ML15314A052

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2015 Clinton Power Station Initial License Examination Forms ES-401-1 and ES-401-3
ML15314A052
Person / Time
Site: Clinton Constellation icon.png
Issue date: 11/09/2015
From:
NRC/RGN-III
To:
Exelon Generation Co
Zoia, C D
Shared Package
ML15124A069 List:
References
Download: ML15314A052 (11)
v • d • e


Text

ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Clinton Date of Exam: 3/16/2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G G* Total A2 Total 1 2 3 4 5 6 1 2 3 4

  • 1. 1 3 4 3 3 4 3 20 4 3 7 Emergency

& Abnormal 2 1 1 1 N/A 1 2 N/A 1 7 2 1 3 Plant Evolutions Tier Totals 4 5 4 4 6 4 27 6 4 10 1 3 3 2 3 2 2 2 3 2 2 2 26 3 2 5 2. Plant 2 1 1 1 1 2 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 4 4 3 4 4 3 3 4 3 3 3 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 10 7 3 2 3 2 2 2 2 1 Note: 1. Ensure that at least two topics from every applicable KJA 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 KJA 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 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 KJA 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 (IA) 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 KJA categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJA 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 KJA catalog, and enter the KJA numbers, descriptions

, I Rs, and point totals(#)

on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. ES-401, Page 16 of 33 ES-401 2 Form ES-401 .. ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 1 (RO) Q# E/APE #I Name I Safety Function K K K A A G 1 2 3 1 2 KIA Topic(s)

IR # 46 1295001 Partial or Complete Loss of Forced 0 Knowledge of the reasons for the following responses as they apply to Partial or Core Flow Circulation

/ 1 & 4 6 Complete Loss of Forced Core Flow Circulation: Core flow indication 2.9 1 58 295003 Partial or Complete Loss of AC I 6 0 Knowledge of the interrelations between Partial or Complete Loss of AC and the 4 following

A.G. electrica l loads 3.4 1 53 295004 Partial or Total Loss of DC Pwr 16 0 Ability to determine and/or interpret the following as they apply to Partial or Total 4 Loss of DC Pwr: System lineups 3.2 1 39 295005 Main Turbine Generator Trip I 3 0 Knowledge of the operational implications of the following concepts as they appty to 3 Main Turbine Generator Trip: Pressure effects on reactor level 3.5 1 50 1295006 SCRAM I 1 0 Ability to operate and/or monitor the following as they apply to SCRAM: Neutron 5 monitoring system 4.2 1 49 1295016 Control Room Abandonment 17 0 Ability to operate and/or monitor the following as they apply to Control Room 8 Abandonment:

Reactor pressure 4.0 1 47 1295018 Partial or Total Loss of CCW / 8 0 Knowledge of the reasons for the fonowing responses as they apply to Partial or 1 Total Loss of CCW: Isolation of non-essential heat loads: Plant-Specttic 2.9 1 43 1295019 Partial or Total Loss of Inst. Air/ 8 0 Knowledge of the interrelations between Panial or Total Loss of Inst. Air and the 1 following

CRD hydraulics 3.8 1 44 1295021 Loss of Shutdown Cooling/

4 0 Knowledge of the interrela tions between Loss of Shutdown Cooling and the 6 following

Reactor vessel headspray
Plant-Specific 2.5 1 54 1295023 Refueling Ace I 8 01. Ability to pertorm specific system and integrated plant procedures during all modes 23 of plant operatton

. 4.3 42 1295024 High Drywell Pressure I 5 0 Knowledge of the interrelat ions between High Drywall Pressure and the following

2 HPCS: Plant-Specttic 3.7 1 57 1295025 High Reactor Pressure I 3 0 Ability to determine and/or interpret the following as they appty to High Reactor 3 Pressure: Suppression pool temperature 3.9 1 45 295026 Suppression Pool High Water -0 Ability to determine and/or interpret the following as they appty to Suppression Poot tTemp. / 5 1 High Water Temp.: Suppression pool water temperature 4.1 1 55 1295027 High Containment Temperature/

5 . 01. Ability to evaluate plant performance and make operational judgments based on 07 operating characteristics, reactor behavior, and instrument interpretation. 4.4 1 56 1295028 High Drywell Temperature/

5 02. Ability to interpret control room indications to verify the status and operation of a 44 system, and understand how operator actions and directives affect plant and system 4.2 1 conditions.

51 1295030 Low Suppression Pool Wtr Lvl I 5 0 Ability to determine and/or interpret the following as they apply to Low Suppressio n 3 Pool Wtr Lvt: Reactor pressure 3.7 1 41 1295031 Reactor Low Water Level/ 2 0 Knowledge of the operational implications of the following concepts as they apply to 3.7 1 3 !'.1* Reactor Low Water Level: Water level effects on reactor power 1295037 SCRAM Condition Present and I; Knowledge of the operaHonal implicatlons of the following concepts as they appty to 40 Reactor Power Above APRM Downscale or 0 6 SCRAM Condition Present and Reactor Power Above APRM Downscale or 4.0 1 Unknown/

1 1, Unknown: Cooldown effects on reactor power 52 295038 High Off-site Release Rate/ 9 0 Knowledge of the reasons for the following responses as they apply to High Off-site 4 Release Rate: Emergency depressurization 3.6 1 48 600000 Plant Fire On Site I 8 0 9 1, Ability to operate and/or monitor the following as they apply to Plant Fire On Site: Plant fire zone panel (inducting detector k>catton) 2.5 1 700000 Generator Voltage and Electric Grid ' Disturbances I 6 0 . KIA Category Totals: 3 4 3 3 4 3 Group Point Total: r ES-401, Page 17 of 33 ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2 (RO) Q# E/APE #I Name I Safety Function K K K A 1:A G KIA Topic(s)

IR # 1 2 3 1 I< 62 1295002 Loss of Main Condenser Vac I 3 0 Ability to operate and/or monitor the following as they apply to Loss of Main 5 Condenser Vac: Main turbine 3.2 1 Ii l.295007 High Reactor Pressure I 3 ' 0 u , 295008 High Reactor Water Level I 2 1, 0

  • 63 295009 Low Reactor Water Level I 2 If 0 Ability to determine and/or interpret the following as they apply to Low Reactor 3.6 1 1.,2 Water Level: Steam flow/feedflow mismatch 1295010 High Drywell Pressure I 5 It 0 1 . 64 1295011 High Containment Temp I 5 i 04. ' .. 46 Ability to verify that the alarms are consistent with the plant conditions.

4.2 1 295012 High Drywell Temperatu re I 5 I>>. 0 111 1295013 High Suppression Pool Temp. I 5 1, '. 0 60 1295014 Inadvertent Reactivity Addition I 1 1 I> Knowledge of the interrelations between Inadvertent Reactivity Addition and the 1 ' foUowing:

Recirculation flow control 3.6 1 61 1295015 Incomplete SCRAM I 1 0 ii ' Knowk!dge of the reasons for the following responses as they apply to Incomplete

  • ,* 3.4 1 1 SCRAM: Bypassing rod insertion blocks rt* ._ 295017 High Off-site Release Rate I 9 11* 0 l 1295020 Inadvertent Cont. Isolation I 5 & 7 0 . 59 1295022 Loss of CRD Pumps I 1 0 Knowledge of the operational implications of the following concepts as they apply to 1
  • Loss of CAD Pumps: Reactor pressure vs. rod insertion capability 3.3 1 65 1295029 High Suppression Pool Wtr Lvl I 5 Ability to determine and/or interpret the following as they apply to High Suppression 1, i Pool Wtr Lvl: Suppression pool water level 3.5 1 295032 High Secondary Containment Area IT emperature I 5 0 1295033 High Secondary Containment Area Radiation Levels I 9 ' 0 1295034 Secondary Containment Ventilation High Radiation I 9 ... 0 l295035 Secondary Containment High . Differential Pressure I 5 0 295036 Secondary Containment High Sump/Area Water Level I 5 lei' 0 .. 500000 High CTMT Hydrogen Cone. I 5 , < 0 IKIA Category Totals: 1 1 1 1 '2 1 Group Point Total: 7 ES-401, Page 18 of 33

IA I. 1 2 3 4 5 6 1 2 3 4 4 203000 RHR/LPCI:

Injection Mode 0 Knowledge of electrical power supplies to the following

Initiation logic 2.7 1 3 7 205000 Shutdown Cooling 0 Knowledge of Shutdown Cooling design feature(s) and/or interlocks whk:h 3.7 1 2 provide for the following:

High pressure isolation

Plant-Specific 206000 HPCI 0 Isolation (Emergency) 0 Condenser 21 209001 LPCS 02. Ability to analyze the effect of maintenance activities

, such as degraded power 3.1 1 36 sources, on the status of limiting conditions for operations

. 0 01. Knowledge of the physical connections and/or cause-effect relationships between 2.5; 2,22 209002 HPCS 9 27 HPCS and the foUowing: Leak detection:

BWA-5, 6; Knowledge of system 3.9 2 purpose and/or functk>n. 17 211000 SLC 0 Ability to monitor automatic operations of the SLC including

Flow indication:

4.1 1 5 Plant-Specific 6 212000 RPS 1 Knowledge of the effect that a loss Of of the RPS will have on 3.0 1 1 following

Recirculation system 1 215003 IRM 0 Knowledge of the physical connecttons and/or cause-effect relationships between 3.0 1 7 IAM and the following
Reactor vessel 19 215004 Source Range Monitor 0 Ability to manually operate and/or monitor in the control room: Alarms and lights 3.2 1 6 0 0 Knowledge of electrical power supplies to the following
APRM channels; 2.6; 3,24 215005 APRM I LPRM 2 6 Knowledge of APRM I LPRM design feature(s) and/or inter1ocks which provide 2.6 2 for the following
Effects of detector aging on LPRM/APRM readings 10, 0 0 Knowledge of electrical power supplies to the following: Motor operated valves; 2.8; 25 217000 RCIC 1 2 Knowledge of the operational implications of the following concepts as they apply 3.1 2 to RCIC: Flow indicatioo 14 218000 ADS 0 Ability to predK;t and/or monitor changes in parameters associated with operating 3.4 1 1 the ADS contrOO; including
ADS valve tail pipe temperatures 8 223002 PCIS/Nuclear Steam Supply 0 Knowledge of PCIS/Nuctear Steam Supply Shutoff design feature(s) and/or 3.0 1 Shutoff 1 interlocks which provide for the following
Redundancy 18 239002 SRVs 0 Ability to monitor automatic operaUons of the SAVs including
Acoustical monitor 3.6 1 ' 4 noise: Plant-Specttic 11 259002 Reactor Water Level Control 0 Ability to manually operate and/or monitor in the control room: All individual 3.7 1 2 component controllers in the automatic mode Ability to (a) predict the impacts of the following on the SGTS; and (b) based on 16 261000 SGTS 1 those predictions, use procedures to correct,
control, or mitigate the 3.2 1 1 consequences of those abnormal conditions or operations
High containment pressure Knowledge of the physical connections and/or cause.effect relationships between 15, AC Electrical Distribution and the following
Emergency generatOfS (dieseViet);

262001 AC Electrical Distribution 0 . 1 Ability to (a) predict the impacts of the following on the AC Electrical Distribution; 3.8; 2 26 1 1 and {b} based on those predichons, use procedures to correct,

control, or 3.2 mijigate the consequences of those abnonnaf concitions Of operations
Degraded system voltages 20 262002 UPS (AC/DC) 0 Knowledge of the effect that a loss Of mattunction of the following will have on 2.7 1 the UPS (AC/DC): A.C. electrical power 1 263000 DC Electrical Distribution 0 Knowledge of the effect that a loss or mattunc1ion of the DC Electrical Oistributioo 5 will have on following
Systems wlth O.C. components

{i.e. valves, motors, 3.4 1 3 solenoids.

etc.) : Ability to predict and/or monitor changes in parameters associated with operating 13, 0 0 the EDGs controls including

Operating voltages, currents, and temperatures
264000 EDGs Ability to (a) predict the impacts of the following on the EDGs
and (b) based on 2.8; 2 23 3 3 those predictions

, use procedures to correct,

control, or mitigate the 3.4 consequences of those abnormal conditions or operations
Operating unloaded, lightly loaded. and highly loaded 9 300000 Instrument Air ' 1 3 Knowledge of the operational implications of the following concepts as they apply 2.9 lo Instrument Air : Fitters 1 12 400000 Component Cooling Water 0 Knowledge of the effect that a k>ss or malfunction of the following will have on 2.9 1 6 the Component Cooling Water: Heat exchangers and condensers KIA Category Totals: 3 3 2 3 2 2 2 3 2 2 1/ Group Point Total: 26 ES-401, Page 19 of 33 ES-401-1 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier 2 (RO) Q# System # I 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 . Ability to (a) predict the impacts of the following on the CAD Hydraulic System; 34 1201001 CRD Hydraulic 0 and (b) based on those predictions, use procedures to correct,

control, or 3.0 1 3 mitigate the consequences of those abnormal conditions or operations
Power suoplv failures 201002 RMCS 0 201003 Control Rod and Drive Mechanism

' 0 201004 RSCS t 0 ' 201005 RCIS 0 201006 RWM i 0 29 ?02001 Recirculation 0 Ability to monitor automatic operations of the Recirculation including: Pump trips: 3.3 1 7 Plant-Specific I 1202002 Recirculation Flow Control T 0 ' 1204000 RWCU ' 0 1214000 RPIS ' 0 1215001 Traversing In-core Probe 0 1215002 RBM 11* 0 33 1216000 Nuclear Boiler Inst. 0 Ability to predtct and/or monitor changes in parameters associated with 2.9 1 3 operating the Nuclear Boiler Inst. controls including

Surveillance testing 1219000 RHR/LPCI: Torus/Pool Cooling 0 Mode 27 223001 Primary CTMT and Aux. 0 ' Knowledge of the physical connections and/or cause-effect relationships 3.4 1 6 l between Primary CTMT and Aux. and the following
RHR/LPCI 31 226001 RHR/LPCI:

CTMT Spray Mode 0 Ability to manually operate and/or monitor in the control room: System flow 3.2 1 8 230000 RHR/LPCI:

Torus/Pool Spray Mode 0 28 233000 Fuel Pool Cooling/Cleanup 0 Knowledge of the effect that a loss or mattunction of the following will have on 2.5 1 1 the Fuel Pool Cooling/Cleanup

A.C. electrical power 234000 Fuel Handling Equipment

" I' 0 .. 36 239001 Main and Reheat Steam 0 Knowledge of the operational implications of the following concepts as they 2.8 1 6 apply to Main and Reheat Steam: Air operated MSIV's 1239003 MSIV Leakage Control 0 35 1241000 Reactorffurbine Pressure Regulator 0 . Knowledge of the effect that a loss or matt unction of the Reactor/Turbine 4.1 1 6 Pressure Regulator will have on following:

Bypass valves 1245000 Main Turbine Gen. I Aux. 0 1256000 Reactor Condensate 0 32 1259001 Reactor Feedwater 0 Knowledge of electrical power supplies to the following

RFP auxiliary oil 3 268000 Radwaste II 0 271000 Offgas 0 272000 Radiation Monrtoring 0 286000 Fire Protection 0 30 288000 Plant Ventilation 0 Knowledge of Plant Ventilation design feature(s) and/or intertocks which provide 3.7 1 , for the following
AutomaUc initiation of standby gas treatment system ,, 1290001 Secondary CTMT 0 38 1290003 Control Room HVAC 0 Knowledge of the operational implications of the following concepts as they 2.8 1 2 apply to Control Room HVAC : Differential pressure control 37 1290002 Reactor Vessel Internals
04. Knowledge of the specific bases for EOPs. 3.3 1 18 KIA Category Totals: 1 1 1 1 2 1 1 1 1 1 1 Group Point Total: 12 ES-401, Page 20 of 33 ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-4-.. Emergency and Abnormal Plant Evolutions -Tier 1/Group 1 (SRO) Q# E/APE #I Name I Safety Function K K K A A G KIA Topic(s)

IA # 1 2 3 1 2 79 295001 Partial or Complete Loss of Forced 02. Ability to recognize system parameters that are entry-level conditions for 4.6 1 Core Flow Circulation I 1 & 4 42 Technical Specifications

. 295003 Partial or Complete Loss of AC I 6 0 77 295004 Partial or Total Loss of DC Pwr I 6 0 Ability to determine and/or interpret the following as they apply to Partial or 2.9 1 3 Total Loss of DC Pwr: Battery voltage 295005 Main Turbine Generator Trip I 3 0 81 295006 SCRAM I 1 02. Ability to apply Technical Specifications for a system. 4.7 1 40 82 295016 Control Room Abandonment 17 0 Ab[lity to determine and/or interpret the following as they apply to Control 4.3 1 2 Room Abandonment:

Reactor water level 29501 B Partial or Total Loss of CCW I B 0 295019 Partial or Total Loss of Inst. Air I B 0 295021 Loss of Shutdown Cooling I 4 < 0 295023 Refueling Ace I 8 1295024 High Drywell Pressure I 5 0 1295025 High Reactor Pressure I 3 0 78 1295026 Suppression Pool High Water '0 Ability to determine and/or interpret the following as they apply to 4.2 1 ITemp. / 5 1 Suppression Pool High Water Temp.: Suppression pool water temperature 76 295027 High Containment Temperature/ 5 0 Ability to determine and/or interpret the following as they apply to High 3.3 1 I*/ 3 Containment Temperature:

Reactor pressure: Mark-Ill

' 295028 High Drywell Temperature/

5 0 295030 Low Suppression Pool Wtr Lvl I 5 ! 0 ?95031 Reactor Low Water Level/ 2 0 1295037 SCRAM Condition Present land Reactor Power Above APRM 0 Downscale or Unknown / 1 1295038 High Off-site Release Rate / 9 ; 0 600000 Plant Fire On Site I B 0 BO 700000 Generator Voltage and Electric Grid IC* 02. Ability to determine operability and/or availability of safety related 4.6 1 Disturbances I 6 37 equipment.

11 KIA Category Totals: 0 0 0 0 I' 4 3 Group Point Total: , ES-401, Page 17 of 33 ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2 (SRO) Q# E/APE #I Name I Safety Function K K K A A G KIA Topic(s)

IA # 1 2 3 1 2

  • 295002 Loss of Main Condenser Vac I 3 0 83 295007 High Reactor Pressure I 3 0 Ability to determine and/or interpret the following as they apply to High Reactor 4.1 1 2 Pressure: Reactor power 295008 High Reactor Water Level I 2 0 295009 Low Reactor Water Level I 2 0 1295010 High Drywell Pressure I 5 0 1295011 High Containment Temp I 5 > 0 04. Knowledge of the parameters and logic used to assess the status of safety 84 1295012 High Drywell Temperature I 5 21 functions

. such as reactivity

control, core coofing and heat removal, reactor coolant 4.6 1 system integrity, containment conditions, radioactivity release control, etc. 1295013 High Suppression Pool Temp. I 5 0 1295014 Inadvertent Reactivity Addition I 1 0 295015 Incomplete SCRAM I 1 0 I* 295017 High Off-site Release Rate I 9 0 .. 295020 Inadvertent Cont. Isolation I 5 & 7 0 295022 Loss of CAD Pumps I 1 It 0 ' 1295029 High Suppression Pool Wtr Lvl I 5 0 85 1295032 High Secondary Containment Area o* Ability to determine and/or interpret the following as they apply to High Secondary 3.8 1 IT emperature I 5 1 Containment Area Temperature
Area temperature 1295033 High Secondary Containment Area 0 Radiation Levels I 9 295034 Secondary Containment Ventilation 0 High Radiation I 9 295035 Secondary Containment High 0 Differential Pressure I 5 295036 Secondary Containment High 0 Sump/Area Water Level I 5 500000 High CTMT Hydrogen Cone. I 5 0 KIA Category Totals: 0 0 0 0 2* 1 Group Point Total: 3 ES-401, Page 18 of 33 ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-111 Plant Systems -Tier 2/Group 1 (SRO) Q# System # I Name K K K K K K A A A A G KIA Topic(s)

IR # 1 2 3 4 5 6 1 2 3 4 88 203000 RHR/LPCI: Injection 01. 20 Ability to interpret and execute procedure steps. 4.6 1 0 Ability to (a) predict the impacts of the following on the Shutdown Cooling: and 86 205000 Shutdown Cooling Mode 3 (b) based on those predictions, use procedures to correct,

control, or mitigate 3.2 1 the consequences of those abnormal conditions or operations: A.C. failure 206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser 209001 LPCS 0 209002 HPCS 0 *' 211000 SLC 0 212000 RPS 0 215003 IRM 0 215004 Source Range Monitor 0 1215005 APRM I LPRM 0 89 217000 RCIC 04. Knowledge of low power/shutdown implications in accident (e.g., k>ss of 4.2 09 coolant accident or loss of residual heat removal) mitigation strategies.

1218000 ADS 0 223002 PCIS/Nuclear Steam Supply Ability to (a) predict the impacts of the following on the PCIS/Nudear Steam 87 0 Supply Shutoff; and (b) based on those predictions

, use procedures to correct, 3.2 1 Shutoff 1,2 control, or mitigate the consequences of those abnormal conditions or operations:

O.C. electrica l distribution failures 239002 SRVs 0 1; . 259002 Reactor Water Level Control 0 261000 SGTS 0 262001 AC Electrical Distribution 0 I< 262002 UPS (AC/DC) 0 -0 Ability to (a) predict the impacts of the following on the DC Electrical 90 263000 DC Electrical Distribution Distribution; and {b) based on those predictions, use procedures to correct, '<1 control, or mitigate the consequ.ences of those abnormal conditions or 3.2 1 \. ooerations:

Grounds 264000 EDGs / 0 ' 300000 Instrument Air 11-0 II 400000 Component Cooling Water I" 0 1r

  • KIA Category Totals: 0 0 0 0 0 0 0 1;3 0 0 Group Point Total: 5 ES-401, Page 19 of 33 ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier 2/Group 2 (SRO) Q# System # I Name K K K K K K A A A A \, KIA Topic(s) 1 2 3 4 5 6 1 2 3 4 G IR # 201001 CRD Hydraulic ; 0 ?01002 RMCS !*. t I 0 201003 Control Rod and Drive Mechanism

,f ' 0 201004 RSCS 0 1201005 RCIS 0 1201006 RWM 0 1202001 Recirculat ion J 0 ' Ability to (a) predict the impacts of the following on the Recirculation Flow 93 1202002 Recirculation Flow Control 0 Control; and (b) based on those predictions

, use procedures to correct, control, 3.3 1 9 ,, or mitigate the consequences of those abnormal conditions or operations

Recirculation flow mismatch: Plant-Specific l204000RWCU 0 Ability to (a) predict the impacts of the following on the RWCU; and (bl. based 91 6 on those predictions

, use procedures to correct,

control, or mitigate the 2.6 1 *' consequences of those abnormal conditions or operations
A.C. fallure 92 1214000 RPIS 02. Knowledge of the bases in Technical Specifications for limiting conditions for 4.2 1 *25 operations and safety limits. 1215001 Traversing In-core Probe 0 1215002 RBM 0 1216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 0 Mode ' 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode I : 0 233000 Fuel Pool Cooling/Clea

.nup I 0 , .. 234000 Fuel Handling Equipment I' -0 239001 Main and Reheat Steam 0 1239003 MSIV Leakage Control 1:* 0 1241000 Reactor/Turbine Pressure Regulator 0 1245000 Main Turbine Gen. I Aux. 0 1256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 1290001 Secondary CTMT 0 1290003 Control Room HVAC 0 1290002 Reactor Vessel Internals 0 KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 20 of 33 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

!Facility Name:Clinton Date of Exam:3/16/2015 I Category KIA# Topic RO SHU-Only -IR IR Q# # # 94 2.1. 34 Knowledge of primary and secondary plant chemistry limits. 2.7 3.5 1 -98 2.1. 09 Ability to direct personnel activities inside the control room. 2.9 4.5 1 -66 2.1. 45 Ability to identify and interpret diverse indications to validate the response of another 4.3 1 4.3 1. indicator

. -67 Conduct of 2.1. 29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. 4.1 1 4.0 -Operations 75 2.1. 32 Ability to explain and apply system limits and precautions

. 3.8 1 4.0 -2.1. -Subtotal 3 2 95 2.2. 15 Ability to determine the expected plant configuration using design and configuration 3.9 4.3 1 control documentation

, such as drawings, line-ups, tag-outs. etc. -100 2.2. 14 Knowledge of the process for controlling equipment configuration or status. 3.9 4.3 1 -68 2. 2.2. 22 Knowledge of limiting conditions for operations and safety limits. 4.0 1 4.7 -69 Equipment 2.2. 21 Knowledge of pre-and post-maintenance operability requirements

. 2.9 1 4.1 ,___ Control 2.2. -2.2. --Subtotal 2 2 96 2.3. 05 Ability to use radiation monitoring

systems, such as fixed radiation monitors and alarms, 2.9 2.9 1 portable survey instruments.

personnel monitoring equipment

. etc. ,____ Knowledge of radiological safety procedures pertaining to licensed operator duties. such 99 2.3. 13 as response to radiation monitor alarms. containment entry requirements

, fuel handling 3.4 3.8 1 responsibilities

. access to locked high-radiation areas, aligning filters, etc. -70 3. 2.3. 11 Ability to control radiation releases. 3.8 1 4.3 -Radiation 71 Control 2.3. 15 Knowledge of radiation monitoring systems. such as fixed radiation monitors and alarms, 2.9 1 3.1 portable survey instruments.

personnel monitoring equipment, etc. -74 2.3. 14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 3.4 1 3.8 or emergency conditions or activities

. -2.3 . .......__

-Subtotal 3 2 97 2.4. 25 Knowledge of fire protection procedures.

3.3 3.7 1 ,____ Knowledge of EOJ;' implementat ion hierarchy and coordination with other support 72 2.4. 16 procedures or guidelines such as, operating procedures. abnormal operating procedures, 3.5 1 4.4 -and severe accident manaoement ouidelines. 73 4. 2.4. 04 Ability to recognize abnormal indications for system operating parameters that are entry-4.5 1 4.7 level conditions for emergency and abnormal operating procedures

. -Emergency Procedures 2.4. -I Plan 2.4. -2.4. -Subtotal 2 1 Tier 3 Point Total 10 7 ES-401, Page 26 of 33 Written Exam Status NUREG-1021-Rev 9 Sup 1 Criteria "O :>: "O :>: "O :>: "O :>: GI :>: GI :>: GI :>: 0 GI :>: 0 "O GI 0 "O GI 0 "O GI a: "O GI a: GI > GI > "O GI a: GI > GI *:.; "O GI > GI *:.; "O GI > GI > "O > GI GI "O *:.; GI GI a: "O GI > GI GI I/) "O GI > GI GI GI 0 GI GI GI 0 GI 0 GI 0 c. a: iii c. GI a: iii GI a: iii GI IF-u D:. a: c u D:. a: c u Cl D:. a: *;:: u Cl ll: a: GI :0 .I::. :!:? Cl GI :0 .I::. :!:? Cl GI :0 .I::. :!:? Cl GI :0 .I::. Qi -,.. 0 iii ;;; ,.. 0 ;;; ,.. 0 ;;; ,.. .. GI GI Ul GI 0 .. Qi GI Ul GI iii 0 .. Qi GI Ul GI iii 0 .. Qi GI Ul 0 I/) a. a: a. I-> (.) 0 I/) a. a: a. I-> (.) 0 I/) a. a: a. I-> (.) 0 I/) a. a: a. f-Total 100 10 0 0 0 63 ' .Jo, ,4 !* ,,, . ** I ,,, *1*, ; 25 2 0 0 0 19 25' 1 0 0 0 10 25 1 0 0 0 12 25 6 0 0 1 x N M 26 x N M 51 x N M 76 x N 2 x B H 27 x M M 52 x B M 77 x N 3 x B M 28 x B M 53 x B M 78 x M 4 x B H 29 x B M 54 x M H 79 x M x 5 x B H 30 x B M 55 x N M 80 x N 6 x N H 31 x N H 56 x N H 81 x N 7 x N x H 32 x N M 57 x N H 82 x N 8 x B M 33 x N M 58 x M H 83 x N x 9 x N M 34 x N H 59 x B H 84 x B 10 x B H 35 x B H 60 x B M 85 x B 11 x N H 36 x N M 61 x B M 86 x N 12 x B H 37 x B M 62 x B x H 87 x N 13 x N H 38 x N M 63 x N H 88 x N 14 x N H 39 x N H 64 x B M 89 x N 15 x B H 40 x B M 65 x B H 90 x N 16 x N H 41 x B M 66 x N H 91 x N 17 x B M 42 x M H 67 x N M 92 x N 18 x N H 43 x B H 68 x B M 93 x N 19 x B H 44 x N M 69 x N M 94 x B x 20 x B H 45 x B M 70 x B M 95 x N x 21 x N H 46 x N x H 71 x B M 96 x M 22 x B H 47 x N H 72 x N H 97 x B x 23 x N x H 48 x B M 73 x B H 98 x B 24 x B M 49 x B H 74 x N H 99 x B x 25 x B H 50 x B H 75 x B M 100 x N *" "' <"' , .. '" ' " *)4 ,., . : !Questions Ready_ to Validate RO Exam Totals Combined Exam Totals Memory (30-37) Memory Memory Higher (38-45) Higher Higher New High New High \lew High New New New Modified Modified Modified Bank Bank (<76) Bank (<19) Ref Provided Ref Provided

(<11) Provided

(<7) Selected

-draft question was found in any bank or new question drafted OR question is ready for psychometric or technical reviews (X is ready for review I D is drafted) Pedigree

-Question pedigree New I Modified I Direct from Bank Ref Provided

-A reference is provided for the question (X-yes) Reviewed

-question has been checked for Technical accuracy, Psychometrics, KIA match, and SRO only applicability

. (Xis OK IT, P, Kor S indicates issue) Validated

-question validated by operators (X) Cognigitive

-Question cognitive level Memory I Higher (Comprehens ion, Analysis, etc) Exelon Nuclear Confidential 1/13/2015 "O GI .! "' c :!:? Cl iii 0 > (.) 0 22 H H H H H H H H H H H H H H H H M H H H H H M H M 3 22

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