NG-09-0460, DAEC 2009 Revised Written Exam Outline (Es 401-1,3,4)

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DAEC 2009 Revised Written Exam Outline (Es 401-1,3,4)
ML100351189
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 09/21/2009
From:
NextEra Energy Duane Arnold
To:
NRC/RGN-III
References
NG-09-0460, NUREG-1021
Download: ML100351189 (14)
v • d • e


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 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G* Total A2 G* Total 1 3 4 2 4 4 3 20 5 2 7 2 1 1 2 1 1 1 7 2 1 3 1. Emergency

& Plant Evolutions Tier Totals 4 5 4 5 5 4 27 7 3 10 1 3 2 2 2 2 2 3 2 3 3 2 26 2 3 5 2 1 1 1 1 1 1 2 1 1 1 1 12 0 2 1 3 2. Plant Systems Tier Totals 4 3 3 3 3 3 5 3 4 4 3 38 4 4 8 1 2 3 4 1 2 3 4 3. Generic Knowledge & Abilities Categories 3 3 2 2 10 2 2 1 2 7 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 specifi ed 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/A's

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-401-1Duane 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# 295030 Low Suppression Pool Water Level / 5 X EA2.01 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL : Suppression pool level 4.2 76 295004 Partial or Total Loss of DC Pwr / 6 X AA2.04 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : System lineups 3.3 77 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown / 1 X EA2.03 - Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC Tank Level.

4.4 78 295031 Reactor Low Water

Level / 2 X 2.4.35 - Emergency Procedures / Plan:

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects.

4.0 79 295005 Main Turbine Generator

Trip / 3 X AA2.02 - Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP Turbine vibration 2.7 80 295025 High Reactor Pressure /

3 X 2.1.19 - Conduct of Operations: Ability to use plant computers to evaluate system or component status.

3.8 81 700000 Generator Voltage and

Electric Grid Disturbances / 6 X AA2.08 - Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Criteria to trip the turbine or reactor 4.4 82 295004 Partial or Total Loss of DC Pwr / 6 X AK1.05 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : Loss of breaker protection 3.3 39 295026 Suppression Pool High Water Temp. / 5 X EK1.01 Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Pump NPSH 3.0 40 295001 Partial or Complete Loss of Forced Core Flow

Circulation / 1 & 4 X AK1.03 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Thermal limits 3.6 41 295005 Main Turbine Generator Trip / 3 X AK2.03 - Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: Recirculation system 3.2 42 600000 Plant Fire On-site / 8 X AK2.01 - Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Sensors/

detectors, valves 2.6 43 295006 SCRAM / 1 X AK2.01 - Knowledge of the interrelations between SCRAM and the following: RPS 4.3 44 295025 High Reactor Pressure

/ 3 X EK2.08 - Knowledge of the interrelationships between HIGH REACTOR PRESSURE and the following: Reactor/turbine pressure regulating system 3.7 45 ES-401 Form ES-401-1Duane 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# 295028 High Drywell Temperature / 5 X EK3.03 - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE : Drywell spray operation: Mark-I&II 3.6 46 295024 High Drywell Pressure /

5 X EK3.08 - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE : Containment spray: Plant-Specific 3.7 47 295031 Reactor Low Water

Level / 2 X EA1.03 - Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL : Low pressure core spray 4.4 48 295030 Low Suppression Pool

Water Level / 5 X EA1.05 - Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER

LEVEL: HPCI 3.5 49 295018 Partial or Total Loss of CCW / 8 X AA1.03 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :

Affected systems so as to isolate damaged portions 3.3 50 295003 Partial or Complete Loss of AC / 6 X AA2.04 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER : System lineups 3.5 51 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown / 1 X EA2.05 - Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Control rod position 4.2 52 700000 Generator Voltage and

Electric Grid Disturbances X AA2.01 - Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Operating point on the generator capability curve.

3.5 53 295038 High Off-site Release Rate / 9 X 2.1.23 - Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.3 54 295016 Control Room Abandonment / 7 X AA1.06 - Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: Reactor Water Level 4.0 55 295019 Partial or Total Loss of

Inst. Air / 8 X 2.1.20 - Conduct of Operations: Ability to interpret and execute procedure

steps. 4.6 56 295021 Loss of Shutdown Cooling / 4 X 2.1.25 - Conduct of Operations: Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 57 295025 High Reactor Pressure

/ 3 X EA2.04 - Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Suppression pool level 3.9 58 K/A Category Totals:

3 4 2 4 4/5 3/2 Group Point Total:

20/7 ES-401 Form ES-401-1Duane 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# 295015 Incomplete Scram / 1 X AA2.01 - Ability to determine and / or interpret the following as they apply to INCOMPLETE SCRAM: Reactor power 4.3 83 295017 High Off-site Release Rate / 9 X 2.4.41 - Emergency Procedures / Plan:

Knowledge of the emergency action level thresholds and classifications.

4.6 84 295033 High Secondary Containment Area Radiation Levels / 9 X EA2.03 - Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Cause of high area radiation 4.2 85 295022 Loss of CRD Pumps /

1 X AK1.01 - Knowledge of the operational implications of the following concepts as they apply to LOSS OF CRD PUMPS: Reactor pressure vs. rod insertion capability 3.3 59 295012 High Drywell Temperature / 5 X AK2.02 - Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following:

Drywell cooling 3.6 60 295009 Low Reactor Water

Level / 2 X AK3.01 - Knowledge of the reasons for the following responses as they apply to LOW REACTOR WATER LEVEL:

Recirculation pump runback 3.2 61 295007 High Reactor Pressure

/ 3 X AA1.02 - Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE : HPCI 3.5 62 295014 Inadvertent Reactivity Addition / 1

X AA2.01 - Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION : Reactor power 4.1 63 295002 Loss of Main Condenser Vac / 3 X 2.4.47 - Emergency Procedures / Plan:

Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 64 295032 High Secondary Containment Area Temperature

/ 5 X EK3.03 - Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE : Isolating affected systems 3.8 65 K/A Category Totals:

1 1 2 1 1/2 1/1 Group Point Total:

7/3 ES-401 Form ES-401-1Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G Imp. Q# 209001 LPCS X 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 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Core Spray line break 3.6 86 223002 PCIS/Nuclear Steam Supply Shutoff X A2.03 - 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 abnormal conditions or operations: System Logic failures 3.3 87 215003 IRM X 2.2.36 - Equipment Control:

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

4.2 88 239002 SRVs X 2.1.23 - Conduct of Operations: Ability to perform specific system and integrated plant procedures

during all modes of plant operation.

4.4 89 211000 SLC X 2.2.25 - Equipment Control: Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

4.2 90 205000 Shutdown Cooling X K1.03 - Knowledge of the physical connections and/or cause- effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: Recirculation loop temperature 3.4 1 259002 Reactor Water

Level Control X K1.01 - Knowledge of the physical connections and/or cause- effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: RPS 3.8 2 218000 ADS X K2.01 - Knowledge of electrical power supplies to the following:

ADS logic 3.1 3 215005 APRM / LPRM X K2.02 - Knowledge of electrical power supplies to the following:

APRM channels 2.6 4 ES-401 Form ES-401-1Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G Imp. Q# 400000 Component Cooling Water X K3.01 - Knowledge of the effect

that a loss or malfunction of the CCWS will have on the following: Loads cooled by CCWS 2.9 5 239002 SRVs X K3.01 - Knowledge of the effect

that a loss or malfunction of the RELIEF/SAFETY VALVES will have on following: Reactor pressure control 3.9 6 264000 EDGs X K4.05 - Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for the following: Load shedding and sequencing 3.2 7 215004 Source Range

Monitor X K4.02 - Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Reactor SCRAM signals 3.4 8 206000 HPCI X K5.06 - Knowledge of the

operational implications of the following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSTEM : Turbine speed measurement: BWR-2,3,4 2.6 9 215003 IRM X K5.01 - Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM : Detector operation 2.6 10 262002 UPS (AC/DC)

X K6.02 - Knowledge of the effect

that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) : D.C. electrical power 2.8 11 211000 SLC X K6.03 - Knowledge of the effect

that a loss or malfunction of the following will have on the STANDBY LIQUID CONTROL SYSTEM : A.C. power 3.2 12 217000 RCIC X A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: RCIC flow 3.7 13 263000 DC Electrical

Distribution X A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including: Battery charging/discharging rate 2.5 14 ES-401 Form ES-401-1Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G Imp. Q# 300000 Instrument Air X A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer

and filter malfunctions 2.9 15 209001 LPCS X A2.08 - 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 consequences of those abnormal conditions or operations: Valve openings 3.1 16 261000 SGTS X A3.03 - Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Valve operation 3.0 17 223002 PCIS/Nuclear Steam Supply Shutoff X A3.02 - Ability to monitor automatic operations of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF including:

Valve closures 3.5 18 212000 RPS X A4.04 - Ability to manually operate and/or monitor in the control room: Bypass SCRAM

instrument volume high level SCRAM signal 3.9 19 262001 AC Electrical

Distribution X A4.04 - Ability to manually operate and/or monitor in the control room: Synchronizing and

paralleling of different A.C.

supplies 3.6 20 203000 RHR/LPCI: Injection Mode X 2.2.40 - Equipment Control::

Ability to apply Technical Specifications for a system.

3.4 21 215005 APRM / LPRM X 2.4.46 - Emergency Procedures

/ Plan: Ability to verify that the alarms are consistent with the plant conditions.

4.2 22 261000 SGTS X K1.06- Knowledge of the physical connections and/or

cause effect relationships between STANDBY GAS TREATMENT SYSTEM and the following: High pressure coolant injection system; Plant-specific 3.0 23 ES-401 Form ES-401-1Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G Imp. Q# 218000 ADS X A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures 3.4 24 217000 RCIC X A4.03 - Ability to manually operate and/or monitor in the control room: System valves 3.4 25 205000 Shutdown Cooling X A3.02 - Ability to monitor automatic operations of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including:

Pump trips 3.2 26 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-401-1Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 2 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G Imp. Q

  1. 201003 Control Rod and

Drive Mechanism X A2.08 - Ability to predict and/or monitor changes in parameters associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including: Low HCU accumulator pressure/high level 3.7 91 216000 Nuclear Boiler

Instrumentation X 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 3.3 92 272000 Radiation Monitoring X 2.1.31 - Conduct of Operations:

Ability to locate control room switches, controls, and

indications, and to determine that they correctly reflect the desired plant lineup.

4.3 93 204000 RWCU X K1.04 - Knowledge of the physical connections and/or cause- effect relationships between REACTOR WATER CLEANUP SYSTEM and the following: Component cooling water systems 2.9 27 233000 Fuel Pool Cooling/Cleanup X K2.02 - Knowledge of electrical power supplies to the following:

RHR pumps 2.8 28 201003 Control Rod and

Drive Mechanism X K3.01 - Knowledge of the effect

that a loss or malfunction of the CONTROL ROD AND DRIVE MECHANISM will have on following: Reactor power 3.2 29 290003 Control Room HVAC X K4.01 - Knowledge of CONTROL ROOM HVAC design feature(s) and/or interlocks which provide for the following: System initiations/reconfiguration:

Plant-Specific 3.1 30 259001 Reactor Feedwater X K5.02 - Knowledge of the

operational implications of the following concepts as they apply to REACTOR FEEDWATER SYSTEM : Water hammer 2.5 31 226001 RHR/LPCI: CTMT Spray Mode X 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 2.7 32 ES-401 Form ES-401-1Duane Arnold NRC Written 2009 Written Examination Outline Plant Systems - Tier 2 Group 2 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G Imp. Q

  1. 201006 RWM X A1.02 - Ability to predict and/or monitor changes in parameters associated with operating the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) controls including:

Status of control rod movement blocks; P-Spec(Not-BWR6) 3.4 33 245000 Main Turbine Generator / Auxiliaries X 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 3.7 34 215001 Traversing In-core Probe X A3.03 - Ability to monitor automatic operations of the TRAVERSING IN-CORE

PROBE including: Valve operation: Not-BWR1 2.5 35 219000 RHR/LPCI: Torus/Pool Cooling Mode X A4.05 - Ability to manually operate and/or monitor in the control room: Heat exchanger cooling flow 3.4 36 216000 Nuclear Boiler Inst.

X 2.4.3 - Emergency Procedures /

Plan: Ability to identify post-accident instrumentation.

3.7 37 256000 Reactor

Condensate X A1.08 - Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CONDENSATE SYSTEM controls including:

System water quality 2.7 38 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, minimum crew complement, overtime limitation, etc.

3.9 100 2.1.39 Knowledge of conservative dec ision making practices.

3.6 66 2.1.27 Knowledge of system purpose and / or function.

3.9 67 2.1.3 Knowledge of shift or short-term relief turnover practices.

3.7 75 1. Conduct of Operations Subtotal 3 2 2.2.7 Knowledge of the process for conducting special or infrequent tests.

3.6 95 2.2.21 Knowledge of pre- and post-maintenance operability

requirements 4.1 96 2.2.12 Knowledge of surveillance procedures 3.7 68 2.2.43 Knowledge of the process used to track inoperable alarms. 3.0 69 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.0 74 2. Equipment Control Subtotal 3 2 2.3.11 Ability to control radiation releases.

4.3 98 2.3.12 Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.2 70 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency

conditions or activities.

3.4 71 3.

Radiation Control Subtotal 2 1 2.4.9 Knowledge of low power / shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

4.2 97 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

4.4 99 2.4.27 Knowledge of "fire in the plant" procedures.

3.4 72 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.

4.0 73 4. Emergency Procedures /

Plan Subtotal 2 2 Tier 3 Point Total 10 7 ES-401 Record of Rejected K/A's Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection 2 / 1 223002 / A3.03 RO #18, Ability to monitor automatic operations of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF including: SPDS/ERIS/CRIDS/GDS: Plant-Specific. Low level of difficulty, minutia.

Randomly selected A3.02 - Valve closures 2 / 1 217000 / A2.03 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 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 2 / 2 226001 / K6.04 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). 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 2 / 2 290001 / A2.04 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). 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 1 / 1 295005 / AK2.09 RO #42, Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: Feedwater - HPCI: BWR-2. DAEC is not a BWR-2 Randomly selected AK2.03 - Recirculation system 1 / 1 600000 / AK2.03 RO #43, Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Motors. Low LOD, not discriminating. Randomly selected AK2.01 - Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Sensors/ detectors, valves 1 / 1 295023 / AK3.01 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. Therefore, plausible distractors were not available to result in a question with an LOD>1. Randomly selected AK3.02 - Interl ocks associated the fuel handling equipment 1 / 1 295030 / EA1.06 RO #49, Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Condensate storage and transfer (make-up to the suppression pool): Plant-Specific. Does not apply at DAEC Randomly selected EA1.05 - HPCI 1 / 1 295016 / 2.1.27 RO #55, Conduct of Operations: Knowledge of system purpose and / or function. Topic does not pertain to APE (control room abandonment).

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/A's Form ES-401-4 1 / 1 295021 / 2.1.30 RO #57, Conduct of Operations: Ability to locate and operate components, including local controls. This topic area is demonstrated on the JPM portion of the exam. Randomly selected 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

1 / 2 500000 / EA1.07 RO # 62, Ability to operate and monitor the following as they apply to HIGH CONTAINMENT HYDROGEN CONTROL: Nitrogen purge system. 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 1 / 2 295002 / 2.1.32 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 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.

3 2.2.17 RO #68, Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, 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 3 2.2.3 RO #69 , (multi-unit license) Knowledge of the design, procedural, and operational differences between units. DAEC is a single unit site.

Randomly selected 2.2.43 - Knowledge of the process used to track inoperable alarms.

3 2.2.41 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 written question. Randomly selected 2.2.22 - Knowledge of limiting conditions for operations and safety limits.

1 / 1 295037 / EA2.05 SRO #78, Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Control rod position. This is the same K/A as RO #52. Randomly selected EA2.03 - SBLC Tank Level 1 / 1 700000 / AA2.02 SRO #82, - Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID 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 1 / 2 500000 / EA2.03 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 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 2 / 1 209001 / A2.03 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 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/A's Form ES-401-4 2 / 1 223002 / A2.11 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 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 3 2.3.14 SRO #96, Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. Overlap with RO exam #71. Randomly selected 2.2.21 - Knowledge of pre- and post-maintenance operability requirements 3 2.1.41 SRO #100, Knowledge of the refueling process. Topic oversampled for the SROs. See question 94.

Randomly selected 2.1.5 - Ability to use procedures related to shift staffing, minimum crew complement, overtime limitation, etc.

1 / 1 295026 / EK1.02 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. Randomly selected 295026 Knowledge of the operational implications of the following concepts as they apply to SUPPRESS ION 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 1 / 1 295023 / AK3.02 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 DAEC. Randomly selected 295025 EK2.08 - Knowledge of the interrelationships between HIGH REACTOR PRESSURE and the following: Reactor/turbine pressure regulating system 1 / 2 295034 / EK3.05 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. 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.

1 / 1 600000 / 2.2.37 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. 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 2 / 2 256000 / 2.4.49 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. 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

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