ML18149A504
| ML18149A504 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/12/2015 |
| From: | NRC Region 1 |
| To: | Exelon Generation Co |
| Shared Package | |
| ML15286A047 | List: |
| References | |
| U01932 | |
| Download: ML18149A504 (13) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility: 2016 NRC Date of Exam:
RO Kl A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4
- I. 1 4 3 3 3 4 3 20 4 3 7 Emergency
& 2 1 1 1 2 1 , 1 7 2 1 3 Plant Tier Evolutions 5 4 4 5 5 4 27 6 4 10 Totals 1 3 3 2 2 2 3 2 2 2 2 3 26 2 3 5 2.
Plant 2 1 1 1 1 1 1 1 1 1 2 1 12 0 1 2 3 Systems Tier 4 4 3 3 3 4 3 3 3 4 4 38 3 5 8 Totals 1 2 3 4 l 2 3 4
- 3. Generic Knowledge & Abilities 10 7 Categories 3 2 3 2 2 2 I 2 Note: 1. Ensure that at least two topics from every applicable KIA 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 KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA 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 0.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA 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 KIA categories.
- 7. The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 KIA catalog, and enter the KIA 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 KIAs
ES-401 2 Form ES-401-1 2016 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#
EA2.02 - Ability to detem1ine and/or interpret the following as they apply to 295024 High Drywell Pressure/ 5 X HIGH DRYWELL PRESSURE: Drywell 4.0 76 temperature AA2.07 - Ability to determine and/or 295016 Control Room interpret the following as they apply to X CONTROL ROOM ABANDONMENT .
3.4 77 Abandonment/ 7 Suppression chamber pressure AA2.02 - Ability to determine and/or interpret the following as they apply to 295003 Partial or Complete Loss of X PARTIAL OR COMPLETE LOSS OF A.C 4.3 78 AC/6 POWER : Reactor power, pressure. and level 2.4.47 - Emergency Procedures/ Plan:
29503 l Reactor Low Water Level/ Ability to diagnose and recognize trends in X an accurate and timely manner utilizing the 4.2 79 2
appropriate control room reference material.
2.4.35 - Emergency Procedures/ Plan:
295038 High Off-site Release Rate Knowledge of local auxiliary operator tasks X during emergency and the resultant 4.0 80
/9 operational effects.
2.4.1 l - Emergency Procedures/ Plan:
295018 Partial or Total Loss of X Knowledge of abnormal condition 4.2 81 ccw /8 procedures.
EA2.03 - Ability to determine and/or 295026 Suppression Pool High interpret the following as they apply to X SUPPRESSION POOL HIGH WATER 4.0 82 Water Temp./ 5 TEMPERATURE: Reactor pressure EKl.01 - Knowledge of the operational 295026 Suppression Pool High implications of the following concepts as X they apply to SUPPRESSION POOL HIGH 3.0 39 Water Temp. / 5 WATER TEMPERATURE: Pump NPSH EK 1.01 - Knowledge of the operational implications of the following concepts as 295024 High Drywell Pressure / 5 X they apply to HIGH DR YWELL 4.1 40 PRESSURE : Drywell integrity: Plant-Specific AK 1.02 - Knowledge of the operation applications of the following concepts as 600000 Plant Fire On-site / 8 X 2.9 41 they apply to Plant Fire On Site: Fire Fighting EK2.03 - Knowledge of the interrelations 295030 Low Suppression Pool Water Level/ 5 X between LOW SUPPRESSION POOL 3.8 42 WATER LEVEL and the following: LPCS EK2.01 - Knowledge of the interrelations 295038 High Off-site Release Rate X between HIGH OFF-SITE RELEASE 3.1 43
/9 RATE and the following: Radwaste AK2.03 - Knowledge of the interrelations 295021 Loss of Shutdown Cooling between LOSS OF SHUTDOWN X 3.6 44
/4 COOLING and the following:
RHR/shutdown coolinq AK3.01 - Knowledge of the reasons for the following responses as they apply to 295018 Partial or Total Loss of PARTIAL OR COMPLETE LOSS OF ccw /8 X COMPONENT COOLING WATER:
2.9 45 Isolation of non-essential heat loads:
Plant-Specific AK3.02 - Knowledge of the reasons for 295003 Partial or Complete Loss of AC/ 6 X the following responses as they apply to 2.9 46 PARTIAL OR COMPLETE LOSS OF
ES-401 2 Form ES-401-1 2016 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#
A.C. POWER : Selective tripping AK3.03 - Knowledge of the reasons for 295005 Main Turbine Generator the following responses as they apply to X 2.8 47 Trip/ 3 MAIN TURBINE GENERATOR TRIP:
Feedwater temperature decrease AA 1.03 - Ability to operate and/or 29500 I Partial or Complete Loss monitor the following as they apply to of Forced Core Flow Circulation/ I X PARTIAL OR COMPLETE LOSS OF 2.6 48
&4 FORCED CORE FLOW CIRCULATION
- RMCS: Plant-Specific EA 1.04 - Ability to operate and/or monitor the following as they apply to 295025 High Reactor Pressure/ 3 X 3.8 49 HIGH REACTOR PRESSURE: HPCI:
Plant-Specific EA 1.1 O - Ability to operate and/or monitor the following as they apply to 295037 SCRAM Conditions SCRAM CONDITION PRESENT AND Present and Reactor Power Above X REACTOR POWER ABOVE APRM 3.7 50 APRM Downscale or Unknown/ I DOWNSCALE OR UNKNOWN :
Alternate boron injection methods:
Plant-Specific EA2.05 - Ability to determine and/or interpret the following as they apply to 295028 High Drywell Temperature X HIGH DRYWELL TEMPERATURE : 3.6 51 I5 Torus/suppression chamber pressure:
Plant-Specific AA2.07 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and GENERATOR VOLTAGE AND X 3.6 52 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:
Operational status of engineered safety features.
AA2.06 - Ability to determine and/or 295006 SCRAM / I X interpret the following as they apply to 3.5 53 SCRAM : Cause of reactor SCRAM 2.1.20 - Conduct of Operations: Ability 295004 Partial or Total Loss of X to interpret and execute procedure 4.6 54 DCPwr/6 steps.
2.1.27 - Conduct of Operations:
295019 Partial or Total Loss of X Knowledge of system purpose and / or 3.9 55 Inst. Air I 8 function.
2.2.3 - Equipment Control: (multi-unit 295016 Control Room license) Knowledge of the design, X 3.8 56 Abandonment/ 7 procedural, and operational differences between units.
EK1 .01 - Knowledge of the operational 295031 Reactor Low Water Level implications of the following concepts as X 4.6 57
/2 they apply to REACTOR LOW WATER LEVEL : Adequate core cooling AA2.01 - Ability to determine and/or 295023 Refueling Ace Cooling interpret the following as they apply to X 3.6 58 Mode/ 8 REFUELING ACCIDENTS : Area radiation levels KIA Category Totals: 4 3 3 3 4/4 3/3 Group Point Total:
I 20/7
ES-401 3 Form ES-401-1 2016 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#
EA2.0I - Ability to detem1ine and/ or interpret the following as they apply to 500000 High CTMT Hydrogen X HIGH PRIMARY CONTAINMENT 3.5 83 Cone. I 5 HYDROGEN CONCENTRATIONS:
Hvdrogcn monitoring svstem availabilitv
- 2. I. 7 - Conduct of Operations: Ability to e,aluate plant performance and ma.kc 295007 High Reactor Pressure/ 3 X operational judgements based on operating 4.7 84 characteristics. reactor behavior_ and instrument interpretion.
AA2.02 - Ability to determine and/or interpret the following as they apply to 295022 Loss ofCRD Pumps/ I X LOSS OF CRD PUMPS : CRD system 3.4 85 status AKI .02 - Knowledge of the operational implications of the following concepts as 3.
295022 Loss ofCRD Pumps/ I X 59 they apply to LOSS OF CRD PUMPS: 6 Reactivity control AK2.02 - Knowledge of the interrelations 295012 High Drywell between HIGH DRYWELL 3.6 X 60 Temperature / 5 TEMPERATURE and the following:
Drywell cooling AK3.02 - Knowledge of the reasons for the 295002 Loss of Main Condenser following responses as they apply to LOSS 3.
X OF MAIN CONDENSER VACUUM : 4 61 Vac / 3 Turbine trip AA! .09 - Ability to operate and/or monitor 295008 High Reactor Water Level the following as they apply to HIGH 3.
X 62
/2 REACTOR WATER LEVEL : Ability to 3 drain: Plant-Specific EA2.01 - Ability to determine and/or interpret the following as they apply to 295034 Secondary Containment 3.
Ventilation High Radiation/ 9 X SECONDARY CONTAINMENT 63 8
VENTILATION HIGH RADIATION :
Ventilation radiation levels 2.4.47 - Emergency Procedures/ Plan:
295017 High Off-site Release Ability to diagnose and recognize trends in 4.
Rate/ 9 X 64 an accurate and timely manner utilizing the 2 appropriate control room reference material.
EAi .05 - Ability to operate and/or monitor 295033 High Secondary the following as they apply to HIGH 3.
Containment Area Radiation X SECONDARY CONTAINMENT AREA 65 9
Levels/ 9 RADIATION LEVELS : Affected systems so as to isolate damaged portions KIA Category Totals: 1 1 1 2 1/2 1/1 Group Point Total:
I 7/3
ES-401 4 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#
1 2 3 4 5 6 1 3 4 A2. l O- Ability to (a) predict the impacts of the following on the EMERGENCY GENERA TORS (DIESEL/JET); and (b) based on 264000 EDGs X 4.2 86 those predictions, use procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations: LOCA A2.02 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; 215005 APRM / LPRM X 3.7 87 and (b) based on those predictions, use procedures to correct, controL or mitigate the consequences of those abnonnal conditions Upscale or downscale trips 2.2.42 - Equipment Control::
Ability to recognize system 212000 RPS X parameters that are entry-level 4.6 88 conditions for Technical Specifications.
2.2.4 - Equipment Control: (multi-unit license) Ability to explain the 400000 Component Cooling variations in control board layouts.
X 3.6 89 Water systems, instrumentation and procedural actions between units at a facility.
2.1.31 - Conduct of Operations:
Ability to locate control room 203000 RHR/LPCI: Injection X switches, controls, and indications, 4.3 90 Mode and to detennine that they correctly reflect the desired plant lineup.
Kl.04 - Knowledge of the physical connections and/or cause- effect relationships between HIGH 206000 HPCI X PRESSURE COOLANT 3.6 I INJECTION SYSTEM and the following: Reactor feedwater system: BWR-2,3,4 K1.17 - Knowledge of the physical connections and/or cause- effect relationships 262002 UPS (AC/DC) X between UNINTERRUPTABLE 3.1 2 POWER SUPPLY (AC./D.C.)
and the following: Scram solenoid valves: Plant-Specific K2.01 - Knowledge of electrical 26200 I AC Electrical X power supplies to the following: 3.3 3 Distribution Off-site sources of power K2.02 - Knowledge of electrical 211000 SLC X power supplies to the following: 3.1 4 Explosive valves
ES-401 4 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#
1 2 3 4 5 6 1 3 4 K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC 218000 ADS X 4.5 5 DEPRESSURIZATION SYSTEM will have on following: Ability to rapidly depressurize the reactor K3.04 - Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR 215004 Source Range Monitor X 3.7 6 (SRM) SYSTEM will have on following: Reactor power and indication K4.02 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM 215005 APRM / LPRM X 4.1 7 design feature(s) and/or interlocks which provide for the following: Reactor SCRAM signals K4.17 - Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design 259002 Reactor Water Level feature(s) and/or interlocks X 3.1 8 Control which provide for the following:
Simultaneous Manual and Auto operation of the system (i.e. 1 FP in Auto, 1 FP in Manual)
K5.01 - Knowledge of the operational implications of the following concepts as they apply 209001 LPCS X 2.6 9 to LOW PRESSURE CORE SPRAY SYSTEM: Indications of pump cavitation K5.02 - Knowledge of the operational implications of the following concepts as they apply 205000 Shutdown Cooling X to SHUTDOWN COOLING 2.8 10 SYSTEM (RHR SHUTDOWN COOLING MODE) : Valve operation K6.01 - Knowledge of the effect 400000 Component Cooling that a loss or malfunction of the X 2.7 II Water following will have on the CCWS: Valves K6.04 - Knowledge of the effect that a loss or malfunction of the 203000 RHR/LPCI: Injection following will have on the X 3.3 12 Mode RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) : Keep fill system A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the 212000 RPS X REACTOR PROTECTION 2.6 13 SYSTEM controls including:
RPS bus frequency: Plant-Specific
ES-401 4 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#
1 2 3 4 5 6 1 3 4 A 1.03 - Ability to predict and/or monitor changes in parameters associated with operating the 261000 SGTS X 3.2 14 STANDBY GAS TREATMENT SYSTEM controls including: Off-site release levels A2.05 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b) based on those predictions, 215003 IRM X use procedures to correct, 3.3 15 control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic operation of detectors/system A2.08 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEUJET) ; and (b) based on those predictions, use 264000 EDGs X procedures to correct, control, or 3.3 16 mitigate the consequences of those abnormal conditions or operations: Initiation of emergency generator room fire protection system A3.02 - Ability to monitor automatic operations of the 239002 SRVs X RELIEF/SAFETY VALVES 4.3 17 including: SRV operation on hiqh reactor pressure A3.01 - Ability to monitor automatic operations of the D.C.
263000 DC Electrical ELECTRICAL DISTRIBUTION X 3.2 18 Distribution including: Meters, dials, recorders, alarms, and indicating liqhts A4.01 - Ability to manually 300000 Instrument Air X operate and/or monitor in the 2.6 19 control room: Pressure gauges A4.05 - Ability to manually operate and/or monitor in the 217000 RCIC X 4.1 20 control room: Reactor water level 2.4.9 - Emergency Procedures/
Plan: Knowledge of low power/
223002 PCIS/Nuclear Steam shutdown implications in X 3.8 21 Supply Shutoff accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
2.4.20 - Emergency Procedures
/ Plan: Knowledge of operational 218000ADS X 3.8 22 implications of EOP warnings, cautions, and notes.
2.1.30 - Conduct of Operations:
Ability to locate and operate 215004 Source Range Monitor X 4.4 23 components, including local controls.
ES-401 4 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#
1 2 3 4 5 6 1 3 4 K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the 223002 PCIS/Nuclear Steam PRIMARY CONTAINMENT Supply Shutoff X 3.0 24 ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF :
Containment instrumentation K1 .17 - Knowledge of the physical connections and/or cause- effect relationships 203000 RHR/LPCl: Injection Mode X between RHR/LPCI: 4.0 25 INJECTION MODE (PLANT SPECIFIC) and the following:
Reactor pressure K2.02 - Knowledge of electrical 205000 Shutdown Cooling X power supplies to the following: 2.5 26 Motor operated valves KIA Category Totals: 3 3 2 2 2 3 2 212 2 2 3/3 Group Point Total: 26/5 I
ES-401 5 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # / Name A2 G Imp.
1 2 3 4 5 6 1 3 4 #
A2.0 I - Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTERNALS 290002 Reactor Vessel : and (b) based on those X 4.0 91 Internals predictions. use procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations: LOCA 2.2.25 - Equipment Control:
Knowledge of bases in technical 286000 Fire Protection X specifications for limiting 4.2 92 conditions for operations and safctv limits.
2.4.34 - Emergency Procedures/
Plan: Knowledge of RO tasks 214000 RPIS X pcrlonned outside the main control 4.1 93 room during an emergency and the resultant operational effects.
Kl.01 - Knowledge of the physical connections and/or cause- effect relationships between REACTOR 201002 RMCS X 3.2 27 MANUAL CONTROL SYSTEM and the following: Control rod drive hydraulic system K2.09 - Knowledge of electrical 22300 I Primary CTMT and power supplies to the following:
X 2.7 28 Aux. Drywell cooling fans: Plant-Specific K3.02 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION 288000 Plant Ventilation X 2.9 29 SYSTEMS will have on following:
Reactor building temperature:
Plant-Specific K4.05 - Knowledge of REACTOR VESSEL 290002 Reactor Vessel INTERNALS design feature(s)
X 3.3 30 Internals and/or interlocks which provide for the following: Natural circulation K5.09 - Knowledge of the operational implications of the following concepts as they apply 271000 Off-gas X 2.6 31 to OFFGAS SYSTEM :
Hydrogen and oxygen recombination K6.06 - Knowledge of the effect that a loss or malfunction of the 241000 Reactor/Turbine following will have on the X 3.8 32 Pressure Regulator REACTOR/TURBINE PRESSURE REGULATING SYSTEM : Reactor pressure A 1.10 - Ability to predict and/or monitor changes in parameters 239001 Main and Reheat associated with operating the X 3.8 33 Steam MAIN AND REHEAT STEAM SYSTEM controls including:
Reactor power
ES-401 5 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.
1 2 3 4 5 6 1 3 4 #
A2.12 - Ability to (a) predict the impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on those predictions, use 256000 Reactor Condensate X procedures to correct, control, 3.1 34 or mitigate the consequences of those abnormal conditions or operations: Loss of equipment component cooling water systems A3.01 - Ability to monitor automatic operations of the 201003 Control Rod and X CONTROL ROD AND DRIVE 3.7 35 Drive Mechanism MECHANISM including: Control rod position A4.01 - Ability to manually operate and/or monitor in the 214000 RPIS X 3.2 36 control room: RCIS rod action control bypass switches 2.4.2 - Emergency Procedures/
Plan: Knowledge of system set 214000 RPIS X points, interlocks and automatic 4.5 37 actions associated with EOP entry conditions.
A4.10 - Ability to manually 233000 Fuel Pool X operate and/or monitor in the 2.5 38 Cooling/Cleanup control room: Tank levels KIA Category Totals: 1 1 1 1 1 1 1 1/1 1 2 1/2 Group Point Total: 12/3 I
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: 2016 NRC Date:
RO SRO-Only Category K/A# Topic IR Q# IR Q#
Knowledge of new and spent fuel movement 2.1.42 3.4 94 procedures.
Ability to use procedures related to shift 2.1.5 staffing, such as minimum crew complement, 3.9 98 overtime limitations, etc.
- 1. Ability to direct personnel activities inside the 2.1.9 2.9 66 Conduct control room.
of Operations Knowledge of industrial safety procedures (such as rotating equipment, electrical, high 2.1.26 3.4 67 temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
Ability to manage the control room crew 2.1.6 3.8 75 durinq plant transients.
Subtotal 3 2 Ability to determine Technical Specification 2.2.35 4.5 95 Mode of Operation.
Ability to perform pre-startup procedures for the facility, including operating those controls 2.2.1 4.4 100 associated with plant equipment that could affect reactivity.
- 2. (multi-unit license) Ability to explain the Equipment variations in control board layouts, systems, 2.2.4 3.6 68 Control instrumentation and procedural actions between units at a facility.
Ability to interpret control room indications to verify the status and operation of a system, 2.2.44 4.2 69 and understand how operator actions and directives effect plant and system conditions.
Subtotal 2 2 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 3.1 96 portable survey instruments, personnel
- 3. monitorinq equipment, etc.
Radiation Control 2.3.11 Ability to control radiation releases. 3.8 70
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 2.9 71 portable survey instruments, personnel monitoring equipment, etc.
Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 74 responsibilities, access to locked high-radiation areas, aligning filters, etc.
Subtotal 3 1 Ability to take actions called for in the facility 2.4.38 emergency plan, including supporting or 4.4 97 acting as emergency coordinator if required.
Knowledge of abnormal condition 2.4.11 4.2 99 procedures.
4.
Emergency 2.4.17 Knowledge of EOP terms and definitions. 3.9 72 Procedures/
Ability to perform without reference to Plan procedures those actions that require 2.4.49 4.6 73 immediate operation of system components and controls.
Subtotal 2 2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/A's Form ES-401-4 Randomly Tier/ Group Reason for Rejection Selected KIA Q# 3 7 At LGS, there are no times when the RBM is used during Emergency Procedure use. This is due to the RBM 2/2 215002 / 2.4.18 supporting Control Rod Withdraw only.
Replaced with 214000 RPIS 2.4.2 Q# 96 Duplicated in operating test 3/3 G3 I 2.3.6 replaced with 2.3.15 295022 I Q# 85 The subject KIA isn't relevant at the subject facility.
1/2 AA2.03 Replaced with 295022 Loss of CRD Pumps A2.02