ML051780436

CGS-05-2005 - Final - Outline

ML051780436
Person / Time
Site:	Columbia
Issue date:	06/27/2005
From:	Gody A Operations Branch IV
To:	Parrish J Energy Northwest
References
50-397/05-301, CGS-05-2005, ES-401-1, NUREG-1021, Rev 9 50-397/05-301
Download: ML051780436 (33)

Text

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 Facility: Columbia Generating Station Date of Exam:

Tier Group RO Category Points SRO Only Points K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 1 3 5 5 3 3 20 2 5 7 Emergency and 2 1 1 1 N/A 2 2 N/A 0 7 2 1 3 Abnormal Plant Evolutions Tier Totals 2 4 6 7 5 3 27 4 6 10

2. 1 4 1 1 1 2 3 4 4 1 2 3 26 1 4 5 Plant 2 2 1 1 3 0 1 0 1 2 1 0 12 2 1 3 Systems Tier Totals 6 2 2 4 2 4 4 5 3 3 3 38 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 4 2 2 2 10 1 2 2 2 7

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 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 + or - 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 ES-401, Attachment 2 for guidance regarding the 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 a system or evolution.

5. Absent a plant specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO only portions, respectively.

6. Select SRO topics for Tiers 1 and2 from the shaded system and K/A categories.

Page 1 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1

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.

8. On the following page, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. 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 number, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

Page 2 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - RO K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295001 Partial or Complete Loss of X AK3.01 - Knowledge of the reasons for the 3.4 1 Forced Core Flow Circulation / 1 & 4 following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Reactor water level response 295003 Partial or Complete Loss of AC / 6 X 2.1.24 - Ability to obtain and interpret station 2.8 1 electrical and mechanical drawings 295004 Partial or Total Loss of DC PWR / X AA1.02 - Ability to operate and/or monitor the 3.8 1 6 following as they apply to PARTIAL OR COMPLETE LOSS OF DC POWER: System necessary to assure safe plant shutdown 295005 Main Turbine Generator Trip / 3 X AA2.03 - Ability to determine and/or interpret the 3.1 1 following as they apply to MAIN TURBINE GENERATOR TRIP: Turbine valve position 295006 SCRAM / 1 X AK2.06 - Knowledge of the interrelations 4.2 1 between SCRAM and the following: Reactor Power 295016 Control Room Abandonment / 7 X AK2.02 - Knowledge of the interrelations 4.0 1 between CONTROL ROOM ABANDONMENT and the following: Local control stations 295018 Partial or Complete Loss of CCW X AA1.03 - Ability to operate and/or monitor the 3.3 1

/8 following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER Page 3 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295019 Partial or Complete Loss of Inst. X AK2.03 - Knowledge of the interrelations 3.2 1 Air / 8 between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: Reactor feedwater 295021 Loss of Shutdown Cooling / 4 X AA1.02 - Ability to operate and/or monitor the 3.5 1 following as they apply to LOSS OF SHUTDOWN COOLING: RHR/Shutdown Cooling 295021 Loss of Shutdown Cooling / 4 X 2.4.35 - Knowledge of local operator auxiliary 3.3 1 operator tasks during emergency operations including system geography and system implications.

295023 Refueling Accident / 8 X AA1.05 - Ability to operate and/or monitor the 2.8 1 following as they apply to REFUELING ACCIDENTS: Fuel transfer system 295024 High Drywell Pressure / 5 X EK3.06 - Knowledge of the reasons for the 4.0 1 following responses as they apply to HIGH DRYWELL PRESSURE: Reactor Scram 295025 High Reactor Pressure / 3 X EA2.02 - Ability to determine and/or interpret the 4.2 1 following as they apply to HIGH REACTOR PRESSURE: Reactor power 295026 Suppression Pool High Water X EK3.04 - Knowledge of the reasons for the 3.7 1 Temperature / 5 following responses as they apply to HIGH SUPPRESSION POOL WATER TEMPERATURE: SLC injection 295027High Containment Temperature / 5 N/A MARK III CONTAINMENT ONLY 295028 High Drywell Temperature / 5 X 2.4.13 - Knowledge of crew roles and 3.3 1 responsibilities during EOP flowchart use Page 4 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295030 Low Suppression Pool Water X EA1.06 - Ability to operate and/or monitor the 3.4 1 Level / 5 following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Condensate storage and transfer (make up to the suppression pool) 295031 Reactor Low Water Level / 2 X EK3.03 - Knowledge of the reasons for the 4.1 1 following responses as they apply to REACTOR LOW WATER LEVEL: Spray cooling 295037 SCRAM Condition Present and X EK1.03 - Knowledge of the operational 4.2 1 Power Above APRM Downscale or implications of the following concepts as they Unknown / 1 apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Boron affects of reactor power 295038 High Off-site Release Rate / 9 X EK3.02 - - Knowledge of the reasons for the 3.9 1 following responses as they apply to HIGH OFF SITE RELEASE RATE: System isolations 600000 Plant Fire On Site / 8 X AA2.03 - Ability to determine and/or interpret the 2.8 1 following as they apply to PLANT FIRE ON SITE:

Damper position Category Point Totals: 1 3 5 5 3 3 Group Point Totals: 20/7 20 Page 5 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - RO K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295002 Loss of Main Condenser Vacuum

/3 295007 High Reactor Pressure / 3 X AK3.06 - Knowledge of the reasons for the 3.7 1 following responses as they apply to HIGH REACTOR PRESSURE: Reactor/turbine pressure regulating system 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X AA2.01 - Ability to determine and/or interpret the 4.2 1 following as they apply to LOW REACTOR WATER LEVEL: Reactor water level 295010 High Drywell Pressure / 5 295011 High Containment Temperature / N/A MARK III CONTAINMENT ONLY 5

295012 High Drywell Temperature / 5 X AK2.02 - Knowledge of the interrelations 3.6 1 between HIGH DRYWELL TEMPERATURE and the following: Drywell cooling 295013 High Suppression Pool Temperature / 5 295014 Inadvertent Reactivity Addition / 1 X AA1.02 - Ability to operate and or monitor the 3.6 1 following as they apply to INADVERTENT REACTIVITY ADDITION: Recirculation Flow Control 295015 Incomplete SCRAM / 1 Page 6 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295017 High Off-site Release Rate / 9 295020 Inadvertent Containment Isolation

/5&7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Water Level / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment X EK1.02 - Knowledge of the operational 3.8 1 Ventilation High Radiation / 9 implications of the following concepts as they apply to SECONDARY CONTAINMENT VENTILAITON HIGH RADIATION: Personnel protection 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High X EA2.01 - Ability to determine and/or interpret the 3.0 1 Sump/Area Water Level / 5 following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Operability of components within the affected area 500000 High Containment Hydrogen X EA1.06 - Ability to operate and or monitor the 3.3 1 Concentration / 5 following as they apply to HIGH CONTAINMENT HYDROGEN CONTROL: Drywell sprays Category Point Totals: 1 1 1 2 2 0 Group Point Totals: 7/3 7 Page 7 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP I BWR - RO SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

203000 RHR/LPCI: Injection X A1.05 - Ability to predict 3.8 1 Mode and/or monitor changes in parameters associated with operating the RHR/LPCI:

INJECTION MODE controls including: Suppression pool level 205000 Shutdown Cooling X K1.01 - Knowledge of the 3.6 1 physical connections and/or cause-effect relationships between SHUTDOWN COLLING SYSTEM and the following: Reactor pressure 206000 HPCI N/A AT CGS 207000 Iso (Emerg) Cond N/A AT CGS 209001 LPCS X K5.05 - Knowledge of the 2.5 1 operational implications of the following as they apply to LOW PRESSURE CORE SPRAY SYSTEM: System venting 209001 LPCS X K6.11 - Knowledge of the 3.6 1 effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSTEM: ADS Page 8 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

209002 HPCS X K1.02 - Knowledge of the 3.5 1 physical connections and/or cause-effect relationships between HIGH PRESSURE CORE SPRAY SYSTEM and the following: Suppression pool 209002 HPCS X A2.13 - Ability to predict the 3.4 1 impacts of the following on the HPCS and based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Low condensate storage tank level 211000 SLC X K6.03 - Knowledge of the 3.2 1 effect that a loss or malfunction of the following will have on the STANDBY LIQUID CONTROL SYSTEM:

AC power 212000 RPS X A4.05 - Ability to manually 4.3 1 operate and/or monitor in the control room: Reactor power 215003 IRM X A3.02 - Ability to monitor 3.3 1 automatic operations of the IRM SYSTEM including:

Annunciation and alarm signals Page 9 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

215004 SRM X A1.06 - Ability to predict and/or 3.1 1 monitor changes in parameters associated with operating the SRM controls including: Lights and alarms 215005 APRM/LPRM X K2.02 - Knowledge of the 2.6 1 electrical power supplies to the following: APRM channels 217000 RCIC X K1.05 - Knowledge of the 2.6 1 physical connections and/or cause-effect relationships between RCIC SYSTEM and the following: RHR system 218000 ADS X K5.01 - Knowledge of the 3.8 1 operational implications of the following as they apply to ADS SYSTEM: ADS logic operation 218000 ADS X A1.04 - Ability to predict and/or 4.1 1 monitor changes in parameters associated with operating the ADS controls including: Reactor Pressure 223002 PCIS/ Nuclear X 2.4.11 - Knowledge of 3.4 1 Steam Supply Shutoff abnormal condition procedures Page 10 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

239002 SRVs X K4.09 - Knowledge of 3.7 1 RELIEF/SAFETY VALVES design features and/or interlocks which provide for the following: Manual opening of the SRV 239002 SRVs X K6.01 - Knowledge of the 3.2 1 effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES: NBI pressure indication 259002 Reactor Water Level X 2.2.27 - Knowledge of the 2.6 1 Control refueling process 261000 SGTS X 2.1.24 - Ability to obtain and 2.8 1 interpret station electrical and mechanical drawings 262001 AC Elec Dist X K3.04 - Knowledge of the 3.1 1 effect that a loss or malfunction of the AC ELECTRICAL DISTRIBUTION will have on the following: UPS Page 11 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

262001 AC Elec Dist X A2.01 - Ability to predict the 3.4 1 impacts of the following on the AC ELECTRICAL DISTRIBUTION and based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations:

Turbine/generator trip 262002 UPS (AC/DC) X A2.02 - Ability to predict the 2.5 1 impacts of the following on the UPS and based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Overvoltage 263000 DC Elec Dist X A4.01 - Ability to manually 3.3 1 operate and/or monitor in the control room: Major breakers and control power fuses 264000 EDGs X K1.02 - Knowledge of the 2.9 1 physical connections and/or cause-effect relationships between EMERGENY DGS and the following: DC electrical distribution Page 12 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

300000 Instrument Air X A2.01 - Ability to predict the 2.9 1 impacts of the following on the INSTURMENT AIR SYSTEM and based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Air dryer and filter malfunctions 400000 Component Cooling X A1.01 - Ability to predict and/or 2.8 1 Water monitor changes in parameters associated with operating the CCWS controls including: CCW flow rate Category Point Totals: 4 1 1 1 2 3 4 4 1 2 3 Group Point Total: 26/5 26 Page 13 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP II BWR - RO SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

201001 CRD Hydraulic X K6.06 - Knowledge of the 2.8 1 effect that a loss or malfunction of the following will have on the CRDH SYSTEM:

CCW system:

201002 RMCS X K1.05 - Knowledge of the 3.4 1 physical connections and/or cause-effect relationships between RMCS and the following: RWM 201003 CRD Mechanism 201004 RSCS 201005 RCIS N/A AT CGS 201006 RWM 202001 Recirculation X A3.02 - Ability to monitor 3.1 1 automatic operations of the RECIRCULATION SYSTEM including: Pump start sequence 202002 Recirc Flow Control 204000 RWCU X K4.06 - Knowledge of RWCU 2.6 1 design features and/or interlocks which provide for the following: Maximize plant efficiency Page 14 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

214000 RPIS 215001 TIP 215002 RBM 216000 Nuclear Boiler Inst 219000 RHR/LPCI: Pool Cooling Mode 223001 Pri Containment and X K3.04 - Knowledge of the 3.3 1 Aux effect that a loss or malfunction of the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES will have on the following: Drywell hydrogen gas concentration 226001 RHR/LPCI: CTMT X A3.03 - Ability to monitor 2.8 1 Spray Mode automatic operations of the RHR CONTAINMENT SPRAY SYSTEM MODE including:

System flow 230000 RHR/LPCI: Pool X K2.02 - Knowledge of the 2.8 1 Spray Mode electrical power supplies to the following: Pumps Page 15 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

233000 FPC X A4.05 - Ability to manually 2.5 1 operate and/or monitor in the control room: Pool temperature 234000 Fuel Handling Eq. X K4.02 - Knowledge of FUEL 3.3 1 HANDLING EQUIPMENT design features and/or interlocks which provide for the following: Prevention of control rod movement during core alterations 239001 Main & Reheat Stm 239003 MSLC 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Generator/Aux 256000 Reactor Condensate 259001 Reactor Feedwater X K1.08 - Knowledge of the 3.6 1 physical and/or cause-effect relationship between REACTOR FEEDWATER SYSTEM and the following:

Reactor water level control 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring Page 16 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

286000 Fire Protection X A2.11 - Ability to predict the 3.1 1 impacts of the following on the FIRE PROTECTION SYSTEM and based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Pump trips 288000 Plant Ventilation 290001 Secondary X K4.02 - Knowledge of 2.8 1 Containment SECONDARY CONTAINMETN design features and/or interlocks which provide for the following:

Protection against over pressurization 290002 Reactor Vessel Int 290003Control Room HVAC Category Point Totals: 2 1 1 3 0 1 0 1 2 1 0 Group Point Total: 12/3 12 Page 17 of 17

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-3 (Tier 3)

PLANT-WIDE GENERIC RESPONSIBILITIES TIER 3 BWR - RO K/A TOPICS RO SRO Category IMP # IMP #

1. 2.1.24 Ability to obtain and interpret station electrical and mechanical 2.8 1 Conduct drawings.

2.1.32 Ability to explain and apply system limits and precautions 3.4 1 of 2.1.1 Knowledge of Conduct of Operations Requirements 3.7 1 Operations 2.1.30 Ability to locate and operate components / including local 3.9 1 controls Subtotal 4 K/A TOPICS RO SRO Category IMP # IMP #

2. 2.2.30 Knowledge of RO duties in the control room during fuel 3.5 1 handling such as alarms from fuel handling area /

communications with fuel storage facility / system operated Equipment from the control room in support of fueling operations/ and supporting instrumentation Control 2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4 1 Subtotal 2 Page 1 of 2

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-3 (Tier 3)

PLANT-WIDE GENERIC RESPONSIBILITIES TIER 3 BWR - RO K/A TOPICS RO SRO Category IMP # IMP #

3. 2.3.11 Ability to control radiation release 2.7 1 2.3.2 Knowledge of facility ALARA Program 2.5 1 Radiation Subtotal 2 Control K/A TOPICS RO SRO Category IMP # IMP #

4. 2.4.32 Knowledge of operator response to loss of all annunciators 3.3 1 Emergency 2.4.48 Ability to interpret control room indications to verify the status 3.5 1 Procedures and operation of system / and understand how operator actions and directives affect plant and system conditions.

Plan Subtotal 2 Group point totals: 10/7 10 Page 2 of 2

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - SRO K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC PWR / 6 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 295016 Control Room Abandonment / 7 X AA2.01 - Ability to determine and/or interpret the 4.2 1 following a they apply to Control Room Abandonment: Reactor Power 55.43.5 295018 Partial or Complete Loss of CCW / 8 X 2.1.12 - Ability to apply technical specifications 4.0 1 for a system. 55.43.2 295019 Partial or Complete Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 295023 Refueling Accident / 8 X 2.4.1 - Knowledge of EOP entry conditions and 4.6 1 immediate action steps 55.43.5 295024 High Drywell Pressure / 5 Page 1 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water X 2.4.16 - Knowledge of EOP implementation 4.0 1 Temperature / 5 hierarchy and coordination with other support procedures 55.43.5 295027High Containment Temperature / 5 N/A MARK III CONTAINMENT ONLY 295028 High Drywell Temperature / 5 295030 Low Suppression Pool Water Level / 5 X 2.4.21 - Knowledge of the parameters and logic 4.3 1 used to assess the status of safety functions including: 4. Containment conditions 55.43.5 295031 Reactor Low Water Level / 2 X 2.4.38 - Ability to take actions called for in the 4.0 1 facility emergency plan / including supporting or acting as emergency director 55.43.5 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 X EA2.04 - Ability to determine and/or interpret the 4.5 1 following a they apply to HIGH OFF-SITE RELEASE RATE: Source of off-site release 55.43.5 600000 Plant Fire On Site / 8 Category Point Totals: 2 5 Group Point Totals: 20/7 7 Page 2 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - SRO K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295002 Loss of Main Condenser Vacuum / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X 2.1.14 - Knowledge of system status criteria 3.3 1 which require the notification of plant personnel 55.43.5 295010 High Drywell Pressure / 5 295011 High Containment Temperature / 5 N/A MARK III CONTAINMENT ONLY 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temperature /

5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 X AA2.01 - Ability to determine and/or interpret the 4.3 1 following a they apply to INCOMPLETE SCRAM:

Reactor power 55.43.5 295017 High Off-site Release Rate / 9 295020 Inadvertent Containment Isolation / 5 &

7 295022 Loss of CRD Pumps / 1 Page 3 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295029 High Suppression Pool Water Level / 5 295032 High Secondary Containment Area x EA2.02 - Ability to determine and/or interpret the 3.5 1 Temperature / 5 following a they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:

Equipment Operability 55.43.57 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High Containment Hydrogen Concentration / 5 Category Point Totals: 2 1 Group Point Totals: 7/3 3 Page 4 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP I BWR - SRO SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

203000 RHR/LPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI N/A AT CGS 207000 Iso (Emerg) Cond N/A AT CGS 209001 LPCS X 2.2.24 - Ability to analyze the 3.8 1 affect of maintenance activities on LCO status 55.43.2 209002 HPCS 211000 SLC 212000 RPS 215003 IRM 215004 SRM X A2.04 - Ability to predict the 3.7 1 impacts of the following on the SRM System; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Upscale and downscale trips 55.43.5 215005 APRM/LPRM Page 5 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

217000 RCIC 218000 ADS 223002 PCIS/ Nuclear Steam Supply Shutoff 239002 SRVs X 2.2.21 - Knowledge of pre and 3.5 1 post maintenance operability requirements 55.43.2 259002 Reactor Water Level Control 261000 SGTS 262001 AC Elec Dist X 2.2.8 - Knowledge of the 3.3 1 process for determining if the proposed change /test/or experiment involves an unreviewed safety question 55.43.3 262002 UPS (AC/DC) 263000 DC Elec Dist 264000 EDGs X 2.1.33 - Ability to recognize 4.0 1 indications for system operating parameters, which are entry-level conditions for technical specifications.

55.43.2 Page 6 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

300000 Instrument Air 400000 Component Cooling Water Category Point Totals: 1 4 Group Point Total: 26/5 5 Page 7 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP II BWR - SRO SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

201001 CRD Hydraulic 201002 RMCS 201003 CRD Mechanism 201004 RSCS 201005 RCIS N/A AT CGS 201006 RWM 202001 Recirculation 202002 Recirc Flow Control 204000 RWCU 214000 RPIS 215001 TIP 215002 RBM X 2.1.12 Ability to apply 4.0 1 technical specifications for a system. 55.43.2 216000 Nuclear Boiler Inst 219000 RHR/LPCI: Pool Cooling Mode 223001 Pri Containment and Aux Page 8 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Pool Spray Mode 233000 FPC 234000 Fuel Handling Eq.

239001 Main and Reheat Steam 239003 MSLC 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Generator/Aux 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas X A2.08 - Ability to predict the 2.7 1 impacts of the following on the OFF GAS System; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: AC Dist failures 55.43.5 Page 9 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary Containment 290002 Reactor Vessel Int X 2.1.7 - Ability to evaluate plant 4.4 1 performance and make operational judgments based on operation characteristics /

reactor behavior / and instrument interpretation 55.43.5 290003Control Room HVAC Category Point Totals: 2 1 Group Point Total: 12/3 3 Page 10 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-3 (Tier 3)

PLANT-WIDE GENERIC RESPONSIBILITIES TIER 3 BWR - SRO K/A TOPICS RO SRO Category IMP # IMP #

1. 2.1.10 2.1.10 - Knowledge of conditions and limitations in the facility 3.9 1 Conduct license 55.43.5 Subtotal 1 of Operations K/A TOPICS RO SRO Category IMP # IMP #

2. 2.2.25 Knowledge of bases in technical specifications for limiting 3.7 1 conditions for operations and safety limits 55.43.2 2.2.26 Knowledge of refuel administrative requirements 55.43.5 3.7 1 Equipment Subtotal 2 Control Page 1 of 2

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: JUNE 2005 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-3 (Tier 3)

PLANT-WIDE GENERIC RESPONSIBILITIES TIER 3 BWR - SRO K/A TOPICS RO SRO Category IMP # IMP #

3. 2.3.3 Knowledge of SRO responsibilities for auxiliary system that are 2.9 1 outside the control room (e.g. / waste disposal and handling systems) 55.43.4 Radiation 2.3.9 Knowledge of the process for performing a containment purge 3.4 1 55.43.4 Control Subtotal 2 K/A TOPICS RO SRO Category IMP # IMP #

4. 2.4.7 Knowledge of how the event based emergency/abnormal 3.8 1 Emergency operating procedures are used in conjunction with the symptom-based EOPs 55.43.5 Procedures 2.4.27 Knowledge of fire in the plant procedure 55.43.5 3.5 1 Plan Subtotal 2 Group point totals: 10/7 7 Page 2 of 2

ES-401 Record of Rejected K/As Form ES-401-4 Columbia Generating Station JUNE 2005 SRO K/A Rejections Tier / Randomly Selected Reason for Rejection Group K/A T1, GP 1 295028 2.3.7 Generic K/A is not a 55.43 K/A.

295025EA2.02 No significant question could be developed.

295025EA2.05 Un secure email sent - question replaced.

T2, GP 1 209001 2.2.3 Generic K/A does not make sense with the system K/A.

239002 2.1.22 Generic K/A does not make sense with the system K/A.

239002 2.4.4 Generic K/A is not 55.43 related.

239002 2.1.9 Generic K/A is not 55.43 related.

262001 2.4.12 Generic K/A is not 55.43 related.

262001 2.2.1 Generic K/A is not 55.43 related.

295031 2.4.17 Generic K/A is not 55.43 related.

264000 2.2.3 Generic K/A does not make sense with the system K/A.

T2, GP2 290002 2.3.9 Generic K/A does not make sense with the system K/A.

290002 2.1.2 Generic K/A is not 55.43 related.

T3 2.4.20 Generic K/A is not 55.43 related.

2.1.31 Generic K/A is not 55.43 related.

2.1.2 Generic K/A is not 55.43 related.

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ES-401 Record of Rejected K/As Form ES-401-4 Columbia Generating Station JUNE 2005 RO K/A Rejections Tier / Randomly Selected Reason for Rejection Group K/A T1, GP2 2950014AA1.01 Original question similar to Q#4 on SRO exam. No significantly different question could be developed.

T2, GP1 261000 2.1.4 Generic K/A does not make sense with the system K/A.

215005A2.06 Skyscraper model was not correct when completed. This K/A was randomly selected and deleted for balance of the outline. The replacement K/A was then randomly selected.

T2, GP2 233000K2.02 Tested same knowledge as 230000K2.02 which had already been selected.

219000K3.01 No significant question could be developed.

216000K5.09 Un secure email sent - question replaced.

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