ML070740449

Generation Station - 11-2006 - Final Outlines

ML070740449
Person / Time
Site:	Columbia
Issue date:	11/27/2006
From:	Nease R Operations Branch IV
To:	Parrish J Energy Northwest
References
50-397/06-301, ES-301, ES-301-1 50-397/06-301
Download: ML070740449 (40)

Text

ES-301 ADMINISTRATIVE TOPICS OUTLINE FORM ES-301-1 Facility: Columbia Generating Station Date of examination: November 2006 Examination Level (circle one): RO / SRO Operating test number:

Administrative Topic Type Code* Describe activity to be performed (see Note)

D SRO is given a turnover sheet that states a RX S/U is in progress and then parameters that indicate the reactor is critical. He is cued to determine his next Conduct of Operations action. To successfully complete the JPM he has to realize the Reactor is Critical prior to the ECP and take actions per PPM 3.1.2 which states to: stop control rod withdrawal, the CRS should direct the CRO to drive control rods in the reverse order until all rods are fully inserted; POC approval is required to proceed with further rod withdrawal; Consider the applicability of T.S. 3.1.2. He will fill out an attachment indicating what his next action will be and the basis for that action.

N SRO is cued that during an inspection of the Active Fire System in the Control Room, the 18 Halon systems storage tanks were found to be 85% of full charge Conduct of Operations pressure. He is asked to determine if any compensatory measures are required and if they are, what are they. He will refer to PPM 1.3.10B and determine operability. Per PPM 1.3.10B he is to issue an FPSI permit for the inoperable system. Once this is identified he is handed a blank FPSI permit to fill out.

N The SRO is given a turnover sheet that indicates a Division 1 instrument is OOS.

Equipment Control He is then handed a taggout for a Div 2 piece of equipment. The taggout erroneously pulls a fuse for a non-related Div 2 component that is the opposite division of the Div 1 component already OOS. If approved and this fuse is removed, a full scram would occur. He has to determine if he would sign taggout or not and explain why/why not.

D, S The SRO is given data and is required to enter the data into the QEDPS and print out the form. Then, based on the results of the QEDPS, he is to classify the Radiation Control event.

N, S After Scenario #2, Classify the event and fill out a CNF. The scenario should be classified as a Site Area Emergency per EAL 2.2.S.1 (ATWS with power GT Emergency Plan 5%).

Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria (C)ontrol room (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

(S)imulator Page 1

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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. 2.1.22 Ability to determine the Mode of Operation 2.8 1 Conduct 2.1.7 Ability to evaluate plant performance and make operational 3.7 1 of judgments based on operating characteristics, reactor behavior, and instrument interpretations Operations 2.1.31 Ability to locate control room switches, controls and indications 4.2 1 and to determine that they are correctly reflecting the desired plant lineup Subtotal 3 Page 1 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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 #

2. 2.2.26 Knowledge of refueling administrative requirements 2.5 1 Equipment 2.2.28 Knowledge of new and spent fuel movement procedures 2.6 1 2.2.12 Knowledge of surveillance procedures 3.0 1 Control Subtotal 3 Page 2 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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. 2.3.4 Knowledge of the radiation exposure limits and contamination 2.5 1 Radiation control / including permissible levels in excess of those authorized 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control 2.6 1 Control requirements Subtotal 2 Page 3 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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 #

4. 2.4.11 Knowledge of abnormal condition procedures 3.4 1 Emergency 2.4.29 Knowledge of the Emergency Plan 2.6 1 Procedures Subtotal 2 Plan Group point totals: 10/7 10 Page 4 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - RO Target: Actual:

K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295001 Partial or Complete Loss of Forced X AA2.06 Ability to determine and/or interpret the 3.2 1 Core Flow Circulation / 1 & 4 following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Nuclear Boiler Instrumentation 295003 Partial or Complete Loss of AC / 6 X AA1.03 Ability to operate and/or monitor the 4.4 1 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Systems necessary to assure safe plant shutdown 295004 Partial or Total Loss of DC PWR / 6 X AA2.04 Ability to determine and/or interpret the 3.2 1 following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: System lineups 295005 Main Turbine Generator Trip / 3 X AK1.01 Knowledge of the operational 4.0 1 implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP:

Pressure effects on reactor power 295005 Main Turbine Generator Trip / 3 X AK2.03 Knowledge of the interrelations between 3.2 1 MAIN TURBINE GENERATOR TRIP and the following: Recirculation system 295006 SCRAM / 1 X AK3.04 Knowledge of the reasons for the 3.1 1 following responses as they apply to SCRAM:

Reactor water level setpoint Setdown: Plant specific Page 1 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 295016 Control Room Abandonment / 7 X AA1.06 Ability to operate and/or monitor the 4.0 1 following as they apply to CONTROL ROOM ABANDONMENT: Reactor water level 295018 Partial or Complete Loss of CCW / 8 X 2.1.28 Knowledge of the purpose and function of 3.3 1 major system components and controls.

295019 Partial or Complete Loss of Inst. Air / 8 X AA2.02 (AK2.03 RFW) Ability to determine 3.6 1 and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Status of safety related instrument air system loads (see AK2.1- AK2-19) 295021 Loss of Shutdown Cooling / 4 X AK1.03 Knowledge of the operational 3.9 1 implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING:

Adequate core cooling 295023 Refueling Accident / 8 X AA1.04 Ability to operate and/or monitor the 3.4 1 following as they apply to REFUELING ACCIDENTS: Radiation Monitoring equipment 295024 High Drywell Pressure / 5 X EK2.12 Knowledge of the interrelations between 3.5 1 HIGH DRYWELL PRESSURE and the following:

Suppression pool cooling 295025 High Reactor Pressure / 3 X EK2.04 Knowledge of the interrelations between 3.9 1 HIGH REACTOR PRESSURE and the following:

ARI/RPT/ATWS: Plant specific 295026 Suppression Pool High Water X EK3.01 Knowledge of the reasons for the 3.8 1 Temperature / 5 following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Emergency/normal depressurization 295027High Containment Temperature / 5 N/A MARK III CONTAINMENT ONLY Page 2 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 295028 High Drywell Temperature / 5 X EK2.03 Knowledge of the interrelations between 3.6 1 HIGH DRYWELL TEMPERATURE and the following: Reactor Water level indication 295030 Low Suppression Pool Water Level / 5 X EK1.01 Knowledge of the operational 4.1 1 implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: Steam condensation 295031 Reactor Low Water Level / 2 X 2.4.24 Knowledge of loss of cooling water 3.3 1 procedures 295037 SCRAM Condition Present and Power X EA1.04 Ability to operate and/or monitor the 4.5 1 Above APRM Downscale or Unknown / 1 following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC 295038 High Off-site Release Rate / 9 X EA2.04 Ability to determine and/or interpret the 4.1 1 following as they apply to HIGH OFF-SITE RELEASE RATE: Source of off-site release 600000 Plant Fire On Site / 8 X AK1.02 Knowledge of the operation applications 2.9 1 of the following concepts as they apply to Plant Fire On Site: Fire fighting Category Point Totals: 4 4 2 4 4 2 Group Point Totals: 20/7 Page 3 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - RO Target: Actual:

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 AK3.04 Knowledge of the reasons for the following 4.0 1 responses as they apply to HIGH REACTOR PRESSURE: Safety/relief valve operation: Plant specific 295008 High Reactor Water Level / 2 X AA2.05 Ability to determine and/or interpret the 2.9 1 followiing as they apply to HIGH REACTOR WATER LEVEL: Swell 295009 Low Reactor Water Level / 2 X 2.1.32 Ability to explain and apply system limits 3.4 1 and precautions 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 X AA1.02 Ability to operate and/or monitor the 3.6 1 following as they apply to HIGH SUPPRESSION POOL TEMPERATURE: Systems that add heat to the suppression pool 295014 Inadvertent Reactivity Addition / 1 X AK2.06 Knowledge of the interrelationships 3.5 1 between INADVERTENT REACTIVITY ADDITION and the following: Moderator Temperature 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 Page 4 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 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 Ventilation High X EA1.02 Ability to operate and/or monitor the 3.9 1 Radiation / 9 following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: Process Radiation monitoring system 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area X EA2.03 Ability to determine and/or interpret the 3.4 1 Water Level / 5 following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Cause of the high water level 500000 High Containment Hydrogen Concentration / 5 Category Point Totals: 0 1 1 2 2 1 Group Point Totals: 7/3 Page 5 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP I BWR - RO/SRO Target: Actual:

SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

203000 RHR/LPCI: Injection X K3.03 Knowledge of the effect 4.2 1 Mode that a loss or malfunction of the RHR/LPCI: INJECTION MODE will have on following:

Automatic depressurization logic 205000 Shutdown Cooling X A1.05 Ability to predict and/or 3.4 1 monitor changes in parameters associated with operating the SHUTDOWN COOLING SYSTEM/MODE controls including: Reactor water level 206000 HPCI N/A AT CGS 207000 Iso (Emerg) Cond N/A AT CGS 209001 LPCS X K1.09 Knowledge of the 3.2 1 physical connections and/or cause- effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the following: Nuclear boiler instrumentation Page 6 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 209002 HPCS X A2.12 Ability to (a) predict the 3.3 1 impacts of the following on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS);

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High suppression pool level 209002 HPCS X A1.03 Ability to predict and/or 3.7 1 monitor changes in parameters associated with operating the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) controls including: Reactor water level 211000 SLC X A4.06 Ability to manually 3.9 1 operate and/or monitor in the control room: RWCU system isolation 211000 SLC X A1.04 Ability to predict and/or 3.6 1 monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: Valve operations Page 7 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 212000 RPS X A2.19 Ability to (a) predict the 3.8 1 impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Partial system activation (Half-SCRAM) 215003 IRM X A4.03 Ability to manually 3.6 1 operate and/or monitor in the control room: IRM range switches 215004 SRM X K1.03 Knowledge of the 3.0 1 physical connections and/or cause- effect relationships between SOURCE RANGE MONITOR (SRM) SYSTEM and the following: Rod control and information system: Plant specific 215005 APRM/LPRM X K2.02 Knowledge of electrical 2.6 1 power supplies to the following: APRM channels 217000 RCIC X K4.07 Knowledge of 3.6 1 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) design feature(s) and/or interlocks which provide for the following:

Alternate supplies of water Page 8 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 217000 RCIC X A3.01 Ability to monitor 3.5 1 automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including:

Valve operation 218000 ADS X K6.04 Knowledge of the effect 3.6 1 that a loss or malfunction of the following will have on the AUTOMATIC DEPRESSURIZATION SYSTEM: Air supply to ADS valves: Plant specific 223002 PCIS/ Nuclear X A2.06 Ability to (a) predict the 3.0 1 Steam Supply Shutoff impacts of the following on the PCIS/NSSSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Containment instrumentation failures 239002 SRVs X K4.05 Knowledge of 3.6 1 RELIEF/SAFETY VALVES design feature(s) and/or interlocks which provide for the following: Allows for SRV operation from more than one location: Plant specific Page 9 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 259002 Reactor Water Level X K5.03 Knowledge of the 3.2 1 Control operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM:

Water level measurement 261000 SGTS X K3.02 Knowledge of the effect 3.6 1 that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following: Off-site release rate 261000 SGTS X K6.01 Knowledge of the effect 2.9 1 that a loss or malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM: A. C. Electrical distribution 262001 AC Elec Dist X K5.02 Knowledge of the 2.6 1 operational implications of the following concepts as they apply to A. C. ELECTRICAL DISTRIBUTION: Breaker control 262002 UPS (AC/DC) X K4.01 Knowledge of 3.1 1 UNINTERRUPTIBLE POWER SUPPLY (A. C./D. C.) design feature(s) and/or interlocks which provide for the following:

Transfer from preferred power to alternate power supplies Page 10 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 263000 DC Elec Dist X A1.01 Ability to predict and / or 2.5 1 monitor changes in parameters associated with operating the D.C.

ELECTRICAL DISTRIBUTION controls including: Battery charging/discharging rate 264000 EDGs X A3.06 Ability to monitor 3.1 1 automatic operations of the EMERGENCY GENERATORS (DIESEL/JET) including: Cooling water system operation 264000 EDGs X K3.01 Knowledge of the effect 4.2 1 that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following:

Emergency core cooling systems 300000 Instrument Air X K1.04 Knowledge of the 2.8 1 connections and/or cause effect relationships between INSTRUMENT AIR SYSTEM and the following: Cooling water to compressor 400000 Component Cooling X 2.1.24 Ability to obtain and 2.8 1 Water interpret station electrical and mechanical drawings Category Point Totals: 3 1 3 3 2 2 4 3 2 2 1 Group Point Total: 26/5 Page 11 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP II BWR - RO Target: Actual:

SYSTEM #/NAME K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A TOPICS IMP #

201001 CRD Hydraulic X A3.10 Ability to monitor 3.0 1 automatic operations of the CONTROL ROD DRIVE HYDRAULIC SYSTEM including: Lights and Alarms 201002 RMCS X K4.04 Knowledge of 3.3 1 REACTOR MANUAL CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

Single notch rod withdrawal and insertion 201003 CRD Mechanism 201004 RSCS 201005 RCIS N/A AT CGS 201006 RWM 202001 Recirculation X K2.01 Knowledge of electrical 3.2 1 power supplies to the following: Recirculation Pumps Plant specific Page 12 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 202002 Recirc Flow Control X A2.01 Ability to (a) predict the 3.4 1 impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation Pump Trip 204000 RWCU 214000 RPIS 215001 TIP 215002 RBM 216000 Nuclear Boiler Inst X K5.07 Knowledge of the 3.6 1 operational implications of the following concepts as they apply to NUCLEAR BOILER INSTRUMENTATION:

Elevated temperature effects on level indication 219000 RHR/LPCI: Pool Cooling Mode 223001 Pri Containment and Aux 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Pool Spray Mode Page 13 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 233000 FPC/Cleanup X 2.1.30 Ability to locate and 3.9 1 operate components /

including local controls 234000 Fuel Handling Equip 239001 Main and Reheat X A2.08 Ability to (a) predict the 3.6 1 Steam impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low condenser vacuum 239003 MSLC 241000 Reactor/Turbine X K1.28 Knowledge of the 3.2 1 Pressure Regulator physical connections and/or cause- effect relationships between REACTOR/TURBINE PRESSURE REGULATING SYSTEM and the following:

Reactor startup 245000 Main Turbine X K3.03 Knowledge of the effect 3.9 1 Generator/Aux that a loss or malfunction of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on following: reactor power 256000 Reactor Condensate Page 14 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 259001 Reactor Feedwater X K6.06 Knowledge of the effect 2.7 1 that a loss or malfunction of the following will have on the REACTOR FEEDWATER SYSTEM: Plant service water 268000 Radwaste 271000 Offgas X A1.15 Ability to predict and/or 2.7 1 monitor changes in parameters associated with operating the OFFGAS SYSTEM controls including:

Steam supply pressures 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary Containment 290002 Reactor Vessel Int 290003Control Room HVAC X K1.03 Knowledge of the 2.8 1 physical connections and/or cause- effect relationships between CONTROL ROOM HVAC and the following:

Remote air intakes: Plant Specific Category Point Totals: 2 1 1 1 1 1 1 2 1 0 1 Group Point Total: 12/3 Page 15 of 15

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 Facility: Columbia Generating Station Date of Exam: November 2006 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 4 4 2 4 4 2 20 5 2 7 Emergency and 2 0 1 1 N/A 2 2 N/A 1 7 2 1 3 Abnormal Plant Evolutions Tier Totals 4 5 3 6 6 3 27 7 3 10

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

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

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 1 of 1

ES-401 Record of Rejected K/As Form ES-401- 4 Tier/Group Randomly Selected Reason for Rejection K/A RO WRITTEN EXAM 1/1 295018; 2.1.15 KA has a value of less than a 2.5 for RO 1/1 295031; 2.4.28 KA has a value of less than a 2.5 for RO 1/2 295009; 2.1.26 KA has a value of less than a 2.5 for RO 2/2 259001; K2.01 CGS does not have Motor Driven RFW pumps 2/2 286000; A4.06 Randomly deleted this to select a K2 Category as sample had only 1 K2 question at the time. 202001 K2.01 was subsequently selected 1/1 295012 AA1.03 Could not write a discerning question. AA1.04 randomly selected in its place 1/2 295017 AK2.12 Duplicate knowledge to CGS Q#8/exam Q#59 (295038 EA2.04). 295014 AK2.06 randomly selected in its place 1/1 295018 2.1.20 KA 2.1.20 was deleted during NRC development of the question. Deleted KA documented on question template. KA 2.1.28 selected in its place 1/1 295030 EK1.03 KA EK1.03 was deleted during NRC development of the question. Deleted KA documented on question template. KA EK1.01 selected in its place 1/1 295023 AA1.03 Could not write a discerning question. AA1.04 randomly selected in its place 2/1 295002 K5.09 KA K5.09 was deleted during NRC development of the question. Deleted KA documented on question template. KA K5.03 selected in its place SRO WRITTEN EXAM 1/1 295006 AA2.06 Could not write an SRO only question. 295028 EA2.03 randomly selected in its place 1/2 295033 2.4.47 Could not write an SRO Only question. 295029 EA2.01 randomly selected in its place 2/1 215004 A2.02 Could not write an SRO only question. 212000 A2.03 randomly selected in its place

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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. 2.1.4 Knowledge of shift staffing requirements 3.4 1 Conduct Subtotal 1 of Operations Page 1 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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 #

2. 2.2.29 Knowledge of SRO fuel handling responsibilities 3.8 1 Equipment 2.2.11 Knowledge of the process for controlling temporary changes 3.4 1 Control Subtotal 2 Page 2 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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. 2.3.2 Knowledge of facility ALARA program 2.9 1 Radiation 2.3.6 Knowledge of the requirements for reviewing and approving 3.1 1 Control release permits Subtotal 2 Page 3 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: November 2006 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 #

4. 2.4.30 Knowledge of which events related to system operation/status 3.6 1 Emergency should be reported to outside agencies Procedures 2.4.22 Knowledge of the bases for prioritizing safety functions during 4.0 1 abnormal/emergency conditions Plan Subtotal 2 Group point totals: 10 / 7 7 Page 4 of 4

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - SRO Target: Actual:

K1 K2 K3 A1 A2 G K/A TOPICS IMP #

E / APE # - NAME / SAFETY FUNCTION 295001 Partial or Complete Loss of Forced Core X AA2.01 Ability to determine and/or interpret the 3.8 1 Flow Circulation / 1 & 4 following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Power/Flow map 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC PWR / 6 X AA2.04 Ability to determine and/or interpret the 3.3 1 following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: System lineups 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 295016 Control Room Abandonment / 7 295018 Partial or Complete Loss of CCW / 8 295019 Partial or Complete Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 X AA2.06 Ability to determine and/or interpret the 3.3 1 following as they apply to LOSS OF SHUTDOWN COOLING: Reactor pressure 295023 Refueling Accident / 8 295024 High Drywell Pressure / 5 X EA2.04 Ability to determine and/or interpret the 3.9 1 following as they apply to HIGH DRYWELL PRESSURE: Suppression Chamber pressure: Plant specific Page 1 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Temperature / 5 295027High Containment Temperature / 5 N/A MARK III CONTAINMENT ONLY 295028 High Drywell Temperature / 5 X EA2.03 Ability to determine and/or interpret the 3.9 1 following as they apply to HIGH DRYWELL TEMPERATURE: Reactor water level 295030 Low Suppression Pool Water Level / 5 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Power X 2.4.6 Knowledge of symptom based EOP mitigation 4.0 1 Above APRM Downscale or Unknown / 1 strategies 295038 High Off-site Release Rate / 9 X 2.4.44 Knowledge of emergency plan protective 4.0 1 action recommendations 600000 Plant Fire On Site / 8 Category Point Totals: 5 2 Group Point Totals: 20 / 7 7 Page 2 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - SRO Target: Actual:

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 295010 High Drywell Pressure / 5 295011 High Containment Temperature / 5 N/A MARK III CONTAINMENT ONLY 295012 High Drywell Temperature / 5 X 2.1.25 Ability to obtain and interpret station 3.1 1 reference materials such as graphs, monographs, and tables which contain performance data 295013 High Suppression Pool Temperature/ 5 295014 Inadvertent Reactivity Addition / 1 X AA2.05 Ability to determine and/or interpret the 4.6 1 following as they apply to INADVERTENT REACTIVITY ADDITION: Violation of Safety Limits 295015 Incomplete SCRAM / 1 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: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 295029 High Suppression Pool Water Level / 5 X EA2.01 Ability to determine and/or interpret the 3.9 1 following as they apply to HIGH SUPPRESSION POOL WATER LEVEL: Suppression Pool Water Level 295032 High Secondary Containment Area Temperature / 5 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: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP I BWR - SRO Target: Actual:

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 209002 HPCS X A2.11 Ability to (a) predict the 3.5 1 impacts of the following on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS);

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low Suppression pool level 211000 SLC Page 5 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 212000 RPS X A2.03 Ability to (a) predict the 3.5 impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Surveillance Testing 215003 IRM 215004 SRM 1 215005 APRM/LPRM 217000 RCIC X 2.1.20 Ability to execute 4.2 1 procedural steps 218000 ADS 223002 PCIS/ Nuclear Steam Supply Shutoff 239002 SRVs X A2.03 Ability to (a) predict the 4.2 1 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 relief valve 259002 Reactor Water Level Control Page 6 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 261000 SGTS 262001 AC Elec Dist X 2.1.11 Knowledge of less than 3.8 1 one hour technical specification action statements for systems: AC Distribution 262002 UPS (AC/DC) 263000 DC Elec Dist 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water Category Point Totals: 3 2 Group Point Total: 26 / 5 5 Page 7 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 PLANT SYSTEMS - TIER 2 GROUP II BWR - SRO Target: Actual:

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 X A2.04 Ability to (a) predict the 3.8 1 impacts of the following on the RECIRCULATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Multiple Recirculation Pump trips 202002 Recirc Flow Control 204000 RWCU 214000 RPIS 215001 TIP 215002 RBM X 2.1.12 Ability to apply technical 4.0 1 specification for a system Page 8 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 216000 Nuclear Boiler Inst 219000 RHR/LPCI: Pool Cooling Mode 223001 Pri Containment and Aux 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 X 2.1.34 Ability to maintain 2.9 1 primary and secondary plant chemistry within allowable limits 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring Page 9 of 10

Facility: Columbia Generating Station Knowledge and Ability Record Form Exam Date: NOVEMBER 2006 ref: NUREG - 1021 rev 9 BWR RO/SRO EXAM OUTLINE ES-401-1 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary Containment 290002 Reactor Vessel Int 290003Control Room HVAC Category Point Totals: 1 2 Group Point Total: 12 / 3 3 Page 10 of 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Columbia Generating Station Date of examination: November 2006 Exam level (circle one): RO / SRO-I / SRO-U Operating Test No:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U JPM # System / JPM Title Type Code* Safety Function

1. 1 Remove FW Heater 1A, 1B, and 1C From Service N, S 2 R / SRO-I

1. 2 Restore Power to RPS-A From Alternate Power Supply N, S 7 (ESF)

R / SRO-I

1. 3 Transfer SL-21 From SL-11 to SM-2 N, S 6 R / SRO-I / SRO-U

1. 4 Manually Initiate Containment Isolation - TIP fails to A, D, L, E, S 5 Isolate (ESF)

R

1. 5 Lower Reactor Pressure using DEH L, N, S 3 R / SRO-I / SRO-U

1. 6 Manually Initiate RCIC, RCIC-V-46 Fails to Auto Open A, D, S 4 R / SRO-I

1. 7 RB Ventilation Fails; Start Standby Gas Treatment (ESF) A, N, S 9 R / SRO-I

1. 8 Start HPCS Service Water Pump after it fails to Auto A, N, S 8 start R / SRO-I / SRO-U In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

1. 9 Insert Control Rods by Venting Scram Air Header E, D, R 1 R / SRO-I / SRO-U Page 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Columbia Generating Station Date of examination: November 2006 Exam level (circle one): RO / SRO-I / SRO-U Operating Test No:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U JPM # System / JPM Title Type Code* Safety Function

1. 10 Start DG-2 During Control Room Evacuation (ESF) A, E, M, R 6 R / SRO-I

1. 11 Respond to CR HVAC High Rad Levels in One Intake - A, E, D, R 9 Pull Fuse (ESF)

R / SRO-I / SRO-U All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and safety functions may overlap those tested in the control room.

Page 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)control room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (L)ow-Power >1/>1/>1 (N)ew or (M)odified from bank including 1(A) >2/>2/>2 (P)revious 2 exams < 3 / < 3 / < 2 (randomly selected)

(R)CA >1/>1/>1 (S)imulator Actual Count:

Alternate Path = 6 / 4 / 2 Control Room Direct From Bank = 4 / 3 / 2 Emergency or Abnormal In-Plant = 3 / 3 / 2 Low Power = 2/ 1 / 1 New or Modified = 6 / 6 / 3 Previous 2 exams = 0 / 0 / 0 RCA = 3 / 3 / 2 Simulator Page 3

ES-301 ADMINISTRATIVE TOPICS OUTLINE FORM ES-301-1 Facility: Columbia Generating Station Date of examination: November 2006 Examination Level (circle one): RO / SRO Operating test number:

Administrative Topic Type Code* Describe activity to be performed (see Note)

D The RO is given a turnover sheet that states a RX S/U is in progress and then parameters that indicate the reactor is critical. He has to Conduct of Operations realize the Reactor is Critical or will be critical prior to the ECP and take actions per PPM 3.1.2 which states to: stop control rod withdrawal and notify the CRS. He will fill out an attachment indicating what his next action will be and the basis for that action.

M The RO is given that a startup is in progress and plant data showing current APRM indicated Power and Bypass Valve Positions and told to Conduct of Operations complete step Q31 of PPM 3.1.2 and inform the CRS of the results.

When done he will check the block on the attachment indicating APRM readings are GT power readings extrapolated from BPV position.

N The RO is given a section of OSP-INST-H101 that has 3 out of spec reading entered and not identified as out of spec readings. Candidate is Equipment Control told to verify readings and to submit the surveillance to the CRS for review. He should find the 3 out of spec readings and circle them.

N The RO is given a tagout that requires entry into a contaminated area of the plant to hang. His directions are to sign onto a specific RWP to Radiation Control perform the task. He is to determine if the tagout can be hung. The tagout has no discrepancies. When the RWP is reviewed it is discovered that the RWP does not allow entry into contaminated zones of the plant. The candidate will indicate that the task can not be performed.

Emergency Plan Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria (C)ontrol room (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

(S)imulator Page 2