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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.
{{#Wiki_filter:ES-401                                          BWR Examination Outline                                                          FORM ES-401-1 Facility Name: Dresden                               Date of Exam: 3/7/11 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 *
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).
: 1.              1          4    3    3                  3    4              3          20             4              3          7 Emergency &
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.
Abnormal            2           1   1   1       N/A        2   1     N/A    1           7             2              1          3 Plant Evolutions    Tier Totals        5   4   4                   5   5             4         27             6              4        10 1           3   2   2   3   2   3   2   2     2   3   2         26             3              2          5 2.
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)
Plant            2          1   1   1   1   1   1   1     1   1   2   1         12           0     2         1          3 Systems Tier Totals       4   3   3   4   3     4   3     3   3   5   3         38             5              3          8
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
: 3. Generic Knowledge and Abilities                1         2         3         4                         1      2     3      4 10                                        7 Categories                            2         3        2        3                        2      2      1     2 Note: 1.       Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
IR#17295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0
Note: 2.       The point total for each group and tier in the proposed outline must match that specified in the table.
6Reactor power3.8 1 54295003 Partial or Complete Loss of AC / 6 0
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.
4Electrical bus divisional separation3.1 1 7295004 Partial or Total Loss of DC Pwr / 6 0
Note: 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 the elimination of inappropriate K/A statements.
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
Note: 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.
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
Note: 5.       Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
4Alternate heat removal methods3.7 1 41295023 Refueling Acc / 8 0
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
2Interlocks associated with fuel handling equipment3.4 1 61295024 High Drywell Pressure / 5 0
Note: 6.       Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
6Emergency generators3.7 1 29295025 High Reactor Pressure / 3 0
Note: 7.*      The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
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
Note: 8.        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.
1Reactor water level measurement3.5 1 27295030 Low Suppression Pool Wtr Lvl / 5 0
Note: 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 10 CFR 55.43.
1Emergency depressurization3.8 1 1295031 Reactor Low Water Level / 2 0
ES-401, Page 17 of 34
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
ES-401                                                                2                                                        Form ES-401-1 ES-401                                                    BWR Examination Outline                                                        Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
2Protection of the general public4.2 1 49600000 Plant Fire On Site / 8 0
K  K    K  A    A Q#      E/APE # / Name / Safety Function                                  G                            K/A Topic(s)                            IR      #
6Need for pressurizing control room (recirculating mode)2.5 1 30 700000 Generator Voltage and Electric Grid Disturbances / 6 0
1  2    3   1   2 295001 Partial or Complete Loss of Forced          0 17                                                                          Reactor power                                                      3.8    1 Core Flow Circulation / 1 & 4                      6 0
1Operating point on the generator capability curve3.5 1K/A Category Totals:
54 295003 Partial or Complete Loss of AC / 6                                Electrical bus divisional separation                              3.1    1 4
4 3 3 3 4 3 20Group Point Total:
0 7 295004 Partial or Total Loss of DC Pwr / 6                                Reactor SCRAM: Plant-Specific                                      3.1    1 3
ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
Ability to perform without reference to procedures those actions 04.
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
21 295005 Main Turbine Generator Trip / 3                                   that require immediate operation of system components and          4.6    1 49  controls.
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
0 25 295006 SCRAM / 1                                                         Reactor water level control system                                3.8    1 2
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
0 59 295016 Control Room Abandonment / 7                                      Isolation/emergency condenser(s): Plant-Specific                  4.0    1 9
1Suppression pool cooling operation3.6 1 55295014 Inadvertent Reactivity Addition / 1 0
02.
6Abnormal reactivity additions.3.8 1 47295015 Incomplete SCRAM / 1 0
24 295018 Partial or Total Loss of CCW / 8                                   Knowledge of surveillance procedures.                              3.7    1 12 01.
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
46 295019 Partial or Total Loss of Inst. Air / 8                            Ability to interpret and execute procedure steps.                  4.6   1 20 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:
31 295021 Loss of Shutdown Cooling / 4                                      Alternate heat removal methods                                    3.7    1 4
1 1 1 2 1 1 7ES-401, Page 19 of 34Group Point Total:
0 41 295023 Refueling Acc / 8                                                  Interlocks associated with fuel handling equipment                3.4   1 2
ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (RO)
0 61 295024 High Drywell Pressure / 5                                          Emergency generators                                              3.7    1 6
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)
0 29 295025 High Reactor Pressure / 3                                          Pressure effects on reactor power                                  3.9    1 1
IR#34, 74203000 RHR/LPCI: Injection Mode 0 2 0 1Core cooling methods; Pumps3.5; 4.3 2 56205000 Shutdown Cooling 0
295026 Suppression Pool High Water                                0 64                                                                          Suppression pool level                                            3.8    1 Temp. / 5                                                        2 295027 High Containment Temperature / 5                                  Not Applicable To Dresden                                                0 0
2SDC/RHR pump flow3.3 150, 5206000 HPCI 0
19 295028 High Drywell Temperature / 5                                      Reactor water level measurement                                    3.5    1 1
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
0 27 295030 Low Suppression Pool Wtr Lvl / 5                                  Emergency depressurization                                        3.8   1 1
7Tank heater operation 2.7 1 52212000 RPS 0
0 1 295031 Reactor Low Water Level / 2                                        Reactor water level                                                4.6    1 1
1RPS motor-generator set failure 3.7 1 40215003 IRM 0
295037 SCRAM Condition Present            and 1
1RPS3.9 1 18215004 Source Range Monitor 0
67 Reactor Power Above APRM Downscale or                                    Alternate boron injection methods: Plant-Specific                  3.4    1 3
3RPS status3.6 1 35215005 APRM / LPRM 0
Unknown / 1 0
3Inoperative trip (all causes)3.6 1217000 RCICNot Applicable To Dresden 0 36218000 ADS 0
33 295038 High Off-site Release Rate / 9                                    Protection of the general public                                  4.2    1 2
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
0 49 600000 Plant Fire On Site / 8                                             Need for pressurizing control room (recirculating mode)            2.5    1 6
1Reactor water level3.8 165, 10261000 SGTS 0
700000 Generator Voltage and Electric Grid                        0 30                                                                          Operating point on the generator capability curve                  3.5    1 Disturbances / 6                                                 1 K/A Category Totals:                           4  3    3  3    4   3 Group Point Total:                                                        20
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
ES-401                                                              3                                                        Form ES-401-1 ES-401                                                  BWR Examination Outline                                                      Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
2Synchroscope3.4 170, 22300000 Instrument Air 0
K  K    K  A    A Q#      E/APE # / Name / Safety Function                              G                          K/A Topic(s)                            IR    #
2 1 2Service air; Breakers, relays and disconnects2.7; 2.9 29, 75400000 Component Cooling Water 0
1  2    3   1    2 0
1 0 1Loads cooled by CCWS; CCW indications and control2.9; 3.1 2 0K/A Category Totals:
13 295002 Loss of Main Condenser Vac / 3                                  Condenser circulating water system                              3.1    1 8
3 2 2 3 2 3 2 2 2 3 2 26ES-401, Page 20 of 34Group Point Total:
295007 High Reactor Pressure / 3                                                                                                              0 0
ES-401-1 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (RO)
44 295008 High Reactor Water Level / 2                                   Reactor water level control: Plant-Specific                      3.7    1 1
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)
295009 Low Reactor Water Level / 2                                                                                                            0 295010 High Drywell Pressure / 5                                                                                                              0 295011 High Containment Temp / 5                                                                                                              0 295012 High Drywell Temperature / 5                                                                                                            0 0
IR#57201001 CRD Hydraulic 0 2Scram valve solenoids3.6 1201002 RMCS 0 37201003 Control Rod and Drive Mechanism 0
48 295013 High Suppression Pool Temp. / 5                                 Suppression pool cooling operation                              3.6   1 1
1Stuck rod3.4 1201004 RSCS 0201005 RCIS 0201006 RWM 0 11202001 Recirculation 0
0 55 295014 Inadvertent Reactivity Addition / 1                             Abnormal reactivity additions.                                   3.8   1 6
7Pump trips: Plant-Specific3.3 1202002 Recirculation Flow Control 0 63204000 RWCU 0
0 47 295015 Incomplete SCRAM / 1                                           Rod worth minimizer: Plant-Specific                              2.5   1 5
4Component cooling water systems2.9 1214000 RPIS 0 3215001 Traversing In-core Probe 0
295017 High Off-site Release Rate / 9                                                                                                         0 295020 Inadvertent Cont. Isolation / 5 & 7                                                                                                     0 295022 Loss of CRD Pumps / 1                                                                                                                   0
3Isolation valves: Mark-I&II(Not-BWR1)3.0 1215002 RBM 0216000 Nuclear Boiler Inst.
: 01. Ability to use plant computers to evaluate system or component 73 295029 High Suppression Pool Wtr Lvl / 5                                                                                                3.9   1 19  status.
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.
295032 High Secondary Containment Area 0
1 1Temperature measurement2.7 1226001 RHR/LPCI: CTMT Spray Mode 0 66230000 RHR/LPCI: Torus/Pool Spray Mode 0
Temperature / 5 295033 High Secondary Containment Area                         0 8                                                                        Area radiation levels                                            3.8    1 Radiation Levels / 9                                           1 295034 Secondary Containment Ventilation 0
1Pumps3.7 1233000 Fuel Pool Cooling/Cleanup 0234000 Fuel Handling Equipment 0 39239001 Main and Reheat Steam 0
High Radiation / 9 295035 Secondary Containment High 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
Differential Pressure / 5 295036 Secondary Containment High 0
3Reactor power3.3 1 0K/A Category Totals:
Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5                                                                                                           0 K/A Category Totals:                         1   1   1   2   1   1 Group Point Total:                                                      7 ES-401, Page 19 of 34
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)
ES-401                                                         4                                                  Form ES-401-1 ES-401                                             BWR Examination Outline                                                  Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
K K K K K K A A A A Q#  System # / Name                                                G                          K/A Topic(s)                         IR     #
IR#77295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 402.
1 2 3 4 5 6 1 2 3 4 0              0                                                                    3.5; 34, 74 203000 RHR/LPCI: Injection Mode                                   Core cooling methods; Pumps                                        2 2              1                                                                    4.3 0
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
56  205000 Shutdown Cooling                                           SDC/RHR pump flow                                            3.3   1 2
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.
0     0                 Resetting turbine trips: BWR-2, 3, 4; Condensate storage   4.2; 50, 5 206000 HPCI                                                                                                                            2 3      3                  tank level: BWR-2, 3, 4                                      3.5 207000 Isolation (Emergency)                                 04. Knowledge of annunciator alarms, indications, or response 14                                                                                                                                  4.2   1 Condenser                                                    31  procedures.
/ 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 53  209001 LPCS                                                       Initiation logic                                             2.9   1 3
0 0 0 0 4 3 7Group Point Total:
209002 HPCS                                                        Not Applicable To Dresden                                           0 0
ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
28  211000 SLC                                                        Tank heater operation                                       2.7   1 7
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
0 52  212000 RPS                                                        RPS motor-generator set failure                             3.7   1 1
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
0 40  215003 IRM                                                         RPS                                                          3.9   1 1
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 18  215004 Source Range Monitor                                       RPS status                                                  3.6   1 3
0 0 0 0 2 1 3ES-401, Page 19 of 34Group Point Total:
0 35  215005 APRM / LPRM                                                 Inoperative trip (all causes)                               3.6   1 3
ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (SRO)
217000 RCIC                                                        Not Applicable To Dresden                                           0 0
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)
36  218000 ADS                                                        RHR/LPCI: Plant-Specific                                    4.0   1 1
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
223002 PCIS/Nuclear Steam Supply         0                         Manual defeating of selected isolations during specified 42                                                                                                                                  3.3   1 Shutoff                                  8                        emergency conditions 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:
62  239002 SRVs                                                       SRV solenoids                                               2.8   1 1
0 0 0 0 0 0 0 3 0 0 2 5ES-401, Page 20 of 34Group Point Total:
0 60  259002 Reactor Water Level Control                                 Reactor water level                                          3.8   1 1
ES-401 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (SRO)
0             0                                                                     3.7; 65, 10 261000 SGTS                                                        Automatic system initiation; System flow                            2 1              1                                                                      3.2
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)
: 01. Ability to locate and operate components, including local 23  262001 AC Electrical Distribution                                                                                              4.4   1 30  controls.
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.
0 68  262002 UPS (AC/DC)                                                 Static inverter                                              2.7   1 3
0219000 RHR/LPCI: Torus/Pool Cooling Mode 0223001 Primary CTMT and Aux.
0 71  263000 DC Electrical Distribution                                 A.C. electrical distribution                                3.2   1 1
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.
0 72  264000 EDGs                                                       Synchroscope                                                3.4    1 2
0256000 Reactor Condensate 076259001 Reactor Feedwater 0
0         1                                                                                2.7; 70, 22 300000 Instrument Air                                             Service air; Breakers, relays and disconnects                      2 2        2                                                                                  2.9 0                  0                                                                    2.9; 9, 75 400000 Component Cooling Water                                     Loads cooled by CCWS; CCW indications and control                  2 1                  1                                                                    3.1 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:
K/A Category Totals:               3 2 2 3 2 3 2   2   2 3   2 Group Point Total:                                                  26 ES-401, Page 20 of 34
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
ES-401-1                                                             5                                                    Form ES-401-1 ES-401                                                    BWR Examination Outline                                                  Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)
/ Plan2. Equipment Control ROSRO-OnlyCategoryTopic1.
K K K K K K   A   A A A Q# System # / Name                                                      G                          K/A Topic(s)                         IR   #
Conduct of Operations}}
1 2 3 4 5 6  1  2  3  4 0
57 201001 CRD Hydraulic                       2 Scram valve solenoids                                        3.6   1 201002 RMCS                                                                                                                                 0 0
37 201003 Control Rod and Drive Mechanism                     1 Stuck rod                                                    3.4   1 201004 RSCS                                                                                                                                 0 201005 RCIS                                                                                                                                 0 201006 RWM                                                                                                                                   0 0
11 202001 Recirculation                                          7 Pump trips: Plant-Specific                                    3.3   1 202002 Recirculation Flow Control                                                                                                           0 0
63 204000 RWCU                              4 Component cooling water systems                              2.9   1 214000 RPIS                                                                                                                                 0 0
3 215001 Traversing In-core Probe 3
Isolation valves: Mark-I&II(Not-BWR1)                         3.0   1 215002 RBM                                                                                                                                   0 216000 Nuclear Boiler Inst.                                                                                                                 0 219000 RHR/LPCI: Torus/Pool Cooling             1                       Prevention of leakage to the environment through system 51                                                                                                                                        3.3  1 Mode                                            0                        heat exchanger: Plant-Specific 1
16 223001 Primary CTMT and Aux.                     1 Temperature measurement                                      2.7   1 226001 RHR/LPCI: CTMT Spray Mode                                                                                                             0 0
66 230000 RHR/LPCI: Torus/Pool Spray Mode                           1 Pumps                                                        3.7   1 233000 Fuel Pool Cooling/Cleanup                                                                                                             0 234000 Fuel Handling Equipment                                                                                                               0 0
39 239001 Main and Reheat Steam                       2 Plant air systems                                             3.2   1 239003 MSIV Leakage Control                                                                                                                 0 241000 Reactor/Turbine Pressure Regulator                                                                                                   0
: 01. Knowledge of operator responsibilities during all modes of 45 245000 Main Turbine Gen. / Aux.                                                                                                       4.1   1 02 plant operation.
256000 Reactor Condensate                                                                                                                   0 259001 Reactor Feedwater                                                                                                                     0 268000 Radwaste                                                                                                                             0 0
43 271000 Offgas                                           8 System flow                                                  3.1   1 272000 Radiation Monitoring                                                                                                                 0 286000 Fire Protection                                                                                                                       0 288000 Plant Ventilation                                                                                                                     0 290001 Secondary CTMT                                                                                                                       0 290003 Control Room HVAC                                                                                                                     0 0
69 290002 Reactor Vessel Internals               3 Reactor power                                                3.3  1 0
K/A Category Totals:                     1 1 1 1 1 1 1   1 1 2   1 Group Point Total:                                                  12 ES-401, Page 22 of 34
 
ES-401                                                                 2                                                  Form ES-401-1 ES-401                                                    BWR Examination Outline                                                Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
K    K  K    A  A Q#       E/APE # / Name / Safety Function                                 G                        K/A Topic(s)                       IR     #
1    2    3  1    2 295001 Partial or Complete Loss of Forced                           02. Knowledge of the bases in Technical Specifications for 77                                                                                                                                      4.2    1 Core Flow Circulation / 1 & 4                                        25 limiting conditions for operations and safety limits.
0       Whether a partial or complete loss of A.C. power has 90 295003 Partial or Complete Loss of AC / 6                                                                                            4.2   1 5      occurred 295004 Partial or Total Loss of DC Pwr / 6                                                                                                 0 295005 Main Turbine Generator Trip / 3                                                                                                     0
: 01. Ability to manage the control room crew during plant 92 295006 SCRAM / 1                                                                                                                    4.8   1 06 transients.
0 97 295016 Control Room Abandonment / 7                                       Reactor water level                                      4.3   1 2
295018 Partial or Total Loss of CCW / 8                                                                                                   0 0      Status of safety-related instrument air system loads 100 295019 Partial or Total Loss of Inst. Air / 8                                                                                       3.7    1 2      (see AK2.1-AK2.19) 295021 Loss of Shutdown Cooling / 4                                                                                                       0 295023 Refueling Acc / 8                                                                                                                   0 295024 High Drywell Pressure / 5                                                                                                           0 295025 High Reactor Pressure / 3                                                                                                           0 Knowledge of criteria or conditions that require plant-295026 Suppression Pool High Water Temp.                            01.
87                                                                            wide announcements, such as pump starts, reactor         3.1    1
    /5                                                                  14 trips, mode changes, etc.
295027 High Containment Temperature / 5                                                                                                   0 295028 High Drywell Temperature / 5                                                                                                       0 295030 Low Suppression Pool Wtr Lvl / 5                                                                                                   0 295031 Reactor Low Water Level / 2                                                                                                         0 295037 SCRAM Condition Present 0
79 and Reactor Power Above APRM                                               Reactor power                                            4.3    1 1
Downscale or Unknown / 1 295038 High Off-site Release Rate / 9                                                                                                     0 600000 Plant Fire On Site / 8                                                                                                             0 700000 Generator Voltage and Electric Grid 0
Disturbances / 6 K/A Category Totals:                           0   0   0   0   4   3 Group Point Total:                                               7
 
ES-401                                                               3                                              Form ES-401-1 ES-401                                                   BWR Examination Outline                                        Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
K    K    K  A  A Q#       E/APE # / Name / Safety Function                               G                        K/A Topic(s)               IR     #
1    2    3  1    2 295002 Loss of Main Condenser Vac / 3                                                                                           0 295007 High Reactor Pressure / 3                                                                                                 0 295008 High Reactor Water Level / 2                                                                                             0 0
94 295009 Low Reactor Water Level / 2                                     Steam flow/feedflow mismatch                      3.7   1 2
295010 High Drywell Pressure / 5                                                                                                 0 295011 High Containment Temp / 5                                                                                                 0 0
88 295012 High Drywell Temperature / 5                                     Drywell temperature                              3.9   1 1
295013 High Suppression Pool Temp. / 5                                                                                           0 295014 Inadvertent Reactivity Addition / 1                                                                                       0 295015 Incomplete SCRAM / 1                                                                                                     0 295017 High Off-site Release Rate / 9                                                                                           0 295020 Inadvertent Cont. Isolation / 5 & 7                                                                                       0 04.
89 295022 Loss of CRD Pumps / 1                                            Knowledge of abnormal condition procedures.       4.2   1 11 295029 High Suppression Pool Wtr Lvl / 5                                                                                         0 295032 High Secondary Containment Area 0
Temperature / 5 295033 High Secondary Containment Area 0
Radiation Levels / 9 295034 Secondary Containment Ventilation 0
High Radiation / 9 295035 Secondary Containment High 0
Differential Pressure / 5 295036 Secondary Containment High 0
Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5                                                                                             0 K/A Category Totals:                         0   0   0   0   2   1 Group Point Total:                                      3 ES-401, Page 19 of 34
 
ES-401                                                         4                                                    Form ES-401-1 ES-401                                            BWR Examination Outline                                                    Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A A A A Q# System # / Name                                               G                        K/A Topic(s)                            IR    #
1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection                                                                                                             0 0
81 205000 Shutdown Cooling Mode                                     Recirculation loop high temperature: Plant-Specific          3.3   1 1
206000 HPCI                                                                                                                           0 207000 Isolation (Emergency)                                 04.
83                                                                  Knowledge of EOP mitigation strategies.                       4.7   1 Condenser                                                    06 209001 LPCS                                                                                                                           0 209002 HPCS                                                                                                                           0 0
96 211000 SLC                                                       Failure of explosive valve to fire                           3.9   1 2
212000 RPS                                                                                                                             0 215003 IRM                                                                                                                             0 215004 Source Range Monitor                                                                                                           0 0
85 215005 APRM / LPRM                                               Recirculation flow channels flow mismatch                    3.4   1 7
217000 RCIC                                                                                                                           0 218000 ADS                                                                                                                             0 223002 PCIS/Nuclear Steam Supply 0
Shutoff 239002 SRVs                                                                                                                           0 259002 Reactor Water Level Control                                                                                                     0 261000 SGTS                                                                                                                           0 262001 AC Electrical Distribution                                                                                                     0 262002 UPS (AC/DC)                                                                                                                     0 01.
80 263000 DC Electrical Distribution                                Ability to explain and apply system limits and precautions. 4.0   1 32 264000 EDGs                                                                                                                           0 300000 Instrument Air                                                                                                                 0 400000 Component Cooling Water                                                                                                         0 0
K/A Category Totals:               0 0 0 0 0 0 0   3 0 0   2 Group Point Total:                                                    5 ES-401, Page 20 of 34
 
ES-401                                                               5                                                      Form ES-401-1 ES-401                                                    BWR Examination Outline                                                      Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)
K K K K K K   A A   A A Q# System # / Name                                                      G                          K/A Topic(s)                             IR   #
1 2 3 4 5 6  1  2  3 4 201001 CRD Hydraulic                                                                                                                           0 201002 RMCS                                                                                                                                     0 201003 Control Rod and Drive Mechanism                                                                                                         0 201004 RSCS                                                                                                                                     0 201005 RCIS                                                                                                                                     0 201006 RWM                                                                                                                                     0 202001 Recirculation                                                                                                                           0 202002 Recirculation Flow Control                                                                                                               0 204000 RWCU                                                                                                                                     0 Ability to recognize abnormal indications for system operating 04.
99 214000 RPIS                                                              parameters that are entry-level conditions for emergency and     4.7  1 04 abnormal operating procedures.
215001 Traversing In-core Probe                                                                                                                 0 215002 RBM                                                                                                                                     0 216000 Nuclear Boiler Inst.                                                                                                                     0 219000 RHR/LPCI: Torus/Pool Cooling 0
Mode 223001 Primary CTMT and Aux.                                                                                                                   0 226001 RHR/LPCI: CTMT Spray Mode                                                                                                               0 230000 RHR/LPCI: Torus/Pool Spray Mode                                                                                                         0 0
91 233000 Fuel Pool Cooling/Cleanup                           9 A.C. electrical power failures                                  2.9   1 234000 Fuel Handling Equipment                                                                                                                 0 239001 Main and Reheat Steam                                                                                                                   0 239003 MSIV Leakage Control                                                                                                                     0 241000 Reactor/Turbine Pressure Regulator                                                                                                       0 245000 Main Turbine Gen. / Aux.                                                                                                                 0 256000 Reactor Condensate                                                                                                                       0 0
76 259001 Reactor Feedwater                                   1 Pump trip                                                        3.7   1 268000 Radwaste                                                                                                                                 0 271000 Offgas                                                                                                                                   0 272000 Radiation Monitoring                                                                                                                     0 286000 Fire Protection                                                                                                                         0 288000 Plant Ventilation                                                                                                                       0 290001 Secondary CTMT                                                                                                                           0 290003 Control Room HVAC                                                                                                                       0 290002 Reactor Vessel Internals                                                                                                                 0 0
K/A Category Totals:                     0 0 0 0 0 0   0 2   0 0   1 Group Point Total:                                                      3 ES-401, Page 21 of 34
 
ES-401                    Generic Knowledge and Abilities Outline (Tier 3)                                                     Form ES-401-3 Facility Name:Dresden             Date of Exam:3/7/11 RO      SRO-Only Category    K/A #                                              Topic Q#                                                                                                                     IR     #     IR   #
4              2.1. 17  Ability to make accurate, clear, and concise verbal reports.                                 3.9   1 Ability to use procedures to determine the effects on reactivity of plant changes, such as 12              2.1. 43  reactor coolant system temperature, secondary plant, fuel depletion, etc.                     4.1   1
: 1.           2.1.
Conduct of 2.1.
Operations            Knowledge of individual licensed operator responsibilities related to shift staffing, such as 86              2.1. 04  medical requirements, no-solo operation, maintenance of active license status,                           3.8    1 10CFR55, etc.
82              2.1. 40  Knowledge of refueling administrative requirements.                                                       3.9   1 Subtotal                                                                                                      2           2 6              2.2. 03  Knowledge of the design, procedural, and operational differences between units.               3.8   1 26              2.2. 22  Knowledge of limiting conditions for operations and safety limits.                           4.0   1 Ability to interpret control room indications to verify the status and operation of a system, 58 2.            2.2. 44  and understand how operator actions and directives affect plant and system conditions.       4.2   1 Equipment 2.2.
Control 78              2.2. 23  Ability to track Technical Specification limiting conditions for operations.                               4.6   1 95              2.2. 35  Ability to determine Technical Specification Mode of Operation.                                           4.5   1 Subtotal                                                                                                      3           2 15              2.3. 04  Knowledge of radiation exposure limits under normal or emergency conditions.                 3.2   1 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 32              2.3. 12  containment entry requirements, fuel handling responsibilities, access to locked high-       3.2    1 radiation areas, aligning filters, etc.
: 3.           2.3.
Radiation    2.3.
Control 2.3.
84              2.3. 11  Ability to control radiation releases.                                                                     4.3   1 Subtotal                                                                                                      2           1 Knowledge of system set points, interlocks and automatic actions associated with EOP 2              2.4. 02  entry conditions.                                                                             4.5   1 20              2.4. 14  Knowledge of general guidelines for EOP usage.                                               3.8   1 38 4.            2.4. 32  Knowledge of operator response to loss of all annunciators.                                   3.6   1 Emergency Procedures 2.4.
93 / Plan Knowledge of facility protection requirements, including fire brigade and portable fire 2.4. 26  fighting equipment usage.                                                                                 3.6   1 Knowledge of events related to system operation/status that must be reported to internal 98              2.4. 30  organizations or external agencies, such as the State, the NRC, or the transmission                       4.1    1 system operator.
Subtotal                                                                                                      3           2 Tier 3 Point Total                                                                                                          10           7 ES-401, Page 27 of 34}}

Latest revision as of 11:08, 12 November 2019

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
From:
NRC/RGN-III
To:
Exelon Generation Co
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ML11104A075 List:
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Download: ML11363A124 (10)
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ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Dresden Date of Exam: 3/7/11 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 4 3 3 3 4 3 20 4 3 7 Emergency &

Abnormal 2 1 1 1 N/A 2 1 N/A 1 7 2 1 3 Plant Evolutions Tier Totals 5 4 4 5 5 4 27 6 4 10 1 3 2 2 3 2 3 2 2 2 3 2 26 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

Note: 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.

Note: 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 the elimination of inappropriate K/A statements.

Note: 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.

Note: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

Note: 7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

Note: 8. 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.

Note: 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 10 CFR 55.43.

ES-401, Page 17 of 34

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

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced 0 17 Reactor power 3.8 1 Core Flow Circulation / 1 & 4 6 0

54 295003 Partial or Complete Loss of AC / 6 Electrical bus divisional separation 3.1 1 4

0 7 295004 Partial or Total Loss of DC Pwr / 6 Reactor SCRAM: Plant-Specific 3.1 1 3

Ability to perform without reference to procedures those actions 04.

21 295005 Main Turbine Generator Trip / 3 that require immediate operation of system components and 4.6 1 49 controls.

0 25 295006 SCRAM / 1 Reactor water level control system 3.8 1 2

0 59 295016 Control Room Abandonment / 7 Isolation/emergency condenser(s): Plant-Specific 4.0 1 9

02.

24 295018 Partial or Total Loss of CCW / 8 Knowledge of surveillance procedures. 3.7 1 12 01.

46 295019 Partial or Total Loss of Inst. Air / 8 Ability to interpret and execute procedure steps. 4.6 1 20 0

31 295021 Loss of Shutdown Cooling / 4 Alternate heat removal methods 3.7 1 4

0 41 295023 Refueling Acc / 8 Interlocks associated with fuel handling equipment 3.4 1 2

0 61 295024 High Drywell Pressure / 5 Emergency generators 3.7 1 6

0 29 295025 High Reactor Pressure / 3 Pressure effects on reactor power 3.9 1 1

295026 Suppression Pool High Water 0 64 Suppression pool level 3.8 1 Temp. / 5 2 295027 High Containment Temperature / 5 Not Applicable To Dresden 0 0

19 295028 High Drywell Temperature / 5 Reactor water level measurement 3.5 1 1

0 27 295030 Low Suppression Pool Wtr Lvl / 5 Emergency depressurization 3.8 1 1

0 1 295031 Reactor Low Water Level / 2 Reactor water level 4.6 1 1

295037 SCRAM Condition Present and 1

67 Reactor Power Above APRM Downscale or Alternate boron injection methods: Plant-Specific 3.4 1 3

Unknown / 1 0

33 295038 High Off-site Release Rate / 9 Protection of the general public 4.2 1 2

0 49 600000 Plant Fire On Site / 8 Need for pressurizing control room (recirculating mode) 2.5 1 6

700000 Generator Voltage and Electric Grid 0 30 Operating point on the generator capability curve 3.5 1 Disturbances / 6 1 K/A Category Totals: 4 3 3 3 4 3 Group Point Total: 20

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

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 0

13 295002 Loss of Main Condenser Vac / 3 Condenser circulating water system 3.1 1 8

295007 High Reactor Pressure / 3 0 0

44 295008 High Reactor Water Level / 2 Reactor water level control: Plant-Specific 3.7 1 1

295009 Low Reactor Water Level / 2 0 295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 295012 High Drywell Temperature / 5 0 0

48 295013 High Suppression Pool Temp. / 5 Suppression pool cooling operation 3.6 1 1

0 55 295014 Inadvertent Reactivity Addition / 1 Abnormal reactivity additions. 3.8 1 6

0 47 295015 Incomplete SCRAM / 1 Rod worth minimizer: Plant-Specific 2.5 1 5

295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 295022 Loss of CRD Pumps / 1 0

01. Ability to use plant computers to evaluate system or component 73 295029 High Suppression Pool Wtr Lvl / 5 3.9 1 19 status.

295032 High Secondary Containment Area 0

Temperature / 5 295033 High Secondary Containment Area 0 8 Area radiation levels 3.8 1 Radiation Levels / 9 1 295034 Secondary Containment Ventilation 0

High Radiation / 9 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 0

Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 1 1 1 2 1 1 Group Point Total: 7 ES-401, Page 19 of 34

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0 0 3.5; 34, 74 203000 RHR/LPCI: Injection Mode Core cooling methods; Pumps 2 2 1 4.3 0

56 205000 Shutdown Cooling SDC/RHR pump flow 3.3 1 2

0 0 Resetting turbine trips: BWR-2, 3, 4; Condensate storage 4.2; 50, 5 206000 HPCI 2 3 3 tank level: BWR-2, 3, 4 3.5 207000 Isolation (Emergency) 04. Knowledge of annunciator alarms, indications, or response 14 4.2 1 Condenser 31 procedures.

0 53 209001 LPCS Initiation logic 2.9 1 3

209002 HPCS Not Applicable To Dresden 0 0

28 211000 SLC Tank heater operation 2.7 1 7

0 52 212000 RPS RPS motor-generator set failure 3.7 1 1

0 40 215003 IRM RPS 3.9 1 1

0 18 215004 Source Range Monitor RPS status 3.6 1 3

0 35 215005 APRM / LPRM Inoperative trip (all causes) 3.6 1 3

217000 RCIC Not Applicable To Dresden 0 0

36 218000 ADS RHR/LPCI: Plant-Specific 4.0 1 1

223002 PCIS/Nuclear Steam Supply 0 Manual defeating of selected isolations during specified 42 3.3 1 Shutoff 8 emergency conditions 0

62 239002 SRVs SRV solenoids 2.8 1 1

0 60 259002 Reactor Water Level Control Reactor water level 3.8 1 1

0 0 3.7; 65, 10 261000 SGTS Automatic system initiation; System flow 2 1 1 3.2

01. Ability to locate and operate components, including local 23 262001 AC Electrical Distribution 4.4 1 30 controls.

0 68 262002 UPS (AC/DC) Static inverter 2.7 1 3

0 71 263000 DC Electrical Distribution A.C. electrical distribution 3.2 1 1

0 72 264000 EDGs Synchroscope 3.4 1 2

0 1 2.7; 70, 22 300000 Instrument Air Service air; Breakers, relays and disconnects 2 2 2 2.9 0 0 2.9; 9, 75 400000 Component Cooling Water Loads cooled by CCWS; CCW indications and control 2 1 1 3.1 0

K/A Category Totals: 3 2 2 3 2 3 2 2 2 3 2 Group Point Total: 26 ES-401, Page 20 of 34

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0

57 201001 CRD Hydraulic 2 Scram valve solenoids 3.6 1 201002 RMCS 0 0

37 201003 Control Rod and Drive Mechanism 1 Stuck rod 3.4 1 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 0

11 202001 Recirculation 7 Pump trips: Plant-Specific 3.3 1 202002 Recirculation Flow Control 0 0

63 204000 RWCU 4 Component cooling water systems 2.9 1 214000 RPIS 0 0

3 215001 Traversing In-core Probe 3

Isolation valves: Mark-I&II(Not-BWR1) 3.0 1 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 1 Prevention of leakage to the environment through system 51 3.3 1 Mode 0 heat exchanger: Plant-Specific 1

16 223001 Primary CTMT and Aux. 1 Temperature measurement 2.7 1 226001 RHR/LPCI: CTMT Spray Mode 0 0

66 230000 RHR/LPCI: Torus/Pool Spray Mode 1 Pumps 3.7 1 233000 Fuel Pool Cooling/Cleanup 0 234000 Fuel Handling Equipment 0 0

39 239001 Main and Reheat Steam 2 Plant air systems 3.2 1 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0

01. Knowledge of operator responsibilities during all modes of 45 245000 Main Turbine Gen. / Aux. 4.1 1 02 plant operation.

256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 0

43 271000 Offgas 8 System flow 3.1 1 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 290001 Secondary CTMT 0 290003 Control Room HVAC 0 0

69 290002 Reactor Vessel Internals 3 Reactor power 3.3 1 0

K/A Category Totals: 1 1 1 1 1 1 1 1 1 2 1 Group Point Total: 12 ES-401, Page 22 of 34

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

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced 02. Knowledge of the bases in Technical Specifications for 77 4.2 1 Core Flow Circulation / 1 & 4 25 limiting conditions for operations and safety limits.

0 Whether a partial or complete loss of A.C. power has 90 295003 Partial or Complete Loss of AC / 6 4.2 1 5 occurred 295004 Partial or Total Loss of DC Pwr / 6 0 295005 Main Turbine Generator Trip / 3 0

01. Ability to manage the control room crew during plant 92 295006 SCRAM / 1 4.8 1 06 transients.

0 97 295016 Control Room Abandonment / 7 Reactor water level 4.3 1 2

295018 Partial or Total Loss of CCW / 8 0 0 Status of safety-related instrument air system loads 100 295019 Partial or Total Loss of Inst. Air / 8 3.7 1 2 (see AK2.1-AK2.19) 295021 Loss of Shutdown Cooling / 4 0 295023 Refueling Acc / 8 0 295024 High Drywell Pressure / 5 0 295025 High Reactor Pressure / 3 0 Knowledge of criteria or conditions that require plant-295026 Suppression Pool High Water Temp. 01.

87 wide announcements, such as pump starts, reactor 3.1 1

/5 14 trips, mode changes, etc.

295027 High Containment Temperature / 5 0 295028 High Drywell Temperature / 5 0 295030 Low Suppression Pool Wtr Lvl / 5 0 295031 Reactor Low Water Level / 2 0 295037 SCRAM Condition Present 0

79 and Reactor Power Above APRM Reactor power 4.3 1 1

Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 0 600000 Plant Fire On Site / 8 0 700000 Generator Voltage and Electric Grid 0

Disturbances / 6 K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7

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

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 0 295007 High Reactor Pressure / 3 0 295008 High Reactor Water Level / 2 0 0

94 295009 Low Reactor Water Level / 2 Steam flow/feedflow mismatch 3.7 1 2

295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 0

88 295012 High Drywell Temperature / 5 Drywell temperature 3.9 1 1

295013 High Suppression Pool Temp. / 5 0 295014 Inadvertent Reactivity Addition / 1 0 295015 Incomplete SCRAM / 1 0 295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 04.

89 295022 Loss of CRD Pumps / 1 Knowledge of abnormal condition procedures. 4.2 1 11 295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0

Temperature / 5 295033 High Secondary Containment Area 0

Radiation Levels / 9 295034 Secondary Containment Ventilation 0

High Radiation / 9 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 0

Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 0 0 0 0 2 1 Group Point Total: 3 ES-401, Page 19 of 34

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection 0 0

81 205000 Shutdown Cooling Mode Recirculation loop high temperature: Plant-Specific 3.3 1 1

206000 HPCI 0 207000 Isolation (Emergency) 04.

83 Knowledge of EOP mitigation strategies. 4.7 1 Condenser 06 209001 LPCS 0 209002 HPCS 0 0

96 211000 SLC Failure of explosive valve to fire 3.9 1 2

212000 RPS 0 215003 IRM 0 215004 Source Range Monitor 0 0

85 215005 APRM / LPRM Recirculation flow channels flow mismatch 3.4 1 7

217000 RCIC 0 218000 ADS 0 223002 PCIS/Nuclear Steam Supply 0

Shutoff 239002 SRVs 0 259002 Reactor Water Level Control 0 261000 SGTS 0 262001 AC Electrical Distribution 0 262002 UPS (AC/DC) 0 01.

80 263000 DC Electrical Distribution Ability to explain and apply system limits and precautions. 4.0 1 32 264000 EDGs 0 300000 Instrument Air 0 400000 Component Cooling Water 0 0

K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 20 of 34

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 0 201002 RMCS 0 201003 Control Rod and Drive Mechanism 0 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 202001 Recirculation 0 202002 Recirculation Flow Control 0 204000 RWCU 0 Ability to recognize abnormal indications for system operating 04.

99 214000 RPIS parameters that are entry-level conditions for emergency and 4.7 1 04 abnormal operating procedures.

215001 Traversing In-core Probe 0 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 0

Mode 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 0

91 233000 Fuel Pool Cooling/Cleanup 9 A.C. electrical power failures 2.9 1 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 0

76 259001 Reactor Feedwater 1 Pump trip 3.7 1 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 290001 Secondary CTMT 0 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 0

K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 21 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Dresden Date of Exam:3/7/11 RO SRO-Only Category K/A # Topic Q# IR # IR #

4 2.1. 17 Ability to make accurate, clear, and concise verbal reports. 3.9 1 Ability to use procedures to determine the effects on reactivity of plant changes, such as 12 2.1. 43 reactor coolant system temperature, secondary plant, fuel depletion, etc. 4.1 1

1. 2.1.

Conduct of 2.1.

Operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as 86 2.1. 04 medical requirements, no-solo operation, maintenance of active license status, 3.8 1 10CFR55, etc.

82 2.1. 40 Knowledge of refueling administrative requirements. 3.9 1 Subtotal 2 2 6 2.2. 03 Knowledge of the design, procedural, and operational differences between units. 3.8 1 26 2.2. 22 Knowledge of limiting conditions for operations and safety limits. 4.0 1 Ability to interpret control room indications to verify the status and operation of a system, 58 2. 2.2. 44 and understand how operator actions and directives affect plant and system conditions. 4.2 1 Equipment 2.2.

Control 78 2.2. 23 Ability to track Technical Specification limiting conditions for operations. 4.6 1 95 2.2. 35 Ability to determine Technical Specification Mode of Operation. 4.5 1 Subtotal 3 2 15 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 1 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 32 2.3. 12 containment entry requirements, fuel handling responsibilities, access to locked high- 3.2 1 radiation areas, aligning filters, etc.

3. 2.3.

Radiation 2.3.

Control 2.3.

84 2.3. 11 Ability to control radiation releases. 4.3 1 Subtotal 2 1 Knowledge of system set points, interlocks and automatic actions associated with EOP 2 2.4. 02 entry conditions. 4.5 1 20 2.4. 14 Knowledge of general guidelines for EOP usage. 3.8 1 38 4. 2.4. 32 Knowledge of operator response to loss of all annunciators. 3.6 1 Emergency Procedures 2.4.

93 / Plan Knowledge of facility protection requirements, including fire brigade and portable fire 2.4. 26 fighting equipment usage. 3.6 1 Knowledge of events related to system operation/status that must be reported to internal 98 2.4. 30 organizations or external agencies, such as the State, the NRC, or the transmission 4.1 1 system operator.

Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 27 of 34

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