Text

2015-05 - Final Outline
	ML16043A003
Person / Time
Site:	River Bend
Issue date:	06/19/2015
From:	Vincent Gaddy; Operations Branch IV
To:	; Entergy Operations
References
	Download: ML16043A003 (12)
	v • d • e

REV 05 ES-401 BWR Examination Outline Form ES-401-1 Facility: RBS Date of Exam: June 19, 2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 4 3 2 4 4 3 20 Emergency &

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

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

3. Generic Knowledge and Abilities 1 2 3 4 10 Categories 3 3 2 2 Notes: 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.

REV 05

REV 05 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)

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

1 2 3 1 2 295001 Partial or Complete Loss of Forced X 2.1.20 Ability to interpret and execute procedure 4.6 39 Core Flow Circulation / 1 & 4 steps.

295003 Partial or Complete Loss of AC / 6 X AA2. Ability to determine and/or interpret the 3.2 40 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER:

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

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

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

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

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

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

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

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

EA2.06 Suppression pool temperature 295025 High Reactor Pressure / 3 X 2.1.27 Knowledge of system purpose and/or 3.9 49 function.

295026 Suppression Pool High Water X EA2. Ability to determine and/or interpret the 3.9 50 Temp. / 5 following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

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

EA1.02 Containment ventilation/cooling: Mark-III REV 05

REV 05 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO)

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

1 2 3 1 2 295028 High Drywell Temperature / 5 X EK3. Knowledge of the reasons for the following 3.5 52 responses as they apply to HIGH DRYWELL TEMPERATURE:

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

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

EK1.03 Water level effects on reactor power 295037 SCRAM Condition Present X EA2. Ability to determine and/or interpret the 4.0 55 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:

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

EK1.03 Meteorological effects on off-site release 600000 Plant Fire On Site / 8 X AA1 Ability to operate and / or monitor the following 3.0 57 as they apply to PLANT FIRE ON SITE:

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 ELECTRIC GRID DISTURBANCES and the following:

AK2.07 Turbine/generator control K/A Category Totals: 4 3 2 4 4 3 Group Point Total: 20 REV 05

REV 05 ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO)

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

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 X 2.4.4 Ability to recognize abnormal indications for 4.5 59 system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

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

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

AA1.01 Containment ventilation/cooling system 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 X AK3. Knowledge of the reasons for the following 3.6 62 responses as they apply to HIGH SUPPRESSION POOL TEMPERATURE:

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

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

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 295035 Secondary Containment High X EK2. Knowledge of the interrelations between 3.6 65 Differential Pressure / 5 SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE and the following:

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: 1 2 1 1 1 1 Group Point Total: 7 REV 05

REV 05 ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 1 (RO)

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

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection X K3. Knowledge of the effect that a loss or 3.5 1 Mode malfunction of the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) will have on following:

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

K4.05 Reactor cooldown rate 206000 HPCI BWR 6 Design not applicable 207000 Isolation (Emergency)

BWR 6 Design not applicable Condenser 209001 LPCS X A1. Ability to predict and/or monitor changes in 3.2 3 parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including:

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

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

A3.03 Explosive valves indicating lights:

Plant-Specific 212000 RPS X A3. Ability to monitor automatic operations of 4.4 6 the REACTOR PROTECTION SYSTEM including:

A3.01 Reactor Power 215003 IRM X 2.4.21 Knowledge of the parameters and logic 4.0 7 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.

215004 Source Range Monitor X A4. Ability to manually operate and/or monitor 3.4 8 in the control room:

A4.07 Verification of proper functioning/

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

LOCAL POWER RANGE MONITOR SYSTEM including:

A3.08 Control rod block status REV 05

REV 05 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 1 (RO)

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

1 2 3 4 5 6 1 2 3 4 217000 RCIC X A2. Ability to (a) predict the impacts of the 3.8 10 following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

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

A1.02 ADS valve acoustical monitor noise:

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

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

K5.02 Safety function of SRV operation 259002 Reactor Water Level X K4. Knowledge of REACTOR WATER LEVEL 3.4 14 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) 261000 SGTS X K3. Knowledge of the effect that a loss or 3.6 15 malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following:

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

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

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

(CFR: 41.7)

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

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

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

K6.05 Pumps REV 05

REV 05 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 1 (RO)

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

1 2 3 4 5 6 1 2 3 4 218000 ADS X K5. Knowledge of the operational implications 3.8 22 of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM 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 :

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

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

K6.01 Starting air 400000 Component Cooling X 2.1.27 Knowledge of system purpose and/or 3.9 26 Water function.

K/A Category Point Totals: 2 2 3 3 2 3 3 2 3 1 2 Group Point Total: 26 REV 05

REV 05 ES-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 2 (RO)

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 K2. Knowledge of electrical power 3.5 27 supplies to the following:

K2.03 Backup SCRAM valve solenoids 201002 RMCS 201003 Control Rod and Drive X K1. Knowledge of the physical 3.2 28 Mechanism connections and/or cause-effect relationships between Control Rod Drive Mechanism and K1.01 control rod drive hydraulic system 201004 RSCS 201005 RCIS X A4. Ability to manually operate and/or 3.6 29 monitor in the control room:

A4.02 Rod display module (lights and push buttons): BWR-6 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU X 2.4.31 Knowledge of annunciator alarms, 4.2 30 indications, or response procedures.

214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool X A3. Ability to monitor automatic operations 3.3 31 Cooling Mode of the RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE including:

A3.01 Valve operation 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 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:

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

A1.01 Main steam line pressure: BWR-4,5,6 REV 05

REV 05 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 2 (RO)

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 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 :

K6.02 Reactor/turbine pressure control system: Plant-Specific 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas X K4. Knowledge of OFFGAS SYSTEM 3.3 35 design feature(s) and/or interlocks which provide for the following:

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

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:

K3.03 Plant protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC X K5. Knowledge of the operational 3.2 38 implications of the following concepts as they apply to CONTROL ROOM HVAC K5.01 Airborne contamination (e.g.,

radiological, toxic gas, smoke) control 290002 Reactor Vessel Internals K/A Category Point Totals: 1 1 1 1 1 1 1 1 1 2 1 Group Point Total: 12 REV 05

REV 05 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: RBS Date of Exam: June 19, 2015 RO Category K/A # Topic IR #

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

1.

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

2.1 2.1.37 Knowledge of procedures, guidelines, or 4.3 68 limitations associated with reactivity management.

Subtotal 3 2.2 2.2.12 Knowledge of surveillance procedures. 3.7 69 2.2 2.2.14 Knowledge of the process for controlling 3.9 70

2. equipment configuration or status.

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

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

3. 2.3 2.3.13 Knowledge of radiological safety procedures 3.4 73 Radiation pertaining to licensed operator duties, such as Control response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 2 2.4 2.4.45 Ability to prioritize and interpret the significance 4.1 74 of each annunciator or alarm.

4. 2.4 2.4.32 Knowledge of operator response to loss of all 3.6 75 Emergency annunciators.

Procedures /

Plan Subtotal 2 Tier 3 Point Total 10 REV 05

REV. 02 RBS Exam Date 6/19/2015 ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/2 295035 / EK2.01 Not possible to prepare a psychometrically sound question related to the subject K/A for RO level question. Was not able to create three plausible distracters.

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

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

Randomly redrew to K6.03 due to the remaining K5 items that are applicable to RBS having a IR of less than 2.5. the RBS JTA does not disagree with these ratings.

2/2 201002 / K1.01 RMCS is not a BWR6 specific system. BWR6s use RC&IS to perform rod control and movement functions. RC&IS was previously sampled in the original exam outline.

Randomly redrew system 201003 Control Rod and Drive Mechanism Randomly drew K1.01 2/2 214000 / G2.4.21 RPIS is not applicable to RBS. RC&IS was previously sampled in the original exam outline.

Randomly redrew system 204000 RWCU Randomly redrew within G2.4 to G 2.4.31 2/2 226001 / A3.06 CTMT Spray Mode is not a viable mode of RHR operation at RBS.

Randomly redraw to 219000 RHR/LPCI: TORUS/ POOL COOLING MODE and retained A3.01 2/2 234000 / A2.01 Rejected due to low operational validity for discriminatory RO level Question. The RBS RO JTA does not require the RO to use procedures when a refueling interlock failure.

Randomly redrew to A2.03

REV. 02 RBS Exam Date 6/19/2015 3 G2.4.1 Rejected due to no immediate actions steps associated with RBS EOPs.

Systematically redrew G2.4.45