :

(CFR: 41.7 / 45.6)

EA1.02 Containment ventilation/cooling: Mark-III

EK3. Knowledge of the reasons for the following 295028 High Drywell Temperature / 5 X responses as they apply to HIGH DRYWELL 3.5 52 TEMPERATURE :

(CFR: 41.5 / 45.6)

EK3.02 RPV flooding EK1. Knowledge of the operational implications of the 295030 Low Suppression Pool Wtr Lvl / 5 X following concepts as they apply to LOW 3.8 53 SUPPRESSION POOL WATER LEVEL:

(CFR: 41.8 to 41.10)

EK1.03 Heat capacity 295031 Reactor Low Water Level / 2 X EK1. Knowledge of the operational implications of the 3.7 54 following concepts as they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.8 to 41.10)

EK1.03 Water level effects on reactor power EA2. Ability to determine and/or interpret the following 295037 SCRAM Condition Present X as they apply to SCRAM CONDITION PRESENT AND 4.0 55 and Reactor Power Above APRM REACTOR POWER ABOVE APRM DOWNSCALE Downscale or Unknown / 1 OR UNKNOWN :

(CFR: 41.10 / 43.5 / 45.13)

EA2.07 Containment conditions/isolations EK1. Knowledge of the operational implications of the 295038 High Off-site Release Rate / 9 X following concepts as they apply to HIGH OFF-SITE 2.8 56 RELEASE RATE :

(CFR: 41.8 to 41.10)

EK1.01 Biological effects of radioisotope ingestion AA1 Ability to operate and / or monitor the following as 600000 Plant Fire On Site / 8 X they apply to PLANT FIRE ON SITE: 3.0 57 AA1.05 Plant and control room ventilation systems 700000 Generator Voltage and Electric Grid X AK2. Knowledge of the interrelations between 3.6 58 Disturbances / 6 GENERATOR VOLTAGE AND l ELECTRIC GRID DISTURBANCES and the following:

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

AK2.07 Turbine/generator control K/A Category Totals: Group Point Total: 20/7

ES-401 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Rev. 01 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 2.4.4 Ability to recognize abnormal indications for system 295002 Loss of Main Condenser Vac / 3 X operating parameters that are entry-level conditions for 4.5 59 emergency and abnormal operating procedures.

(CFR: 41.10 / 43.2 / 45.6) 295007 High Reactor Pressure / 3 X AA2. Ability to determine and/or interpret the following as 4.1 60 they apply to HIGH REACTOR PRESSURE :

(CFR: 41.10 / 43.5 / 45.13)

AA2.02 Reactor power 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 AA1.01 Ability to operate and/or monitor the following as 295011 High Containment Temp / 5 X they apply to HIGH CONTAINMENT TEMPERATURE 3.6 61 (MARK III CONTAINMENT ONLY) :

(CFR: 41.7 / 45.6)

Containment ventilation/cooling system: Mark-III 295012 High Drywell Temperature / 5 AK3. Knowledge of the reasons for the following responses 295013 High Suppression Pool Temp. / 5 X as they apply to HIGH SUPPRESSION POOL 3.6 62 TEMPERATURE :

(CFR: 41.5 / 45.6)

AK3.01 Suppression pool cooling operation 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 AK2. Knowledge of the interrelations between 295020 Inadvertent Cont. Isolation / 5 & 7 X INADVERTENT CONTAINMENT ISOLATION and the 3.1 63 following:

(CFR: 41.7 / 45.8)

AK2.09 RHR/shutdown cooling: Plant-Specific AK1. Knowledge of the operational implications of the 295022 Loss of CRD Pumps / 1 X following concepts as they apply to LOSS OF CRD 3.6 64 PUMPS:

(CFR: 41.8 to 41.10)

AK1.02 Reactivity control 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 Ventilation High Radiation / 9 EK2. Knowledge of the interrelations between 295035 Secondary Containment High X SECONDARY CONTAINMENT HIGH DIFFERENTIAL 3.6 65 Differential Pressure / 5 PRESSURE and the following:

(CFR: 41.7 / 45.8)

EK2.03 Off-site release rate 295036 Secondary Containment High Sump/Area Water Level / 5

500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: Group Point Total: 7/3

ES-401 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Rev. 01 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 K3. Knowledge of the effect that a loss or 203000 RHR/LPCI: Injection X malfunction of the RHR/LPCI: INJECTION 1 Mode MODE (PLANT SPECIFIC) will have on following: 3.5 (CFR: 41.7 / 45.4)

K3.02 Suppression pool level K4. Knowledge of SHUTDOWN COOLING 205000 Shutdown Cooling X SYSTEM (RHR SHUTDOWN COOLING 3.6 2 MODE) design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7)

K4.05 Reactor cooldown rate BWR 6 Design not applicable 206000 HPCI 207000 Isolation (Emergency) BWR 6 Design not applicable Condenser A1. Ability to predict and/or monitor changes in 209001 LPCS X parameters associated with operating the LOW 3.2 3 PRESSURE CORE SPRAY SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.02 Core spray pressure A2. Ability to (a) predict the impacts of the 209002 HPCS X following on the HIGH PRESSURE CORE 3.8 4 SPRAY SYSTEM (HPCS) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 System initiation: BWR-5,6 A3. Ability to monitor automatic operations of the 211000 SLC X STANDBY LIQUID CONTROL SYSTEM 3.8 5 including:

(CFR: 41.7 / 45.7)

A3.03 Explosive valves indicating lights: Plant-Specific A3. Ability to monitor automatic operations of the 212000 RPS X REACTOR PROTECTION SYSTEM including: 4.4 6 (CFR: 41.7 / 45.7)

A3.01 Reactor Power 2.4.21 Knowledge of the parameters and logic 215003 IRM X used to assess the status of safety functions, such 4.0 7 as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5 / 45.12)

A4. Ability to manually operate and/or monitor in 215004 Source Range Monitor X the control room: 3.4 8 (CFR: 41.7 / 45.5 to 45.8)

A4.07 Verification of proper functioning/

operability A3. Ability to monitor automatic operations of the 215005 APRM / LPRM X AVERAGE POWER RANGE 3.7 9 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including:

(CFR: 41.7 / 45.7)

A3.08 Control rod block status

A2. Ability to (a) predict the impacts of the 217000 RCIC X following on the REACTOR CORE ISOLATION 3.8 10 COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.02 Turbine trips A1. Ability to predict and/or monitor changes in 218000 ADS X parameters associated with operating the 3.7 11 AUTOMATIC DEPRESSURIZATION SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.02 ADS valve acoustical monitor noise: Plant-Specific K1. Knowledge of the physical connections and/or 223002 PCIS/Nuclear Steam X cause/effect relationships between PRIMARY 3.8 12 Supply Shutoff CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Main steam system K5. Knowledge of the operational implications of 239002 SRVs X the following concepts as they apply to 3.7 13 RELIEF/SAFETY VALVES :

(CFR: 41.5 / 45.3)

K5.02 Safety function of SRV operation K4. Knowledge of REACTOR WATER LEVEL 259002 Reactor Water Level X CONTROL SYSTEM design feature(s) and/or 3.4 14 Control interlocks which provide for the following:

(CFR: 41.7)

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

K3. Knowledge of the effect that a loss or 261000 SGTS X malfunction of the STANDBY GAS 3.6 15 TREATMENT SYSTEM will have on following:

(CFR: 41.7 /45.6)

K3.02 Off-site release rate K2. Knowledge of electrical power supplies to the 262001 AC Electrical X following: 3.3 16 Distribution (CFR: 41.7)

K2.01 Off-site sources of power K1. Knowledge of the physical connections and/or 262002 UPS (AC/DC) X cause/effect relationships between 2.6 17 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.10 Fire protection system K2. Knowledge of electrical power supplies to the 263000 DC Electrical X following: 3.1 18 Distribution (CFR: 41.7)

K2.01 Major D.C. loads K3. Knowledge of the effect that a loss or 264000 EDGs X malfunction of the EMERGENCY 4.2 19 GENERATORS (DIESEL/JET) will have on following:

(CFR: 41.7 / 45.4)

K3.01 Emergency core cooling systems K4. Knowledge of (INSTRUMENT AIR 300000 Instrument Air X SYSTEM) design feature(s) and or interlocks 3.0 20 which provide for the following:

(CFR: 41.7)

K4.02 Cross-over to other air systems K6 Knowledge of the effect that a loss or 400000 Component Cooling X malfunction of the following will have on the 3.0 21 Water CCWS:

(CFR: 41.7 / 45.7)

K6.05 Pumps

K5. Knowledge of the operational implications of 218000 ADS X the following concepts as they apply to 3.8 22 AUTOMATIC DEPRESSURIZATION SYSTEM (CFR: 41.5 / 45.3)

K5.01 ADS logic operation 259002 Reactor Water Level X K6. Knowledge of the effect that a loss or 3.1 23 Control malfunction of (the following) will have on REACTOR WATER LEVEL CONTROL SYSTEM :

(CFR: 41.5 / 45.3)

K6.03 Main steam flow input A1. Ability to predict and/or monitor changes in 223002 PCIS/Nuclear Steam X parameters associated with operating the 3.7 24 Supply Shutoff PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:

(CFR: 41.5 / 45.5)

A1.02 Valve closures K6. Knowledge of the effect that a loss or 264000 EDGs X malfunction of the following will have on the 3.8 25 EMERGENCY GENERATORS (DIESEL/JET) :

(CFR: 41.7 / 45.7)

K6.01 Starting air 400000 Component Cooling X 2.1.27 Knowledge of system purpose and/or 3.9 26 Water function. l (CFR: 41.7)

K/A Category Point Totals: Group Point Total: 26/5

ES-401 Form ES-401-1 Rev. 01 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 K2. Knowledge of electrical power supplies to the 201001 CRD Hydraulic X following: 3.5 27 (CFR: 41.7)

K2.03 Backup SCRAM valve solenoids K1. Knowledge of the physical connections and/or 211000 Standby Liquid Control X cause/effect relationships between STANDBY 3.4 28 LIQUID CONTROL and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.05 RWCU 201003 Control Rod and Drive Mechanism 201004 RSCS A4. Ability to manually operate and/or monitor in 201005 RCIS X the control room: 3.6 29 (CFR: 41.7 / 45.5 to 45.8)

A4.02 Rod display module (lights and push buttons): BWR-6 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 2.1.32 Ability to explain and apply system limits 215003 Intermediate Range Monitor X and precautions. 3.8 30 (IRM) System (CFR: 41.10 / 43.2 / 45.12) 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

219000 RHR/LPCI: Torus/Suppression X A3. Ability to monitor automatic operations of the 3.3 31 Pool Cooling Mode RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE including:

(CFR: 41.7 / 45.7)

A3.01 Valve operation 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment X A2. Ability to (a) predict the impacts of the 2.8 32 following on the FUEL HANDLING EQUIPMENT ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.03 Loss of Electrical Power 239001 Main and Reheat Steam 239003 MSIV Leakage Control X A1. Ability to predict and/or monitor changes in 3.1 33 parameters associated with operating the MSIV LEAKAGE CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.01 Main steam line pressure: BWR-4,5,6 241000 Reactor/Turbine Pressure Regulator

245000 Main Turbine Gen. / Aux. X K6. Knowledge of the effect that a loss or 3.5 34 malfunction of the following will have on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS :

(CFR: 41.7 / 45.7)

K6.02 Reactor/turbine pressure control system:

Plant-Specific 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste K4. Knowledge of OFFGAS SYSTEM design 271000 Offgas X feature(s) and/or interlocks which provide for the 3.3 35 following:

(CFR: 41.7)

K4.04 The prevention of hydrogen explosions and/or fires A4. Ability to manually operate and/or monitor in 272000 Radiation Monitoring X the control room: 3.0 36 (CFR: 41.7 / 45.5 to 45.8)

A4.02 Meter indications 286000 Fire Protection X K3. Knowledge of the effect that a loss or 3.6 37 malfunction of the FIRE PROTECTION SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.03 Plant protection 288000 Plant Ventilation 290001 Secondary CTMT K5. Knowledge of the operational implications of 290003 Control Room HVAC X the following concepts as they apply to CONTROL 3.2 38 ROOM HVAC (CFR: 41.5 / 45.3)

K5.01 Airborne contamination (e.g., radiological, toxic gas, smoke) control 290002 Reactor Vessel Internals K/A Category Point Totals: Group Point Total: 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Rev. 01 Facility: Date of Exam:

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

2.1.14 Knowledge of criteria or conditions that require plant-2.1. 3.1 66 wide announcements, such as pump starts, reactor trips, mode changes, etc.

1.

(CFR: 41.10 / 43.5 / 45.12)

Conduct 2.1.29 Knowledge of how to conduct system lineups, such as of Operations 2.1. 4.1 67 valves, breakers, switches, etc.

(CFR: 41.10 / 45.1 / 45.12) 2.1.37 Knowledge of procedures, guidelines, or limitations 2.1. 4.3 68 associated with reactivity management.

(CFR: 41.1 / 43.6 / 45.6) 2.1.

2.1.

Subtotal 3 2.2.12 Knowledge of surveillance procedures.

2.2. 3.7 69 (CFR: 41.10 / 45.13) 2.2.14 Knowledge of the process for controlling equipment 2.2. 3.9 70 configuration or status.

2.

(CFR: 41.10 / 43.3 / 45.13)

Equipment Control 2.2. 2.2.22 Knowledge of limiting conditions for operations and 4.0 71 safety limits.

(CFR: 41.5 / 43.2 / 45.2) 2.2.

2.2.

Subtotal 3 2.3.4 Knowledge of radiation exposure limits under normal or 2.3. 3.2 72 emergency conditions.

(CFR: 41.12 / 43.4 / 45.10) 2.3.13 Knowledge of radiological safety procedures pertaining

3. 2.3. 3.4 73 to licensed operator duties, such as response to radiation Radiation monitor alarms, containment entry requirements, fuel handling Control responsibilities, access to locked high-radiation areas, aligning filters, etc.

l (CFR: 41.12 / 43.4 / 45.9 / 45.10) 2.3.

2.3.

Subtotal 2

2.4.1 Knowledge of EOP entry conditions and immediate action 2.4. 4.6 74 steps.

(CFR: 41.10 / 43.5 / 45.13) 4.

Emergency Procedures / 2.4.32 Knowledge of operator response to loss of all Plan 2.4. 3.6 75 annunciators.

(CFR: 41.10 / 43.5 / 45.13) 2.4.

2.4.

Subtotal 2 Tier 3 Point Total 10 7

Rev 00 ES-401 Record of Rejected K/As Form ES-401-4 Rev. 00 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 295038/EK1.03 Rejected due to low operational validity for discriminatory RO level question. ROs make no decisions about offsite release based on meteorological data at RBS.

Redrew to EK1.01 1/2 295035 / EK2.01 Not possible to prepare a psychometrically sound question related to the subject K/A for RO level question.

Redrew to EK2.03 2/1 262002 / K1.16 This is not applicable to RBS, the MSIV solenoids are powered from RPS.

Redrew to K1.10 2/1 259002 / K5.07 Not applicable to RBS (motor driven RFP)

Redrew to K6.03 2/2 201002 / K1.05 RMCS is not a BWR6 specific system. BWR6s use RC&IS to perform rod control and movement functions.

Redrew within safety function 1 to 211000 K1.05 2/2 214000 / G2.4.21 RPIS is not applicable to RBS.

Redrew within safety function 7 to 215003 G2.1.32 2/2 226001 / A3.01 CTMT Spray Mode is not a viable mode of RHR operation at RBS.

Redraw within Safety Function 5 to 219000 A3.01 2/2 234000 / A2.01 Rejected due to low operational validity for discriminatory RO level Question Redrew to A2.03 Rev 00

ES-401 BWR Examination Outline Form ES-401-1 Rev. 01 Facility: Date of Exam:

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