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{{#Wiki_filter:ES-401BWR Examination OutlineFORM ES-401-1Facility Name: Dresden                                Date of Exam: 3/7/11 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G  *TotalTotal 1 4 3 3 3 4 3 20 7 2 1 1 1 2 1 1 7 3Tier  Totals 5 4 4 5 5 4 27 10 1 3 2 2 3 2 3 2 2 2 3 2 26 5 2 1 1 1 1 1 1 1 1 1 2 1 12 0 2 3Tier  Totals 4 3 3 4 3 4 3 3 3 5 3 38 8 1 2 3 4 2 2 1 2Note:  1.Note:  2.Note:  3.Note:  4.Note:  5.Note:  6.Note:  7.*Note:  8.Note:  9.ES-401, Page 17 of 34 5 2Select 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.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 10 CFR 55.43.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.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.3. Generic Knowledge and Abilities Categories 1 2 3The 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.On the following pages, 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; 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.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 the elimination of inappropriate K/A statements.
4 2N/AN/ARO K/A Category Points 7 10Ensure 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).
3 2 4 3 A2 1 4 2 6 3The 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.
G*TierGroupSRO-Only Points2.              Plant    Systems1.              Emergency &            Abnormal Plant Evolutions 1 3 3 ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#17295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0
6Reactor power3.8 1 54295003 Partial or Complete Loss of AC / 6 0
4Electrical bus divisional separation3.1 1 7295004 Partial or Total Loss of DC Pwr / 6 0
3Reactor SCRAM: Plant-Specific3.1 1 21295005 Main Turbine Generator Trip / 3 04.49Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.4.6 1 25295006 SCRAM / 1 0 2Reactor water level control system3.8 1 59295016 Control Room Abandonment / 7 0
9Isolation/emergency condenser(s): Plant-Specific4.0 1 24295018 Partial or Total Loss of CCW / 8 02.12Knowledge of surveillance procedures.3.7 1 46295019 Partial or Total Loss of Inst. Air / 8 01.20Ability to interpret and execute procedure steps.4.6 1 31295021 Loss of Shutdown Cooling / 4 0
4Alternate heat removal methods3.7 1 41295023 Refueling Acc / 8 0
2Interlocks associated with fuel handling equipment3.4 1 61295024 High Drywell Pressure / 5 0
6Emergency generators3.7 1 29295025 High Reactor Pressure / 3 0
1Pressure effects on reactor power3.9 1 64295026 Suppression Pool High Water Temp. / 5 0 2Suppression pool level3.8 1295027 High Containment Temperature / 5Not Applicable To Dresden 0 19295028 High Drywell Temperature / 5 0
1Reactor water level measurement3.5 1 27295030 Low Suppression Pool Wtr Lvl / 5 0
1Emergency depressurization3.8 1 1295031 Reactor Low Water Level / 2 0
1Reactor water level4.6 1 67295037  SCRAM Condition Present      and Reactor Power Above APRM Downscale or Unknown / 1 1
3Alternate boron injection methods: Plant-Specific3.4 1 33295038 High Off-site Release Rate / 9 0
2Protection of the general public4.2 1 49600000 Plant Fire On Site / 8 0
6Need for pressurizing control room (recirculating mode)2.5 1 30 700000 Generator Voltage and Electric Grid Disturbances / 6 0
1Operating point on the generator capability curve3.5 1K/A Category Totals:
4 3 3 3 4 3 20Group Point Total:
ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#13295002 Loss of Main Condenser Vac / 3 0 8Condenser circulating water system3.1 1295007 High Reactor Pressure / 3 0 44295008 High Reactor Water Level / 2 0
1Reactor water level control: Plant-Specific3.7 1295009 Low Reactor Water Level / 2 0295010 High Drywell Pressure / 5 0295011 High Containment Temp / 5 0295012 High Drywell Temperature / 5 0 48295013 High Suppression Pool Temp. / 5 0
1Suppression pool cooling operation3.6 1 55295014 Inadvertent Reactivity Addition / 1 0
6Abnormal reactivity additions.3.8 1 47295015 Incomplete SCRAM / 1 0
5Rod worth minimizer: Plant-Specific2.5 1295017 High Off-site Release Rate / 9 0295020 Inadvertent Cont. Isolation / 5 & 7 0295022 Loss of CRD Pumps / 1 0 73295029 High Suppression Pool Wtr Lvl / 5 01.19Ability to use plant computers to evaluate system or component status.3.9 1295032 High Secondary Containment Area Temperature / 5 0 8295033 High Secondary Containment Area Radiation Levels / 9 0
1Area radiation levels3.8 1295034 Secondary Containment Ventilation High Radiation / 9 0295035 Secondary Containment High Differential Pressure / 5 0295036 Secondary Containment High Sump/Area Water Level / 5 0500000 High CTMT Hydrogen Conc. / 5 0K/A Category Totals:
1 1 1 2 1 1 7ES-401, Page 19 of 34Group Point Total:
ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (RO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#34, 74203000 RHR/LPCI: Injection  Mode 0 2 0 1Core cooling methods; Pumps3.5; 4.3 2 56205000 Shutdown Cooling 0
2SDC/RHR pump flow3.3 150, 5206000 HPCI 0
3 0 3Resetting turbine trips: BWR-2, 3, 4; Condensate storage tank level: BWR-2, 3, 44.2; 3.5 2 14207000 Isolation (Emergency) Condenser 04.31Knowledge of annunciator alarms, indications, or response procedures.4.2 1 53209001 LPCS 0 3Initiation logic 2.9 1209002 HPCSNot Applicable To Dresden 0 28211000 SLC 0
7Tank heater operation 2.7 1 52212000 RPS 0
1RPS motor-generator set failure 3.7 1 40215003 IRM 0
1RPS3.9 1 18215004 Source Range Monitor 0
3RPS status3.6 1 35215005 APRM / LPRM 0
3Inoperative trip (all causes)3.6 1217000 RCICNot Applicable To Dresden 0 36218000 ADS 0
1RHR/LPCI: Plant-Specific4.0 1 42223002 PCIS/Nuclear Steam Supply Shutoff 0 8Manual defeating of selected isolations during specified emergency conditions3.3 1 62239002 SRVs 0 1SRV solenoids 2.8 1 60259002 Reactor Water Level Control 0
1Reactor water level3.8 165, 10261000 SGTS 0
1 0 1Automatic system initiation; System flow3.7; 3.2 2 23262001 AC Electrical Distribution 01.30Ability to locate and operate components, including local controls.4.4 1 68262002 UPS (AC/DC) 0 3Static inverter2.7 1 71263000 DC Electrical Distribution 0
1A.C. electrical distribution3.2 1 72264000 EDGs 0
2Synchroscope3.4 170, 22300000 Instrument Air 0
2 1 2Service air; Breakers, relays and disconnects2.7; 2.9 29, 75400000 Component Cooling Water 0
1 0 1Loads cooled by CCWS; CCW indications and control2.9; 3.1 2 0K/A Category Totals:
3 2 2 3 2 3 2 2 2 3 2 26ES-401, Page 20 of 34Group Point Total:
ES-401-1 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (RO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#57201001 CRD Hydraulic 0 2Scram valve solenoids3.6 1201002 RMCS 0 37201003 Control Rod and Drive Mechanism 0
1Stuck rod3.4 1201004 RSCS 0201005 RCIS 0201006 RWM 0 11202001 Recirculation 0
7Pump trips: Plant-Specific3.3 1202002 Recirculation Flow Control 0 63204000 RWCU 0
4Component cooling water systems2.9 1214000 RPIS 0 3215001 Traversing In-core Probe 0
3Isolation valves: Mark-I&II(Not-BWR1)3.0 1215002 RBM 0216000 Nuclear Boiler Inst.
0 51219000 RHR/LPCI: Torus/Pool Cooling Mode 1 0Prevention of leakage to the environment through system heat exchanger: Plant-Specific3.3 1 16223001 Primary CTMT and Aux.
1 1Temperature measurement2.7 1226001 RHR/LPCI: CTMT Spray Mode 0 66230000 RHR/LPCI: Torus/Pool Spray Mode 0
1Pumps3.7 1233000 Fuel Pool Cooling/Cleanup 0234000 Fuel Handling Equipment 0 39239001 Main and Reheat Steam 0
2Plant air systems 3.2 1239003 MSIV Leakage Control 0241000 Reactor/Turbine Pressure Regulator 0 45245000 Main Turbine Gen. / Aux.01.02Knowledge of operator responsibilities during all modes of plant operation.4.1 1256000 Reactor Condensate 0259001 Reactor Feedwater 0268000 Radwaste 0 43271000 Offgas 0 8System flow3.1 1272000 Radiation Monitoring 0286000 Fire Protection 0288000 Plant Ventilation 0290001 Secondary CTMT 0290003 Control Room HVAC 0 69290002 Reactor Vessel Internals 0
3Reactor power3.3 1 0K/A Category Totals:
1 1 1 1 1 1 1 1 1 2 112ES-401, Page 22 of 34Group Point Total:
ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#77295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 402.
25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.4.2 190295003 Partial or Complete Loss of AC / 6 0 5Whether a partial or complete loss of A.C. power has occurred4.2 1295004 Partial or Total Loss of DC Pwr / 6 0295005 Main Turbine Generator Trip / 3 092295006 SCRAM / 101.06Ability to manage the control room crew during plant transients.4.8 197295016 Control Room Abandonment / 7 0 2Reactor water level4.3 1295018 Partial or Total Loss of CCW / 8 0100295019 Partial or Total Loss of Inst. Air / 8 0
2Status of safety-related instrument air system loads (see AK2.1-AK2.19)3.7 1295021 Loss of Shutdown Cooling / 4 0295023 Refueling Acc / 8 0295024 High Drywell Pressure / 5 0295025 High Reactor Pressure / 3 087295026 Suppression Pool High Water Temp.
/ 501.14Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.3.1 1295027 High Containment Temperature / 5 0295028 High Drywell Temperature / 5 0295030 Low Suppression Pool Wtr Lvl / 5 0295031 Reactor Low Water Level / 2 079295037 SCRAM Condition Present                    and Reactor Power Above APRM          Downscale or Unknown / 1 0 1Reactor power4.3 1295038 High Off-site Release Rate / 9 0600000 Plant Fire On Site / 8 0700000 Generator Voltage and Electric Grid Disturbances / 6 0K/A Category Totals:
0 0 0 0 4 3 7Group Point Total:
ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#295002 Loss of Main Condenser Vac / 3 0295007 High Reactor Pressure / 3 0295008 High Reactor Water Level / 2 094295009 Low Reactor Water Level / 2 0 2Steam flow/feedflow mismatch3.7 1295010 High Drywell Pressure / 5 0295011 High Containment Temp / 5 088295012 High Drywell Temperature / 5 0
1Drywell temperature3.9 1295013 High Suppression Pool Temp. / 5 0295014 Inadvertent Reactivity Addition / 1 0295015 Incomplete SCRAM / 1 0295017 High Off-site Release Rate / 9 0295020 Inadvertent Cont. Isolation / 5 & 7 089295022 Loss of CRD Pumps / 104.11Knowledge of abnormal condition procedures.4.2 1295029 High Suppression Pool Wtr Lvl / 5 0295032 High Secondary Containment Area Temperature / 5 0295033 High Secondary Containment Area Radiation Levels / 9 0295034 Secondary Containment Ventilation High Radiation / 9 0295035 Secondary Containment High Differential Pressure / 5 0295036 Secondary Containment High Sump/Area Water Level / 5 0500000 High CTMT Hydrogen Conc. / 5 0K/A Category Totals:
0 0 0 0 2 1 3ES-401, Page 19 of 34Group Point Total:
ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (SRO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#203000 RHR/LPCI: Injection 081205000 Shutdown Cooling Mode 0 1Recirculation loop high temperature: Plant-Specific3.3 1206000 HPCI 083207000 Isolation (Emergency) Condenser04.06Knowledge of EOP mitigation strategies.4.7 1209001 LPCS 0209002 HPCS 096211000 SLC 0 2Failure of explosive valve to fire 3.9 1212000 RPS 0215003 IRM 0215004 Source Range Monitor 085215005 APRM / LPRM 0
7Recirculation flow channels flow mismatch3.4 1217000 RCIC 0218000 ADS 0223002 PCIS/Nuclear Steam Supply Shutoff 0239002 SRVs 0259002 Reactor Water Level Control 0261000 SGTS 0262001 AC Electrical Distribution 0262002 UPS (AC/DC) 080263000 DC Electrical Distribution01.32Ability to explain and apply system limits and precautions.4.0 1264000 EDGs 0300000 Instrument Air 0400000 Component Cooling Water 0 0K/A Category Totals:
0 0 0 0 0 0 0 3 0 0 2 5ES-401, Page 20 of 34Group Point Total:
ES-401 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (SRO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#201001 CRD Hydraulic 0201002 RMCS 0201003 Control Rod and Drive Mechanism 0201004 RSCS 0201005 RCIS 0201006 RWM 0202001 Recirculation 0202002 Recirculation Flow Control 0204000 RWCU 099214000 RPIS 04.04Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.4.7 1215001 Traversing In-core Probe 0215002 RBM 0216000 Nuclear Boiler Inst.
0219000 RHR/LPCI: Torus/Pool Cooling Mode 0223001 Primary CTMT and Aux.
0226001 RHR/LPCI: CTMT Spray Mode 0230000 RHR/LPCI: Torus/Pool Spray Mode 091233000 Fuel Pool Cooling/Cleanup 0 9A.C. electrical power failures2.9 1234000 Fuel Handling Equipment 0239001 Main and Reheat Steam 0239003 MSIV Leakage Control 0241000 Reactor/Turbine Pressure Regulator 0245000 Main Turbine Gen. / Aux.
0256000 Reactor Condensate 076259001 Reactor Feedwater 0
1Pump trip3.7 1268000 Radwaste 0271000 Offgas 0272000 Radiation Monitoring 0286000 Fire Protection 0288000 Plant Ventilation 0290001 Secondary CTMT 0290003 Control Room HVAC 0290002 Reactor Vessel Internals 0 0K/A Category Totals:
0 0 0 0 0 0 0 2 0 0 1 3ES-401, Page 21 of 34Group Point Total:
ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3Facility Name:Dresden      Date of Exam:3/7/11 Q#IR#IR#42.1.17Ability to make accurate, clear, and concise verbal reports.3.9 1 122.1.43Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.4.1 12.1.2.1.862.1.04Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.3.8 1 822.1.40Knowledge of refueling administrative requirements.3.9 1Subtotal 2 2 62.2.03Knowledge of the design, procedural, and operational differences between units.3.8 1 262.2.22Knowledge of limiting conditions for operations and safety limits.4.0 1 582.2.44Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.4.2 12.2.782.2.23Ability to track Technical Specification limiting conditions for operations.4.6 1 952.2.35Ability to determine Technical Specification Mode of Operation.4.5 1Subtotal 3 2 152.3.04Knowledge of radiation exposure limits under normal or emergency conditions.3.2 1 322.3.12Knowledge of radiological 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 12.3.2.3.2.3.842.3.11Ability to control radiation releases.4.3 1Subtotal 2 1 22.4.02Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.4.5 1 202.4.14Knowledge of general guidelines for EOP usage.3.8 1 382.4.32Knowledge of operator response to loss of all annunciators.3.6 12.4.932.4.26Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.3.6 1 982.4.30Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.4.1 1Subtotal 3 2 10 7K/A #ES-401, Page 27 of 34Tier 3 Point Total3.      Radiation Control4. Emergency Procedures
/ Plan2. Equipment Control ROSRO-OnlyCategoryTopic1.
Conduct of Operations}}

Revision as of 01:48, 31 July 2018

2011 Dresden Nuclear Power Station Initial License Examination Outline Form Es 401-1 Rev 1 and Form Es 401-3 Rev 1
ML11363A124
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Site: Dresden  Constellation icon.png
Issue date: 03/29/2011
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ES-401BWR Examination OutlineFORM ES-401-1Facility Name: Dresden Date of Exam: 3/7/11 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G *TotalTotal 1 4 3 3 3 4 3 20 7 2 1 1 1 2 1 1 7 3Tier Totals 5 4 4 5 5 4 27 10 1 3 2 2 3 2 3 2 2 2 3 2 26 5 2 1 1 1 1 1 1 1 1 1 2 1 12 0 2 3Tier Totals 4 3 3 4 3 4 3 3 3 5 3 38 8 1 2 3 4 2 2 1 2Note: 1.Note: 2.Note: 3.Note: 4.Note: 5.Note: 6.Note: 7.*Note: 8.Note: 9.ES-401, Page 17 of 34 5 2Select 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.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 10 CFR 55.43.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.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.3. Generic Knowledge and Abilities Categories 1 2 3The 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.On the following pages, 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; 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.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 the elimination of inappropriate K/A statements.

4 2N/AN/ARO K/A Category Points 7 10Ensure 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).

3 2 4 3 A2 1 4 2 6 3The 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.

G*TierGroupSRO-Only Points2. Plant Systems1. Emergency & Abnormal Plant Evolutions 1 3 3 ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#17295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0

6Reactor power3.8 1 54295003 Partial or Complete Loss of AC / 6 0

4Electrical bus divisional separation3.1 1 7295004 Partial or Total Loss of DC Pwr / 6 0

3Reactor SCRAM: Plant-Specific3.1 1 21295005 Main Turbine Generator Trip / 3 04.49Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.4.6 1 25295006 SCRAM / 1 0 2Reactor water level control system3.8 1 59295016 Control Room Abandonment / 7 0

9Isolation/emergency condenser(s): Plant-Specific4.0 1 24295018 Partial or Total Loss of CCW / 8 02.12Knowledge of surveillance procedures.3.7 1 46295019 Partial or Total Loss of Inst. Air / 8 01.20Ability to interpret and execute procedure steps.4.6 1 31295021 Loss of Shutdown Cooling / 4 0

4Alternate heat removal methods3.7 1 41295023 Refueling Acc / 8 0

2Interlocks associated with fuel handling equipment3.4 1 61295024 High Drywell Pressure / 5 0

6Emergency generators3.7 1 29295025 High Reactor Pressure / 3 0

1Pressure effects on reactor power3.9 1 64295026 Suppression Pool High Water Temp. / 5 0 2Suppression pool level3.8 1295027 High Containment Temperature / 5Not Applicable To Dresden 0 19295028 High Drywell Temperature / 5 0

1Reactor water level measurement3.5 1 27295030 Low Suppression Pool Wtr Lvl / 5 0

1Emergency depressurization3.8 1 1295031 Reactor Low Water Level / 2 0

1Reactor water level4.6 1 67295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 1

3Alternate boron injection methods: Plant-Specific3.4 1 33295038 High Off-site Release Rate / 9 0

2Protection of the general public4.2 1 49600000 Plant Fire On Site / 8 0

6Need for pressurizing control room (recirculating mode)2.5 1 30 700000 Generator Voltage and Electric Grid Disturbances / 6 0

1Operating point on the generator capability curve3.5 1K/A Category Totals:

4 3 3 3 4 3 20Group Point Total:

ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#13295002 Loss of Main Condenser Vac / 3 0 8Condenser circulating water system3.1 1295007 High Reactor Pressure / 3 0 44295008 High Reactor Water Level / 2 0

1Reactor water level control: Plant-Specific3.7 1295009 Low Reactor Water Level / 2 0295010 High Drywell Pressure / 5 0295011 High Containment Temp / 5 0295012 High Drywell Temperature / 5 0 48295013 High Suppression Pool Temp. / 5 0

1Suppression pool cooling operation3.6 1 55295014 Inadvertent Reactivity Addition / 1 0

6Abnormal reactivity additions.3.8 1 47295015 Incomplete SCRAM / 1 0

5Rod worth minimizer: Plant-Specific2.5 1295017 High Off-site Release Rate / 9 0295020 Inadvertent Cont. Isolation / 5 & 7 0295022 Loss of CRD Pumps / 1 0 73295029 High Suppression Pool Wtr Lvl / 5 01.19Ability to use plant computers to evaluate system or component status.3.9 1295032 High Secondary Containment Area Temperature / 5 0 8295033 High Secondary Containment Area Radiation Levels / 9 0

1Area radiation levels3.8 1295034 Secondary Containment Ventilation High Radiation / 9 0295035 Secondary Containment High Differential Pressure / 5 0295036 Secondary Containment High Sump/Area Water Level / 5 0500000 High CTMT Hydrogen Conc. / 5 0K/A Category Totals:

1 1 1 2 1 1 7ES-401, Page 19 of 34Group Point Total:

ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (RO)

Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)

IR#34, 74203000 RHR/LPCI: Injection Mode 0 2 0 1Core cooling methods; Pumps3.5; 4.3 2 56205000 Shutdown Cooling 0

2SDC/RHR pump flow3.3 150, 5206000 HPCI 0

3 0 3Resetting turbine trips: BWR-2, 3, 4; Condensate storage tank level: BWR-2, 3, 44.2; 3.5 2 14207000 Isolation (Emergency) Condenser 04.31Knowledge of annunciator alarms, indications, or response procedures.4.2 1 53209001 LPCS 0 3Initiation logic 2.9 1209002 HPCSNot Applicable To Dresden 0 28211000 SLC 0

7Tank heater operation 2.7 1 52212000 RPS 0

1RPS motor-generator set failure 3.7 1 40215003 IRM 0

1RPS3.9 1 18215004 Source Range Monitor 0

3RPS status3.6 1 35215005 APRM / LPRM 0

3Inoperative trip (all causes)3.6 1217000 RCICNot Applicable To Dresden 0 36218000 ADS 0

1RHR/LPCI: Plant-Specific4.0 1 42223002 PCIS/Nuclear Steam Supply Shutoff 0 8Manual defeating of selected isolations during specified emergency conditions3.3 1 62239002 SRVs 0 1SRV solenoids 2.8 1 60259002 Reactor Water Level Control 0

1Reactor water level3.8 165, 10261000 SGTS 0

1 0 1Automatic system initiation; System flow3.7; 3.2 2 23262001 AC Electrical Distribution 01.30Ability to locate and operate components, including local controls.4.4 1 68262002 UPS (AC/DC) 0 3Static inverter2.7 1 71263000 DC Electrical Distribution 0

1A.C. electrical distribution3.2 1 72264000 EDGs 0

2Synchroscope3.4 170, 22300000 Instrument Air 0

2 1 2Service air; Breakers, relays and disconnects2.7; 2.9 29, 75400000 Component Cooling Water 0

1 0 1Loads cooled by CCWS; CCW indications and control2.9; 3.1 2 0K/A Category Totals:

3 2 2 3 2 3 2 2 2 3 2 26ES-401, Page 20 of 34Group Point Total:

ES-401-1 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (RO)

Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)

IR#57201001 CRD Hydraulic 0 2Scram valve solenoids3.6 1201002 RMCS 0 37201003 Control Rod and Drive Mechanism 0

1Stuck rod3.4 1201004 RSCS 0201005 RCIS 0201006 RWM 0 11202001 Recirculation 0

7Pump trips: Plant-Specific3.3 1202002 Recirculation Flow Control 0 63204000 RWCU 0

4Component cooling water systems2.9 1214000 RPIS 0 3215001 Traversing In-core Probe 0

3Isolation valves: Mark-I&II(Not-BWR1)3.0 1215002 RBM 0216000 Nuclear Boiler Inst.

0 51219000 RHR/LPCI: Torus/Pool Cooling Mode 1 0Prevention of leakage to the environment through system heat exchanger: Plant-Specific3.3 1 16223001 Primary CTMT and Aux.

1 1Temperature measurement2.7 1226001 RHR/LPCI: CTMT Spray Mode 0 66230000 RHR/LPCI: Torus/Pool Spray Mode 0

1Pumps3.7 1233000 Fuel Pool Cooling/Cleanup 0234000 Fuel Handling Equipment 0 39239001 Main and Reheat Steam 0

2Plant air systems 3.2 1239003 MSIV Leakage Control 0241000 Reactor/Turbine Pressure Regulator 0 45245000 Main Turbine Gen. / Aux.01.02Knowledge of operator responsibilities during all modes of plant operation.4.1 1256000 Reactor Condensate 0259001 Reactor Feedwater 0268000 Radwaste 0 43271000 Offgas 0 8System flow3.1 1272000 Radiation Monitoring 0286000 Fire Protection 0288000 Plant Ventilation 0290001 Secondary CTMT 0290003 Control Room HVAC 0 69290002 Reactor Vessel Internals 0

3Reactor power3.3 1 0K/A Category Totals:

1 1 1 1 1 1 1 1 1 2 112ES-401, Page 22 of 34Group Point Total:

ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#77295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 402.

25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.4.2 190295003 Partial or Complete Loss of AC / 6 0 5Whether a partial or complete loss of A.C. power has occurred4.2 1295004 Partial or Total Loss of DC Pwr / 6 0295005 Main Turbine Generator Trip / 3 092295006 SCRAM / 101.06Ability to manage the control room crew during plant transients.4.8 197295016 Control Room Abandonment / 7 0 2Reactor water level4.3 1295018 Partial or Total Loss of CCW / 8 0100295019 Partial or Total Loss of Inst. Air / 8 0

2Status of safety-related instrument air system loads (see AK2.1-AK2.19)3.7 1295021 Loss of Shutdown Cooling / 4 0295023 Refueling Acc / 8 0295024 High Drywell Pressure / 5 0295025 High Reactor Pressure / 3 087295026 Suppression Pool High Water Temp.

/ 501.14Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.3.1 1295027 High Containment Temperature / 5 0295028 High Drywell Temperature / 5 0295030 Low Suppression Pool Wtr Lvl / 5 0295031 Reactor Low Water Level / 2 079295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 0 1Reactor power4.3 1295038 High Off-site Release Rate / 9 0600000 Plant Fire On Site / 8 0700000 Generator Voltage and Electric Grid Disturbances / 6 0K/A Category Totals:

0 0 0 0 4 3 7Group Point Total:

ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295002 Loss of Main Condenser Vac / 3 0295007 High Reactor Pressure / 3 0295008 High Reactor Water Level / 2 094295009 Low Reactor Water Level / 2 0 2Steam flow/feedflow mismatch3.7 1295010 High Drywell Pressure / 5 0295011 High Containment Temp / 5 088295012 High Drywell Temperature / 5 0

1Drywell temperature3.9 1295013 High Suppression Pool Temp. / 5 0295014 Inadvertent Reactivity Addition / 1 0295015 Incomplete SCRAM / 1 0295017 High Off-site Release Rate / 9 0295020 Inadvertent Cont. Isolation / 5 & 7 089295022 Loss of CRD Pumps / 104.11Knowledge of abnormal condition procedures.4.2 1295029 High Suppression Pool Wtr Lvl / 5 0295032 High Secondary Containment Area Temperature / 5 0295033 High Secondary Containment Area Radiation Levels / 9 0295034 Secondary Containment Ventilation High Radiation / 9 0295035 Secondary Containment High Differential Pressure / 5 0295036 Secondary Containment High Sump/Area Water Level / 5 0500000 High CTMT Hydrogen Conc. / 5 0K/A Category Totals:

0 0 0 0 2 1 3ES-401, Page 19 of 34Group Point Total:

ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (SRO)

Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)

IR#203000 RHR/LPCI: Injection 081205000 Shutdown Cooling Mode 0 1Recirculation loop high temperature: Plant-Specific3.3 1206000 HPCI 083207000 Isolation (Emergency) Condenser04.06Knowledge of EOP mitigation strategies.4.7 1209001 LPCS 0209002 HPCS 096211000 SLC 0 2Failure of explosive valve to fire 3.9 1212000 RPS 0215003 IRM 0215004 Source Range Monitor 085215005 APRM / LPRM 0

7Recirculation flow channels flow mismatch3.4 1217000 RCIC 0218000 ADS 0223002 PCIS/Nuclear Steam Supply Shutoff 0239002 SRVs 0259002 Reactor Water Level Control 0261000 SGTS 0262001 AC Electrical Distribution 0262002 UPS (AC/DC) 080263000 DC Electrical Distribution01.32Ability to explain and apply system limits and precautions.4.0 1264000 EDGs 0300000 Instrument Air 0400000 Component Cooling Water 0 0K/A Category Totals:

0 0 0 0 0 0 0 3 0 0 2 5ES-401, Page 20 of 34Group Point Total:

ES-401 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (SRO)

Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)

IR#201001 CRD Hydraulic 0201002 RMCS 0201003 Control Rod and Drive Mechanism 0201004 RSCS 0201005 RCIS 0201006 RWM 0202001 Recirculation 0202002 Recirculation Flow Control 0204000 RWCU 099214000 RPIS 04.04Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.4.7 1215001 Traversing In-core Probe 0215002 RBM 0216000 Nuclear Boiler Inst.

0219000 RHR/LPCI: Torus/Pool Cooling Mode 0223001 Primary CTMT and Aux.

0226001 RHR/LPCI: CTMT Spray Mode 0230000 RHR/LPCI: Torus/Pool Spray Mode 091233000 Fuel Pool Cooling/Cleanup 0 9A.C. electrical power failures2.9 1234000 Fuel Handling Equipment 0239001 Main and Reheat Steam 0239003 MSIV Leakage Control 0241000 Reactor/Turbine Pressure Regulator 0245000 Main Turbine Gen. / Aux.

0256000 Reactor Condensate 076259001 Reactor Feedwater 0

1Pump trip3.7 1268000 Radwaste 0271000 Offgas 0272000 Radiation Monitoring 0286000 Fire Protection 0288000 Plant Ventilation 0290001 Secondary CTMT 0290003 Control Room HVAC 0290002 Reactor Vessel Internals 0 0K/A Category Totals:

0 0 0 0 0 0 0 2 0 0 1 3ES-401, Page 21 of 34Group Point Total:

ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3Facility Name:Dresden Date of Exam:3/7/11 Q#IR#IR#42.1.17Ability to make accurate, clear, and concise verbal reports.3.9 1 122.1.43Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.4.1 12.1.2.1.862.1.04Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.3.8 1 822.1.40Knowledge of refueling administrative requirements.3.9 1Subtotal 2 2 62.2.03Knowledge of the design, procedural, and operational differences between units.3.8 1 262.2.22Knowledge of limiting conditions for operations and safety limits.4.0 1 582.2.44Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.4.2 12.2.782.2.23Ability to track Technical Specification limiting conditions for operations.4.6 1 952.2.35Ability to determine Technical Specification Mode of Operation.4.5 1Subtotal 3 2 152.3.04Knowledge of radiation exposure limits under normal or emergency conditions.3.2 1 322.3.12Knowledge of radiological 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 12.3.2.3.2.3.842.3.11Ability to control radiation releases.4.3 1Subtotal 2 1 22.4.02Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.4.5 1 202.4.14Knowledge of general guidelines for EOP usage.3.8 1 382.4.32Knowledge of operator response to loss of all annunciators.3.6 12.4.932.4.26Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.3.6 1 982.4.30Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.4.1 1Subtotal 3 2 10 7K/A #ES-401, Page 27 of 34Tier 3 Point Total3. Radiation Control4. Emergency Procedures

/ Plan2. Equipment Control ROSRO-OnlyCategoryTopic1.

Conduct of Operations

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