ML100880263

2009-09-Final Written Exam Outline

ML100880263
Person / Time
Site:	Cooper
Issue date:	09/21/2009
From:	Garchow S Operations Branch IV
To:	Nebraska Public Power District (NPPD)
References
50-298/09-301, ES-401-1
Download: ML100880263 (14)

Text

ES-401 Written Examination Outline Form ES-401-1 Facility: ILT Class 08-01 NRC Date of Exam:

RO K/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 *

1. 1 5 2 3 4 3 3 20 4 3 7 Emergency

& 2 2 1 1 1 1 1 7 1 2 3 Plant Tier Evolutions 7 3 4 5 4 4 27 5 5 10 Totals 1 2 2 2 3 2 3 2 2 2 3 3 26 3 2 5 2.

Plant 2 2 1 1 2 1 1 0 1 1 1 1 12 0 1 2 3 Systems Tier 4 3 3 5 3 4 2 3 3 4 4 38 4 4 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 2 3 2 3 2 2 2 1 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).

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 D.1.b of ES-401, for guidance regarding 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 KAs 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 (IR) 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. 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 10CFR55.43

ES-401 2 Form ES-401-1 ILT Class 08-01 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

AA2.03 - Ability to determine and/or 295003 Partial or Complete Loss of interpret the following as they apply to X 3.5 76 AC / 6 PARTIAL OR COMPLETE LOSS OF A.C.

POWER : Battery status: Plant-Specific EA2.01 - Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to X 4.2 77 Water Level / 5 LOW SUPPRESSION POOL WATER LEVEL : Suppression pool level AA2.04 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to X 3.8 78 Trip / 3 MAIN TURBINE GENERATOR TRIP :

Reactor pressure 2.2.37 - Equipment Control: Ability to 295023 Refueling Acc Cooling X determine operability and / or availability of 4.6 79 Mode / 8 safety related equipment.

2.2.37 - Equipment Control: Ability to 295021 Loss of Shutdown Cooling X determine operability and / or availability of 4.6 80

/4 safety related equipment.

2.2.44 - Equipment Control: Ability to interpret control room indications to verify 295004 Partial or Total Loss of DC the status and operation of a system, and X 4.4 81 Pwr / 6 understand how operator actions and directives effect plant and system conditions.

AA2.01 - Ability to determine and/or 295006 SCRAM / 1 X interpret the following as they apply to 4.6 82 SCRAM : Reactor power AK1.03 - Knowledge of the operational implications of the following concepts as 295005 Main Turbine Generator X they apply to MAIN TURBINE 3.5 39 Trip / 3 GENERATOR TRIP : Pressure effects on reactor level EK1.01 - Knowledge of the operational implications of the following concepts as 295037 SCRAM Conditions they apply to SCRAM CONDITION Present and Reactor Power Above X PRESENT AND REACTOR POWER 4.1 40 APRM Downscale or Unknown / 1 ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor pressure effects on reactor power EK1.01 - Knowledge of the operational 295026 Suppression Pool High implications of the following concepts as X 3.0 41 Water Temp. / 5 they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Pump NPSH AK2.02 - Knowledge of the interrelations 295018 Partial or Total Loss of between PARTIAL OR COMPLETE LOSS X 3.4 42 CCW / 8 OF COMPONENT COOLING WATER and the following: Plant operations EK1.05 - Knowledge of the operational implications of the following concepts as 295025 High Reactor Pressure / 3 X 4.4 43 they apply to HIGH REACTOR PRESSURE : Exceeding safety limits EK2.02 - Knowledge of the interrelations 295031 Reactor Low Water Level between REACTOR LOW WATER X 3.8 44

/2 LEVEL and the following: Reactor pressure AK3.01 - Knowledge of the reasons for 295016 Control Room the following responses as they apply to X 4.1 45 Abandonment / 7 CONTROL ROOM ABANDONMENT :

Reactor SCRAM

ES-401 2 Form ES-401-1 ILT Class 08-01 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

AK3.02 - Knowledge of the reasons for the following responses as they apply to 295005 Main Turbine Generator X MAIN TURBINE GENERATOR TRIP: 3.4 46 Trip / 3 Recirculation pump downshift/trip:

Plant-Specific AK3.03 - Knowledge of the reasons for 295001 Partial or Complete Loss the following responses as they apply to of Forced Core Flow Circulation / 1 X PARTIAL OR COMPLETE LOSS OF 2.8 47

&4 FORCED CORE FLOW CIRCULATION

Idle loop flow AA1.05 - Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and X GENERATOR VOLTAGE AND 3.9 48 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

Engineered safety features.

AA1.01 - Ability to operate and/or 295006 SCRAM / 1 X monitor the following as they apply to 4.2 49 SCRAM : RPS AA1.04 - Ability to operate and/or monitor the following as they apply to 295003 Partial or Complete Loss X PARTIAL OR COMPLETE LOSS OF 3.6 50 of AC / 6 A.C. POWER : D.C. electrical distribution system 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

/5 Torus/suppression chamber pressure:

Plant-Specific AA2.03 - Ability to determine and/or 295004 Partial or Total Loss of interpret the following as they apply to X 2.8 52 DC Pwr / 6 PARTIAL OR COMPLETE LOSS OF D.C. POWER : Battery voltage EA2.03 - Ability to determine and/or 295038 High Off-site Release Rate interpret the following as they apply to X 3.5 53

/9 HIGH OFF-SITE RELEASE RATE :

Radiation levels 2.1.28 - Conduct of Operations:

295004 Partial or Total Loss of Knowledge of the purpose and function X 4.1 54 DC Pwr / 6 of major system components and controls.

2.1.32 - Conduct of Operations: Ability 295025 High Reactor Pressure / 3 X to explain and apply all system limits 3.8 55 and precautions.

2.2.42 - Equipment Control:: Ability to recognize system parameters that are 295025 High Reactor Pressure / 3 X 3.9 56 entry-level conditions for Technical Specifications.

AK1.02 - Knowledge of the operational 295023 Refueling Acc Cooling implications of the following concepts as X 3.2 57 Mode / 8 they apply to REFUELING ACCIDENTS

Shutdown margin AA1.03 - Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and X GENERATOR VOLTAGE AND 3.8 58 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

Voltage regulator controls.

K/A Category Totals: 5 2 3 4 3/4 3/3 Group Point Total: 20/7

ES-401 3 Form ES-401-1 ILT Class 08-01 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

AA2.02 - Ability to determine and/or interpret the following as they apply to 295010 High Drywell Pressure / 5 X 3.9 83 HIGH DRYWELL PRESSURE : Drywell pressure 2.2.40 - Equipment Control: Ability to apply 295007 High Reactor Pressure / 3 X 4.7 84 technical specifications for a system.

2.1.32 - Conduct of Operations: Ability to 295022 Loss of CRD Pumps / 1 X explain and apply all system limits and 4.0 85 precautions.

EK1.02 - Knowledge of the operational implications of the following concepts as 295035 Secondary Containment 3.

X they apply to SECONDARY 59 High Differential Pressure / 5 7 CONTAINMENT HIGH DIFFERENTIAL PRESSURE : Radiation release EK2.02 - Knowledge of the operational implications of the following concepts as 295033 High Secondary they apply to HIGH SECONDARY 3.8 Containment Area Radiation X 60 CONTAINMENT AREA RADIATION Levels / 9 LEVELS : Process radiation monitoring system AK3.01 - Knowledge of the reasons for the following responses as they apply to 3.

295015 Incomplete SCRAM / 1 X 61 INCOMPLETE SCRAM : Bypassing rod 4 insertion blocks AA1.01 - Ability to operate and/or monitor 295013 High Suppression Pool the following as they apply to HIGH 3.

X 62 Temperature / 5 SUPPRESSION POOL TEMPERATURE : 9 Suppression pool cooling AA2.01 - Ability to determine and/or 295012 High Drywell interpret the following as they apply to 3.

X 63 Temperature / 5 HIGH DRYWELL TEMPERATURE : 8 Drywell temperature 2.4.20 - Emergency Procedures / Plan:

295008 High Reactor Water Level 3.

X Knowledge of operational implications of 64

/2 8 EOP warnings, cautions, and notes.

EK1.02 - Knowledge of the operational implications of the following concepts as 295032 High Secondary 3.

X they apply to HIGH SECONDARY 65 Containment Area Temperature / 5 6 CONTAINMENT AREA TEMPERATURE: Radiation releases K/A Category Totals: 2 1 1 1 1/1 1/2 Group Point Total: 7/3

ES-401 4 Form ES-401-1 ILT Class 08-01 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 .

A2.02 - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) 259002 Reactor Water Level based on those predictions, use X 3.4 86 Control procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of any number of reactor feedwater flow inputs A2.01 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET) ; and (b) based on 264000 EDGs X those predictions, use procedures to 3.6 87 correct, control, or mitigate the consequences of those abnormal conditions or operations: Parallel operation of emergency generator 2.4.21 - Emergency Procedures /

Plan: Knowledge of the parameters and logic used to assess the status of safety functions, such as 217000 RCIC X reactivity control, core cooling and 4.6 88 heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

2.2.37 - Equipment Control: Ability to determine operability and / or 215004 Source Range Monitor X 4.6 89 availability of safety related equipment.

A2.11 - Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b) based on those predictions, use 206000 HPCI X 4.2 90 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Low reactor water level: BWR-2,3,4 K1.01 - Knowledge of the physical connections and/or cause- effect relationships between AVERAGE 215005 APRM / LPRM X POWER RANGE 4.0 1 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: RPS K1.03 - Knowledge of the physical connections and/or 263000 DC Electrical cause- effect relationships X 2.6 2 Distribution between D.C. ELECTRICAL DISTRIBUTION and the following: Battery ventilation K2.02 - Knowledge of electrical 217000 RCIC X power supplies to the following: 2.8 3 RCIC initiation signals (logic)

ES-401 4 Form ES-401-1 ILT Class 08-01 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 .

K2.02 - Knowledge of electrical 400000 Component Cooling X power supplies to the following: 2.9 4 Water CCW valves K3.08 - Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION 212000 RPS X 3.6 5 SYSTEM will have on following:

Reactor coolant primary system integrity K3.05 - Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING 205000 Shutdown Cooling X SYSTEM (RHR SHUTDOWN 2.6 6 COOLING MODE) will have on following: Fuel pool cooling assist: Plant-Specific K4.10 - Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) 209001 LPCS X 2.8 7 and/or interlocks which provide for the following: Testability of all operable components K4.05 - Knowledge of RELIEF/SAFETY VALVES design feature(s) and/or 239002 SRVs X interlocks which provide for the 3.6 8 following: Allows for SRV operation from more than one location: Plant-Specific K5.05 - Knowledge of the operational implications of the following concepts as they apply 206000 HPCI X 3.3 9 to HIGH PRESSURE COOLANT INJECTION SYSTEM : Turbine speed control: BWR-2,3,4 K5.01 - Knowledge of the operational implications of the following concepts as they apply 215003 IRM X 2.6 10 to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :

Detector operation K6.07 - Knowledge of the effect that a loss or malfunction of the 300000 Instrument Air X following will have on the 2.5 11 INSTRUMENT AIR SYSTEM:

Valves K6.08 - Knowledge of the effect that a loss or malfunction of the following will have on the 223002 PCIS/Nuclear Steam PRIMARY CONTAINMENT X 3.5 12 Supply Shutoff ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF : Reactor protection system

ES-401 4 Form ES-401-1 ILT Class 08-01 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 .

A1.09 - Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS 264000 EDGs X 3.0 13 (DIESEL/JET) controls including: Maintaining minimum load on emergency generator (to prevent reverse power)

A1.04 - Ability to predict and/or monitor changes in parameters 262001 AC Electrical associated with operating the X 2.7 14 Distribution A.C. ELECTRICAL DISTRIBUTION controls including: Load currents A2.03 - Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based on 218000 ADS X those predictions, use 3.4 15 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of air supply to ADS valves: Plant-Specific A2.03 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those 400000 Component Cooling predictions, use procedures to X 2.9 16 Water correct, control, or mitigate the consequences of those abnormal operation: High/low CCW temperature A3.04 - Ability to monitor automatic operations of the 259002 Reactor Water Level REACTOR WATER LEVEL X 3.2 17 Control CONTROL SYSTEM including:

Changes in reactor feedwater flow A3.01 - Ability to monitor automatic operations of the UNINTERRUPTABLE POWER 262002 UPS (AC/DC) X 2.8 18 SUPPLY (A.C./D.C.) including:

Transfer from preferred to alternate source A4.03 - Ability to manually operate and/or monitor in the 211000 SLC X 4.1 19 control room: Explosive valves firing circuit status A4.07 - Ability to manually operate and/or monitor in the 215004 Source Range Monitor X 3.4 20 control room: Verification of proper functioning/ operability 2.4.2 - Emergency Procedures /

Plan: Knowledge of system set 206000 HPCI X points, interlocks and automatic 4.5 21 actions associated with EOP entry conditions.

ES-401 4 Form ES-401-1 ILT Class 08-01 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 .

2.4.8 - Emergency Procedures /

Plan: Knowledge of how 261000 SGTS X abnormal operating procedures 3.8 22 are used in conjunction with EOP's.

K6.02 - Knowledge of the effect that a loss or malfunction of the 262001 AC Electrical X following will have on the A.C. 3.6 23 Distribution ELECTRICAL DISTRIBUTION:

Off-site power 2.1.23 - Conduct of Operations:

Ability to perform specific 218000 ADS X system and integrated plant 4.3 24 procedures during all modes of plant operation.

A4.07 - Ability to manually operate and/or monitor in the 215003 IRM X 3.6 25 control room: Verification of proper functioning/ operability K4.11 - Knowledge of REACTOR PROTECTION SYSTEM design feature(s) 212000 RPS X and/or interlocks which provide 3.3 26 for the following: Operation with shorting links removed: Plant-Specific K/A Category Totals: 2 2 2 3 2 3 2 2/3 2 3 3/2 Group Point Total: 26/5

ES-401 5 Form ES-401-1 ILT Class 08-01 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 #

A2.02 - Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTERNALS

and (b) based on those 290002 Reactor Vessel X predictions, use procedures to 3.9 91 Internals correct, control, or mitigate the consequences of those abnormal conditions or operations

Overpressurization transient 2.2.42 - Equipment Control::

Ability to recognize system 290002 Reactor Vessel X parameters that are entry-level 4.6 92 Internals conditions for Technical Specifications.

2.2.44 - Equipment Control: Ability to interpret control room indications to verify the status and 268000 Radwaste X operation of a system, and 4.4 93 understand how operator actions and directives effect plant and system conditions.

K1.01 - Knowledge of the physical connections and/or cause- effect 202002 Recirculation Flow relationships between X 3.5 27 Control RECIRCULATION FLOW CONTROL SYSTEM and the following: Recirculation system K2.02 - Knowledge of electrical 230000 RHR/LPCI:

X power supplies to the following: 2.8 28 Torus/Pool Spray Mode Pumps K3.03 - Knowledge of the effect that a loss or malfunction of the CONTROL ROD DRIVE 201001 CRD Hydraulic X 3.1 29 HYDRAULIC SYSTEM will have on following: Control rod drive mechanisms K4.19 - Knowledge of REACTOR/TURBINE PRESSURE REGULATING 241000 Reactor/Turbine X SYSTEM design feature(s) 3.6 30 Pressure Regulator and/or interlocks which provide for the following: Steam bypass valve control K5.12 - Knowledge of the operational implications of the following concepts as they apply 216000 Nuclear Boiler Inst. X to NUCLEAR BOILER 3.2 31 INSTRUMENTATION : Effects on level indication due to rapid changes in void fraction K6.14 - Knowledge of the effect that a loss or malfunction of the 223001 Primary CTMT and following will have on the X 3.6 32 Aux. PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES :

RHR/LPCI

ES-401 5 Form ES-401-1 ILT Class 08-01 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 #

K1.01 - Knowledge of the physical connections and/or cause- effect relationships 214000 RPIS X between ROD POSITION 3.0 33 INFORMATION SYSTEM and the following: RWM: Plant-Specific A2.01 - Ability to (a) predict the impacts of the following on the RADWASTE ; and (b) based on those predictions, use 268000 Radwaste X 2.9 34 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System rupture A3.02 - Ability to monitor automatic operations of the 215002 RBM X ROD BLOCK MONITOR 3.1 35 SYSTEM including: Meters and recorders: BWR-3,4,5 A4.09 - Ability to manually operate and/or monitor in the 290001 Secondary CTMT X control room: System status 3.2 36 lights and alarms: Plant-Specific 2.1.31 - Conduct of Operations:

Ability to locate control room switches, controls, and 290003 Control Room HVAC X 4.6 37 indications, and to determine that they correctly reflect the desired plant lineup.

K4.09 - Knowledge of RHR/LPCI:

TORUS/SUPPRESSION POOL 219000 RHR/LPCI:

X COOLING MODE design 3.3 38 Torus/Pool Cooling Mode feature(s) and/or interlocks which provide for the following:

Heat exchanger cooling K/A Category Totals: 2 1 1 2 1 1 0 1/1 1 1 1/2 Group Point Total: 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: ILT Class 08-01 NRC Date:

RO SRO-Only Category K/A # Topic IR Q# IR Q#

Ability to interpret and execute procedure 2.1.20 4.6 94 steps.

2.1.41 Knowledge of the refueling process. 3.7 98 1.

Knowledge of operator responsibilities during Conduct 2.1.2 4.1 66 all modes of plant operation.

of Operations Knowledge of procedures and limitations 2.1.36 3.0 67 involved in core alterations.

Subtotal 2 2 Ability to determine operability and / or 2.2.37 4.6 95 availability of safety related equipment.

Ability to track Technical Specification limiting 2.2.23 4.6 99 conditions for operations.

Knowledge of the process for making 2.2.6 3.0 68

2. changes to procedures.

Equipment Knowledge of the process for managing Control maintenance activities during power 2.2.17 operations, such as risk assessments, work 2.6 69 prioritizaion, coordination with the transmission system operator.

Ability to obtain and interpret station electrical 2.2.41 3.5 74 and mechanical drawings.

Subtotal 3 2 Knowledge of radiation monitoring systems, 3.

such as fixed radiation monitors and alarms, Radiation 2.3.15 3.1 96 portable survey instruments, personnel Control monitoring equipment, etc.

Knowledge of radiation exposure limits under 2.3.4 3.7 100 normal or emergency conditions.

Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 70 conditions.

Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 71 responsibilities, access to locked high-radiation areas, aligning filters, etc.

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal 2 2 Knowledge of the bases for prioritizing 2.4.23 emergency procedure implementation during 4.4 97 emergency operations.

4. Knowledge of the bases for prioritizing safety Emergency 2.4.22 functions during abnormal/emergency 3.6 72 Procedures / operations.

Plan Ability to verify that the alarms are consistent 2.4.46 4.2 73 with the plant conditions.

Knowledge of local auxiliary operator tasks 2.4.35 during emergency and the resultant 3.8 75 operational effects.

Subtotal 3 1 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Randomly Tier / Group Reason for Rejection Selected K/A 1/1 295027 / EK1.01 Cooper Station has Mark 1 containment.

Cooper Nuclear Station is a BWR 4 and does not have 2/1 209002 / K2.02 High Pressure Core Spray, this K/A is specific to BWR 5, 6.

Cooper Nuclear Station is a BWR 4 and does not have 2/1 207000 / K2.02 Isolation Condensers, this K/A specific to BWR 2, 3.

Cooper Nuclear Station is a BWR 4 and does not have 2/1 207000 / K6.01 Isolation Condensers, this K/A specific to BWR 2, 3.

Cooper Nuclear Station is a BWR 4 and does not have 2/1 207000 / K4.04 Isolation Condensers, this K/A specific to BWR 2, 3.

Cooper Nuclear Station has specific fire pumps that draw water from a storage tank. This water is supplied via a well 2/2 286000 / K6.05 system and does not come to the fire tanks via the screen wash system. These 2 systems do not intertie so this K/A is not applicable.

Cooper Nuclear Station uses a Mark 1 containment, this 2/2 223001 / K6.10 K/A is for Mark 3 containments and does not apply.

Cooper Nuclear Station uses a Mark 1 containment, this 2/2 223001 / A1.03 K/A is specific to Mark 3 containments and does not apply.

295019 /

1/1 The subject K/A isn't relevant at the subject facility.

AK2.13 600000 / It isn't possible to prepare a psychometrically sound 1/1 AA1.08 question related to the subject K/A.

It isn't possible to prepare a psychometrically sound 2/1 203000 / K5.01 question related to the subject K/A.

2/2 202001 / K3.06 The subject K/A isn't relevant at the subject facility.

2/2 201004 / A3.03 The subject K/A isn't relevant at the subject facility.

295005 /

1/1 Duplicate K/A from question 39.

AK1.03 This K/A requires a from memory immediate operator action. The actions for Low SP level are basedon EOPs and 1/1 295030 / 2.4.49 are not from memory. The EOPs are references for other exam questions on the Exam and the student will have these.

Cooper Nuclear Station uses a Mark 1 containment, this 1/1 295027 / EA2.04 K/A is specific to a Mark 3 containment and does not apply.

Cooper Nuclear Station is a BWR 4 and does not have Flow Control Valves in the Recirculation Flow control 2/2 202002 / A2.08 system, this K/A is specific to BWR 5, 6 and does not apply.

1/1 295038 / 2.4.49 K/A has no compatibility with 10CFR55.43 (b)

ES-401 Record of Rejected K/As Form ES-401-4 2/1 209002 / 2.2.12 The subject K/A isn't relevant at the subject facility.

2/1 262002 / A2.04 The subject K/A isn't relevant at the subject facility.

2/2 215002 / 2.2.38 The subject K/A isn't relevant at the subject facility.

Can not develop question that meets the requirements of 2/1 264000 / 2.4.18 10CFR55.43(b) and this K/A.

Can not develop question that meets the requirements of 2/1 300000 / 2.4.1 10CFR55.43(b) and this K/A.

2/2 239003 / A2.10 The subject K/A isn't relevant at the subject facility.

600000 / Can not develop a question that meets requriements of 1/1 AA2.05 10CFR55.43(b) and this K/A..

Can not develop a question that meets the requirements of 1/1 295023 / AA2.04 10CFR55.43(b) and this K/A Can not develop a question that meets the requirements of 1/2 295008 / AA2.04 10CFR55.43(b) and this K/A.

This is a tech spec basis question which is SRO only and 1/1 295021 / 2.2.25 not appropriate for the RO portion of the exam.