ML023510123

Init EXAM-08/2002 - Final Written Exam Outlines

ML023510123
Person / Time
Site:	Cooper
Issue date:	12/16/2002
From:	Gody A Division of Reactor Safety IV
To:	Denise Wilson Nebraska Public Power District (NPPD)
References
50-298/02-301, NUREG-1021, Rev 8 50-298/02-301
Download: ML023510123 (32)

Text

ES-401 BWR RO Examination Outline Form ES-401-2 Facility: Cooper Nuclear Station Date of Exam: August 5, 2002 Exam Level: RO K/A Category Points Tier Group Point K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Total

1. 1 2 2 2 3 2 2 13 Emergency &

Abnormal Plant 2 3 2 4 4 3 3 19 Evolutions 3 0 1 1 1 0 1 4 Tier 5 5 7 8 5 6 36 Totals 1 3 2 3 3 2 2 3 3 2 3 2 28 2.

Plant 2 2 1 2 2 1 1 2 2 2 2 2 19 Systems 3 1 0 1 0 0 1 0 0 1 0 0 4 Tier 6 3 6 5 3 4 5 5 5 5 4 51 Totals

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 4 3 2 4 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 +/-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 basis of plant-specific priorities. Enter the tier totals for each category in the table above.

12/16/02 2:47:26 PM Page 1 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 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. Points AA1.07 - Ability to operate and/or monitor the following as they apply to 295005 Main Turbine Generator Trip / 3 X MAIN TURBINE GENERATOR TRIP: A.C. electrical distribution. 3.3 1 AK3.05 - Knowledge of the reasons for the following responses as they 295006 SCRAM / 1 X apply to SCRAM: Direct turbine generator trip: Plant-Specific. 3.8 1 AK2.01 - Knowledge of the interrelations between HIGH REACTOR 295007 High Reactor Pressure / 3 X PRESSURE and the following: Reactor/turbine pressure regulating system 3.5 1 AK1.03 - Knowledge of the operational implications of the following 295007 High Reactor Pressure / 3 X concepts as they apply to HIGH REACTOR PRESSURE: Pressure effects 3.8 1 on reactor power.

AA2.01 - Ability to determine and/or interpret the following as they apply to 295009 Low Reactor Water Level / 2 X LOW REACTOR WATER LEVEL: Reactor Water Level 4.2 1 AA1.05 - Ability to operate and/or monitor the following as they apply to 295010 High Drywell Pressure / 5 X HIGH DRYWELL PRESSURE: Drywell/suppression vent and purge. 3.1 1 AK2.06 - Knowledge of the interrelations between INADVERTENT 295014 Inadvertent Reactivity Addition / 1 X REACTIVITY ADDITION and the following: Moderator temperature. 3.4 1 AK1.01 - Knowledge of the operational implications of the following 295015 Incomplete SCRAM / 1 X concepts as they apply to INCOMPLETE SCRAM: Shutdown margin. 3.6 1 EK3.04 - Knowledge of the reasons for the following responses as they 295024 High Drywell Pressure / 5 X apply to HIGH DRYWELL PRESSURE: Emergency depressurization. 3.7 1 X 2.4.11 - Knowledge of abnormal condition procedures. 3.4 1 295025 High Reactor Pressure / 3 EA2.04 - Ability to determine and/or interpret the following as they apply to 295031 Reactor Low Water Level / 2 X REACTOR LOW WATER LEVEL: Adequate core cooling. 4.6 1 16481 295037 SCRAM Condition Present and Reactor 2.4.8 - Knowledge of how the event-based emergency/abnormal operating Power Above APRM Downscale or Unknown / 1 X procedures are used in conjunction with the symptom-based EOPs. 3.0 1 PRA: ATWS EA1.02 - Ability to operate and monitor the following as they apply to HIGH 500000 High Containment Hydrogen Conc. / 5 CONTAINMENT HYDROGEN CONTROL: Primary containment oxygen X 3.3 1 instrumentation.

K/A Category Totals: 2 2 2 3 2 2 Group Point Total: 13 12/16/02 2:47:26 PM Page 2 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 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. Points 295001 Partial or Complete Loss of Forced Core AA1.01 - Ability to operate and/or monitor the following as they apply to Flow Circulation / 1 & 4 X PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW 3.5 1 CIRCULATION: Recirculation system.

AK3.01 - Knowledge of the reasons for the following responses as they 295002 Loss of Main Condenser Vacuum / 3 apply to LOSS OF MAIN CONDENSER VACUUM: Reactor SCRAM:

X 3.7 1 Plant-specific.

AK1.06 - Knowledge of the operational implications of the following 295003 Partial or Complete Loss of AC Power / 6 concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

X 3.8 1 POWER: Station blackout: Plant-specific.

2.4.48 - Ability to interpret control room indications to verify the status and 295004 Partial or Complete Loss of DC Power / 6 operation of system /and understand how operator actions and directives X 3.5 1 affect plant and system conditions.

AA2.02 - Ability to determine and/or interpret the following as they apply to 295008 High Reactor Water Level / 2 HIGH REACTOR WATER LEVEL: Steam flow/feedflow mismatch.

X 3.4 1 AK2.02 - Knowledge of the interrelations between HIGH DRYWELL 295012 High Drywell Temperature / 5 TEMPERATURE and the following: Drywell cooling.

X 3.6 1 AA2.01 - Ability to determine and/or interpret the following as they apply to 295013 High Suppression Pool Temp. / 5 HIGH SUPPRESSION POOL TEMPERATURE: Suppression pool X 3.8 1 temperature.

AA1.06 - Ability to operate and/or monitor the following as they apply to 295016 Control Room Abandonment / 7 CONTROL ROOM ABANDONMENT: Reactor water level.

X 4.0 1 AA1.01 - Ability to operate and/or monitor the following as they apply to 295018 Partial or Complete Loss of CCW / 8 PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

X 3.3 1 Backup systems.

2.4.31 - Knowledge of annunciators alarms and indications / and use of the 295019 Part. Or Comp. Loss of Inst. Air / 8 response instructions.

X 3.3 1 AK3.04 - Knowledge of the reasons for the following responses as they 295020 Inadvertent Cont. Isolation / 5 & 7 apply to INADVERTENT CONTAINMENT ISOLATION: Reactor pressure X response. 4.1 1 EK3.05 - Knowledge of the reasons for the following responses as apply to 295026 High Suppression Pool Water SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor scram.

Temperature / 5 X 3.6 1 12/16/02 2:47:26 PM Page 3 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 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. Points EK1.01 - Knowledge of the operational implications of the following 295028 High Drywell Temperature / 5 X concepts as they apply to HIGH DRYWELL TEMPERATURE: Reactor 3.5 1 water level measurement.

295029 High Suppression Pool Water Level / 5 X 2.4.6 - Knowledge of symptom-based EOP mitigation strategies. 3.1 1 EK3.02 - Knowledge of the reasons for the following responses as they 295030 Low Suppression Pool Water Level / 5 X apply to LOW SUPPRESSION POOL WATER LEVEL: HPCI operation: 3.5 1 Plant-specific.

EK1.02 - Knowledge of the operational implications of the following 295033 High Sec. Cont. Area Rad. Levels / 9 concepts as they apply to HIGH SECONDARY CONTAINMENT AREA 10688 X 3.9 1 RADIATION LEVELS: Personnel protection.

EK2.04 - Knowledge of the interrelations between SECONDARY 295034 Secondary Containment Ventilation High CONTAINMENT VENTILATION HIGH RADIATION and the following:

Radiation / 9 X 3.9 1 Secondary containment ventilation.

17856 EA1.07 - Ability to operate and/or monitor the following as they apply to 295038 High Off-site Release Rate / 9 HIGH OFF-SITE RELEASE RATE: Control room ventilation: Plant-1644 X 3.6 1 specific.

600000 Plant Fire On Site / 8 AA2.04 - Ability to determine and interpret the following as they apply to 16490 X PLANT FIRE ON SITE: The fires extent of potential operational damage to 2.8 1 plant equipment.

K/A Category Point Totals: 3 2 4 4 3 3 Group Point Total: 19 12/16/02 2:47:26 PM Page 4 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 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. Points AK3.05 - Knowledge of the reasons for the following responses as they 295021 Loss of Shutdown Cooling / 4 apply to LOSS OF SHUTDOWN COOLING: Establishing alternate heat X 3.6 1 removal flow paths.

EK2.02 - Knowledge of the interrelations between HIGH SECONDARY 295032 High Secondary Containment Area CONTAINMENT AREA TEMPERATURE and the following: Secondary Temperature / 5 X 3.6 1 containment ventilation.

EA1.01- Ability to determine and/or monitor the following as they apply to 295035 Secondary Containment High SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:

Differential Pressure / 5 X 3.6 1 Secondary containment ventilation system.

295036 Secondary Containment High Sump/Area X 2.4.11 - Knowledge of abnormal condition procedures. 3.4 1 Water Level / 5 K/A Category Point Totals: 0 1 1 1 0 1 Group Point Total: 4 12/16/02 2:47:26 PM Page 5 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points A2.12 - Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE 201001 CRD Hydraulic HYDRAULIC SYSTEM; and (b) based on those predictions, use procedures to correct, X 2.8 1 control, or mitigate the consequences of those abnormal conditions or operations: High cooling water flow.

A1.02 - Ability to predict and/or monitor changes in parameters associated with 201002 RMCS operating the REACTOR MANUAL CONTROL X SYSTEM controls including: control rod 3.4 1 position.

K1.05 - Knowledge of the physical connec-tions and/ cause-effect relationships between 202002 Recirculation Flow Control X RECIRCULATION FLOW CONTROL SYSTEM 3.5 1 and the following: Recirculation MG set:

Plant-specific.

2.1.25 - Ability to obtain and interpret station 202002 Recirculation Flow Control reference materials such as graphs, X 2.8 1 monographs, and tables which contain performance data.

K2.01 - Knowledge of electrical power 203000 RHR/LPCI: Injection Mode X supplies to the following: pumps. 3.5 1 K4.07 - Knowledge of HIGH PRESSURE 206000 HPCI COOLANT INJECTION SYSTEM design X feature(s) and/or interlocks which provide for 4.3 1 the following: Automatic system initiation:

BWR-2,3,4.

A4.11 - Ability to manually operate and/or 209001 LPCS X monitor in the control room: System flow. 3.7 1 K5.04 - Knowledge of the operational 211000 Standby Liquid Control System implications of the following concepts as they X apply to STANDBYLIQUID CONTROL 3.1 1 SYSTEM: Explosive valve operation.

K6.04 - Knowledge of the effect that a loss or 212000 RPS X malfunction of the following will have on the 2.8 1 REACTOR PROTECTION SYSTEM: D.C.

electrical distribution.

12/16/02 2:47:26 PM Page 6 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 A2.21 - Ability to (a) predict the impacts of 212000 RPS the following on the REACTOR PROTECTION 3.6 1 X SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal condi-tions or operations: failure of individual relays to reposition: Plant-specific.

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K3.02 - Knowledge of the effect that a loss or 215003 IRM X malfunction of the INTERMEDIATE RANGE 3.6 1 MONITOR (IRM) SYSTEM will have on the following: reactor manual control.

A3.04 - Ability to monitor automatic 215004 SRM operations of the SOURCE RANGE MONITOR X (SRM) SYSTEM including: control rod block 3.6 1 status.

K1.16 - Knowledge of the physical 215005 APRM/LPRM connections and/or cause-effect relationships between AVERAGE POWER RANGE X MONITOR/LOCAL POWER RANGE 3.3 1 MONITOR SYSTEM and the following: Flow converter/comparator network: Plant-Specific.

K2.02 - Knowledge of electrical power 215005 APRM/LPRM X supplies to the following: APRM channels. 2.6 1 K5.12 - Knowledge of the operational implica-216000 Nuclear Boiler Instrumentation tions of the following concepts as they apply to NUCLEAR BOILER INSTRUMENTATION:

X 3.2 1 Effects on level indication due to rapid changes in void fraction.

A1.01 - Ability to predict and/or monitor 217000 RCIC changes in parameters associated with X operating the REACTOR CORE ISOLATION 3.7 1 COOLING SYSTEM (RCIC) controls including:

RCIC flow.

A4.06 - Ability to manually operate and/or 218000 ADS monitor in the control room: ADS valve tail 3.5 1 X pipe temperature.

2.1.12 - Ability to apply technical 223001 Primary CTMT and Auxiliaries X specifications for a system. 2.9 1 K4.05- Knowledge of PRIMARY CONTAIN-223001 Primary CTMT and Auxiliaries X MENT SYSTEM AND AUXILIARIES design 2.9 1 feature(s) and/or interlocks which provide for the following: Maintains proper suppression pool to drywell differential pressure.

12/16/02 2:47:26 PM Page 7 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 A4.03 - Ability to manually operate and/or 223002 PCIS/Nuclear Steam Supply X monitor in the control room: Reset system 3.6 1 Shutoff isolations.

12/16/02 2:47:26 PM Page 8 of 12 NUREG-1021, Revision 8, Supplement 1

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K1.08 - Knowledge of the physical 223002 PCIS/Nuclear Steam Supply connections and/or cause-effect relationships Shutoff between PRIMARY CONTAINMENT X ISOLATOIN SYSTEM/NUCLEAR STEAM 3.4 1 SUPPLY SHUT-OFF and the following:

Shutdown cooling system/RHR.

A2.02 - Ability to (a) predict the impacts of 239002 SRVs the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, X use procedures to correct, control, or mitigate 3.1 1 the consequences of those abnormal conditions or operations: Leaky SRV.

K3.25 - Knowledge of the effect that a loss or 241000 Reactor/Turbine Pressure malfunction of the REACTOR/TURBINE Regulator X PRESSURE REGULATING SYSTEM will have 3.3 1 on the following: Reactor cooldown.

K6.03 - Knowledge of the effect that a loss or 259001 Reactor Feedwater malfunction of the following will have on the X REACTOR FEEDWATER SYSTEM: A.C. 2.9 1 electrical power.

A3.03 - Ability to monitor automatic 259002 Reactor Water Level Control operations of the REACTOR WATER LEVEL X CONTROL SYSTEM including: Changes in 3.2 1 main steam flow.

A1.01 - Ability to predict and/or monitor 259002 Reactor Water Level Control changes in parameters associated with operating the REACTOR WATER LEVEL X 3.8 1 CONTROL SYSTEM controls including:

Reactor water level.

K4.01 - Knowledge of STANDBY GAS 261000 SGTS TREATMENT SYSTEM design feature(s)

X and/or interlocks which provide for the 3.7 1 following: Automatic system initiation.

K3.02 - Knowledge of the effect that a loss or 264000 EDGs malfunction of the EMERGENCY GENERA-PRA: Station blackout X TORS (DIESEL/JET) will have on the following: 3.9 1 A.C. electrical distribution.

K/A Category Point Totals: 3 2 3 3 2 2 3 3 2 3 2 Group Point Total: 28 12/16/02 2:47:26 PM Page 9 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points A1.01 - Ability to predict and/or monitor 201003 Control Rod and Drive changes in parameters associated with Mechanism operating the CONTROL ROD AND DRIVE X 3.7 1 MECHANISM controls including: Reactor power.

K4.01 - Knowledge of ROD WORTH 201006 RWM MINIMIZER SYSTEM (RWM) (PLANT X SPECIFIC) design feature(s) and/or interlocks 3.4 1 which provide for the following: Insert blocks/errors: Plant specific (not BWR6).

A4.11 - Ability to manually operate and/or 202001 Recirculation monitor in the control room: Seal pressures:

X 3.2 1 Plant-specific.

K3.02 - Knowledge of the effect that a loss of 204000 RWCU the REACTOR WATER CLEANUP SYSTEM X 3.1 1 will have on the following: Reactor water level.

K5.03 - Knowledge of the operational 205000 Shutdown Cooling implications of the following concepts as they X apply to SHUTDOWN COOLING SYSTEM 2.8 1 (RHR SHUTDOWN COOLING MODE): Heat removal mechanisms.

K1.05 - Knowledge of the physical 214000 RPIS connections and/ cause-effect relationships X between ROD POSITION INFORMATION 3.3 1 SYSTEM and the following: Full core display:

Plant-specific.

A3.02 - Ability to monitor automatic 215002 RBM operations of the ROD BLOCK MONITOR X SYSTEM including: meters and recorders: 3.1 1 BWR-3,4,5.

2.1.32 - Ability to explain and apply system 219000 RHR/LPCI: Torus/Pool Cooling X limits and precautions. 3.4 1 Mode A1.05 - Ability to predict and/or monitor 226001 RHR/LPCI: CTMT Spray Mode changes in parameters associated with the X RHR/LPCI CONTAINMENT SPRAY SYSTEM 3.1 1 MODE controls including: System lineup.

12/16/02 2:47:26 PM Page 10 of 12 NUREG-1021, Revision 8, Supplement 1

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K6.09 - Knowledge of the effect that a loss or 230000 RHR/LPCI: Torus/Pool Spray malfunction of the following will have on the Mode X RHR/LPCI: TORUS/ SUPPRESSION POOL 3.5 1 SPRAY MODE: Reactor building to suppres-sion pool vacuum breakers.

A4.04 - Ability to manually operate and/or 239001 Main and Reheat Steam monitor in the control room: System X 3.8 1 pressure.

K1.09 - Knowledge of the physical 245000 Main Turbine Generator and connections and/or cause-effect relationships 2.7 1 Auxiliary Systems X between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following:

D.C. electrical distribution.

A2.10 - Ability to (a) predict the impacts of 262001 AC Electrical Distribution the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those X predictions, use procedures to correct, 2.9 1 control, or mitigate the consequences of those abnormal conditions or operations: exceeding current limitations.

K3.03 - Knowledge of the effect that a loss or 263000 DC Electrical Distribution malfunction of the D.C. ELECTRICAL X DISTRIBUTION will have on the following: 3.4 1 Systems with D.C. components (i.e. valves, motors, solenoids, etc.).

A3.05 - Ability to monitor automatic 271000 Offgas System operations of the OFFGAS SYSTEM X 2.9 1 including: system indicating lights and alarms.

K4.02 - Knowledge of RADIATION MONITOR-272000 Radiation Monitoring System ING System design feature(s) and/or interlocks which provide for the following:

X 3.7 1 Automatic actions to contain the radioactive release in the event that the predetermined release rates are exceeded.

K2.02- Knowledge of electrical power supplies 286000 Fire Protection X to the following: Pumps. 2.9 1 A2.03- Ability to (a) predict the impacts of the 290001 Secondary CTMT following on: SECONDARY CONTAINMENT and (b) based on those predictions, use X procedures to correct, control, or mitigate the 3.4 1 consequences of those abnormal conditions or operations: High area radiation.

2.4.31 - Knowledge of annunciators alarms 400000 Component Cooling Water and indications, and use of the response X 3.3 1 instructions.

K/A Category Point Totals: 2 1 2 2 1 1 2 2 2 2 2 Group Point Total: 19 12/16/02 2:47:26 PM Page 11 of 12 NUREG-1021, Revision 8, Supplement 1

12/16/02 2:47:26 PM Page 12 of 12 NUREG-1021, Revision 8, Supplement 1 ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K6.04 - Knowledge of the effect that a loss or 215001 Traversing In-Core Probe malfunction of the following will have on the X TRAVERSING IN-CORE PROBE: Primary 3.1 1 containment isolation system: Mark-I&II (not BWR1).

K1.02 - Knowledge of the physical 233000 Fuel Pool Cooling and Cleanup connections and/or cause-effect relationships X between FUEL POOL COOLING AND 2.9 1 CLEAN-UP and the following: Residual heat removal system: Plant-specific.

A3.01 - Ability to monitor automatic operation 288000 Plant Ventilation of the PLANT VENTILATION SYSTEMS X 3.8 1 including: Isolation/initiation signals.

K3.07 - Knowledge of the effect that a loss of 290002 Reactor Vessel Internals malfunction of the REACTOR VESSEL X INTERNALS will have on the following: 3.1 1 Nuclear boiler instrumentation.

K/A Category Point Totals: 1 0 1 0 1 1 0 0 0 0 0 Group Point Total: 4 Plant-Specific Priorities System / Topic Recommended Replacement for... Reason Points Plant-Specific Priorities coincided with randomly selected KAs.

Plant-Specific Priority Total: (limit 10) 12/16/02 2:47:26 PM Page 13 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-5 Category K/A# Topic Imp. Points 2.1.1 Knowledge of conduct of operations requirements. 3.7 1 Ability to evaluate plant performance and make operational judgments based on operating 1 2.1.7 characteristics, reactor behavior, and instrument interpretation. 3.7 Conduct of Operations 2.1.20 Ability to execute procedure steps. 4.3 1 2.1.29 Knowledge of how to conduct and verify valve lineups. 3.4 1 Total 4 2.2.11 Knowledge of the process for controlling temporary changes. 2.5 1 Knowledge of surveillance procedures. 3.0 1 2.2.12 Equipment Control Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling 2.2.30 area, communication with fuel storage facility, systems operated from the control room in support of 3.5 1 fueling operations, and supporting instrumentation.

Total 3 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. 2.6 1 Radiation Control 2.3.11 Ability to control radiation releases. 2.7 1 Total 2 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.. 3.4 1 2.4.18 Knowledge of the specific bases for EOPs. 2.7 1 Emergency Procedures/Plan 2.4.27 Knowledge of fire in the plant procedure. 3.0 1 2.4.29 Knowledge of the emergency plan. 2.6 1 Total 4 Tier 3 Point Total (RO/SRO) 13 12/16/02 2:47:26 PM Page 14 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station Date of Exam: August 5, 2002 Exam Level: SRO K/A Category Points Tier Group Point K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Total 5 4 4 5 5 3 26

1. 1 Emergency &

2 2 3 3 3 3 3 17 Abnormal Plant Evolutions Tier 7 7 7 8 8 6 43 Totals 3 2 1 2 2 1 3 3 1 3 2 23 1

2.

2 1 1 1 1 1 1 1 1 2 1 2 13 Plant Systems 3 0 0 1 0 0 1 1 0 1 0 0 4 Tier 4 3 3 3 3 3 5 4 4 4 4 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 +/-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 12/16/02 2:47:26 PM Page 15 of 12 NUREG-1021, Revision 8, Supplement 1

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 table above.

12/16/02 2:47:26 PM Page 16 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 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. Points AK1.06 - Knowledge of the operational implications of the following 295003 Partial or Complete Loss of concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

AC Power / 6 X 4.0* 1 POWER: Station blackout: Plant-specific.

AK1.03 - Knowledge of the operational implications of the following 295003 Partial or Complete Loss of concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

AC Power / 6 X 3.2 1 POWER: Under voltage/degraded voltage effects on electrical loads.

AK3.05 - Knowledge of the reasons for the following responses as they 295006 SCRAM / 1 X apply to SCRAM: Direct turbine generator trip: Plant-specific. 4.0 1 AK2.01 - Knowledge of the interrelations between HIGH REACTOR 295007 High Reactor Pressure / 3 X PRESSURE and the following: Reactor turbine pressure regulating 3.7 1 system.

AA2.01 - Ability to determine and/or interpret the following as they apply to 295009 Low Reactor Water Level / 2 X LOW REACTOR WATER LEVEL: Reactor Water Level 4.2 1 AA1.05 - Ability to operate and/or monitor the following as they apply to 295010 High Drywell Pressure / 5 X HIGH DRYWELL PRESSURE: Drywell/suppression vent and purge. 3.4 1 AA2.01 - Ability to determine and/or interpret the following as they apply to 295013 High Suppression Pool Temp. / 5 X HIGH SUPPRESSION POOL TEMP: Suppression pool temperature. 4.0 1 AK2.06 - Knowledge of the interrelations between INADVERTENT 295014 Inadvertent Reactivity Addition / 1 X REACTIVITY ADDITION and the following: Moderator temperature. 3.5 1 AK1.01 - Knowledge of the operational implications of the following 295015 Incomplete SCRAM / 1 X concepts as they apply to INCOMPLETE SCRAM: Shutdown margin. 3.9* 1 AA1.06 - Ability to operate and/or monitor the following as they apply to 295016 Control Room Abandonment / 7 X CONTROL ROOM ABANDONMENT: Reactor water level. 4.1 1 2.4.48 - Ability to interpret control room indications to verify the status and 295017 High Off-site Release Rate / 9 operation of system, and understand how operator actions and directives X 3.8 1 affect plant and system conditions.

AK1.03 - Knowledge of the operational implications of the following 295023 Refueling Accidents / 8 X concepts as they apply to REFUELING ACCIDENTS: Inadvertent 4.0 1 criticality.

EK3.04 - Knowledge of the reasons for the following responses as they 295024 High Drywell Pressure / 5 X apply to HIGH DRYWELL PRESSURE: Emergency depressurization. 4.1 1 2.4.11 - Knowledge of abnormal condition procedures.

295025 High Reactor Pressure / 3 X 3.6 1 EK1.01 - Knowledge of the operational implications of the following 295026 High Suppression Pool Water Temp. / 5 X concepts as they apply to SUPPRESSION POOL HIGH WATER 3.4 1 TEMPERATURE: Pump NPSH.

EK2.02 - Knowledge of the interrelations between SUPPRESSION POOL 295026 High Suppression Pool Water Temp. / 5 X HIGH WATER TEMPERATURE and the following: Suppression pool 3.8 1 spray: Plant-specific.

12/16/02 2:47:26 PM Page 2 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 EK3.02 - Knowledge of the reasons for the following responses as they 295030 Low Suppression Pool Water Level / 5 X apply to LOW SUPPRESSION POOL WATER LEVEL: HPCI operation: 3.7 1 Plant-specific.

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points EA2.01- Ability to determine and/or interpret the following as they apply to 295030 Low Suppression Pool Water Level / 5 LOW SUPPRESSION POOL WATER LEVEL: Suppression pool level.

X 4.2 1 EA2.04 - Ability to determine and/or interpret the following as they apply to 295031 Reactor Low Water Level / 2 X REACTOR LOW WATER LEVEL: Adequate core cooling. 4.8* 1 EA1.13- Ability to determine and/or monitor the following as they apply to 295031 Reactor Low Water Level / 2 X REACTOR LOW WATER LEVEL: Reactor Water Level control 4.4* 1 2.4.8 - Knowledge of how the event-based emergency/abnormal operating 295037 SCRAM Condition Present and Power procedures are used in conjunction with the symptom-based EOPs.

Above APRM Downscale or Unknown / 1 X 3.7 1 PRA: ATWS EK3.02 - - Knowledge of the reasons for the following responses as they 295037 SCRAM Condition Present and Power apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE Above APRM Downscale or Unknown / 1 X APRM DOWNSCALE OR UNKNOWN: SBLC injection. 4.5* 1 PRA: ATWS EA1.07 - Ability to operate and/or monitor the following as they apply to 295038 High Off-site Release Rate / 9 HIGH OFF-SITE RELEASE RATE: Control room ventilation: Plant-X 3.8 1 specific.

EK2.05 - Knowledge of the interrelations between HIGH OFF-SITE 295038 High Off-site Release Rate / 9 X RELEASE RATE and the following: Site emergency plan. 4.7* 1 EA1.02 - Ability to operate and monitor the following as they apply to HIGH 500000 High Containment Hydrogen Conc. / 5 CONTAINMENT HYDROGEN CONTROL: Primary containment oxygen X 3.2 1 instrumentation.

EA2.03 - Ability to determine and/or interpret the following as they apply to 500000 High Containment Hydrogen Conc. / 5 HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:

X 3.3 1 Combustible limits for drywell.

K/A Category Totals: 5 4 4 5 5 3 Group Point Total: 26 12/16/02 2:47:26 PM Page 3 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 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. Points 2.1.7 - Ability to evaluate plant performance and make operational 295001 Partial or Complete Loss of Forced Core judgments based on operating characteristics, reactor behavior, and Flow Circulation / 1 & 4 X 4.4 1 instrument interpretation.

AK3.01 - Knowledge of the reasons for the following responses as they 295002 Loss of Main Condenser Vacuum / 3 apply to LOSS OF MAIN CONDENSER VACUUM: Reactor SCRAM:

X 3.8 1 Plant-specific.

AK1.06 - Knowledge of the operational implications of the following 295004 Partial or Complete Loss of concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C.

DC Power / 6 X POWER: Prevention of inadvertent system(s) actuation upon restoration of 3.6 1 D.C. POWER.

AA1.07 - Ability to operate and/or monitor the following as they apply to 295005 Main Turbine Generator Trip / 3 X MAIN TURBINE GENERATOR TRIP: A.C. electrical distribution. 3.3 1 AA2.02 - Ability to determine and/or interpret the following as they apply to 295008 High Reactor Water Level / 2 X HIGH REACTOR WATER LEVEL: Steam flow/feedflow mismatch. 3.4 1 AK2.02 - Knowledge of the interrelations between HIGH DRYWELL 295012 High Drywell Temperature / 5 X TEMPERATURE and the following: Drywell cooling. 3.7 1 AA1.01 - Ability to operate and/or monitor the following as they apply to 295018 Partial or Complete Loss of CCW / 8 PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

X 3.4 1 Backup systems.

2.4.31 - Knowledge of annunciators alarms and indications, and use of the 295019 Part. Or Comp. Loss of Inst. Air / 8 X response instructions. 3.4 1 AK3.04 - Knowledge of the reasons for the following responses as they 295020 Inadvertent Cont. Isolation / 5 & 7 apply to INADVERTENT CONTAINMENT ISOLATION: Reactor pressure X 4.1 1 response.

AK3.05 - Knowledge of the reasons for the following responses as they 295021 Loss of Shutdown Cooling / 4 apply to LOSS OF SHUTDOWN COOLING: Establishing alternate heat X 3.8 1 removal flow paths.

EK1.01 - Knowledge of the operational implications of the following 295028 High Drywell Temperature / 5 concepts as they apply to HIGH DRYWELL TEMPERATURE: Reactor X 3.7 1 water level measurement.

EK2.05 - Knowledge of the interrelations between HIGH SUPPRESSION 295029 High Suppression Pool Water Level / 5 POOL WATER LEVEL and the following: Containment/drywell vacuum 1 X breakers. 3.3 295032 High Secondary Containment Area X 2.4.27 - Knowledge of fire in the plant procedure. 3.5 1 Temperature / 5 12/16/02 2:47:26 PM Page 4 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 EA2.03 - Ability to determine and/or interpret the following as they apply to 295033 High Sec. Cont. Area Rad. Levels / 9 HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Cause X 4.2 1 of high area radiation.

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points EK2.04 - Knowledge of the interrelations between SECONDARY 295034 Sec. Cont. Ventilation High Rad. / 9 CONTAINMENT VENTILATION HIGH RADIATION and the following:

X 3.9 1 Secondary containment ventilation.

EA1.01 - Ability to operate and/or monitor the following as they apply to 295035 Sec. Cont. High Differential Pressure / 5 X SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: 3.6 1 Secondary containment ventilation system.

AA2.04 - Ability to determine and interpret the following as they apply to 600000 Plant Fire On Site / 8 PLANT FIRE ON SITE: The fires extent of potential operational damage to X 3.1 1 plant equipment.

K/A Category Point Totals: 2 3 3 3 3 3 Group Point Total: 17 12/16/02 2:47:26 PM Page 5 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K1.05 - Knowledge of the physical 202002 Recirculation Flow Control connections and/or cause-effect relationships between RECIRCULATION FLOW CONTROL X 3.5 1 SYSTEM and the following: Recirculation MG set: Plant-Specific.

A2.04 - Ability to (a) predict the impacts of the 202002 Recirculation Flow Control following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, X control, or mitigate the consequences of those 3.2 1 abnormal conditions or operations:

Recirculation pump speed mismatch between loops: Plant-Specific.

K2.01 - Knowledge of electrical power 203000 RHR/LPCI: Injection Mode X supplies to the following: Pumps. 3.5* 1 K4.07 - Knowledge of HIGH PRESSURE 206000 HPCI COOLANT INJECTION SYSTEM design X feature(s) and/or interlocks which provide for 4.3 1 the following: Automatic system initiation:

BWR-2,3,4.

A4.11 - Ability to manually operate and/or 209001 LPCS X monitor in the control room: System flow. 3.6 1 K5.04- Knowledge of the operational 211000 SLC implications of the following concepts as they X 3.2 1 apply to STANDBY LIQUID CONTROL SYSTEM: Explosive valve operation.

212000 RPS A4.07 - Ability to manually operate and/or X monitor in the control room: System status 3.9* 1 lights and alarms.

A3.04 - Ability to monitor automatic opera-215004 SRM tions of the AVERAGE POWER RANGE X MONITOR/LOCAL POWER RANGE 3.6 1 MONITOR SYSTEM including: Annunciators and alarm signals.

K1.16 - Knowledge of the physical 215005 APRM/LPRM connections and/or cause-effect relationships between AVERAGE POWER RANGE X MONITOR/LOCAL POWER RANGE 3.4 1 MONITOR SYSTEM and the following: Flow converter/comparator network: Plant-Specific.

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System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 215005 APRM/LPRM X K2.02-Knowledge of electrical power supplies 2.8 1 to the following: APRM channels.

K5.12 - Knowledge of the operational 216000 Nuclear Boiler Instrumentation implications of the following concepts as they apply to NUCLEAR BOILER X INSTRUMENTATION: Effects on level 3.3 1 indication due to rapid changes in void fraction.

A1.01 - Ability to predict and/or monitor 217000 RCIC changes in parameters associated with X operating the REACTOR CORE ISOLATION 3.7 1 COOLING SYSTEM (RCIC) controls including: RCIC flow.

A4.06 - Ability to manually operate and/or 218000 ADS monitor in the control room: ADS valve tail 3.6 1 X pipe temperature.

2.1.2 - Knowledge of operator responsibilities 223001 Primary CTMT and Auxiliaries X during modes of plant operation. 4.0 1 K1.08 - Knowledge of the physical 223002 PCIS/Nuclear Steam Supply X connections and/or cause-effect relationships Shutoff between PRIMARY CONTAINMENT 3.5 1 ISOLATION SYSTEM/ NUCLEAR STEAM SUPPLY SHUT-OFF and the following:

Shutdown cooling system/RHR.

A1.05 - Ability to predict and/or monitor 226001 RHR/LPCI Containment Spray changes in parameters associated with the Mode X RHR/LPCI CONTAINMENT SPRAY SYSTEM 3.4 1 MODE controls including: System lineup.

A2.02 - Ability to (a) predict the impacts of 239002 SRVs the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, X 3.2 1 control, or mitigate the consequences of those abnormal conditions or operations:

Leaky SRV.

241000 Reactor/Turbine Pressure 2.2.22 - Knowledge of limiting conditions for X operations and safety limits. 4.1 1 Regulator A1.01 - Ability to predict and/or monitor 259002 Reactor Water Level Control changes in parameters associated with operating the REACTOR WATER LEVEL X 3.1 1 CONTROL SYSTEM controls including:

Reactor water level.

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System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K4.01 - Knowledge of STANDBY GAS 261000 SGTS TREATMENT SYSTEM design feature(s)

X and/or interlocks which provide for the 3.8 1 following: Automatic system initiation.

K6.03 - Knowledge of the effect that a loss or 262001 AC Electrical Distribution malfunction of the following will have on the X 3.7 1 A.C. ELECTRICAL DISTRIBUTION: Generator Trip.

K3.02 - Knowledge of the effect that a loss or 264000 EDGs malfunction of the EMERGENCY X GENERATORS (DIESEL/JET) will have on the 4.0 1 following: A.C. electrical distribution.

A2.03 - Ability to (a) predict the impacts of the 290001 Secondary CTMT following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, X 3.6 1 or mitigate the consequences of those abnormal conditions or operations: High area radiation.

K/A Category Point Totals: 3 2 1 2 2 1 3 3 1 3 2 Group Point Total: 23 12/16/02 2:47:26 PM Page 8 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points A2.12 - Ability to (a) predict the impacts of 201001 CRD Hydraulic the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM; and (b) based on those predictions, use procedures to correct, X 2.9 1 control, or mitigate the consequences of those abnormal conditions or operations: High cooling water flow.

A1.02 - Ability to predict and/or monitor 201002 RMCS changes in parameters associated with X operating the REACTOR MANUAL CONTROL 3.3 1 SYSTEM controls including: Control rod position.

K4.01 - Knowledge of ROD WORTH 201006 RWM MINIMIZER SYSTEM (RWM) (PLANT X SPECIFIC) design feature(s) and/or interlocks 3.5 1 which provide for the following: Insert blocks/errors: Plant specific (not BWR6).

A4.11 - Ability to manually operate and/or 202001 Recirculation X monitor in the control room: Seal pressures:

3.3 1 Plant-specific.

K3.02 - Knowledge of the effect that a loss or 204000 RWCU malfunction of the REACTOR WATER X CLEANUP SYSTEM will have on the following: 3.1 1 Reactor water level.

K5.03 - Knowledge of the operational 205000 Shutdown Cooling implications of the following concepts as they X apply to SHUTDOWN COOLING SYSTEM 3.1 1 (RHR SHUTDOWN COOLING MODE): Heat removal mechanisms.

A3.02 - Ability to monitor automatic 215002 RBM operations of the ROD BLOCK MONITOR X SYSTEM including: Meters and recorders: 3.0 1 BWR-3,4,5.

K6.09 - Knowledge of the effect that a loss or 230000 RHR/LPCI: Torus/Pool Spray malfunction of the following will have on the Mode X RHR/LPCI TORUS/SUPPRESSION POOL 3.8 1 SPRAY MODE: Reactor building to suppression pool vacuum breakers.

2.4.24 - Ability to analyze the effect of 234000 Fuel Handling Equipment X maintenance activities on LCO status. 3.8 1 12/16/02 2:47:26 PM Page 9 of 12 NUREG-1021, Revision 8, Supplement 1

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K1.09 - Knowledge of the physical con-245000 Main Turbine Generator and nections and/or cause/effect relationships Auxiliaries X between MAIN TURBINE GENERATOR AND 2.7 1 AUXILIARY SYSTEMS and the following:

D.C. electrical distribution.

A3.05 - Ability to monitor automatic 271000 Offgas operations of the OFFGaS SYSTEM X including: System indicating lights and 2.9 1 alarms.

K2.02- Knowledge of electrical power supplies 286000 Fire Protection X to the following: Pumps. 3.1 1 2.4.31 - Knowledge of annunciators alarms 400000 Component Cooling Water and indications, and use of the response X 3.4 1 instructions K/A Category Point Totals: 1 1 1 1 1 1 1 1 2 1 2 Group Point Total: 13 12/16/02 2:47:26 PM Page 10 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points A1.01 - Ability to predict and/or monitor 201003 Control Rod and Drive changes in parameters associated with Mechanism X operating the CONTROL ROD AND DRIVE 3.8 1 MECHANISM controls including: Reactor Power.

K6.04 - Knowledge of the effect that a loss or 215001 Traversing In-Core Probe malfunction of the following will have on the X TRAVERSING IN-CORE PROBE: Primary 3.4 1 containment isolation system Mark I&II (Not BWR1).

A3.01 - Ability to monitor automatic operation 288000 Plant Ventilation X of the PLANT VENTILATION SYSTEMS 3.8 1 including: Isolation/initiation signals.

K3.07 - Knowledge of the effect that a loss or 290002 Reactor Vessel Internals malfunction of the REACTOR VESSEL X INTERNALS will have on the following: 3.1 1 Nuclear boiler instrumentation.

K/A Category Point Totals: 0 0 1 0 1 1 1 0 0 0 0 Group Point Total: 4 Plant-Specific Priorities System / Topic Recommended Replacement for... Reason Points Plant-Specific Priorities coincided with randomly selected KAs.

Plant-Specific Priority Total: (limit 10) 12/16/02 2:47:26 PM Page 11 of 12 NUREG-1021, Revision 8, Supplement 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-5 Category K/A# Topic Imp. Points 2.1.1 Knowledge of conduct of operations requirements. 3.8 1 2.1.10 Knowledge of conditions and limitations in the facility license. 3.9 1 2.1.12 Ability to apply technical specifications for a system. 4.0 1 Conduct of Operations 2.1.29 Knowledge of how to conduct and verify valve lineups. 3.3 1 Ability to recognize indications for system operating parameters that are entry-level conditions for 1 2.1.33 technical specifications. 4.0 TOTAL 5 2.2.11 Knowledge of the process for controlling temporary changes. 3.4 1 2.2.12 Knowledge of surveillance procedures. 3.4 1 Equipment Control 2.2.26 Knowledge of refueling administrative requirements. 3.7 1 2.2.28 Knowledge of SRO fuel handling responsibilities. 3.8 1 TOTAL 4 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. 3.0 1 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personal 3.3 1 Radiation Control exposure.

2.3.11 Ability to control radiation releases. 3.2 1 TOTAL 3 12/16/02 2:47:26 PM Page 12 of 12 NUREG-1021, Revision 8, Supplement 1

Category K/A# Topic Imp. Points 2.4.6 Knowledge symptom based EOP mitigation strategies 4.0 1 2.4.12 Knowledge of general operating crew responsibilities during emergency operations. 3.6 1 2.4.18 Knowledge of the specific bases for EOPs. 3.5 1 Emergency Procedures/Plan 2.4.27 Knowledge of fire in the plant procedure. 4.0 1 2.4.29 Knowledge of the emergency plan. 4.0 1 TOTAL 5 Tier 3 Point Total (RO/SRO) 17 12/16/02 2:47:26 PM Page 13 of 12 NUREG-1021, Revision 8, Supplement 1

Tier / Group Randomly Selected K/A Reason for Rejection Tier 2/Group 2 226001, K2.02 RO/SRO K/A 226001, K2.02, was changed to prevent double jeopardy with RO/SRO K/A (RO) 203000, K2.01. (Both K/As required knowledge of the power supplies to the RHR Pumps.)

Tier 2/Group 1 (SRO) Another token for 226001, was randomly selected and the K/A was changed to A1.05 (New K/A) 226001, A1.05, Ability to predict and/or monitor changes in parameters associated with the RHR/LPCI CONTAINMENT SPRAY SYSTEM MODE controls including: System lineup.

(Old K/A) 226001, K2.02, Knowledge of electrical power supplies to the following: Pumps.

(Double Jeopardy K/A) 203000, K2.01, Knowledge of electrical power supplies to the following:

Pumps.

Tier 1/Group 2 295026, EK2.02 RO/SRO K/A 295026, EK2.02 was changed on the RO and SRO Sample Plan because there (RO) are no procedures that relate suppression pool sprays and high Suppression Pool Water Tier 1/Group 1 Temperature. Another token was randomly selected and new K/As independently replaced in (SRO) the RO and SRO Sample Plans.

(Old K/A RO & SRO) 295026, EK2.02, Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following: Suppression pool spray: Plant-specific.

(New RO K/A) 295026, EK3.05, Knowledge of the reasons for the following responses as apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor scram.

(New SRO K/A) 295026, EK1.01, Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Pump NPSH.

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Tier / Group Randomly Selected K/A Reason for Rejection Tier 1/Group 1 295006, AK3.05 RO/SRO K/A, 295006, AK3.05, was changed because the Cooper Station does not have a (RO) direct trip between RPS (Reactor Scram) and the Main Turbine.

Tier 1/Group 1 (SRO) Another token for 295006, AK03 was randomly selected and the K/A was changed to 295006, AK3.06.

(New K/A) 295006, AK3.06, Knowledge of the reason for the following responses as they apply to scram: Recirculation pump speed reduction: Plant-Specific (3.2/3.3).

(Old K/A) 295006, AK3.05, Knowledge of the reason for the following responses as they apply to scram: Direct turbine generator trip: Plant-Specific (3.8/4.0).

295008, AA2.02 RO/SRO K/A 295008, AA2.02, was changed to prevent double jeopardy with RO/SRO K/A 295002, A2.03. (Both K/As required knowledge of the effects of steam flow on RPV water level.)

Another token for 295008, AA2, was randomly selected and the K/A was changed to AA2.05 (New K/A) - 295008, AA2.05, Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL: Swell (2.9/3.1)

(Old K/A) 295008, AA2.02, - Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL: Steam flow/feedflow mismatch. (3.4/3.4)

(Double Jeopardy K/A) 259002, A3.03, - Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including: Changes in main steam flow.

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Tier / Group Randomly Selected K/A Reason for Rejection Tier 2/Group 2 226001, K2.02 RO/SRO K/A 239002, A2.02, was changed to prevent double jeopardy with RO/SRO K/A (RO) 218000, A4.06. (Both K/As required knowledge of the operator detection of a leaking SRV. The Tier 2/Group 1 239002 K/A was specifically difficult because the Cooper Station does not have a procedure for (SRO) a leaky SRV. If a leaky SRV is detected engineering is contacted and a procedure developed at that time.)

It is also double jeopardy with 295013.AA2.01 as it relates to open SRV effects on suppression pool temperature Another token for 239002.A2 was randomly selected and the K/A was changed to A2.01 (New K/A) 239002, A2.01, Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open vacuum breakers. (3.0/3.3).

(Old K/A) 226001, A2.02, Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Leaky SRV.

(3.1/3.2)

(Double Jeopardy K/A) 218000A4.06, Ability to manually operate and/or monitor in the control room: ADS valve tail pipe temperature.

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