ML17142A442
| ML17142A442 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/18/2017 |
| From: | David Reeser NRC/RGN-III/DRS/OLB |
| To: | Nuclear Management Co |
| Shared Package | |
| ML15274A421 | List: |
| References | |
| Download: ML17142A442 (17) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 Facility: Monticello Nuclear Generating Plant Date of Exam: November 2016 Tier Group RO K/A Category Points SRO-Only Points K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total
- 1. 1 4 4 3 3 3 3 20 4 3 7 Emergency & N/A N/A 2 1 1 1 1 1 2 7 2 1 3 Abnormal Plant Evolutions Tier Totals 5 5 4 4 4 5 27 6 4 10 3 2 3 2 2 3 3 3 1 2 2 26 3 2 5 1
1 2 2.
Plant 2 1 1 2 1 1 1 1 1 1 1 1 12 0 2 1 3 Systems 4 3 5 3 3 4 4 4 2 3 3 38 5 3 8 Tier Totals 2 3
- 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category.)
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
- 7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As
ES-401 2 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 1 2
- 295001 Partial or Complete Loss of X AA2.03 Ability to determine and/or interpret 3.3 1 Forced Core Flow Circulation / 1 & 4 the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Actual core flow 295003 Partial or Complete Loss of AC X 2.4.6 Knowledge of EOP mitigation 3.7 2
/6 strategies.
295004 Partial or Total Loss of DC Pwr X AK1.05 Knowledge of the operational 3.3 3
/6 implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Loss of breaker protection 295005 Main Turbine Generator Trip / 3 X AK2.01 Knowledge of the interrelations 3.8 4 between MAIN TURBINE GENERATOR TRIP and the following: RPS 295006 SCRAM / 1 X AK3.01 Knowledge of the reasons for the 3.8 5 following responses as they apply to SCRAM:
Reactor water level response...
X AA2.01 Ability to determine and/or interpret 4.6 76 the following as they apply to SCRAM:
Reactor power 295016 Control Room Abandonment / 7 X AA1.06 Ability to operate and/or monitor the 4.0 6 following as they apply to CONTROL ROOM ABANDONMENT: Reactor water level...
X 2.4.30 Knowledge of events related to system 4.1 77 operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
295018 Partial or Total Loss of CCW / 8 X AA2.03 Ability to determine and/or interpret 3.2 7 the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Cause for partial or complete loss...
295019 Partial or Total Loss of Inst. Air / X 2.4.4 Ability to recognize abnormal 4.5 8 8 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
ES-401 3 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 1 2
- 295021 Loss of Shutdown Cooling / 4 X AK1.04 Knowledge of the operational 3.6 9 implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING:
Natural circulation X 2.1.20 Ability to interpret and execute 4.6 78 procedure steps.
295023 Refueling Acc / 8 X AK2.03 Knowledge of the interrelations 3.4 10 between REFUELING ACCIDENTS and the following: Radiation monitoring equipment...
295024 High Drywell Pressure / 5 X EK3.07 Knowledge of the reasons for the 3.5 11 following responses as they apply to HIGH DRYWELL PRESSURE: Drywell venting X EA2.05 Ability to determine and/or interpret 3.7 79 the following as they apply to HIGH DRYWELL PRESSURE: Suppression chamber air-space temperature: Plant-Specific EA2.01 Ability to determine and/or interpret the following as they apply to HIGH 4.4 DRYWELL PRESSURE: Drywell Pressure 295025 High Reactor Pressure / 3 X EA1.03 Ability to operate and/or monitor the 4.4 12 following as they apply to HIGH REACTOR PRESSURE: Safety/relief valves: Plant-Specific...
295026 Suppression Pool High Water X EA2.03 Ability to determine and/or interpret 3.9 13 Temp. / 5 the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor pressure...
295027 High Containment Temperature N/A at MNGP
/5
ES-401 4 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 1 2
- 295028 High Drywell Temperature / 5 X 2.2.39 Knowledge of less than or equal to 3.9 14 one hour Technical Specification action statements for systems 2.4.41 Knowledge of the emergency action 2.9 level thresholds and classifications.
2.2.44 Ability to interpret control room 4.2 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
X EA2.01 Ability to determine and/or interpret 4.1 80 the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell temperature 295030 Low Suppression Pool Wtr Lvl / X EK1.02 Knowledge of the operational 3.5 15 5 implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: Pump NPSH X 2.4.31 Knowledge of annunciator alarms, 4.1 81 indications, or response procedures.
295031 Reactor Low Water Level / 2 X EK2.11 Knowledge of the interrelations 4.4 16 between REACTOR LOW WATER LEVEL and the following: Reactor protection system X EA2.01 Ability to determine and/or interpret 4.6 82 the following as they apply to REACTOR LOW WATER LEVEL: Reactor water level...
295037 SCRAM Condition Present and X EK1.05 Knowledge of the operational 3.4 17 Reactor Power Above APRM implications of the following concepts as they Downscale or Unknown / 1 apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Cold shutdown boron weight: Plant-Specific...
295038 High Off-site Release Rate / 9 X EK2.03 Knowledge of the interrelations 3.6 18 between HIGH OFF-SITE RELEASE RATE and the following: Plant ventilation systems 600000 Plant Fire On Site / 8 X AK3.04 Knowledge of the reasons for the 2.8 19 following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site...
ES-401 5 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 1 2
- 700000 Generator Voltage and Electric X AA1.01 Ability to operate and/or monitor the 3.6 20 Grid Disturbances / 6 following as l they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Grid frequency and voltage K/A Category Totals: 4 4 3 3 3 3 Group Point Total: 20/
/ / 7 4 3
ES-401 6 Form ES-401-1 2016 Monticello Generating Plant Examination Outline 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 # Q#
1 2 3 1 2
- 295002 Loss of Main Condenser Vac / 3 X AA2.02 Ability to determine and/or interpret 3.2 21 the following as they apply to LOSS OF MAIN CONDENSER VACUUM: Reactor power:
Plant-Specific..
295007 High Reactor Pressure / 3 X AK2.04 Knowledge of the interrelations 3.2 22 between HIGH REACTOR PRESSURE and the following: LPCS...
295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 X AA2.03 Ability to determine and/or interpret 3.6 83 the following as they apply to HIGH DRYWELL PRESSURE: Drywell radiation levels...
295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / X AA1.01 Ability to operate and/or monitor the 3.9 23 5 following as they apply to HIGH SUPPRESSION POOL TEMPERATURE:
Suppression pool cooling...
295014 Inadvertent Reactivity Addition / X 2.4.46 Ability to verify that the alarms are 4.2 84 1 consistent with the plant conditions.
295015 Incomplete SCRAM / 1 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 / X EK1.01 Knowledge of the operational 3.4 24 5 implications of the following concepts as they apply to HIGH SUPPRESSION POOL WATER LEVEL: Containment integrity...
X EA2.01 Ability to determine and/or interpret 3.9 85 the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL:
Suppression pool water level...
ES-401 7 Form ES-401-1 2016 Monticello Generating Plant Examination Outline 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 # Q#
1 2 3 1 2
- 295032 High Secondary Containment X EK3.03 Knowledge of the reasons for the 3.8 25 Area Temperature / 5 following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Isolating affected systems...
295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment X 2.1.28 Knowledge of the purpose and 4.1 26 Ventilation High Radiation / 9 function of major system components and controls.
295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High X 2.4.6 Knowledge of EOP mitigation 3.7 27 Sump/Area Water Level / 5 strategies.
500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 1 1 1 1 1 2 Group Point Total: 7/3
/ /
2 1
ES-401 8 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- 203000 RHR/LPCI: X 2.4.31 Knowledge of annunciator alarms, 4.2 28 Injection Mode indications, or response procedures X A4.08 Ability to manually operate and/or 4.3 29 monitor in the control room: Reactor pressure.
X 2.2.12 Knowledge of surveillance 4.1 86 procedures 205000 Shutdown X K1.03 Knowledge of the physical 3.4 30 Cooling connections and/or cause effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following:
Recirculation loop temperature . . .
206000 HPCI X K2.03 Knowledge of electrical power 2.8 31 supplies to the following: Initiation logic:
BWR-2,3,4 207000 Isolation N/A (Emergency)
Condenser 209001 LPCS X K3.02 Knowledge of the effect that a loss or 3.8 32 malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:
ADS logic . . .
X A2.01 Ability to (a) predict the impacts of 3.4 87 the 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: Pump trips 209002 HPCS N/A 211000 SLC X K4.05 Knowledge of STANDBY LIQUID 3.4 33 CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: Dispersal of boron upon injection into the vessel 212000 RPS X K5.02 Knowledge of the operational 3.3 34 implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM: Specific Logic arrangements
ES-401 9 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- 215003 IRM X K6.06 Knowledge of the effect that a loss or 3.2 35 malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM: APRM X A2.06 Ability to (a) predict the impacts of 3.2 88 the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty range switch 215004 Source Range X A1.05 Ability to predict and/or monitor 3.6 36 Monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including:
SCRAM, rod block, and period alarm trip setpoints 215005 APRM / LPRM X A2.06 Ability to (a) predict the impacts of 3.4 37 the following on the AVERAGE POWER 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: Recirculation flow channels upscale X A1.04 Ability to predict and/or monitor 4.1 38 changes in parameters associated with operating the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including:
SCRAM and rod block trip setpoints
ES-401 10 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- 217000 RCIC X A3.04 Ability to monitor automatic 3.6 39 operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: System flow X A2.05 Ability to (a) predict the impacts of 3.3 40 the 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: D.C. power loss X A2.11 Ability to (a) predict the impacts of 3.2 89 the 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: Inadequate system flow 218000 ADS X A4.03 Ability to manually operate and/or 4.2 41 monitor in the control room: ADS logic reset 223002 PCIS/Nuclear X 2.1.27 Knowledge of system purpose 3.9 42 Steam Supply Shutoff and/or function X K1.01 Knowledge of the physical 3.8 43 connections and/or cause effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the following: Main steam system 239002 SRVs X K1.08 Knowledge of the physical 4.0 44 connections and/or cause effect relationships between RELIEF/SAFETY VALVES and the following: Automatic depressurization system 259002 Reactor Water X K2.02 Knowledge of electrical power 3.5 45 Level Control supplies to the following: Feedwater coolant injection (FWCI) initiation logic: FWCI/HPCI X A3.05 Ability to monitor automatic 3.4 operations of the Reactor Water Level Control System including: Changes in reactor power IR 3.4
ES-401 11 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- X 2.1.20 Ability to interpret and execute 4.6 90 procedure steps.
261000 SGTS X K3.01 Knowledge of the effect that a loss or 3.3 46 malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following: Secondary containment and environment differential pressure 262001 AC Electrical X K4.02 Knowledge of A.C. ELECTRICAL 2.9 47 Distribution DISTRIBUTION design feature(s) and/or interlocks which provide for the following:
Circuit breaker automatic trips 262002 UPS (AC/DC) X K3.10 Knowledge of the effect that a loss or 2.7 48 malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following: Containment isolation: Plant-Specific 263000 DC Electrical X K6.01 Knowledge of the effect that a loss or 3.2 49 Distribution malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION: A.C.
electrical distribution 264000 EDGs X K5.06 Knowledge of the operational 3.4 50 implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET): Load sequencing 300000 Instrument Air X A2.01 Ability to (a) predict the impacts of 2.9 51 the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions 400000 Component X A1.02 Ability to predict and / or monitor 2.8 52 Cooling Water changes in parameters associated with operating the CCWS controls including:
CCW temperature X K6.05 Knowledge of the effect that a loss or 3.0 53 malfunction of the following will have on the CCWS: Motors
ES-401 12 Form ES-401-1 2016 Monticello Nuclear Generating Plant Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- K/A Category Point 3 2 3 2 2 3 3 3 1 2 2 Group Point Total: 26/
Totals: / / 5 1 3 2 2
ES-401 13 Form ES-401-1 BWR Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- 201001 CRD Hydraulic X K2.04 Knowledge of electrical power 3.2 54 supplies to the following: Scram discharge volume vent and drain valve solenoids 201002 RMCS 201003 Control Rod X K5.03 Knowledge of the operational 3.3 55 and Drive Mechanism implications of the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM: Reactor power control 201004 RSCS 201005 RCIS 201006 RWM X K6.01 Knowledge of the effect that a loss or 2.8 56 malfunction of the following will have on the ROD WORTH MINIMIZER SYSTEM (RWM): RWM power supply: P-Spec(Not-BWR6) 202001 Recirculation X A3.05 Ability to monitor automatic 2.9 57 operations of the RECIRCULATION SYSTEM including: Pump speed: Plant-Specific 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-Core Probe 215002 RBM X K1.01 Knowledge of the physical 2.9 58 connections and/or cause effect relationships between ROD BLOCK MONITOR SYSTEM and the following:
APRM: BWR-3,4,5 216000 Nuclear Boiler Inst.
219000 RHR/LPCI: X A2.14 Ability to (a) predict the impacts of 4.3 91 Torus/Pool Cooling the following on the RHR/LPCI:
Mode TORUS/SUPPRESSION POOL COOLING MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident
ES-401 14 Form ES-401-1 BWR Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- 223001 Primary CTMT and Aux.
226001 RHR/LPCI: X K3.02 Knowledge of the effect that a loss or 3.5 59 CTMT Spray Mode malfunction of the RHR/LPCI:
CONTAINMENT SPRAY SYSTEM MODE will have on following:
Containment/drywell/suppression chamber temperature 230000 RHR/LPCI:
Torus/Pool Spray Mode 233000 Fuel Pool X A2.02 Ability to (a) predict the impacts of 3.3 92 Cooling/Cleanup the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Low pool level 234000 Fuel Handling Equipment 239001 Main and X A2.07 Ability to (a) predict the impacts of 3.8 60 Reheat Steam the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Main steam area high temperature or differential temperature high 239003 MSIV Leakage Control 241000 X K3.07 Knowledge of the effect that a loss or 3.3 61 Reactor/Turbine malfunction of the REACTOR/TURBINE Pressure Regulator PRESSURE REGULATING SYSTEM will have on following: Main stop/throttle valves K3.05 Knowledge of the effect that a loss or 3.7 malfunction of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will have on following: Main turbine steam flow 245000 Main Turbine X A1.02 Ability to predict and/or monitor 2.6 62 Gen. / Aux. changes in parameters associated with operating the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS controls including: Turbine speed 256000 Reactor Condensate
ES-401 15 Form ES-401-1 BWR Examination Outline 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 # Q#
1 2 3 4 5 6 1 2 3 4
- 259001 Reactor X A4.01 Ability to manually operate and/or 3.6 63 Feedwater monitor in the control room: System flow 268000 Radwaste X 2.2.38 Knowledge of conditions and 4.5 93 limitations in the facility license.
271000 Offgas X 2.4.4 Ability to recognize abnormal 4.5 64 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
272000 Radiation Monitoring 286000 Fire Protection 288000 Plant X K4.01 Knowledge of PLANT VENTILATION 3.7 65 Ventilation SYSTEMS design feature(s) and/or interlocks which provide for the following:
Automatic initiation of standby gas treatment system 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point 1 1 2 1 1 1 1 1 1 1 1 Group Point Total: 12/
Totals: / / 3 2 1
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Monticello Nuclear Generating Plant Date of Exam: November 2016 Category K/A # Topic RO SRO-Only Q#
IR # IR #
2.1.32 Ability to explain and apply system limits and precautions. 3.8 66 2.1.4 Knowledge of individual licensed operator responsibilities 3.3 related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
2.1.29 Knowledge of how to conduct system lineups, such as 4.1 67 valves, breakers, switches, etc.
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
- 1. handling area Conduct of Knowledge of industrial safety procedures (such as 3.4 2.1.26 Operations rotating equipment, lelectrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
2.1.7 Ability to evaluate plant performance and make 4.7 94 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2.1.39 Knowledge of conservative decision making practices. 4.3 95 Subtotal 3 2 2.2.36 Ability to analyze the effect of maintenance activities, such 3.1 69 as degraded power sources, on the status of limiting conditions for operations.
2.2.13 Knowledge of tagging and clearance procedures. 4.1 70 2.2.12 Knowledge of surveillance procedures. 3.7 71 2.
Equipment Control 2.2.37 Ability to determine operability and/or availability of safety 4.6 96 related equipment.
2.2.6 Knowledge of the process for making changes to 3.6 97 procedures.
Subtotal 3 2
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Monticello Nuclear Generating Plant Date of Exam: November 2016 Category K/A # Topic RO SRO-Only Q#
IR # IR #
2.3.13 Knowledge of radiological safety procedures pertaining to 3.4 72 licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
2.3.12 Knowledge of radiological safety principles pertaining to 3.2 73
- 3. licensed operator duties, such as containment entry Radiation requirements, fuel handling responsibilities, access to Control locked high-radiation areas, aligning filters, etc.
2.3.4 Knowledge of radiation exposure limits under normal or 3.7 98 emergency conditions.
Subtotal 2 1 2.4.21 Knowledge of the parameters and logic used to assess 4.0 74 the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
2.4.47 Ability to diagnose and recognize trends in an accurate 4.2 and timely manner utilizing the appropriate control room reference material.
2.4.12 Knowledge of general operating crew responsibilities 4.0
- 4. during emergency operations.
Emergency Procedures / 2.4.8 Knowledge of how abnormal operating procedures are 3.8 75 Plan used in conjunction with EOPs.
2.4.14 Knowledge of general guidelines for EOP usage. 4.5 99 2.4.44 Knowledge of emergency plan protective action 4.4 100 recommendations.
Subtotal 2 2 Tier 3 Point Total 10 7