NG-09-0460, DAEC 2009 Revised Written Exam Outline (Es 401-1,3,4)
| ML100351189 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 09/21/2009 |
| From: | NextEra Energy Duane Arnold |
| To: | NRC/RGN-III |
| References | |
| NG-09-0460, NUREG-1021 | |
| Download: ML100351189 (14) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility: DAEC Date of Exam: September 2009 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4
- 1 3 4 2 4 4 3 20 5 2 7 1.
Emergency
& 2 1 1 2 1 1 1 7 2 1 3 Plant Evolutions Tier 4 5 4 5 5 4 27 7 3 10 Totals 1 3 2 2 2 2 2 3 2 3 3 2 26 2 3 5 2.
Plant 2 1 1 1 1 1 1 2 1 1 1 1 12 0 2 1 3 Systems Tier 4 3 3 3 3 3 5 3 4 4 3 38 4 4 8 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowledge & Abilities 10 7 Categories 3 3 2 2 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply).
Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A Catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10CFR55.43 ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
EA2.01 - Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to X 4.2 76 Water Level / 5 LOW SUPPRESSION POOL WATER LEVEL : Suppression pool level AA2.04 - Ability to determine and/or 295004 Partial or Total Loss of interpret the following as they apply to X 3.3 77 DC Pwr / 6 PARTIAL OR COMPLETE LOSS OF D.C. POWER : System lineups EA2.03 - Ability to determine and/or 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND X 4.4 78 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown / 1 DOWNSCALE OR UNKNOWN: SBLC Tank Level.
2.4.35 - Emergency Procedures / Plan:
295031 Reactor Low Water Knowledge of local auxiliary operator X 4.0 79 Level / 2 tasks during emergency and the resultant operational effects.
AA2.02 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to X 2.7 80 Trip / 3 MAIN TURBINE GENERATOR TRIP Turbine vibration 2.1.19 - Conduct of Operations: Ability 295025 High Reactor Pressure /
X to use plant computers to evaluate 3.8 81 3
system or component status.
AA2.08 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and X GENERATOR VOLTAGE AND 4.4 82 Electric Grid Disturbances / 6 ELECTRIC GRID DISTURBANCES:
Criteria to trip the turbine or reactor AK1.05 - Knowledge of the operational implications of the following concepts as 295004 Partial or Total Loss of X they apply to PARTIAL OR COMPLETE 3.3 39 DC Pwr / 6 LOSS OF D.C. POWER : Loss of breaker protection EK1.01 Knowledge of the operational implications of the following concepts as 295026 Suppression Pool High X they apply to SUPPRESSION POOL 3.0 40 Water Temp. / 5 HIGH WATER TEMPERATURE : Pump NPSH AK1.03 - Knowledge of the operational 295001 Partial or Complete implications of the following concepts as Loss of Forced Core Flow X they apply to PARTIAL OR COMPLETE 3.6 41 Circulation / 1 & 4 LOSS OF FORCED CORE FLOW CIRCULATION : Thermal limits AK2.03 - Knowledge of the 295005 Main Turbine interrelations between MAIN TURBINE X 3.2 42 Generator Trip / 3 GENERATOR TRIP and the following:
Recirculation system AK2.01 - Knowledge of the interrelations between PLANT FIRE 600000 Plant Fire On-site / 8 X 2.6 43 ON SITE and the following: Sensors/
detectors, valves AK2.01 - Knowledge of the 295006 SCRAM / 1 X interrelations between SCRAM and the 4.3 44 following: RPS EK2.08 - Knowledge of the interrelationships between HIGH 295025 High Reactor Pressure X REACTOR PRESSURE and the 3.7 45
/3 following: Reactor/turbine pressure regulating system ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
EK3.03 - Knowledge of the reasons for 295028 High Drywell the following responses as they apply to X 3.6 46 Temperature / 5 HIGH DRYWELL TEMPERATURE :
Drywell spray operation: Mark-I&II EK3.08 - Knowledge of the reasons for 295024 High Drywell Pressure / the following responses as they apply to X 3.7 47 5 HIGH DRYWELL PRESSURE :
Containment spray: Plant-Specific EA1.03 - Ability to operate and/or 295031 Reactor Low Water monitor the following as they apply to X 4.4 48 Level / 2 REACTOR LOW WATER LEVEL : Low pressure core spray EA1.05 - Ability to operate and/or 295030 Low Suppression Pool monitor the following as they apply to X 3.5 49 Water Level / 5 LOW SUPPRESSION POOL WATER LEVEL: HPCI AA1.03 - Ability to operate and/or monitor the following as they apply to 295018 Partial or Total Loss of PARTIAL OR COMPLETE LOSS OF X 3.3 50 CCW / 8 COMPONENT COOLING WATER :
Affected systems so as to isolate damaged portions AA2.04 - Ability to determine and/or 295003 Partial or Complete interpret the following as they apply to X 3.5 51 Loss of AC / 6 PARTIAL OR COMPLETE LOSS OF A.C. POWER : System lineups EA2.05 - Ability to determine and/or 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND X 4.2 52 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown / 1 DOWNSCALE OR UNKNOWN : Control rod position AA2.01 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and GENERATOR VOLTAGE AND X 3.5 53 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:
Operating point on the generator capability curve.
2.1.23 - Conduct of Operations: Ability 295038 High Off-site Release to perform specific system and X 4.3 54 Rate / 9 integrated plant procedures during all modes of plant operation.
AA1.06 - Ability to operate and/or 295016 Control Room monitor the following as they apply to X 4.0 55 Abandonment / 7 CONTROL ROOM ABANDONMENT:
Reactor Water Level 2.1.20 - Conduct of Operations: Ability 295019 Partial or Total Loss of X to interpret and execute procedure 4.6 56 Inst. Air / 8 steps.
2.1.25 - Conduct of Operations: Ability 295021 Loss of Shutdown X to interpret reference materials, such as 3.9 57 Cooling / 4 graphs, curves, tables, etc.
EA2.04 - Ability to determine and/or 295025 High Reactor Pressure interpret the following as they apply to X 3.9 58
/3 HIGH REACTOR PRESSURE:
Suppression pool level K/A Category Totals: 3 4 2 4 4/5 3/2 Group Point Total: 20/7 ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
AA2.01 - Ability to determine and / or 295015 Incomplete Scram / 1 X interpret the following as they apply to 4.3 83 INCOMPLETE SCRAM: Reactor power 2.4.41 - Emergency Procedures / Plan:
295017 High Off-site Release X Knowledge of the emergency action 4.6 84 Rate / 9 level thresholds and classifications.
EA2.03 - Ability to determine and/or 295033 High Secondary interpret the following as they apply to Containment Area Radiation X HIGH SECONDARY CONTAINMENT 4.2 85 Levels / 9 AREA RADIATION LEVELS: Cause of high area radiation AK1.01 - Knowledge of the operational implications of the following concepts 295022 Loss of CRD Pumps /
X as they apply to LOSS OF CRD 3.3 59 1
PUMPS: Reactor pressure vs. rod insertion capability AK2.02 - Knowledge of the 295012 High Drywell interrelations between HIGH DRYWELL 3.6 X 60 Temperature / 5 TEMPERATURE and the following:
Drywell cooling AK3.01 - Knowledge of the reasons for 295009 Low Reactor Water the following responses as they apply to X 3.2 61 Level / 2 LOW REACTOR WATER LEVEL:
Recirculation pump runback 295007 High Reactor Pressure AA1.02 - Ability to operate and/or
/3 X monitor the following as they apply to 3.5 62 HIGH REACTOR PRESSURE : HPCI AA2.01 - Ability to determine and/or 295014 Inadvertent Reactivity interpret the following as they apply to X 4.1 63 Addition / 1 INADVERTENT REACTIVITY ADDITION : Reactor power 2.4.47 - Emergency Procedures / Plan:
Ability to diagnose and recognize trends 295002 Loss of Main X in an accurate and timely manner 4.2 64 Condenser Vac / 3 utilizing the appropriate control room reference material.
EK3.03 - Knowledge of the reasons for 295032 High Secondary the following responses as they apply to Containment Area Temperature X HIGH SECONDARY CONTAINMENT 3.8 65
/5 AREA TEMPERATURE : Isolating affected systems K/A Category Totals: 1 1 2 1 1/2 1/1 Group Point Total: 7/3 ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#
1 2 3 4 5 6 1 3 4 .
A2.05 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on those predictions, use 209001 LPCS X 3.6 86 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Core Spray line break A2.03 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM 223002 PCIS/Nuclear Steam SUPPLY SHUT-OFF ; and (b)
X 3.3 87 Supply Shutoff based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System Logic failures 2.2.36 - Equipment Control:
Ability to analyze the effect of maintenance activities, such as 215003 IRM X 4.2 88 degraded power sources, on the status of limiting conditions for operations.
2.1.23 - Conduct of Operations:
Ability to perform specific system 239002 SRVs X and integrated plant procedures 4.4 89 during all modes of plant operation.
2.2.25 - Equipment Control:
Knowledge of bases in technical 211000 SLC X specifications for limiting 4.2 90 conditions for operations and safety limits.
K1.03 - Knowledge of the physical connections and/or cause- effect relationships between SHUTDOWN 205000 Shutdown Cooling X 3.4 1 COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: Recirculation loop temperature K1.01 - Knowledge of the physical connections and/or 259002 Reactor Water cause- effect relationships X 3.8 2 Level Control between REACTOR WATER LEVEL CONTROL SYSTEM and the following: RPS K2.01 - Knowledge of electrical 218000 ADS X power supplies to the following: 3.1 3 ADS logic K2.02 - Knowledge of electrical 215005 APRM / LPRM X power supplies to the following: 2.6 4 APRM channels ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#
1 2 3 4 5 6 1 3 4 .
K3.01 - Knowledge of the effect that a loss or malfunction of the 400000 Component Cooling X CCWS will have on the 2.9 5 Water following: Loads cooled by CCWS K3.01 - Knowledge of the effect that a loss or malfunction of the 239002 SRVs X RELIEF/SAFETY VALVES will 3.9 6 have on following: Reactor pressure control K4.05 - Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) 264000 EDGs X 3.2 7 and/or interlocks which provide for the following: Load shedding and sequencing K4.02 - Knowledge of SOURCE RANGE MONITOR (SRM) 215004 Source Range SYSTEM design feature(s)
X 3.4 8 Monitor and/or interlocks which provide for the following: Reactor SCRAM signals K5.06 - Knowledge of the operational implications of the following concepts as they apply 206000 HPCI X to HIGH PRESSURE COOLANT 2.6 9 INJECTION SYSTEM : Turbine speed measurement: BWR-2,3,4 K5.01 - Knowledge of the operational implications of the following concepts as they apply 215003 IRM X 2.6 10 to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :
Detector operation K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the 262002 UPS (AC/DC) X 2.8 11 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) : D.C.
electrical power K6.03 - Knowledge of the effect that a loss or malfunction of the 211000 SLC X following will have on the 3.2 12 STANDBY LIQUID CONTROL SYSTEM : A.C. power A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 217000 RCIC X 3.7 13 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: RCIC flow A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 263000 DC Electrical X D.C. ELECTRICAL 2.5 14 Distribution DISTRIBUTION controls including: Battery charging/discharging rate ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#
1 2 3 4 5 6 1 3 4 .
A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those 300000 Instrument Air X predictions, use procedures to 2.9 15 correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions A2.08 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) 209001 LPCS X based on those predictions, use 3.1 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings A3.03 - Ability to monitor automatic operations of the 261000 SGTS X STANDBY GAS TREATMENT 3.0 17 SYSTEM including: Valve operation A3.02 - Ability to monitor automatic operations of the PRIMARY CONTAINMENT 223002 PCIS/Nuclear X ISOLATION 3.5 18 Steam Supply Shutoff SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF including:
Valve closures A4.04 - Ability to manually operate and/or monitor in the 212000 RPS X control room: Bypass SCRAM 3.9 19 instrument volume high level SCRAM signal A4.04 - Ability to manually operate and/or monitor in the 262001 AC Electrical X control room: Synchronizing and 3.6 20 Distribution paralleling of different A.C.
supplies 2.2.40 - Equipment Control::
203000 RHR/LPCI: Injection X Ability to apply Technical 3.4 21 Mode Specifications for a system.
2.4.46 - Emergency Procedures
/ Plan: Ability to verify that the 215005 APRM / LPRM X 4.2 22 alarms are consistent with the plant conditions.
K1.06- Knowledge of the physical connections and/or cause effect relationships 261000 SGTS X between STANDBY GAS 3.0 23 TREATMENT SYSTEM and the following: High pressure coolant injection system; Plant-specific ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#
1 2 3 4 5 6 1 3 4 .
A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 218000 ADS X AUTOMATIC 3.4 24 DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures A4.03 - Ability to manually X
217000 RCIC operate and/or monitor in the 3.4 25 control room: System valves A3.02 - Ability to monitor automatic operations of the SHUTDOWN COOLING 205000 Shutdown Cooling X 3.2 26 SYSTEM (RHR SHUTDOWN COOLING MODE) including:
Pump trips K/A Category Totals: 3 2 2 2 2 2 3 2/2 3 3 2/3 Group Point Total: 26/5 ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # / Name A2 G Imp.
1 2 3 4 5 6 1 3 4 #
A2.08 - Ability to predict and/or monitor changes in parameters associated with operating the 201003 Control Rod and X CONTROL ROD AND DRIVE 3.7 91 Drive Mechanism MECHANISM controls including:
Low HCU accumulator pressure/high level A2.11 - Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) 216000 Nuclear Boiler based on those predictions, use X 3.3 92 Instrumentation procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Heatup or cooldown of the reactor vessel 2.1.31 - Conduct of Operations:
Ability to locate control room 272000 Radiation switches, controls, and X 4.3 93 Monitoring indications, and to determine that they correctly reflect the desired plant lineup.
K1.04 - Knowledge of the physical connections and/or cause- effect relationships 204000 RWCU X between REACTOR WATER 2.9 27 CLEANUP SYSTEM and the following: Component cooling water systems K2.02 - Knowledge of electrical 233000 Fuel Pool X power supplies to the following: 2.8 28 Cooling/Cleanup RHR pumps K3.01 - Knowledge of the effect that a loss or malfunction of the 201003 Control Rod and X CONTROL ROD AND DRIVE 3.2 29 Drive Mechanism MECHANISM will have on following: Reactor power K4.01 - Knowledge of CONTROL ROOM HVAC design feature(s) and/or 290003 Control Room X interlocks which provide for the 3.1 30 HVAC following: System initiations/reconfiguration:
Plant-Specific K5.02 - Knowledge of the operational implications of the 259001 Reactor Feedwater X following concepts as they apply 2.5 31 to REACTOR FEEDWATER SYSTEM : Water hammer K6.08 - Knowledge of the effect that a loss or malfunction of the 226001 RHR/LPCI: CTMT following will have on the X 2.7 32 Spray Mode RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE :
Nuclear boiler instrumentation ES-401 Form ES-401-1 Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # / Name A2 G Imp.
1 2 3 4 5 6 1 3 4 #
A1.02 - Ability to predict and/or monitor changes in parameters associated with operating the ROD WORTH MINIMIZER 201006 RWM X 3.4 33 SYSTEM (RWM) (PLANT SPECIFIC) controls including:
Status of control rod movement blocks; P-Spec(Not-BWR6)
A2.01 - Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY 245000 Main Turbine SYSTEMS ; and (b) based on X 3.7 34 Generator / Auxiliaries those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine trip A3.03 - Ability to monitor automatic operations of the 215001 Traversing In-core X TRAVERSING IN-CORE 2.5 35 Probe PROBE including: Valve operation: Not-BWR1 A4.05 - Ability to manually 219000 RHR/LPCI: operate and/or monitor in the X 3.4 36 Torus/Pool Cooling Mode control room: Heat exchanger cooling flow 2.4.3 - Emergency Procedures /
216000 Nuclear Boiler Inst. X Plan: Ability to identify post- 3.7 37 accident instrumentation.
A1.08 - Ability to predict and/or monitor changes in parameters 256000 Reactor associated with operating the X 2.7 38 Condensate REACTOR CONDENSATE SYSTEM controls including:
System water quality K/A Category Totals: 1 1 1 1 1 1 2 1/2 1 1 1/1 Group Point Total: 12/3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: DAEC Date of Exam: September 2009 RO SRO-Only Category K/A # Topic IR Q# IR Q#
2.1.40 Knowledge of refueling administrative requirements 3.9 94 2.1.5 Ability to use procedures related to shift staffing, 3.9 100 minimum crew complement, overtime limitation, etc.
- 1. 2.1.39 Knowledge of conservative decision making practices. 3.6 66 Conduct of Operations 2.1.27 Knowledge of system purpose and / or function. 3.9 67 Knowledge of shift or short-term relief turnover practices.
2.1.3 3.7 75 Subtotal 3 2 Knowledge of the process for conducting special or 2.2.7 3.6 95 infrequent tests.
2.2.21 Knowledge of pre- and post-maintenance operability 4.1 96 requirements
- 2. 2.2.12 Knowledge of surveillance procedures 3.7 68 Equipment Knowledge of the process used to track inoperable 2.2.43 3.0 69 Control alarms.
2.2.22 Knowledge of limiting conditions for operations and safety 4.0 74 limits.
Subtotal 3 2 2.3.11 Ability to control radiation releases. 4.3 98 Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as containment entry
- 3. 2.3.12 3.2 70 requirements, fuel handling responsibilities, access to Radiation Control locked high-radiation areas, aligning filters, etc.
Knowledge of radiation or contamination hazards that 2.3.14 may arise during normal, abnormal, or emergency 3.4 71 conditions or activities.
Subtotal 2 1 Knowledge of low power / shutdown implications in 2.4.9 accident (e.g., loss of coolant accident or loss of residual 4.2 97 heat removal) mitigation strategies.
Ability to take actions called for in the facility emergency 2.4.38 plan, including supporting or acting as emergency 4.4 99
- 4. coordinator if required.
Emergency Procedures /
Plan 2.4.27 Knowledge of "fire in the plant" procedures. 3.4 72 Knowledge of general operating crew responsibilities 2.4.12 4.0 73 during emergency operations.
Subtotal 2 2 Tier 3 Point Total 10 7 ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection RO #18, Ability to monitor automatic operations of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY 2/1 223002 / A3.03 SHUT-OFF including: SPDS/ERIS/CRIDS/GDS: Plant-Specific. Low level of difficulty, minutia.
Randomly selected A3.02 - Valve closures RO #25, Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or 2/1 217000 / A2.03 mitigate the consequences of those abnormal conditions or operations:
Valve closures. Similar in concept to #13 Randomly selected A4.03 - Ability to manually operate and/or monitor in the control room: System valves RO #32, K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE: Keep fill system. Same concept as #31 (water hammer).
2/2 226001 / K6.04 Randomly selected K6.08 - Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE: Nuclear boiler instrumentation RO #34, Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High airborne radiation . Similar concept to #45 (refuel floor evacuation due to high rad).
2/2 290001 / A2.04 Randomly selected 245000 A2.01 - Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine trip RO #42, Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: Feedwater - HPCI: BWR-2.
1/1 295005 / AK2.09 DAEC is not a BWR-2 Randomly selected AK2.03 - Recirculation system RO #43, Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Motors. Low LOD, not discriminating.
1/1 600000 / AK2.03 Randomly selected AK2.01 - Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Sensors/ detectors, valves RO #45, Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS : Refueling floor evacuation. There is only one reason for evacuating the refuel floor, radiation issues.
1/1 295023 / AK3.01 Therefore, plausible distractors were not available to result in a question with an LOD>1.
Randomly selected AK3.02 - Interlocks associated the fuel handling equipment RO #49, Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Condensate storage and 1/1 295030 / EA1.06 transfer (make-up to the suppression pool): Plant-Specific. Does not apply at DAEC Randomly selected EA1.05 - HPCI RO #55, Conduct of Operations: Knowledge of system purpose and / or function. Topic does not pertain to APE (control room abandonment).
1/1 295016 / 2.1.27 Randomly selected AA1.06 - Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: Reactor Water Level.
ES-401 Record of Rejected K/As Form ES-401-4 RO #57, Conduct of Operations: Ability to locate and operate components, including local controls. This topic area is demonstrated on 1/1 295021 / 2.1.30 the JPM portion of the exam.
Randomly selected 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.
RO # 62, Ability to operate and monitor the following as they apply to HIGH CONTAINMENT HYDROGEN CONTROL: Nitrogen purge system.
1/2 500000 / EA1.07 Does not apply at DAEC.
Randomly selected 295007 AA1.02 - Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE : HPCI RO #64, Conduct of Operations: Ability to explain and apply all system limits and precautions. System limits and precautions are very limited and result in a question involving very basic (LOD-1) questions such as 1/2 295002 / 2.1.32 the MSIV closure and main Turbine Trip setpoints.
Randomly selected 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
RO #68, Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, 3 2.2.17 coordination with the transmission system operator. This activity is performed and managed by the SROs at DAEC.
Randomly selected 2.2.12 - Knowledge of surveillance procedures RO #69, (multi-unit license) Knowledge of the design, procedural, and operational differences between units. DAEC is a single unit site.
3 2.2.3 Randomly selected 2.2.43 - Knowledge of the process used to track inoperable alarms.
RO #74, Ability to obtain and interpret station electrical and mechanical drawings. This KA, Obtain and Interpret drawings may be tested during different portions of the operating exam and does not lend itself to a 3 2.2.41 written question.
Randomly selected 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
SRO #78, Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER 1/1 295037 / EA2.05 ABOVE APRM DOWNSCALE OR UNKNOWN: Control rod position.
This is the same K/A as RO #52.
Randomly selected EA2.03 - SBLC Tank Level SRO #82, - Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID 1/1 700000 / AA2.02 DISTURBANCES: Voltage outside the generator capability curve. Very similar topic area as K/A for RO #53.
Randomly selected AA2.08 - Criteria to trip the turbine or reactor SRO #83, Ability to determine and / or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Combustible limits for drywell. This information 1/2 500000 / EA2.03 has removed from EOP guidance and is in the SAGs.
Randomly selected 295015 AA2.01 - Ability to determine and / or interpret the following as they apply to INCOMPLETE SCRAM: Reactor power SRO #86, Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the 2/1 209001 / A2.03 consequences of those abnormal conditions or operations: A.C. failures.
System covered in Q #7, 16 & 48. #7 covers the same topic area.
Randomly selected A2.05 - Core Spray line break ES-401 Record of Rejected K/As Form ES-401-4 SRO #87, Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those 2/1 223002 / A2.11 abnormal conditions or operations: Standby liquid initiation. SLC initiation does not affect the PCIS system. Although RWCU isolates on SLC initiation, it is not part of the PCIS logic.
Randomly selected A2.03 - System logic failures SRO #96, Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3 2.3.14 Overlap with RO exam #71.
Randomly selected 2.2.21 - Knowledge of pre- and post-maintenance operability requirements SRO #100, Knowledge of the refueling process. Topic oversampled for the SROs. See question 94.
3 2.1.41 Randomly selected 2.1.5 - Ability to use procedures related to shift staffing, minimum crew complement, overtime limitation, etc.
RO #40, Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Steam condensation. TS Bases question not tied to RO objectives at DAEC.
1/1 295026 / EK1.02 Randomly selected 295026 Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Pump NPSHEK1.01 Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Pump NPSH RO #45, Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS : Interlocks associated the fuel handling equipment. TS Bases question not tied to RO objectives at 1/1 295023 / AK3.02 DAEC.
Randomly selected 295025 EK2.08 - Knowledge of the interrelationships between HIGH REACTOR PRESSURE and the following: Reactor/turbine pressure regulating system RO #61, - Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION : Manual SCRAM and depressurization: Plant-Specific.
1/2 295034 / EK3.05 Could not write higher difficulty question with plausible distractors.
Randomly selected 295009 AK3.01 - Knowledge of the reasons for the following responses as they apply to LOW REACTOR WATER LEVEL:
Recirculation pump runback.
SRO #80 - 2.2.37 - Equipment Control: Ability to determine operability and / or availability of safety related equipment. Plant fire on site could not support an SRO level question without providing references that led to a direct lookup question.
1/1 600000 / 2.2.37 Memorizing the fire protection plan and equipment in associated fire zones is not required at DAEC.
Randomly selected 295005 AA2.02 - Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP Turbine vibration SRO #92 - 2.4.49 - Emergency Procedures / Plan: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. Topic, Immediate actions, is also an RO responsibility and does not equate to an SRO level question.
2/2 256000 / 2.4.49 Randomly selected 216000 A2.11 - Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Heatup or cooldown of the reactor vessel