Text

Initial Exam - 07/2002 - Draft Outlines
	ML030630740
Person / Time
Site:	Callaway
Issue date:	08/23/2002
From:	Gody A; Operations Branch IV
To:	Randolph G; Union Electric Co
References
	50-483/02-301, ES-401, ES-401-3, NUREG-1021, Rev 8, Suppl 1 50-483/02-301
	Download: ML030630740 (36)
	v • d • e

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Facility: Callaway Date of Exam: August 2002 Exam Level: SRO K/A Category Points Tier Group Point K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 5 4 3 4 3 5 24 Emergency &

Abnormal 2 2 1 3 2 6 2 16 Plant Evolutions 3 0 0 0 1 0 2 3 Tier 7 5 6 7 9 9 43 Totals

2. 1 2 1 0 2 2 2 2 2 1 1 4 19 Plant Systems 2 1 1 2 1 0 1 1 4 2 2 2 17 3 0 0 2 0 0 0 0 1 0 0 1 4 Tier 3 2 4 3 2 3 3 7 3 3 7 40 Totals

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 5 4 3 5 17 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.* The generic 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.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 table above.

NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

000001 Continuous Rod Withdrawal / 1 X AK3.02 Tech Spec Limits For Control Rods 4.3 S001 000003 Dropped Control Rod / 1 X AK1.11 Long Term Effect Of Dropped Rod 3.5 B017 000005 Inoperable / Stuck Control Rod / 1 X AA1.01 Inoperable Rod - Malfunctioning Coil 3.4 B001 Currents 000011 Large Break LOCA / 3 X EA1.13 Manually Align ECCS Components 4.2 B021 (IPE/PRA)

W/E04 LOCA Outside Containment / 3 X EK1.2 Precaution During Valve Strokes In 4.2 B022 ECA-1.2 W/E02 SI Termination / 3 X EK2.2 Primary Coolant Indication For SI 3.9 B024 Termination 000015/17 RCP Malfunctions / 4 X 2.1.32 RCP Starting Limitations 3.8 B002 W/E09&E10 Natural Circ. / 4 X EK1.3 Natural Circulation Indications 3.6 B003 (IPE/PRA) 000024 Emergency Boration / 1 X 2.4.4 OTO-ZZ-00003 Entry Conditions 4.3 B004 000026 Loss of Component Cooling Water / 8 X AK3.03 Loss of CCW Pump - Operator 4.2 B005 Actions 000029 Anticipated Transient w/o Scram / 1 X 2.4.16 ATWS Coincident With SI 4.0 S002 000040 Steam Line Rupture - Excessive X AK1.06 Steam Line Break Outside CTMT 3.8 B007 (W/E12) Heat Transfer / 4 W/E08 RCS Overcooling - PTS / 4 X EA1.3 RCS Post-Soak C/D Limits 4.0 B008 Following PTS 000051 Loss of Condenser Vacuum / 4 X AK3.01 Loss of Steam Dumps With Loss 3.1 B009 Of Vacuum 000055 Station Blackout / 6 X EK1.01 Battery Discharge Rate (IPE/PRA) 3.7 B010 000057 Loss of Vital AC Elec. Inst. Bus / 6 X AA2.19 Auto Actions On Loss Of NN02 4.3 B011 000059 Accidental Liquid Radwaste Rel. / 9 X AA2.02 LRW Release Permit 3.9 S003 000062 Loss of Nuclear Service Water / 4 X 2.2.25 ESW Tech Spec Bases 3.7 S004 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

000067 Plant Fire On-site / 9 X AA1.08 Fire In NB01 Switchgear 3.7 B012 000068 Control Room Evac. / 8 X AK2.02 Activating RPS From Outside The 3.9 B013 Control Room 000069 Loss of CTMT Integrity / 5 X 2.1.12 CTMT Integrity Tech Spec 4.0 S005 (W/E14)

X EK2.1 Manual Actions On High CTMT 3.7 B014 Pressure 000074 Inad. Core Cooling / 4 X EK2.2 RCP Requirements For Inadequate 4.1 B015 (W/E06&E07) Core Cooling 000076 High Reactor Coolant Activity / 9 X AA2.02 High RCS Activity Sampling 3.4 B016 Requirements K/A Category Point Totals: 5 4 3 4 3 5 Group Point Total: 24 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

000007 Reactor Trip - Stabilization - Recovery /1 X EK1.05 How Long For Source Ranges To 3.8 B018 Energize On Rx Trip 000008 Pressurizer Vapor Space Accident / 3 X AK2.02 Indication Of Stuck Open Pzr Safety 2.7 B019 000009 Small Break LOCA / 3 X EA1.04 Indications Of Small LOCA In CVCS 3.5 B020 (IPE/PRA)

W/E03 LOCA Cooldown-Depress. / 4 X EK1.2 ES-1.2 RNO Actions 4.1 B023 W/E11 Loss of Emergency Coolant Recirc / 4 X EA2.1 Transition To Loss Of Emergency 4.2 S006 Coolant Recirc (IPE/PRA) 000022 Loss of Reactor Coolant Makeup / 2 X AK3.02 Valve Closure In Charging Line 3.8 B025 000025 Loss of RHR System / 4 X AA1.02 Loss Of RHR At Mid-Loop 3.9 B026 000027 Pressurizer Pressure Control System X AA2.16 Pzr Pressure Instrument Fails Low 3.9 B006 Malfunction / 3 000032 Loss of Source Range NI / 7 X 2.4.11 Loss Of Source Range Due To P-10 3.6 B027 000033 Loss of Intermediate Range NI / 7 X AA2.02 Indication Of IR Channel Failure 3.6 B028 000037 Steam Generator Tube Leak / 3 X 2.4.11 Quantify S/G Tube Leak 3.6 B029 000038 Steam Generator Tube Rupture / 3 X EK3.06 Ruptured S/G Depressurization 4.5 B030 Methods (IPE/PRA) 000054 Loss of Main Feedwater / 4 X AK3.04 Immediate Actions For MFP Trip 4.6 B031 000058 Loss of DC Power / 6 X AA2.03 Loss Of DC Power For Failed Flash 3.9 B032 W/E16 High Containment Radiation / 9 X EA2.1 Response To High CTMT Radiation 3.3 S007 000065 Loss Of Instrument Air / 8 X AA2.08 Failure Mode Of EFHV43/44 3.3 B034 K/A Category Point Totals: 2 1 3 2 6 2 Group Point Total: 16 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 3 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

000028 Pressurizer Level Malfunction / 2 X AA1.02 Effect Of Pzr Level Channel 3.4 B033 Failure On RMCS 000036 Fuel Handling Accident / 8 X 2.2.25 Fuel Handling Tech Spec Bases 3.7 S008 000056 Loss Of Off-Site Power / 6 X 2.4.21 CSF Status During Loss Of Off- 4.3 S009 Site Power K/A Category Point Totals: 0 0 0 1 0 2 Group Point Total: 3 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

001 Control Rod Drive X K5.04 Rod Insertion Limit / P/A 4.7 B035 Converter Malfunction 003 Reactor Coolant Pump X A1.07 Securing RCP At Power 3.4 B036 004 Chemical and Volume Control X K6.13 Boration Control Malfunction 3.3 B037 013 Engineered Safety Features Actuation X A2.01 ESFAS Response To LOCA 4.8 B038 014 Rod Position Indication X A2.03 Multiple Dropped Rods 4.1 S010 015 Nuclear Instrumentation X 2.1.12 QPTR Tech Spec 4.0 S011 017 In-core Temperature Monitor X K4.01 CET Input To Subcooling 3.7 B039 Monitor 022 Containment Cooling X K2.01 Containment Coolers Power 3.1 B040 Supply X A4.01 CTMT Cooler Operation On SI 3.6 B041 026 Containment Spray X A3.01 CTMT Spray Pump Response 4.5 B053 To LOCA 056 Condensate X K1.03 MFW Temperature Response 2.6 B042 To LP Htr Isolation 059 Main Feedwater X K1.04 S/G Water Level Control 3.4 B043 X A1.07 MFP Speed Change Due To 2.6 B044 AEPT508 Failure 061 Auxiliary/Emergency Feedwater X K5.01 Relationship Between AFW 3.9 B045 Flow And RCS heat Transfer X 2.2.25 CST Tech Spec Bases 3.7 S012 063 DC Electrical Distribution X 2.2.22 125 VDC Tech Spec 4.1 S013 068 Liquid Radwaste X K6.10 LRW Discharge With 2.9 B046 Inoperable Monitor NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

071 Waste Gas Disposal X K4.04 Automatic Action On High 3.4 B047 Radiation 072 Area Radiation Monitoring X 2.2.22 Fuel Handling ARM Required 4.1 B048 By FSAR K/A Category Totals: 2 1 0 2 2 2 2 2 1 1 4 Group Point Total: 19 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

002 Reactor Coolant X A3.03 Master Pzr Press Controller 4.6 B049 Setting 006 Emergency Core Cooling X A4.02 ECCS Valve Interlocks 3.8 B050 010 Pressurizer Pressure Control X A1.08 Spray Nozzle T Limits 3.3 B051 011 Pressurizer Level Control X A2.03 Response To Pzr Level 3.9 S014 Malfunction 012 Reactor Protection X A2.01 Multiple Rx Prot Channel 3.6 S015 Failures 016 Non-nuclear Instrumentation X K3.03 Steam Dump Response To 3.1 B052 ABPT507 Failure 029 Containment Purge X A2.04 HP Sampling Requirements For 3.2 S016 Release Permit 033 Spent Fuel Pool Cooling X K4.05 SFP Dilution - Shutdown Margin 3.3 B054 034 Fuel Handling Equipment X A2.02 Dropped Fuel Cask 3.9 S017 035 Steam Generator X K6.01 Inadvertent Main Steam Line 3.6 B055 Isolation 039 Main and Reheat Steam X K3.04 MFW Pump Discharge Pressure 2.6 B056 During Transient 062 AC Electrical Distribution X K2.01 Loss Of Startup Transformer 3.4 B057 064 Emergency Diesel Generator X A3.07 Load Sequencing During SI 3.7 B058 073 Process Radiation Monitoring X K1.01 Response To CCW Rad Mon 3.9 B059 Alarm 079 Station Air X A4.01 Loss Of Instrument Air Pressure 2.7 B060 086 Fire Protection X 2.4.27 Actions Upon Discovery Of Fire 3.5 B061 103 Containment X 2.1.33 Loss Of CTMT Integrity 4.0 S018 K/A Category Totals: 1 1 2 1 0 1 1 4 2 2 2 Group Point Total: 17 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2 / Group 3 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

005 Residual Heat Removal X A2.02 RHR Overpressure Protection 3.7 S019 008 Component Cooling Water X K3.02 Control Rod Response To CCW 3.1 B062 Dilution 076 Service Water X 2.1.12 Inoperable ESW Trains 4.0 S020 078 Instrument Air X K3.02 RHR System Air Operated 3.6 B063 Valves K/A Category Point Totals: 0 0 2 0 0 0 0 1 0 0 1 Group Point Total: 4 Plant-Specific Priorities System / Topic Recommended Replacement for Reason Points Plant-Specific Priority Total: (limit 10)

NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 SRO Examination Outline Form ES-401-5 Generic Knowledge and Abilities Outline (Tier 3)

Facility: Callaway Date of Exam: August 2002 Exam Level: SRO Category K/A # Topic Imp. Q#

2.1.1 License Candidate Requirements In Main CR 3.8 B064 2.1.11 Minimum Temp For Criticality T/S 3.8 B065 Conduct of 2.1.18 RO Log Entries 3.0 B066 Operations 2.1.26 Confined Space Entry Requirements 2.6 S021 2.1.32 Precautions And Limitations For Radwaste 3.8 B067 Supply Total 5 2.2.11 Continuous Use Procedure Adherence 3.4 B068 2.2.13 Operation Of Equipment Under Local Control 3.8 B069 Tag Equipment 2.2.22 LCO For Refueling Water Storage Tank 4.1 B070 Control 2.2.33 Rod Bank Overlap 2.9 B071 2.2.

Total 4 2.3.1 Radiological Posting 3.0 B072 2.3.10 CTMT Entry Requirements 3.3 S022 Radiation 2.3.11 Release Termination On Ruptured And 3.2 B073 Control Faulted S/G 2.3.

Total 3 2.4.7 ECA-0.0 Mitigation Strategy 3.8 S023 2.4.20 AFW Flow / S/G Level Requirements With 4.0 B074 Adverse Containment Emergency 2.4.22 CSF Implementation Requirements 4.0 S024 Procedures/ 2.4.23 Prioritization Of Emergency Operating 3.8 B075 Plan Procedures 2.4.29 Emergency Response Data System 4.0 S025 2.4.

Total 5 Tier 3 Point Total SRO 17 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Facility: Callaway Date of Exam: August 2002 Exam Level: RO K/A Category Points Tier Group Point K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 3 2 3 3 2 16 Emergency &

Abnormal 2 4 2 3 3 2 3 17 Plant Evolutions 3 0 0 1 1 1 0 3 Tier 7 5 6 7 6 5 36 Totals

2. 1 2 1 1 4 3 3 2 3 2 1 1 23 Plant Systems 2 1 1 4 3 1 1 1 1 3 3 1 20 3 0 1 2 0 0 0 1 1 1 1 1 8 Tier 3 3 7 7 4 4 4 5 6 5 3 51 Totals

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 4 4 2 3 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.* The generic 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.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 basis of plant-specific priorities. Enter the tier totals for each category in the table above.

NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

000005 Inoperable / Stuck Control Rod / 1 X AA1.01 Inoperable Rod - Malfunctioning 3.6 B001 Coil Currents 000015/17 RCP Malfunctions / 4 X 2.1.32 RCP Starting Limitations 3.4 B002 W/E09&E10 Natural Circ. / 4 X EK1.3 Natural Circulation Indications 3.3 B003 (IPE/PRA) 000024 Emergency Boration / 1 X 2.4.4 OTO-ZZ-00003 Entry Conditions 4.0 B004 000026 Loss of Component Cooling Water / 8 X AK3.03 Loss of CCW Pump - Operator 4.0 B005 Actions 000027 Pressurizer Pressure Control System X AA2.16 Pzr Pressure Instrument Fails Low 3.6 B006 Malfunction / 3 000040 Steam Line Rupture - Excessive X AK1.06 Steam Line Break Outside CTMT 3.7 B007 (W/E12) Heat Transfer / 4 W/E08 RCS Overcooling - PTS / 4 X EA1.3 RCS Post-Soak C/D Limits 3.6 B008 Following PTS 000051 Loss of Condenser Vacuum / 4 X AK3.01 Loss of Steam Dumps With Loss 2.8 B009 Of Vacuum 000055 Station Blackout / 6 X EK1.01 Battery Discharge Rate (IPE/PRA) 3.3 B010 000057 Loss of Vital AC Elec. Inst. Bus / 6 X AA2.19 Auto Actions On Loss Of NN02 4.0 B011 000067 Plant Fire On-site / 9 X AA1.08 Fire In NB01 Switchgear 3.4 B012 000068 Control Room Evac. / 8 X AK2.02 Activating RPS From Outside The 3.7 B013 Control Room 000069 Loss of CTMT Integrity / 5 X EK2.1 Manual Actions On High CTMT 3.4 B014 (W/E14) Pressure 000074 Inad. Core Cooling / 4 X EK2.2 RCP Requirements For Inadequate 3.8 B015 (W/E06&E07) Core Cooling 000076 High Reactor Coolant Activity / 9 X AA2.02 High RCS Activity Sampling 2.8 B016 Requirements NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 K/A Category Point Totals: 3 3 2 3 3 2 Group Point Total: 16 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

000003 Dropped Control Rod / 1 X AK1.11 Long Term Effect Of Dropped Rod 2.5 B017 000007 Reactor Trip - Stabilization - Recovery /1 X EK1.05 How Long For Source Ranges To 3.3 B018 Energize On Rx Trip 000008 Pressurizer Vapor Space Accident / 3 X AK2.02 Indication Of Stuck Open Pzr Safety 2.7 B019 000009 Small Break LOCA / 3 X EA1.04 Indications Of Small LOCA In CVCS 3.7 B020 (IPE/PRA) 000011 Large Break LOCA / 3 X EA1.13 Manually Align ECCS Components 4.1 B021 (IPE/PRA)

W/E04 LOCA Outside Containment / 3 X EK1.2 Precaution During Valve Strokes In 3.5 B022 ECA-1.2 W/E03 LOCA Cooldown/Depress. / 4 X EK1.2 ES-1.2 RNO Actions 3.6 B023 W/E02 SI Termination / 3 X EK2.2 Primary Coolant Indication For SI 3.5 B024 Termination 000022 Loss of Reactor Coolant Makeup / 2 X AK3.02 Valve Closure In Charging Line 3.5 B025 000025 Loss of RHR System / 4 X AA1.02 Loss Of RHR At Mid-Loop 3.8 B026 000029 Anticipated Transient w/o Scram / 1 X 2.4.1 ATWS Immediate Actions 4.3 R001 000032 Loss of Source Range NI / 7 X 2.4.11 Loss Of Source Range Due To P-10 3.4 B027 000033 Loss of Intermediate Range NI / 7 X AA2.02 Indication Of IR Channel Failure 3.3 B028 000037 Steam Generator Tube Leak / 3 X 2.4.11 Quantify S/G Tube Leak 3.4 B029 000038 Steam Generator Tube Rupture / 3 X EK3.06 Ruptured S/G Depressurization 4.2 B030 Methods (IPE/PRA) 000054 Loss of Main Feedwater / 4 X AK3.04 Immediate Actions For MFP Trip 4.4 B031 000058 Loss of DC Power / 6 X AA2.03 Loss Of DC Power For Field Flash 3.5 B032 K/A Category Point Totals: 4 2 3 3 2 3 Group Point Total: 17 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 3 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

000028 Pressurizer Level Malfunction / 2 X AA1.02 Effect Of Pzr Level Channel Failure 3.4 B033 On RMCS 000036 Fuel Handling Accident / 8 X AK3.03 Actions On Decreasing Refuel Pool 3.7 R002 Level 000065 Loss Of Instrument Air / 8 X AA2.08 Failure Mode Of EFHV43/44 2.9 B034 K/A Category Point Totals: 0 0 1 1 1 0 Group Point Total: 3 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Plant Systems - Tier 2 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

001 Control Rod Drive X K4.23 Rod Motion Inhibit 3.4 R003 X K5.04 Rod Insertion Limit / P/A 4.3 B035 Converter Malfunction 003 Reactor Coolant Pump X K3.04 Rx Trip Due To Loss Of RCP 3.9 R004 X A1.07 Securing RCP At Power 3.4 B036 004 Chemical and Volume Control X K5.20 Reactivity Effect Of Boration 3.6 R005 X K6.13 Boration Control Malfunction 3.1 B037 013 Engineered Safety Features Actuation X A2.01 ESFAS Response To LOCA 4.6 B038 X A3.02 ESFAS Status Panel 4.1 R006 Indication 015 Nuclear Instrumentation X K4.07 Source Range Permissive 3.7 R007 X A2.02 SR Discriminator Failure 3.1 R008 017 In-core Temperature Monitor X K4.01 CET Input To Subcooling 3.4 B039 Monitor X K6.01 Thermocouple Failures 2.7 R009 022 Containment Cooling X K2.01 Containment Coolers Power 3.0 B040 Supply X A4.01 CTMT Cooler Operation On 3.6 B041 SI 056 Condensate X K1.03 MFW Temperature Response 2.6 B042 To LP Htr Isolation X A2.04 Trip Of All Condensate Pumps 2.6 R010 059 Main Feedwater X K1.04 S/G Water Level Control 3.4 B043 X A1.07 MFP Speed Change Due To 2.5 B044 AEPT508 Failure NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Plant Systems - Tier 2 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

061 Auxiliary/Emergency Feedwater X K5.01 Relationship Between AFW 3.6 B045 Flow And RCS Heat Transfer X A3.01 AMSAC Actuation Of AFW 4.2 R011 068 Liquid Radwaste X K6.10 LRW Discharge With 2.5 B046 Inoperable Monitor 071 Waste Gas Disposal X K4.04 Automatic Action On High 2.9 B047 Radiation 072 Area Radiation Monitoring X 2.2.22 Fuel Handling ARM Required 3.4 B048 By FSAR K/A Category Totals: 2 1 1 4 3 3 2 3 2 1 1 Group Point Total: 23 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Plant Systems - Tier 2 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

002 Reactor Coolant X A3.03 Master Pzr Press Controller 4.4 B049 Setting 006 Emergency Core Cooling X A4.02 ECCS Valve Interlocks 4.0 B050 010 Pressurizer Pressure Control X A1.08 Spray Nozzle T Limits 3.2 B051 011 Pressurizer Level Control X A2.10 Pzr Level Channel Fails High 3.4 R012 012 Reactor Protection X A4.06 Operation Of Rx Trip Breakers 4.3 R013 014 Rod Position Indication X K5.01 DRPI Data Failure 2.7 R014 016 Non-nuclear Instrumentation X K3.03 Steam Dump Response To 3.0 B052 ABPT507 Failure 026 Containment Spray X A3.01 CTMT Spray Pump Response 4.3 B053 To LOCA 029 Containment Purge X K4.02 Maintain Negative Pressure In 2.9 R015 CTMT 033 Spent Fuel Pool Cooling X K4.05 SFP Dilution - Shutdown 3.1 B054 Margin 035 Steam Generator X K6.01 Inadvertent Main Steam Line 3.2 B055 Isolation 039 Main and Reheat Steam X K3.04 MFW Pump Discharge 2.5 B056 Pressure During Transient 055 Condenser Air Removal X K3.01 Vacuum Pump Auto Starts 2.5 R016 062 AC Electrical Distribution X K2.01 Loss Of Startup Transformer 3.3 B057 063 DC Electrical Distribution X K3.02 Loss Of DC Control Power 3.5 R017 064 Emergency Diesel Generator X A3.07 Load Sequencing During SI 3.6 B058 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Plant Systems - Tier 2 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

073 Process Radiation Monitoring X K1.01 Response To CCW Rad Mon 3.6 B059 Alarm 075 Circulating Water X K4.01 Cooling Tower Bypass Valve 2.5 R018 Operation 079 Station Air X A4.01 Loss Of Instrument Air Pressure 2.7 B060 086 Fire Protection X 2.4.27 Actions Upon Discovery Of Fire 3.0 B061 K/A Category Totals: 1 1 4 3 1 1 1 1 3 3 1 Group Point Total: 20 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-4 Plant Systems - Tier 2 / Group 3 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#

005 Residual Heat Removal X A1.03 Isolating CCW To RHR Hx 2.5 R019 007 Pressurizer Relief/Quench Tank X A2.05 Impact Of Pressure On PRT 3.2 R020 008 Component Cooling Water X K3.02 Control Rod Response To CCW 2.9 B062 Dilution 034 Fuel Handling Equipment X 2.2.30 RO Responsibility During Core 3.5 R021 Reload 045 Main Turbine Generator X A4.01 Main Turbine Chest Warming 3.1 R022 076 Service Water X K2.08 ESW Valve Power Supplies 3.1 R023 (IPE/PRA) 078 Instrument Air X K3.02 RHR System Air Operated 3.4 B063 Valves 103 Containment X A3.01 Rad Monitor Response To CISA 3.9 R024 K/A Category Point Totals: 0 1 2 0 0 0 1 1 1 1 1 Group Point Total: 8 Plant-Specific Priorities System / Topic Recommended Replacement for Reason Points Plant-Specific Priority Total: (limit 10)

NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-401 Callaway 2002 RO Examination Outline Form ES-401-5 Generic Knowledge and Abilities Outline (Tier 3)

Facility: Callaway Date of Exam: August 2002 Exam RO Level:

Category K/A # Topic Imp. Q#

2.1.1 License Candidate Requirements In Main CR 3.7 B064 2.1.11 Minimum Temp For Criticality T/S 3.0 B065 Conduct of 2.1.18 RO Log Entries 2.9 B066 Operations 2.1.32 Precautions And Limitations For Radwaste Supply 3.4 B067 2.1.

2.1.

Total 4 2.2.11 Continuous Use Procedure Adherence 2.5 B068 2.2.13 Operation Of Equipment Under Local Control Tag 3.6 B069 Equipment 2.2.22 LCO For Refueling Water Storage Tank 3.4 B070 Control 2.2.33 Rod Bank Overlap 2.5 B071 2.2.

2.2.

Total 4 2.3.1 Radiological Posting 2.6 B072 2.3.11 Release Termination On Ruptured And Faulted S/G 2.7 B073 Radiation 2.3.

Control 2.3.

2.3.

Total 2 2.4.1 Reactor Trip Requirements 25% 4.3 R025 2.4.20 AFW Flow / S/G Level Requirements With Adverse 3.3 B074 Containment Emergency 2.4.23 Prioritization Of Emergency Operating Procedures 2.8 B075 Procedures/ 2.4.

Plan 2.4.

Total 3 Tier 3 Point Total RO 13 NUREG-1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: August 2002 Examination Level: RO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Conduct Of Determine If Rod Insertion Limit Has Been Exceeded Operations / G 2.1.7 (3.7) A1 RO/SRO Evaluate Plant Performance Conduct Of Determine Dilution Requirements Operations / G 2.1.25 (2.8) A2 RO/SRO Interpret Reference Material A.2 Equipment Control / Calculate RHR Pump Run Time For Flood Up Refueling Process G 2.2.27 (2.6) A3 RO A.3 Radiation Control / Calculate Stay Time Stay Times G 2.3.10 (2.9) A4 RO A.4 Emergency Knowledge Of Emergency Plan Duties Procedures / Plan G 2.4.29 (2.6) A5.1 RO Knowledge Of RERP Knowledge Of Emergency Communications G 2.4.43 (2.8) A5.2 RO FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

NUREG-1021 Revision 8

Callaway Rev. 0, Feb. 27, 2002 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: August 2002 Examination Level: SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Conduct Of Determine If Rod Insertion Limit Has Been Exceeded Operations / G 2.1.7 (4.4) A1 RO/SRO Evaluate Plant Performance Conduct Of Determine Dilution Requirements Operations / G 2.1.25 (3.1) A2 RO/SRO Interpret Reference Material A.2 Equipment Control / Determine Actions For Valve Stroke Test Surveillance G 2.2.12 (3.4) A3 SRO Procedures A.3 Radiation Control / Reportability For Exceeding Exposure Limits Exposure Limits G 2.3.4 (3.1) A4 SRO A.4 Emergency Emergency Event Classification Procedures / Plan G 2.4.41 (4.1) A5 SRO RERP Notifications FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

NUREG-1021 Revision 8

Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS1 EXAMINERS: APPLICANTS:

INITIAL CONDITIONS: 100% Reactor Power, 'B' RHR Pump OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type

A N Increase Letdown Flow From 75 GPM to 120 GPM 004A4.06 t=0 (RO, SRO) (3.6 / 3.1)

B I 'B' S/G Level Channel 529 Fails High 016K3.12 t = 10 (BOP, SRO) (3.4 / 3.6)

C I VCT Level Channel 149 Fails High 004A2.18 t = 20 (RO, SRO) (3.1 / 3.1)

D C 'B' Circulating Water Pump Trip 075A2.02 t = 25 (ALL) (2.5 / 2.7)

E R Turbine Setback to 75% Power 045K4.12 t = 25 (RO) (3.3 / 3.6)

F M Hotwell Instrumentation Leak - Loss of Feed 054AA2.01 t = 35 (ALL) (4.3 / 4.4)

G C Turbine Automatic Trip Failure 007EA1.07 PRE (BOP, SRO) (4.3 / 4.3)

H M Large Break LOCA 011EK3.12 PRE (ALL) (4.4 / 4.6)

I C ESF Bus NB01 Lockout (IPE / PRA) 062A2.04 PRE (ALL) (3.1 / 3.4)

(N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

NUREG -1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 NUREG -1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS2 EXAMINERS: APPLICANTS:

INITIAL CONDITIONS: 30% Reactor Power, 'B' RHR Pump OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type

A N Swap Charging From NCP To CCP 004A4.08 t=0 (RO, SRO) (3.8 / 3.4)

B I Pressurizer Pressure Channel 455 Fails High 027AA2.15 t = 10 (RO, SRO) (3.7 / 4.0)

C I Steam Flow Channel 542 Fails High On 'D' S/G 059A2.11 t = 20 (BOP, SRO) (3.0 / 3.3)

D C Steam Generator Tube Leak On 'D' S/G 037AK3.05 t = 25 (ALL) (3.7 / 4.0)

E R Plant Shutdown Due To S/G Tube Leak 004A4.01 t = 25 (RO) (3.8 / 3.9)

F M Steam Generator Tube Rupture On 'D' S/G (IPE / PRA) 038EA2.02 t = 40 (ALL) (4.5 / 4.8)

G C Failure Of 'D' FWIV To Automatically Close 013A4.01 PRE (ALL) (4.5 / 4.8)

H M S/G Safety Stuck Open On 'D' S/G 035A2.01 t = 42 (ALL) (4.5 / 4.6)

(N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

NUREG -1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS B/U EXAMINERS: APPLICANTS:

INITIAL CONDITIONS: 80% Reactor Power, 'B' RHR Pump OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type

A I Pressurizer Level Channel 459 Fails Low 011A2.11 t=0 (RO, SRO) (3.4 / 3.6)

B C Letdown Isolation Valve Fails Closed 004A2.07 t=0 (RO, SRO) (3.4 / 3.7)

C N Place Excess Letdown In Service 028AA1.05 N/A (RO, SRO) (2.8 / 2.9)

D C 'A' RCP High Vibration 015AA1.23 t = 20 (ALL) (3.1 / 3.2)

E R Plant Shutdown Due To RCP High Vibration 004A4.01 t = 20 (RO) (3.8 / 3.9)

F I 'A' S/G PORV Failure 041A4.06 t = 35 (BOP, SRO) (2.9 / 3.1)

G M Loss of Off-Site Power and NB02 056AA2.44 t = 40 (ALL) (4.3 / 4.5)

H C Auto Reactor Trip Failure 029EA1.12 PRE (ALL) (4.1 / 4.0)

I C TDAFP Fails To Auto Start 061A2.04 PRE (ALL) (3.4 / 3.8)

J C Loss of All AC due to NE01 Failure (IPE / PRA) 055EA2.02 PRE (ALL) (4.4 / 4.6)

(N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

NUREG -1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 NUREG -1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS2 EXAMINERS: APPLICANTS:

INITIAL CONDITIONS: 30% Reactor Power, 'B' RHR Pump OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type

A N Swap Charging From NCP To CCP 004A4.08 t=0 (RO, SRO) (3.8 / 3.4)

B I Pressurizer Pressure Channel 455 Fails High 027AA2.15 t = 10 (RO, SRO) (3.7 / 4.0)

C I Steam Flow Channel 542 Fails High On 'D' S/G 059A2.11 t = 20 (BOP, SRO) (3.0 / 3.3)

D C Steam Generator Tube Leak On 'D' S/G 037AK3.05 t = 25 (ALL) (3.7 / 4.0)

E R Plant Shutdown Due To S/G Tube Leak 004A4.01 t = 25 (RO) (3.8 / 3.9)

F M Steam Generator Tube Rupture On 'D' S/G (IPE / PRA) 038EA2.02 t = 40 (ALL) (4.5 / 4.8)

G C Failure Of 'D' FWIV To Automatically Close 013A4.01 PRE (ALL) (4.5 / 4.8)

H M S/G Safety Stuck Open On 'D' S/G 035A2.01 t = 42 (ALL) (4.5 / 4.6)

(N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

NUREG -1021 Revision 8, Supplement 1

Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS B/U EXAMINERS: APPLICANTS:

INITIAL CONDITIONS: 80% Reactor Power, 'B' RHR Pump OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type

A I Pressurizer Level Channel 459 Fails Low 011A2.11 t=0 (RO, SRO) (3.4 / 3.6)