ML13308A398
| ML13308A398 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/08/2013 |
| From: | NRC/RGN-III |
| To: | NextEra Energy Duane Arnold |
| Randal Baker | |
| Shared Package | |
| ML11354A409 | List: |
| References | |
| ES-401, ES-401-1 | |
| Download: ML13308A398 (19) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 Facility: DAEC Date of Exam: 04/16/12 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.
1 3 3 4 3 4 3 20 3 4 7 Emergency 2 1 2 1 1 1 1 7 2 1 3 Plant Evaluations Tier 4 5 5 4 5 4 27 5 5 10 Totals 1 3 2 2 2 3 2 2 2 2 3 3 26 3 2 5 2.
2 1 1 1 1 2 1 1 1 1 1 1 12 0 1 2 3 Plant Systems Tier 4 3 3 3 5 3 3 3 3 4 4 38 4 4 8 Totals
- 3. Generic Knowledge & Abilities 1 2 3 4 10 1 2 3 4 7 2 3 3 2 2 2 2 1 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/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 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR 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#
AA2.01 - Ability to determine and/or interpret the following 295021 Loss of Shutdown as they apply to LOSS OF X 3.6 76 Cooling / 4 SHUTDOWN COOLING:
Reactor water heatup/cooldown rate EA2.02 - Ability to determine and/or interpret the following 295028 High Drywell as they apply to HIGH X 3.9 77 Temperature / 5 DRYWELL TEMPERATURE: Reactor pressure AA2.03 - Ability to determine and/or interpret the following 295016 Control Room X as they apply to CONTROL 4.4 78 Abandonment / 7 ROOM ABANDONMENT:
Reactor pressure 295031 Reactor Low Water 2.2.12, Knowledge of X 4.1 79 Level / 2 surveillance procedures 295037 SCRAM Condition 2.4.6, Emergency Present and Reactor Power Procedures / Plan:
X 4.7 80 Above APRM l Downscale Knowledge of EOP or Unknown / 1 mitigation strategies.
2.4.4, Emergency Procedures / Plan: Ability to recognize abnormal 295003, Partial or Complete indications for system X 4.7 81 Loss of AC / 6 operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
2.4.35 - Emergency Procedures / Plan:
Knowledge of local auxiliary 295006 SCRAM / 1 X 4.0 82 operator tasks during emergency and the resultant operational effects.
EK1.02 - Knowledge of the operational implications of 295025 High Reactor the following concepts as X 4.1 39 Pressure / 3 they apply to HIGH REACTOR PRESSURE:
Reactor vessel integrity DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR 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#
EK1.01 - Knowledge of the operational implications of the following concepts as 295026 Suppression Pool they apply to X 3.0 40 High Water Temp. / 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: Pump NPSH AK1.02 - Knowledge of the operational implications of 295021 Loss of Shutdown the following concepts as X 3.3 41 Cooling / 4 they apply to LOSS OF SHUTDOWN COOLING:
Thermal stratification EK2.13 - Knowledge of the interrelations between 295031 Reactor Low Water REACTOR LOW WATER X 4.1 42 Level / 2 LEVEL and the following:
ARI/RPT/ATWS: Plant-Specific AK2.08 - Knowledge of the interrelations between 295019 Partial or Total PARTIAL OR COMPLETE X 2.8 43 Loss of Inst. Air / 8 LOSS OF INSTRUMENT AIR and the following: Plant ventilation AK2.01 - Knowledge of the interrelations between 295004 Partial or Total PARTIAL OR COMPLETE X 3.1 44 Loss of DC Pwr / 6 LOSS OF D.C. POWER and the following: Battery charger AK3.01 - Knowledge of the reasons for the following 295006 SCRAM / 1 X responses as they apply to 3.8 45 SCRAM: Reactor water level response AK3.05 - Knowledge of the reasons for the following responses as they apply to 295001 Partial or Complete PARTIAL OR COMPLETE Loss of Forced Core Flow X 3.2 46 LOSS OF FORCED CORE Circulation / 1 & 4 FLOW CIRCULATION:
Reduced loop operating requirements: Plant-Specific DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR 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#
EK3.07 - Knowledge of the reasons for the following 295024 High Drywell X responses as they apply to 3.5 47 Pressure / 5 HIGH DRYWELL PRESSURE: Drywell venting EA1.03 - Ability to operate and/or monitor the following 295028 High Drywell as they apply to HIGH X 3.9 48 Temperature / 5 DRYWELL TEMPERATURE: Drywell cooling system AA1.01 - Ability to operate and/or monitor the following 295005 Main Turbine as they apply to MAIN X 3.1 49 Generator Trip / 3 TURBINE GENERATOR TRIP: Recirculation system:
Plant-Specific AA1.06 - Ability to operate 600000 Plant Fire On-site / and / or monitor the following X 3.0 50 8 as they apply to PLANT FIRE ON SITE: Fire alarm EA2.06 - Ability to determine and/or interpret the following as they apply to SCRAM 295037 SCRAM Conditions CONDITION PRESENT Present and Reactor Power X AND REACTOR POWER 4.0 51 Above APRM Downscale or ABOVE APRM Unknown / 1 DOWNSCALE OR UNKNOWN: Reactor pressure AA2.04 - Ability to determine and/or interpret the following 295018 Partial or Total as they apply to PARTIAL X 2.9 52 Loss of CCW / 8 OR COMPLETE LOSS OF COMPONENT COOLING WATER: System flow AA2.01 - Ability to determine and/or interpret the following 295023 Refueling X as they apply to 3.6 53 Accidents / 8 REFUELING ACCIDENTS:
Area radiation levels 295001 Partial or Complete 2.1.1, Conduct of Loss of Forced Core Flow Operations: Knowledge of X 3.8 54 Circulation / 1 & 4 conduct of operations requirements DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR 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#
2.1.20 - Conduct of 295003 Partial or Complete Operations: Ability to X 2.7 55 Loss of AC / 6 interpret and execute procedure steps.
2.4.45 - Emergency Procedures / Plan: Ability to 295038 High Off-site X prioritize and interpret the 4.1 56 Release Rate / 9 significance of each annunciator or alarm.
AA2.02 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage GENERATOR VOLTAGE and Electric Grid X 3.5 57 AND ELECTRIC GRID Disturbances DISTURBANCES: Voltage outside the generator capability curve.
AK3.03 - Knowledge of the reasons for the following 295016 Control Room responses as they apply to X 3.5 58 Abandonment / 7 CONTROL ROOM ABANDONMENT: Disabling control room controls K/A Category Totals 3 3 4 3 4/3 3/4 Group Point Total: 20/7 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR 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#
EA2.01 - Ability to determine and/or interpret the following 295029 High Suppression as they apply to HIGH X 3.9 83 Pool Water Level / 5 SUPPRESSION POOL WATER LEVEL:
Suppression pool water level 2.4.45 - Emergency Procedures / Plan: Ability to 295009 Low Reactor Water X prioritize and interpret the 4.3 84 Level / 2 significance of each annunciator or alarm.
AA2.01 - Ability to determine and/or interpret the following 295012 High Drywell as they apply to HIGH X 3.9 85 Temperature / 5 DRYWELL TEMPERATURE: Drywell temperature AK1.05 - Knowledge of the operational implications of 295009 Low Reactor Water the following concepts as X 3.3 59 Level / 2 they apply to LOW REACTOR WATER LEVEL:
Natural circulation AK2.01 - Knowledge of the interrelations between 295014 Inadvertent X INADVERTENT 3.9 60 Reactivity Addition / 1 REACTIVITY ADDITION and the following: RPS AK3.01 - Knowledge of the reasons for the following 295015 Incomplete responses as they apply to X 3.4 61 SCRAM / 1 INCOMPLETE SCRAM:
Bypassing rod insertion blocks AA1.02 - Ability to operate and/or monitor the following as they apply to HIGH 295008 High Reactor X REACTOR WATER LEVEL: 3.3 62 Water Level / 2 Reactor water cleanup (ability to drain): Plant-Specific DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR 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#
EA2.02 - Ability to determine and/or interpret the following as they apply to 295035 Secondary SECONDARY Containment High X 2.8 63 CONTAINMENT HIGH Differential Pressure / 5 DIFFERENTIAL PRESSURE: Off-site release rate: Plant-Specific 2.4.2 - Emergency Procedures / Plan:
295034 Secondary Knowledge of system set Containment Ventilation X 4.5 64 points, interlocks and High Radiation / 9 automatic actions associated with EOP entry conditions.
AK2.12 - Knowledge of the interrelations between INADVERTENT 295020 Inadvertent Cont.
X CONTAINMENT 3.1 65 Isolation / 5 & 7 ISOLATION and the following: Instrument air/nitrogen: Plant-Specific K/A Category Totals 1 2 1 1 1/2 1/1 Group Point Total: 7/3 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
A2 Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; 215005 APRM /
X and (b) based on those 3.2 86 LPRM predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions:
Faulty or erratic operation of detectors/systems A2.03 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION 223002 SYSTEM/NUCLEAR PCIS/Nuclear STEAM SUPPLY SHUT-X 3.0 87 Steam Supply OFF; and (b) based on Shutoff those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System Logic Failures 2.4.18 - Emergency Procedures / Plan:
239002 SRVs X Knowledge of the 4.0 88 specific bases for EOPs.
2.2.25 - Equipment Control: Knowledge of bases in technical 211000 SLC X 4.2 89 specifications for limiting conditions for operations and safety limits.
DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
A2.15 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based on those 217000 RCIC X 3.8 90 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Steam line break K1.03 - Knowledge of the physical connections and/or cause- effect relationships between 217000 RCIC X REACTOR CORE 3.6 1 ISOLATION COOLING SYSTEM (RCIC) and the following: Suppression pool K1.01 - Knowledge of the physical connections and/or cause- effect relationships between 205000 Shutdown SHUTDOWN COOLING X 3.6 2 Cooling SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: Reactor pressure K2.01 - Knowledge of electrical power supplies 300000 Instrument X to the following: 2.8 3 Air Instrument air compressor K2.01 - Knowledge of 263000 DC electrical power supplies Electrical X 3.1 4 to the following: Major Distribution D.C. loads DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
K3 01 - Knowledge of the effect that a loss or malfunction of the LOW 209001 LPCS X PRESSURE CORE 3.8 5 SPRAY SYSTEM will have on following:
Reactor water level K3.02 - Knowledge of the effect that a loss or malfunction of the SOURCE RANGE 215004 Source X MONITOR (SRM) 3.4 6 Range Monitor SYSTEM will have on following: Reactor manual control: Plant-Specific K4.06 - Knowledge of A.C. ELECTRICAL DISTRIBUTION design 262001 AC feature(s) and/or Electrical X 3.6 7 interlocks which provide Distribution for the following:
Redundant power sources to vital buses K4.02 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) and/or 261000 SGTS X 2.6 8 interlocks which provide for the following:
Charcoal bed decay heat removal K5.06 - Knowledge of the operational implications of the following concepts as they apply to HIGH 206000 HPCI X 2.6 9 PRESSURE COOLANT INJECTION SYSTEM:
Turbine speed measurement: BWR-2,3,4 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
K5.01 - Knowledge of the operational implications of the following concepts as 218000 ADS X they apply to 3.8 10 AUTOMATIC DEPRESSURIZATION SYSTEM: ADS logic operation K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the 215003 IRM X INTERMEDIATE 3.6 11 RANGE MONITOR (IRM) SYSTEM: 24/48 volt D.C. power: Plant-Specific K6.04 - Knowledge of the effect that a loss or malfunction of the 239002 SRVs X following will have on the 3.0 12 RELIEF/SAFETY VALVES: D.C. power:
Plant-Specific A1.11 - Ability to predict and/or monitor changes in parameters associated with 212000 RPS X operating the REACTOR 3.4 13 PROTECTION SYSTEM controls including:
System status lights and alarms A1.07 - Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE 215005 APRM / POWER RANGE X 3.0 14 LPRM MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including:
APRM (gain adjustment factor)
DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
A2.03 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those 211000 SLC X predictions, use 3.2 15 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. power failures A2.03 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use 400000 Component X procedures to correct, 2.9 16 Cooling Water control, or mitigate the consequences of those abnormal operation:
High/low CCW temperature A3.02 - Ability to monitor automatic operations of 203000 RHR/LPCI: the RHR/LPCI:
X 4.0 17 Injection Mode INJECTION MODE (PLANT SPECIFIC) including: Pump start A3.03 - Ability to monitor automatic operations of the PRIMARY 223002 CONTAINMENT PCIS/Nuclear ISOLATION X 2.5 18 Steam Supply SYSTEM/NUCLEAR Shutoff STEAM SUPPLY SHUT-OFF including:
SPDS/ERIS/CRIDS/GD S: Plant-Specific A4.01 - Ability to manually operate and/or 262002 UPS monitor in the control X 2.8 19 (AC/DC) room: Transfer from alternative source to preferred source DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
A4.02 - Ability to manually operate and/or 264000 EDGs X 3.4 20 monitor in the control room: Synchroscope 2.4.50 - Emergency Procedures / Plan:
Ability to verify system 259002 Reactor X alarm setpoints and 4.2 21 Water Level Control operate controls identified in the alarm response manual.
2.4.3 - Emergency 262002 UPS Procedures / Plan:
X 3.7 22 (AC/DC) Ability to identify post-accident instrumentation.
2.1.7 - Conduct of Operations: Ability to evaluate plant 262001 AC performance and make Electrical X operational judgments 4.4 23 Distribution based on operating characteristics, reactor behavior, and instrument interpretation.
K5.06 - Knowledge of the operational implications of the following concepts as 264000 EDGs X they apply to 3.4 24 EMERGENCY GENERATORS (DIESEL/JET): Load sequencing A4.04 - Ability to 223002 manually operate and/or PCIS/Nuclear X monitor in the control 3.5 25 Steam Supply room: System indicating Shutoff lights and alarms DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
K1.03 - Knowledge of the physical connections and/or cause- effect relationships between 211000 SLC X STANDBY LIQUID 2.5 26 CONTROL SYSTEM and the following: Plant air systems: Plant-Specific K/A Category Totals 3 2 2 2 3 2 2 2/3 2 3 3/2 Group Point Total: 26/5 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 2 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
A2.11 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) 223001 Primary X based on those 3.8 91 CTMT and Aux.
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Abnormal suppression pool level 2.2.40 - Equipment 288000 Plant Control: Ability to apply X 4.7 92 Ventilation technical specifications for a system.
2.4.41 - Emergency Procedures / Plan:
215001 Traversing Knowledge of the X 4.6 93 In-core Probe emergency action level thresholds and classifications.
K1.01 - Knowledge of the physical connections and/or cause-effect 290002 Reactor relationships between X 3.2 27 Vessel Internals REACTOR VESSEL INTERNALS and the following: Main steam system K2.03 - Knowledge of 202001 electrical power supplies Recirculation X to the following: 2.7 28 System Recirculation system valves DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 2 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
K3.01 - Knowledge of the effect that a loss or malfunction of the 219000 RHR/LPCI: RHR/LPCI:
Torus/Pool Cooling X TORUS/SUPPRESSION 3.9 29 Mode POOL COOLING MODE will have on following:
Suppression pool temperature control K4.07 - Knowledge of REACTOR MANUAL CONTROL SYSTEM design feature(s) and/or interlocks which provide 201002 RMCS X 2.5 30 for the following: Timing of rod insert and withdrawal cycles (rod movement sequence timer)
K5.01 - Knowledge of the operational implications of the 202002 following concepts as Recirculation Flow X they apply to 2.8 31 Control RECIRCULATION FLOW CONTROL SYSTEM: Fluid coupling:
BWR-3,4 K6.03 - Knowledge of the effect that a loss or malfunction of the 216000 Nuclear following will have on the X 2.8 32 Boiler Inst. NUCLEAR BOILER INSTRUMENTATION:
Temperature Compensation A1.02 - Ability to predict and/or monitor changes in parameters 201003 Control Rod associated with and Drive X operating the CONTROL 2.8 33 Mechanism ROD AND DRIVE MECHANISM controls including: CRD drive pressure DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2 Group 2 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
A2.11 - Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use 271000 Off-gas X 2.8 34 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Offgas system low flow A3.02 - Ability to monitor automatic operations of the ROD POSITION 214000 RPIS X INFORMATION 3.2 35 SYSTEM including:
Alarm and indicating lights A4.13 - Ability to 241000 manually operate and/or Reactor/Turbine X monitor in the control 2.9 36 Pressure Regulator room: Turbine inlet pressure 2.4.31 - Emergency Procedures / Plan:
256000 Reactor Knowledge of X 4.2 37 Condensate annunciator alarms, indications, or response procedures.
K5.10 - Knowledge of ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) design 201006 RWM X 3.2 38 feature(s) and/or interlocks which provide for the following:
Withdraw error: P-Spec(Not-BWR6)
K/A Category Totals 1 1 1 1 2 1 1 1/1 1 1 1/2 Group Point Total: 12/3 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date:
Category KA # Topic RO SRO-Only IR Q# IR Q#
Ability to make accurate, clear and 2.1.17 3.9 66 concise verbal reports.
Ability to interpret and execute 2.1.20 4.6 67 procedure steps.
- 1. Conduct of Ability to interpret and execute 2.1.20 4.6 94 Operations procedure steps.
Ability to use procedures to determine the effects on reactivity of plant 2.1.43 4.3 99 changes, such as RCS temperature, secondary plant, fuel depletion, etc.
Subtotal 2 2 Knowledge of less than or equal to one 2.2.39 hour technical specification action 3.9 68 statements for systems.
Knowledge of limiting conditions for 2.2.22 4.0 69 operations and safety limits.
Knowledge of the process for making 2.2.6 3.0 75 changes to procedures.
Knowledge of the process for making
- 2. Equipment 2.2.5 design or operating changes to the 3.2 95 Control facility.
Ability to perform pre-startup procedures for the facility, including 2.2.1 operating those controls associated 4.4 98 with plant equipment that could affect reactivity.
Subtotal 3 2 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 2.3.11 Ability to control radiation releases. 3.8 70 Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment 2.3.12 3.2 71 entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Knowledge of radiation or contamination hazards that may arise 2.3.14 3.4 74 during normal, abnormal, or emergency conditions or activities.
Knowledge of radiological safety
- 3. Radiation procedures pertaining to licensed Control operator duties, such as response to 2.3.13 radiation monitor alarms, containment 3.8 96 entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey 2.9 100 instruments, personnel monitoring equipment, etc.
Subtotal 3 2 Knowledge of RO tasks performed outside the main control room during an 2.4.34 4.2 72 emergency and the resultant operational effects.
Knowledge of crew roles and 2.4.13 4.0 73 responsibilities during EOP usage.
- 4. Emergency Procedures /
Plan Knowledge of how abnormal operating 2.4.8 procedures are used in conjunction with 4.5 97 EOP's.
Subtotal 2 1 Tier 3 Point Total: 10 7 DAEC NRC WRITTEN OUTLINE 1-18-13.DOC