ML16188A251

Final Outlines (Folder 3)

ML16188A251
Person / Time
Site:	Calvert Cliffs
Issue date:	07/05/2016
From:	Jaeger J Exelon Generation Co
To:	David Silk Operations Branch I
Shared Package
ML15308A607	List: ML16012A008 ML16155A226 ML16188A232 ML16188A233 ML16188A234 ML16188A235 ML16188A237 ML16188A251 ML16188A279 ML16188A304 ML16229A510 ML16229A511
References
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Download: ML16188A251 (17)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility:

CALVERT CLIFFS NUCLEAR POWER PLANT Date of Exam: 06/13/2016 RO Category Kl A Points SRO Only Points Group Tier 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 1. Emergency

& 1 3 3 3 3 3 3 18 3 3 6 Abnormal Plant 2 1 2 1 NIA 2 2 NIA 1 9 2 2 4 Evolutions Tier Totals 4 5 4 5 5 4 27 5 5 10 1 3 2 3 3 2 2 3 3 2 2 3 28 3 2 5 2. Plant Systems 2 0 1 1 1 1 1 1 1 1 1 1 10 0 2 1 3 Tier Totals 3 3 4 4 3 3 4 4 3 3 4 38 5 3 8 1 2 3 4 1 2 3 4 3. Generic Knowledge

& Abilities Categories 10 7 2 3 2 3 2 1 2 2 Note: 1. Ensure that at least two topics from every applicable Kl 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 KIA 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 ofES-401 for guidance regarding the elimination of inappropriate Kl 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 Kl A categories.

7. *The generic (G) K/As in Tiers 1and2 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 D. l .b of ES-401 for the applicable K/As. 8. On the following pages, enter the Kl 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 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.

ES-401 PWR Examination Outline Form ES-401-2 Emergency

& Abnormal Plant Evolutions

-Tier 1 I Group 1 -REACTOR OPERA TOR E/APE #/Name/Safety Function K K K A A G KA Topic Imp Pts 1 2 3 1 2 007 Rx Trip -Stabilization

-Recovery EA2 -Ability to determine or interpret the x following as they apply to a reactor trip: 4.3 1 ( 1) EA2.06 -Occurrence of a reactor trip 2.1-Conduct of Operations 008 Pressurizer Vapor Space Accident x 2.1.28 -Knowledge of the purpose and 4.1 1 (3) function of major system components and controls.

EKl -Knowledge of the operational 009 Small Break LOCA implications of the following concepts as (3) x they apply to the small break LOCA: 4.2 1 EKl.01 -Natural circulation and cooling, including reflux boiling AK2 -Knowledge of the interrelations 000015/000017 RCP Malfunctions between the Reactor Coolant Pump x Malfunctions (Loss of RC Flow) and the 2.9 1 (4) following:

AK2.07 -RCP seals AK3 -Knowledge of the reasons for the 022 Loss of Rx Coolant Makeup x following responses as they apply to the 3.2 1 (2) Loss of Reactor Coolant Makeup: AK3.04 -Isolating letdown AK2 -Knowledge of the interrelations 025 Loss ofRHR System between the Loss of Residual Heat (4) x Removal System and the following:

2.6 1 AK2.05 -Reactor building sump AAl -Ability to operate and I or monitor the following as they apply to the Loss of 026 Loss of Component Cooling Water x Component Cooling Water: 2.9 1 (8) AAl.07 -Flow rates to the components and systems that are serviced by the CCWS; interactions among the components AK2 -Knowledge of the interrelations 027 Pzr Press Control Sys Malfunction between the Pressurizer Pressure Control (3) x Malfunctions and the following:

2.6 1 AK2.03 -Controllers and positioners 029 ATWS EA2-Ability to determine or interpret the (1) x following as they apply to a ATWS: 4.4 1 EA2.0l -Reactor nuclear instrumentation EKl -Knowledge of the operational 038 Steam Gen. Tube Rupture x implications of the following concepts as 3.1 1 (3) they apply to the SGTR: EKl.01 -Use of steam tables ES-401 PWR Examination Outline Form ES-401-2 Emergency

& Abnormal Plant Evolutions-Tier 1IGroup1 -REACTOR OPERATOR E/APE #/Name/Safety Function K K K A A G KA Topic Imp Pts 1 2 3 1 2 AK3 -Knowledge of the reasons for the 000054 Loss of Main Feedwater following responses as they apply to the (4) x Loss of Main Feedwater:

3.4* 1 AK3.02 -Matching offeedwater and steam flows 055 Station Blackout EA2 -Ability to determine or interpret the (6) x following as they apply to a SBO: 3.9 1 EA2.03 -Actions necessary to restore power 2.4 -Emergency Procedures I Plan 057 Loss of Vital AC Instrument Bus 2.4.49 -Ability to perform without reference (6) x to procedures those actions that require 4.6 1 immediate operation of system components and controls.

2.4 -Emergency Procedures I Plan 058 Loss of DC Power 2.4.49 -Ability to perform without reference (6) x to procedures those actions that require 4.6 1 immediate operation of system components and controls.

AAl -Ability to operate and/or monitor 062 Loss of Nuclear Service Water the following as they apply to the Loss of (4) x Nuclear Service Water): 3.2 1 AAl .02 -Loads on the SWS in the control room AAl-Ability to operate and I or monitor 065 Loss of Instrument Air x the following as they apply to the Loss of 3.5* 1 (8) Instrument Air: AAl .04-Emergency Air Compressor AKl -Knowledge of the operational 077 Generator Voltage and Electric Grid implications of the following concepts as x they apply to Generator Voltage and 3.3 1 Disturbances (6) Electric Grid Disturbances:

AKI .02 -Over-excitation EK3 -Knowledge of the reasons for the following responses as they apply to the CE/E05 Excess Steam Demand (4) x (Excess Steam Demand) EK3.3 -Manipulation of controls required to 3.8 1 obtain desired operating results during abnormal, and emergency situations KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 ES-401 PWR Examination Outline Form ES-401-2 Emergency

& Abnormal Plant Evolutions

-Tier 1 I Group 2 -REACTOR OPERA TOR El APE #IN amelSafety Function K K K A A G KA Topic Imp Pts 1 2 3 1 2 AK2 -Knowledge of the interrelations 003 Dropped Control Rod between the Dropped Control Rod and the x following:

2.5 1 (1) AK2.05 -Control rod drive power supplies and logic circuits AA2 -Ability to determine and interpret 024 Emergency Boration the following as they apply to the x Emergency Boration:

3.6 1 (1) AA2.06 -When boron dilution is taking place AKl -Knowledge of the operational 028 Pressurizer Level Malfunction implications of the following concepts as (2) x they apply to Pressurizer Level Control 2.8 1 Malfunctions:

AKl.01 -PZR reference leak abnormalities AAl -Ability to operate and I or monitor 061 ARM System Alarms x the following as they apply to Area 3.6 1 (7) Radiation Monitoring System Alarms: AAl.01 -Automatic actuation 068 Control Room Evacuation 2.1-Conduct of Operations (8) x 2.1.20 -Ability to interpret and execute 4.6 1 procedure steps. EK2 -Knowledge of the interrelations 074 Inadequate Core Cooling x between Inadequate Core Cooling and the 3.9 1 (4) following:

EK2.04 -HPI pumps AK3 -Knowledge of the reasons for the following responses as they apply to RCS CE/All RCS Overcooling x Overcooling:

2.9 1 (4) AK3.2 -Normal, abnormal and emergency operating procedures associated with (RCS Overcooling)

AAl -Ability to operate and I or monitor the following as they apply to Natural CE/A13 Natural Circulation Circulation Operations:

(4) x AAl.1 -Components, and functions of 3.3 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features AA2 -Ability to determine and interpret the following as they apply to Excess RCS CE/Al6 Excess RCS Leakage Leakage: (2) x AA2.2 -Adherence to appropriate 2.9 1 procedures and operation within the limitations in the facility's license and amendments KIA Category Totals: 1 2 1 2 2 1 Group Point Total: 9 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2 I Group 1 -REACTOR OPERATOR System/Evolution

1. /Name K K K K K K A A A A G KA Topic Imp Pts 1 2 3 4 5 6 1 2 3 4 K2 -Knowledge of bus power 003 Reactor Coolant Pump x supplies to the following:

3.1 1 K2.0l -RCPS 2.2 -Equipment Control 003 Reactor Coolant Pump x 2.2.12 -Knowledge of surveillance 3.7 1 procedures.

KS -Knowledge of the operational implications of the 004 Chemical and Volume x following concepts as they apply 3.2 1 Control to the eves: K5.16 -Source of TAVE. and TREF signals to control and RPS K3 -Knowledge of the effect that 005 Residual Heat Removal x a loss or malfunction of the RHRS will have on the following:

3.1

• 1 K3.06 -CSS K6 -Knowledge of the effect of a 006 Emergency Core Cooling loss or malfunction on the x following will have on the ECCS: 4.2 1 K6.13 -Pumps 2.4 -Emergency Procedures/Plan 006 Emergency Core Cooling x 2.4.31 -Knowledge of annunciator alarms, indications, or response 3.4 1 procedures.

Kl -Knowledge of the physical connections and/or cause-effect 007 Pressurizer Quench Tank x relationships between the PRTS 3.0 1 and the following systems: Kl.03 -RCS Kl -Knowledge of the physical connections and/or cause-effect 008 Component Cooling Water x relationships between the CCWS 3.0 1 and the following systems: Kl.05 -Sources of makeup water A4 -Ability to manually operate and/or monitor in the control 008 Component Cooling Water room: x 2.5* 1 A4.06 -Remote operation of hand-operated throttle valves to regulate CCW flow rate 010 Pressurizer Pressure K2 -Knowledge of bus power Control x supplies to the following:

3.0 1 K2.0l -PZR heaters ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 1 -REACTOR OPERATOR System/Evolution

1. IN ame K K K K K K A A A A G KA Topic Imp Pts 1 2 3 4 5 6 1 2 3 4 2.4 -Emergency 010 Pressurizer Pressure Procedures/Plan x 3.3 1 Control 2.4.18 -Knowledge of the specific bases for EOPs. K4 -Knowledge of RPS design feature(s) and/or interlock(s) which provide for the following:

012 Reactor Protection x K4.02 -Automatic reactor trip 3.9 1 when RPS setpoints are exceeded for each RPS function; basis for each K4 -Knowledge ofESFAS design feature(s) and/or 013 ESFAS x interlock( s) which provide for 4.3* 1 the following:

K4.04 -Auxiliary feed actuation signal A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those 022 Containment Cooling x predictions, use procedures to 2.6 1 correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 -Fan motor thermal overload/high-speed operation Al -Ability to predict aud/or monitor changes in parameters (to prevent exceeding design 026 Containment Spray x limits) associated with operating 2.7 1 the CSS controls including:

Al .06 -Containment spray pump cooling K4 -Knowledge of MRSS design feature(s) and/or interlock(s) 039 Main and Reheat Steam x which provide for the following:

3.7 1 K4.05 -Automatic isolation of steam line A4 -Ability to manually operate 059 Main Feedwater x and monitor in the control room: 3.1

• 1 A4.01 -SGFPT trip indication ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 1 -REACTOR OPERATOR System/Evolution

1. /Name K K K K K K A A A A G KA Topic Imp Pts 1 2 3 4 5 6 1 2 3 4 A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on 059 Main Feedwater x those predictions, use 2.9* 1 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 -Feeding a dry SIG K6 -Knowledge of the effect of a loss or malfunction of the 061 Auxiliary/Emergency x following will have on the AFW 2.5 1 Feedwater components:

K6.0l -Controllers and positioners Kl -Knowledge of the physical connections and/or cause-effect 062 AC Electrical Distribution x relationships between the ac 3.7 1 distribution system and the following systems: Kl .04 -Off-site power sources Al -Ability to predict and/or monitor changes in parameters associated with operating the 063 DC Electrical Distribution x DC electrical system controls 2.5 1 including:

Al.01 -Battery capacity as it is affected by discharge rate A3 -Ability to monitor automatic operation of the ED/G 064 EDG x system, including:

2.8 1 A3.IO-Function ofED/G megawatt load controller A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use 064 EDG x procedures to correct, control, 2.7 1 or mitigate the consequences of those malfunctions or operations:

A2.14 -Effects (verification) of stopping ED/G under load on isolated bus ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2 I Group 1 -REACTOR OPERATOR System/Evolution

1. /Name K K K K K K A A A A G KA Topic Imp Pts 1 2 3 4 5 6 1 2 3 4 KS -Knowledge of the operational implications as they 073 Process Radiation apply to concepts as they apply Monitoring x to the PRM system: 2.5 1 K5.0l -Radiation theory, including sources, types, units, and effects K3 -Knowledge of the effect that a loss or malfunction of the 076 Service Water x SWS will have onthe following:

3.5* 1 K3.03 -Reactor building closed cooling water A3 -Ability to monitor auto 076 Service Water x operation of the SWS, including:

3.7 1 A3.02 -Emergency heat loads K3 -Knowledge of the effect 078 Instrument Air that a loss or malfunction of the x IAS will have on the following:

3.0 1 K3.03 -Cross-tied units Al -Ability to predict and/or monitor changes in parameters (to prevent exceeding design 103 Containment x limits) associated with operating 3.7 1 the containment system controls including:

Al.01 -Containment pressure, temperature, and humidity Kl A Category Totals: 3 2 3 3 2 2 3 3 2 2 3 Group Point Total: 28 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2 I Group 2 -REACTOR OPERA TOR System/Evolution

1. /Name K K K K K K A A A A G KA Topic Imp Pts 1 2 3 4 5 6 1 2 3 4 A4 -Ability to manually operate and/or monitor in the control 002 Reactor Coolant x room: 3.4* 1 A4.08 -Safety parameter display systems 011 Pressurizer Level Control K2 -Knowledge of bus power System x supplies to the following:

3.1 1 K2.01 -Charging pumps KS -Knowledge of the operational implications of the 016 Non-nuclear x following concepts as they apply 2.7* Instrumentation to the NNIS system: K5.01 -Separation of control and protection circuits A3 -Ability to monitor automatic operation of the ITM, 017 In-core Temperature x including:

3.6* 1 Monitor A3.01 -Indications of normal, ' natural, and interrupted circulation of RCS Al -Ability to predict and/or monitor changes in parameters to prevent exceeding design 029 Containment Purge x limits) associated with operating 3.4 1 the Containment Purge System controls including:

Al.02 -Radiation levels K6 -Knowledge of the effect of a 035 Steam Generator loss or malfunction on the x following will have on the S/GS: 2.6 1 K6.03 -SIG level detector K4 -Knowledge of SDS design 041 Steam Dump/Turbine x feature(s) and/or interlock(s) 2.6* Bypass Control which provide for the following:

K4.16 -Low main steam pressure A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use 056 Condensate x Procedures to correct, control, 2.6 1 or mitigate the consequences of those malfunctions or operations:

A2.04 -Loss of condensate pumps ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 2 -REACTOR OPERATOR System/Evolution

1. /Name K K K K K K A A A A G KA Topic Imp Pts 1 2 3 4 5 6 1 2 3 4 2.2 -Equipment Control 2.2.44 -Ability to interpret control room indications to verify 068 Liquid Radwaste x the status and operation of a 4.2 1 system, and understand how operator actions and directives affect plant and system conditions.

K3 -Knowledge of the effect that a loss or malfunction of the 086 Fire Protection x Fire Protection System will have 2.7 1 on the following:

K3.0l -Shutdown capability with redundant equipment KIA Category Totals: 0 1 1 1 1 1 1 1 1 1 1 Group Point Total: 10 I ES-401 PWR Examination Outline Form ES-401-2 Emergency

& Abnormal Plant Evolutions

-Tier 1 I Group 1 -Senior Reactor Operator El APE #IN ame/Safety K K K A A G KA Topic Imp Pts Function 1 2 3 1 2 2.4 -Emergency Procedures I Plan 011 Large Break LOCA x 2.4.35 -Knowledge of local auxiliary 4.0 1 (3) operator tasks during an emergency and the resultant operational effects. AA2 -Ability to determine and interpret 040 Steam Line Rupture the following as they apply to the Steam x Line Rupture: 4.7 1 (4) AA2.02 -Conditions requiring a reactor trip AA2 -Ability to determine and interpret 056 Loss of Off-site the following as they apply to the Loss of x Offsite Power: 4.3 1 Power (6) AA2.32 -Transient trend of coolant temperature toward no-load TAvE 2.1 -Conduct of Operations 062 Loss of Nuclear x 2.1.23 -Ability to perform specific system 4.4 1 Service Water (4) and integrated plant procedures during all modes of plant operation.

EA2 -Ability to determine and interpret the following as they apply to the CE/E02 Reactor Trip -(Reactor Trip Recovery)

Stabilization

-Recovery x EA2.2 -Adherence to appropriate 4.0 1 (1) procedures and operation within the limitations in the facility's license and amendments 2.4 -Emergency Procedures/Plan 2.4.4 -Ability to recognize abnormal CE/E06 Loss of Main x indications for system operating 4.7 1 Feedwater (4) parameters that are entry-level conditions for emergency and abnormal operating procedures.

I KIA Category Totals: 0 0 0 0 3 3 Group Point Total: 6 ES-401 PWR Examination Outline Form ES-401-2 Emergency

& Abnormal Plant Evolutions

-Tier 1 I Group 2 -Senior Reactor Operator El APE #IN ame/Safety Kl K2 K3 Al A2 G KA Topic Imp Pts Function AA2 -Ability to determine and interpret 005 Inoperable/Stuck the following as they apply to the x Inoperable/Stuck Control Rod: 4.4 1 Control Rod (1) AA2.03 -Required actions if more than one rod is stuck or inoperable.

2.4 -Emergency Procedures I Plan 2.4.21 -Knowledge of the parameters and 032 Loss of Source logic used to assess the status of safety Range NI (7) x functions, such as reactivity control, core 4.6 1 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. 2.2 -Equipment Control 036 Fuel Handling x 2.2.39 -Knowledge of Jess than or equal to 4.5 1 Accident (8) one hour Technical Specification action statements for systems. AA2 -Ability to determine and interpret 051 Loss of Condenser x the following as they apply to the Loss of 2.7* 1 Vacuum (4) Condenser Vacuum: AA2.01 -Cause for low vacuum condition KIA Category Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2 I Group 1 -Senior Reactor Operator System/Evolution K K K K K K A A A A G KA Topic Imp Pts #/Name 1 2 3 4 5 6 1 2 3 4 A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on 005 Residual Heat those predictions, use x procedures to correct, control, 3.1 1 Removal or mitigate the consequences of those malfunctions or operations:

A2.03 -RHR pump/motor malfunction 2.4 -Emergency Procedures I Plan 2.4.49 -Ability to perform 012 Reactor Protection x without reference to procedures 4.4 1 those actions that require immediate operation of system components and controls.

A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on 022 Containment x those predictions, use 2.6 1 Cooling procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02 -Fan motor vibration A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on 039 Main and Reheat x predictions, use procedures to 3.2 1 Steam correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 -Flow paths of steam during a LOCA 061 2.2 -Equipment Control Auxiliary/Emergency x 2.2.38 -Knowledge of 4.5 1 Feedwater conditions and limitations in the facility license. I KIA Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2 /Group 2 -Senior Reactor Operator System/Evolution K K K K K K A A A A G KA Topic Imp Pts #/Name 1 2 3 4 5 6 1 2 3 4 2.2 -Equipment Control 015 Nuclear 2.2.42 -Ability to recognize Instrumentation x system parameters that are 4.6 1 entry-level conditions for Technical Specifications.

A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System ; and (b) based on 071 Waste Gas x those predictions, use 2.5 1 Disposal procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.06 -Supply failure to the isolation valve A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to 075 Circulating Water x correct, control, or mitigate 2.7* 1 the consequences of those malfunctions or operations:

A2.03 -Safety features and relationship between condenser vacuum, turbine trip, and steam dump I KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401 PWR Examination Outline Form ES-401-3 Tier 3 Generic Knowledge

& Abilities Outline -RO & SRO Facility:

CALVERT CLIFFS NUCLEAR POWER PLANT Date of Exam: 06/13/2016 RO SRO Category KIA# Topic IR Pts IR Pts 2.1.37 Knowledge of procedures, guidelines, or limitations 4.3 1 associated with reactivity management.

2.1.45 Ability to identify and interpret diverse indications to 4.3 1 Conduct validate the response of another indication.

of Ability to perform specific system and integrated plant Operations 2.1.23 procedures during all modes of plant operation.

4.4 1 2.1.40 Knowledge of refueling administrative requirements.

3.9 1 Subtotals:

2 2 Ability to perform pre-startup procedures for the facility, 2.2.1 including operating those controls associated with plant 4.5 1 equipment that could affect reactivity.

Ability to manipulate the console controls as required to Equipment 2.2.2 operate the facility between shutdown and designated power 4.6 1 levels. Control 2.2.13 Knowledge of tagging and clearance procedures.

4.1 1 ' 2.2.7 Knowledge of the process for conducting special or 3.6 1 infrequent tests. Subtotals:

3 1 2.3.11 Ability to control radiation releases. 3.8 1 Knowledge of radiation or contamination hazards that may 2.3.14 arise during normal, abnormal, or emergency conditions or 3.4 1 activities.

Radiation Ability to use radiation monitoring systems, such as fixed Control 2.3.5 radiation monitors and alarms, portable survey instruments, 2.9 1 personal monitoring equipment, etc. 2.3.6 Ability to approve release permits. 3.8 1 Subtotals:

2 2 2.4.13 Knowledge of crew roles and responsibilities during EOP 4.0 1 usage. 2.4.25 Knowledge of fire protection procedures. 3.3 1 Emergency 2.4.43 Knowledge of emergency communications systems and 3.2 1 Procedures/Plan techniques.

2.4.6 Knowledge ofEOP mitigation strategies.

4.7 1 2.4.40 Knowledge of SRO responsibilities in emergency plan 4.5 1 implementation.

Subtotals:

3 2 Tier 3 Totals 10 7 ES-401 Record of Rejected Kl As Form ES-401-4 Tier I Group Randomly Selected KIA Reason for Rejection This KIA is not applicable to plant since CCNPP utilizes Component RO 022 Loss of Reactor Cooling Water to cool the thermal barrier. KIA would be applicable at 111 Coolant Makeup a site that utilizes seal injection to help cool the barrier. Kept system AK3.06 and replaced KIA with one that had not been sampled. KIA AK3.04 was randomly selected using numbered poker chips. Spent several unsuccessful hours attempting to develop a question for RO 060 Accidental Gaseous this combination of system/Kl A. Randomly selected system from Radwaste Rel. systems that had not been sampled, using numbered poker chips. 1/2 A2.06 Replaced with System 024 Emergency Boration.

Kept A2 and randomly selected KIA using numbered poker chips. Replaced with A2.06. RO 003 Reactor Coolant This KIA is not applicable to the RO. Knowledge of bases in Technical Pump Specifications is a SRO responsibility.

Kept system and replaced KIA 2/1 2.2.25 with one that had not been sampled. KIA 2.2.12 was randomly selected using numbered poker chips. RO 010 Pressurizer Pressure This KIA is not applicable to plant and previously approved for Control suppression.

Kept system and replaced KIA with one that had not been 2/1 AK2.04 sampled. KIA AK2.01 was randomly selected using numbered poker chips. This Kl A is not applicable to plant since Containment Iodine Removal RO 027 Containment Iodine units are not monitored for temperature and there are no actions for the Removal operator to perform. Replaced system since there was only one KIA 2/2 A2.01 choice under A2 for the Containment Iodine Removal system. Replaced with System 056 Condensate and KIA A2.04. System and KIA were randomly selected using numbered poker chips. RO 068 Liquid Radwaste This Kl A is not applicable to the Liquid Radwaste System since Liquid Radwaste is common between the two units. Kept system 068 and 2/2 2.2.3 replaced Kl A with one that had not been sampled. Kl A 2.2.44 was randomly selected, using numbered poker chips. RO This Kl A is not applicable to the RO. Management of shutdown 2.2.18 maintenance activities is a SRO responsibility.

Replaced KIA with one 3/NA that had not been sampled. Kl A 2.2.1 was randomly selected, using numbered poker chips. Spent several unsuccessful hours attempting to develop a question for SRO 001 Continuous Rod this combination of system/KIA.

Randomly selected system from Withdrawal (1) systems that had not been sampled, using numbered poker chips. 1/2 A2.05 Replaced with System 005 Inoperable/Stuck Control Rod. Kept A2 and randomly selected KIA using numbered poker chips. Replaced with A2.03. SRO 032 Loss of Source Spent several unsuccessful hours attempting to develop a question for Range NI (7) this combination of system/Kl A. Kept system 032 and replaced Kl A 1/2 2.4.6 with one that had not been sampled. KIA 2.4.21 was randomly selected, using numbered poker chips. SRO 039 Main and Reheat NRC review resulted in recommendation to resample KIA. Kept Steam system 039 and replaced Kl A with one that had not been sampled. Kl A 211 A2.05 A2.01 was randomly selected, using numbered poker chips.

ES-401 Record of Rejected K/As Form ES-401-4