ML12285A291: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(3 intermediate revisions by the same user not shown)
Line 9: Line 9:
| docket = 05000368
| docket = 05000368
| license number =  
| license number =  
| contact person = Osterholtz C O
| contact person = Osterholtz C
| document type = License-Operator, Part 55 Examination Related Material
| document type = License-Operator, Part 55 Examination Related Material
| page count = 22
| page count = 22
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:Revision 0ES-301Administrative Topics OutlineForm ES-301-1Facility:   Arkansas Nuclear One Unit 2Date of Examination: 08/27/2012Examination Level:   RO X       SROOperating Test Number:   2012-1Administrative Topic (see Note)Type Code*Describe activity to be performedA1. Conduct of Operations2.1.25 RO (3.9)D/P/RDetermine any limits for CEA positions using the COLRPDILANO-2-JPM-NRC-ADMIN-PDILA2. Conduct of Operations2.1.23 RO (4.3)D/RCalculate Time to Boil using computer programANO-2-JPM-NRC-ADMIN-TTBCROA3. Equipment Control2.2.42 RO (3.9)D/RReview 2P-89B surveillance to determine operabilityANO-2-JPM-NRC-ADMIN-2P89BSURVA4. Radiation Control2.3.4 RO (3.2)N/RCalculate expected dose for Re-entry during emergencyand if applicable limits will be exceededANO-2-JPM-NRC-ADMIN-EMGRESPEmergency Procedures/PlanNOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)
{{#Wiki_filter:ES-301                              Administrative Topics Outline                            Form ES-301-1 Facility: Arkansas Nuclear One Unit 2                              Date of Examination: 08/27/2012 Examination Level: RO X           SRO                              Operating Test Number:     2012-1 Administrative Topic           Type                   Describe activity to be performed (see Note)               Code*
ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:ANO Unit 2                            Date of Exam:6/24/2012 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G*Total Total 1 333 33 3 18 6 2 112 22 1 9 4Tier  Totals445 55 4 27 10 1 23233332313 28 5 2 11111111011 10 0 1 3Tier  Totals34344443324 38 8 1 2 3 4 2 2 1 2 Note:   1.
Determine any limits for CEA positions using the COLR PDIL A1. Conduct of Operations            D/P/R ANO-2-JPM-NRC-ADMIN-PDIL 2.1.25 RO (3.9)
Note: 2.Note: 3.Note: 4.Note: 5.Note: 6.Note: 7.*Note: 8.Note: 9.ES-401, 21 of 33 2.Plant Systems 2 5 SRO-Only Points RO K/A Category Points A2 G*1. Emergency
Calculate Time to Boil using computer program A2. Conduct of Operations              D/R ANO-2-JPM-NRC-ADMIN-TTBCRO 2.1.23 RO (4.3)
&Abnormal Plant Evolutions Tier Group 3 N/A N/A 3 2 5For 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.
Review 2P-89B surveillance to determine operability A3. Equipment Control                  D/R      ANO-2-JPM-NRC-ADMIN-2P89BSURV 2.2.42 RO (3.9)
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Calculate expected dose for Re-entry during emergency and if applicable limits will be exceeded A4. Radiation Control                  N/R ANO-2-JPM-NRC-ADMIN-EMGRESP 2.3.4 RO (3.2)
Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:         (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
Revision 0
 
ES-401                                         PWR Examination Outline                                                             FORM ES-401-2 Facility Name:ANO Unit 2                            Date of Exam:6/24/2012 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. Emergency          1          3    3    3                    3    3             3          18             3              3          6 Abnormal            2          1    1    2      N/A          2    2     N/A    1           9             2              2          4 Plant Evolutions                                                                                                    5              5 Tier Totals 4          4    5                    5    5              4         27                                       10 1           2    3    2    3    3    3    3    2    3  1    3          28             2              3          5 2.
2          1    1    1    1    1    1    1    1    0  1    1          10         0       1           2          3 Plant Systems Tier Totals 3          4    3    4    4    4    4    3    3  2    4          38             3              5          8 1         2          3        4                        1      2       3     4
: 3. Generic Knowledge and            Abilities 10                                        7 Categories 2          2          3        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.
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.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: 6.      Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
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: 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.
3 2 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: 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.
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: 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.
3 2 4 2 2 3. Generic Knowledge and      Abilities Categories 10 3 2 5 1 3 3 7 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.
ES-401, 21 of 33
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.
ES-401                                                                  2                                                               Form ES-401-2 ES-401                                                        PWR Examination Outline                                                              Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
K  K  K  A  A E/APE # / Name / Safety Function                                G                              K/A Topic(s)                                  IR    #
E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)
1  2  3  1   2 0                      Reasons for closing the main turbine governor valve and the main 000007 Reactor Trip / 1                                                                                                                              3.7 3                      turbine stop valve after a reactor trip 1
IR#000007 Reactor Trip / 1 0 3Reasons for closing the main turbine governor valve and the main turbine stop valve after a reactor trip 3.7 CE/E02 Reactor Trip Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 0 6Control of PZR level 3.6 1 000009 Small Break LOCA / 3 3 3RCS water inventory balance and Tech-Spec limits 3.3 1 000011 Large Break LOCA / 3 0 8Flowpath for sump recirculation 3.9 1 000015 RCP Malfunctions / 4 000017 RCP Malfunctions (Loss of RC Flow) / 4 0 1Natural circulation in a nuclear reactor power plant 4.4 1 000022 Loss of Rx Coolant Makeup / 2 0 6CVCS charging pump ammeters and running indicators 2.9 1 000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 02.44Ability to interpret control room indications to verify the status andoperation of a system, and understand how operator actions anddirectives affect plant and system conditions.
CE/E02 Reactor Trip Recovery / 1 0
4.2 1 000027 Pressurizer Pressure Control System Malfunction / 3 0 000029 ATWS / 1 0 5definition of negative temperature coefficient as applied to large PWR coolant systems 2.8 1 000038 Steam Gen. Tube Rupture / 3 0 8Criteria for securing RCP 4.1 1 000040 Steam Line Rupture / 4 0 2 Sensors and detectors 2.6 CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 CE/E06 Loss of Feedwater / 4 0 2Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, andrelations between the proper operation of these systems to the
000008 Pressurizer Vapor Space Accident / 3                                Control of PZR level                                                      3.6    1 6
3 000009 Small Break LOCA / 3                                                RCS water inventory balance and Tech-Spec limits                          3.3    1 3
0 000011 Large Break LOCA / 3                                                 Flowpath for sump recirculation                                          3.9    1 8
000015 RCP Malfunctions / 4                        0 Natural circulation in a nuclear reactor power plant                      4.4    1 000017 RCP Malfunctions (Loss of RC Flow) / 4      1 0
000022 Loss of Rx Coolant Makeup / 2                                        CVCS charging pump ammeters and running indicators                        2.9    1 6
000025 Loss of RHR System / 4                                                                                                                                0 Ability to interpret control room indications to verify the status and 02.
000026 Loss of Component Cooling Water / 8                                  operation of a system, and understand how operator actions and            4.2    1 44  directives affect plant and system conditions.
000027 Pressurizer Pressure Control System 0
Malfunction / 3 0                       definition of negative temperature coefficient as applied to large 000029 ATWS / 1                                                                                                                                      2.8    1 5                      PWR coolant systems 0
000038 Steam Gen. Tube Rupture / 3                                          Criteria for securing RCP                                                4.1    1 8
0 000040 Steam Line Rupture / 4                                              Sensors and detectors                                                    2.6 2
1 CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 1
Facilitys heat removal systems, including primary coolant, 0
CE/E06 Loss of Feedwater / 4                                                emergency coolant, the decay heat removal systems, and                   3.5 2                   relations between the proper operation of these systems to the 0
000055 Station Blackout / 6                                                Existing valve positioning on a loss of instrument air system            3.4    1 1
04.
000056 Loss of Off-site Power / 6                                          Ability to identify post-accident instrumentation.                       3.7    1 03 2      Interlocks in effect on loss of ac vital electrical instrument bus that 000057 Loss of Vital AC Inst. Bus / 6                                                                                                                3.6    1 0       must be bypassed to restore normal equipment operation
: 04. Knowledge of system set points, interlocks and automatic actions 000058 Loss of DC Power / 6                                                                                                                          4.5    1 02  associated with EOP entry conditions.
0              Effect on the nuclear service water discharge flow header of a 000062 Loss of Nuclear Svc Water / 4                                                                                                                  3.5    1 4              loss of CCW 0          Restoration of systems served by instrument air when pressure is 000065 Loss of Instrument Air / 8                                                                                                                    2.9    1 3          regained 000077 Generator Voltage and Electric                  0 Breakers, relays                                                          3.1    1 Grid Disturbances / 6                                  2 K/A Category Totals:                                3  3  3  3  3    3 Group Point Total:                                                                18 ES-401, 22 of 33
 
ES-401                                                                  3                                                          Form ES-401-2 ES-401                                                      PWR Examination Outline                                                    Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
K    K    K  A    A E/APE # / Name / Safety Function                                  G                            K/A Topic(s)                        IR    #
1  2    3  1    2 000001 Continuous Rod Withdrawal / 1                                                                                                            0 000003 Dropped Control Rod / 1                                    02      Signal inputs to rod control system                            2.7    1
: 04. Knowledge of the operational implications of EOP warnings, 000005 Inoperable/Stuck Control Rod / 1 cautions, and notes.
3.8    1 20 000024 Emergency Boration / 1                  02                        Relationship between boron addition and reactor power          3.6    1 000028 Pressurizer Level Malfunction / 2                    02            CVCS                                                          3.4    1 000032 Loss of Source Range NI / 7                          01            Manual restoration of power                                    3.1    1 000033 Loss of Intermediate Range NI / 7                                                                                                        0 000036 Fuel Handling Accident / 8                                                                                                                0 000037 Steam Generator Tube Leak / 3                    08                Criteria for securing RCP                                      4.1    1 000051 Loss of Condenser Vacuum / 4                                                                                                              0 000059 Accidental Liquid RadWaste Rel. / 9                                                                                                      0 000060 Accidental Gaseous Radwaste Rel. / 9                                                                                                      0 000061 ARM System Alarms / 7                                                                                                                    0 Vital equipment and control systems to be maintained and 000067 Plant Fire On-site / 9 8                                  16      operated during a fire 3.3    1 000068 Control Room Evac. / 8                      02                    Reactor trip system                                            3.7    1 000069 Loss of CTMT Integrity / 5                                                                                                                0 000074 Inad. Core Cooling / 4                                                                                                                    0 000076 High Reactor Coolant Activity / 9                06                Actions contained in EOP for high reactor coolant activity    3.2    1 CE/A13 Natural Circ. / 4                                                                                                                        0 CE/A11 RCS Overcooling / 4                                                                                                                      0 CE/A16 Excess RCS Leakage / 2                                                                                                                    0 CE/E09 Functional Recovery                                                                                                                      0 0
0 0
0 0
0 0
0 0
K/A Category Totals:                            1  1    2  2    2    1 Group Point Total:                                                    9 ES-401, 23 of 33
 
ES-401                                                        4                                                        Form ES-401-2 ES-401                                            PWR Examination Outline                                                      Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
K K K K K K A A A A System # / Name                                                G                            K/A Topic(s)                            IR    #
1 2 3 4 5 6 1 2 3 4 0
003 Reactor Coolant Pump                                          S/G                                                            3.5    1 2
01.
004 Chemical and Volume Control                                    Knowledge of system purpose and/or function.                    3.9    1 27 0  0                        RHR pumps; System protection logics, including high-005 Residual Heat Removal                                          pressure interlock, reset controls, and valve interlocks 3; 3.2  2 1  7 0
006 Emergency Core Cooling                                        ESFAS-operated valves                                          3.6    1 4
0 007 Pressurizer Relief/Quench Tank                                Method of forming a steam bubble in the PZR                    3.1    1 2
0            01. CCW temperature; Knowledge of the purpose and function          2.9; 008 Component Cooling Water                                        of major system components and controls.
2 2            28                                                                  4.1 0 0                    Constant enthalpy expansion through a valve; Pressure          2.6; 010 Pressurizer Pressure Control                                  detection systems 2
2 1                                                                                    2.7 0
012 Reactor Protection                                            RPS channels, components, and interconnections                  3.3    1 1
013 Engineered Safety Features              0 Sensors and detectors                                          2.7    1 Actuation                                    1 0
022 Containment Cooling                                            Initiation of safeguards mode of operation                      4.1    1 1
025 Ice Condenser                                                                                                                        0 Ability to interpret control room indications to verify the 02.
026 Containment Spray                                              status and operation of a system, and understand how            4.2    1 44  operator actions and directives affect plant and system Utilization of steam pressure program control when steam 0
039 Main and Reheat Steam                                          dumping through atmospheric relief/dump valves, including      2.9    1 4                        T-ave. limits 1
059 Main Feedwater                                                Failure of feedwater control system                            3.0    1 1
0 061 Auxiliary/Emergency Feedwater                                  Pumps                                                          2.6    1 2
0 062 AC Electrical Distribution                                    Synchronizing and paralleling of different ac supplies          3.1    1 7
0    0          Battery capacity as it is affected by discharge rate; Meters,  2.5; 063 DC Electrical Distribution                                    annunciators, dials, recorders, and indicating lights 2
1    1                                                                          2.7 0
064 Emergency Diesel Generator                                    ED/G lube oil temperature and pressure                          3.0    1 1
0        0              Radiation theory, including sources, types, units, and          2.5; 073 Process Radiation Monitoring                                  effects; Erratic or failed power supply 2
1        1                                                                              2.5 RHR components, controls, sensors, indicators, and alarms, 0 0 076 Service Water                                                  including rad monitors; Automatic start features associated    3; 2.9  2 5 2                        with SWS pump controls 0                    0                                                                          3.4; 078 Instrument Air                                                MSIV air; Air pressure                                                  2 5                    1                                                                          3.1 0
103 Containment                                                    CCS                                                            3.6    1 1
K/A Category Totals:              2 3 2 3 3 3  3  2  3 1    3 Group Point Total:                                                      28 ES-401, 24 of 33
 
ES-401                                                              5                                                      Form ES-401-2 ES-401                                                  PWR Examination Outline                                                    Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
K K K K K K  A  A  A  A System # / Name                                                      G                        K/A Topic(s)                            IR    #
1 2 3 4 5 6  1  2  3  4 001 Control Rod Drive                                                                                                                          0 1                    Relationship between effects of the primary coolant system and 002 Reactor Coolant 1                    the secondary coolant system 4.0    1 011 Pressurizer Level Control                                                                                                                  0 014 Rod Position Indication                                                                                                                    0 0
015 Nuclear Instrumentation 1
NIS channels, components, and interconnections                  3.3    1 016 Non-nuclear Instrumentation                                                                                                                0 0
017 In-core Temperature Monitor 1
Sensors and detectors                                          2.7    1 027 Containment Iodine Removal                                                                                                                0 028 Hydrogen Recombiner and Purge Control                                                                                                      0 029 Containment Purge                                                                                                                          0 0
033 Spent Fuel Pool Cooling 3
Spent fuel temperature                                          3.0    1 034 Fuel Handling Equipment                                                                                                                    0 0      Recognition that increasing radiation levels in secondary 035 Steam Generator 8      systems may mean leaking and possibly ruptured S/G tubes 4.1    1 0
041 Steam Dump/Turbine Bypass Control 2
Steam pressure                                                  3.1    1 045 Main Turbine Generator                                                                                                                    0 0
055 Condenser Air Removal 6
PRM system                                                      2.6    1 056 Condensate                                                                                                                                0 068 Liquid Radwaste                                                                                                                            0
: 01. Knowledge of the purpose and function of major system 071 Waste Gas Disposal                                                                                                                  4.1    1 28 components and controls.
0 072 Area Radiation Monitoring 2
Detector failure                                                2.8    1 0
075 Circulating Water 1
Heat sink                                                      2.5    1 079 Station Air                                                                                                                                0 086 Fire Protection                                                                                                                            0 K/A Category Totals:                      1 1 1 1 1 1  1  1  0  1  1 Group Point Total:                                                    10 ES-401, 25 of 33
 
ES-401                                                                  2                                                            Form ES-401-2 ES-401                                                        PWR Examination Outline                                                          Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
K  K  K  A  A E/APE # / Name / Safety Function                                G                            K/A Topic(s)                              IR    #
1  2  3  1  2 0      Proper actions to be taken if the automatic safety functions have 000007 Reactor Trip / 1                                                                                                                          4.6 2      not taken place 1
CE/E02 Reactor Trip Recovery / 1 000008 Pressurizer Vapor Space Accident / 3                                                                                                            0 000009 Small Break LOCA / 3                                                                                                                            0 000011 Large Break LOCA / 3                                                                                                                            0 000015 RCP Malfunctions / 4 0
000017 RCP Malfunctions (Loss of RC Flow) / 4 Ability to analyze the effect of maintenance activities, such as 02.
000022 Loss of Rx Coolant Makeup / 2                                        degraded power sources, on the status of limiting conditions for    4.2    1 36  operations.
000025 Loss of RHR System / 4                                                                                                                          0 000026 Loss of Component Cooling Water / 8                                                                                                              0 000027 Pressurizer Pressure Control System                          0 Tech-Spec limits for RCS pressure                                    4.3    1 Malfunction / 3                                                    4 000029 ATWS / 1                                                                                                                                        0 000038 Steam Gen. Tube Rupture / 3                                                                                                                      0 000040 Steam Line Rupture / 4 0
CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 0
CE/E06 Loss of Feedwater / 4 000055 Station Blackout / 6                                                                                                                            0 000056 Loss of Off-site Power / 6                                                                                                                      0 000057 Loss of Vital AC Inst. Bus / 6                                                                                                                  0
: 04. Ability to diagnose and recognize trends in an accurate and timely 000058 Loss of DC Power / 6                                                                                                                      4.2    1 47  manner utilizing the appropriate control room reference material.
0      The normal values for SWS-header flow rate and the flow rates to 000062 Loss of Nuclear Svc Water / 4                                                                                                            2.5    1 5      the components cooled by the SWS
: 02. Ability to recognize system parameters that are entry-level 000065 Loss of Instrument Air / 8                                                                                                                4.6    1 42  conditions for Technical Specifications.
000077 Generator Voltage and Electric 0
Grid Disturbances / 6 K/A Category Totals:                                0  0  0  0  3    3 Group Point Total:                                                          6 ES-401, 22 of 33
 
ES-401                                                                  3                                                            Form ES-401-2 ES-401                                                      PWR Examination Outline                                                        Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
K    K  K    A  A E/APE # / Name / Safety Function                                    G                            K/A Topic(s)                            IR    #
1    2    3  1    2 000001 Continuous Rod Withdrawal / 1                                                                                                                  0 Dropped rod, using in-core/ex-core instrumentation, in-core or 000003 Dropped Control Rod / 1                                    03      loop temperature measurements 3.8    1 000005 Inoperable/Stuck Control Rod / 1                                                                                                              0 000024 Emergency Boration / 1                                                                                                                        0 Ability to analyze the effect of maintenance activities, such as 02.
000028 Pressurizer Level Malfunction / 2                                    degraded power sources, on the status of limiting conditions for  4.2    1 36  operations.
04.
000032 Loss of Source Range NI / 7                                          Knowledge of abnormal condition procedures.                        4.2    1 11 000033 Loss of Intermediate Range NI / 7                                                                                                              0 000036 Fuel Handling Accident / 8                                  02      Occurrence of a fuel handling incident                            4.1    1 000037 Steam Generator Tube Leak / 3                                                                                                                  0 000051 Loss of Condenser Vacuum / 4                                                                                                                  0 000059 Accidental Liquid RadWaste Rel. / 9                                                                                                            0 000060 Accidental Gaseous Radwaste Rel. / 9                                                                                                          0 000061 ARM System Alarms / 7                                                                                                                          0 000067 Plant Fire On-site / 9 8                                                                                                                      0 000068 Control Room Evac. / 8                                                                                                                        0 000069 Loss of CTMT Integrity / 5                                                                                                                    0 000074 Inad. Core Cooling / 4                                                                                                                        0 000076 High Reactor Coolant Activity / 9                                                                                                              0 CE/A13 Natural Circ. / 4                                                                                                                              0 CE/A11 RCS Overcooling / 4                                                                                                                            0 CE/A16 Excess RCS Leakage / 2                                                                                                                        0 CE/E09 Functional Recovery                                                                                                                            0 K/A Category Totals:                            0    0    0  0    2    2 Group Point Total:                                                        4 ES-401, 23 of 33
 
ES-401                                                        4                                                    Form ES-401-2 ES-401                                            PWR Examination Outline                                                  Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A A A A System # / Name                                                G                          K/A Topic(s)                        IR    #
1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump                                                                                                              0 004 Chemical and Volume Control                                                                                                      0 005 Residual Heat Removal                                                                                                            0 006 Emergency Core Cooling                                                                                                            0 0
007 Pressurizer Relief/Quench Tank                                Abnormal pressure in the PRT                                3.2    1 2
008 Component Cooling Water                                                                                                          0 010 Pressurizer Pressure Control                                                                                                      0 012 Reactor Protection                                                                                                                0 013 Engineered Safety Features 0
Actuation 022 Containment Cooling                                                                                                              0 025 Ice Condenser                                                                                                                    0 02.
026 Containment Spray                                              Knowledge of surveillance procedures.                      4.1    1 12 039 Main and Reheat Steam                                                                                                            0
: 01. Ability to locate and operate components, including local 059 Main Feedwater                                                controls.
4.0    1 30 061 Auxiliary/Emergency Feedwater                                                                                                    0 062 AC Electrical Distribution                                                                                                        0 0
063 DC Electrical Distribution                                    Loss of ventilation during battery charging                3.1    1 2
04.
064 Emergency Diesel Generator                                    Knowledge of EOP mitigation strategies.                    4.7    1 06 073 Process Radiation Monitoring                                                                                                      0 076 Service Water                                                                                                                    0 078 Instrument Air                                                                                                                    0 103 Containment                                                                                                                      0 K/A Category Totals:              0 0 0 0 0 0  0  2  0  0    3 Group Point Total:                                                  5 ES-401, 24 of 33
 
ES-401                                                                5                                                    Form ES-401-2 ES-401                                                    PWR Examination Outline                                                    Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
K K K K K K  A  A  A A System # / Name                                                      G                          K/A Topic(s)                          IR    #
1 2 3 4 5 6  1  2  3  4 001 Control Rod Drive                                                                                                                        0 002 Reactor Coolant                                                                                                                          0 011 Pressurizer Level Control                                                                                                                0 014 Rod Position Indication                                                                                                                  0 015 Nuclear Instrumentation                                                                                                                  0 016 Non-nuclear Instrumentation                                                                                                              0 0
017 In-core Temperature Monitor 2
Core damage                                                    4.1  1 027 Containment Iodine Removal                                                                                                                0 028 Hydrogen Recombiner and Purge Control                                                                                                    0 029 Containment Purge                                                                                                                        0
: 02. Ability to recognize system parameters that are entry-level 033 Spent Fuel Pool Cooling                                                                                                            4.6  1 42 conditions for Technical Specifications.
034 Fuel Handling Equipment                                                                                                                  0 035 Steam Generator                                                                                                                          0 041 Steam Dump/Turbine Bypass Control                                                                                                        0 045 Main Turbine Generator                                                                                                                    0
: 01. Knowledge of facility requirements for controlling 055 Condenser Air Removal                                                                                                              3.2  1 13 vital/controlled access.
056 Condensate                                                                                                                                0 068 Liquid Radwaste                                                                                                                          0 071 Waste Gas Disposal                                                                                                                        0 072 Area Radiation Monitoring                                                                                                                0 075 Circulating Water                                                                                                                        0 079 Station Air                                                                                                                              0 086 Fire Protection                                                                                                                          0 K/A Category Totals:                      0 0 0 0 0 0  0  1  0  0  2 Group Point Total:                                                    3 ES-401, 25 of 33
 
ES-401                          Generic Knowledge and Abilities Outline (Tier 3)                                            Form ES-401-3 Facility Name:ANO Unit 2            Date of Exam:6/24/2012 RO      SRO-Only Category    K/A #                                            Topic IR      #    IR    #
2.1. 20 Ability to interpret and execute procedure steps.                                          4.6    1 2.1. 03 Knowledge of shift or short-term relief turnover practices.                                3.7    1
: 1.            2.1. 03 Knowledge of shift or short-term relief turnover practices.                                              3.9    1 Conduct of 2.1. 13    Knowledge of facility requirements for controlling vital/controlled access.                              3.2    1 Operations 2.1.
2.1.
Subtotal                                                                                                    2          2 Ability to determine the expected plant configuration using design and configuration 2.2. 15 control documentation, such as drawings, line-ups, tag-outs, etc.                          3.9    1 2.2. 40 Ability to apply Technical Specifications for a system.                                    3.4    1
: 2.            2.2. 11 Knowledge of the process for controlling temporary design changes.                                      3.3    1 Equipment            Knowledge of the process for managing maintenance activities during shutdown 2.2. 18 operations, such as risk assessments, work prioritization, etc.                                          3.9    1 Control 2.2.
2.2.
Subtotal                                                                                                    2          2 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 2.3. 12 containment entry requirements, fuel handling responsibilities, access to locked high-      3.2    1 radiation areas, aligning filters, etc.
Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 15 portable survey instruments, personnel monitoring equipment, etc.                          2.9    1 Ability to comply with radiation work permit requirements during normal or abnormal
: 3.            2.3. 07 conditions.                                                                                3.5    1 Radiation Control      2.3. 06 Ability to approve release permits.                                                                      3.8    1 2.3.
2.3.
Subtotal                                                                                                    3          1 2.4. 01 Knowledge of EOP entry conditions and immediate action steps.                              4.6    1 2.4. 42 Knowledge of emergency response facilities.                                                2.6    1
: 4.                    Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 2.4. 47 appropriate control room reference material.                                                4.2    1 Emergency Procedures 2.4. 14    Knowledge of general guidelines for EOP usage.                                                          4.5    1
/ Plan 2.4. 08 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.                        4.5    1 2.4.
Subtotal                                                                                                    3          2 Tier 3 Point Total                                                                                                      10          7 ES-401, Page 26 of 33
 
ES-401                      Record of Rejected K/As                                  Form ES-401-4 Tier /  Randomly Reason for Rejection Group  Selected K/A 1/2 (RO) 003/AA2.05  A TC map for Unit 2 (simulator) does not show an appreciable difference between the location for a dropped CEA as compared to other core locations. Selected 003 AA2.02 as the replacement KA.
1/2 (RO) 028/AA1.01  This KA states "Ability to operate and/or monitor the following as they apply to the Pressurizer Level Control Malfunctions: PZR level reactor protection bistables" Unit 2 does not have reactor protection bistables for PZR level.
Selected KA 028 AA1.02 2/1 (RO)  073/A2.02  This KA is too close to the other KA selected for this system. Selected KA 073 K 5.01 as a replacement.
2/1 (RO)  076/K4.03  Unit 2 does not have an auto opening feature for SWS valves to CCW heat exchangers. Selected 076 K4.02 as the replacement KA.
2/2 (RO)  071/2.4.3  This KA was also chosen in T1G1 for system 056 and is therefore redundant. Selected 071 2.1.28 as the replacement KA.
3 (RO)    G/2.2.5  This KA has too low of a KA value for the RO position to be used for this system (KA 2.2.5), replaced with KA 2.2.40 (RO rating 3.4).
1/2  005/AA2.04  A TC map for Unit 2 (simulator) does not show an appreciable difference (SRO)                between the location for a dropped CEA as compared to other core locations. Selected 003 AA2.03 as the replacement KA.
1/2    032/2.1.19  This generic KA states: Ability to use plant computer to evaluate system or (SRO)                component status. This KA is best evaluated on the operating exam vs.
the written exam. Selected 2.4.11 as the replacement KA.
2/2    055/2.2.3  This KA applies to multi-unit sites with similar units, ANO is a multi-unit site (SRO)                but with dissimilar units. A KA with a value >2.5 could not be selected from the CARS system (055) for the SRO so KA 055 2.1.13 was selected.
3 (SRO)      2.1.6    This KA states: Ability to manage the control room crew during plant transients. This KA does not lend itself to written exam evaluation but should be reserved for the operating exam. Replaced with KA 2.1.13.
ES-401, Page 27 of 33
 
ES-301                                Control Room/In-Plant Systems Outline                        Form ES-301-2 Facility: Arkansas Nuclear One Unit 2                                    Date of Examination: 08/27/2012 Exam Level: RO X                SRO-I            SRO-U                  Operating Test No.: 2012-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                Type Code*            Safety Function S1. ANO-2-JPM-NRC-SIT09                                                                                    2 006 A4.02 RO-4.0/SRO-3.8                                                      A/D/EN/L/S      Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05                                                                                    6 062 A4.01 RO3.3/SRO3.1                                                            N/S              Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2                                                                                    4 041 A4.05 RO-3.1/SRO-3.3                                                        A/L/N/S          Heat Removal Manually Operate SDBCS valves S4. ANO-2-JPM-NRC-CCW01                                                                                    8 008 A4.01 RO-3.3/SRO-3.1 Secure CCW system using EOP D/L/S            Plant service systems S5. ANO-2-JPM-NRC-CNMT2                                                                                    5 103 A3.01 RO-3.9/SRO-4.2                                                        A/D/P/S Containment Drain the containment sump                                                                          Integrity S6. ANO-2-JPM-NRC-CEA01                                                                                    1 001 A4.03 RO-4.0/SRO-3.7                                                        D/P/S        Reactivity control Perform a CEA exercise S7. ANO-2-JPM-NRC-CPC06                                                                                    7 012 A4.02 RO-3.3/SRO-3.4                                                          D/S Place #1 CEAC to inop on B CPC                                                                Instrumentation S8. ANO-2-JPM-NRC-AOP3                                                                                      3 010 A2.02 RO-3.9/SRO-3.9                                                        A/D/P/S Pressure Control Isolate failed PZR spray valve In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1. ANO-2-JPM-NRC-EDDCB                                                                                    6 064 A4.01 RO-4.0/SRO-4.3                                                        A/D/E/L Electrical Start EDG 2K-4B without DC P2. ANO-2-JPM-NRC-MGSU                                                                                      1 001 A4.08 RO-3.7/SRO-3.4                                                          D/L          Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1                                                                                    8 033 A2.03 RO-3.1/SRO-3.5                                                        D/E/R            Plant service Perform emergency SW make up to SFP systems
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                                9/ 8/ 4 (E)mergency or abnormal in-plant                                                  1/ 1/ 1 (EN)gineered safety feature                                                      - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                            1/ 1/ 1 (N)ew or (M)odified from bank including 1(A)                                      2/ 2/ 1 (P)revious 2 exams                                                                3 / 3 / 2 (randomly selected)
(R)CA                                                                              1/ 1/ 1 (S)imulator Revision 0
 
ES-301                              Administrative Topics Outline                            Form ES-301-1 Facility: Arkansas Nuclear One Unit 2                              Date of Examination: 08/27/2012 Examination Level: RO              SRO X                          Operating Test Number: 2012-1 Administrative Topic            Type                    Describe activity to be performed (see Note)                Code*
Review performing transferring Unit Auxiliary Calculation and determine if it they can be transferred.
A5. Conduct of Operations              D/R ANO-2-JPM-NRC-ADMIN-SU2LOADSRO 2.1.32 SRO (4.0)
Review Time to Boil Calculation.
A6. Conduct of Operations              D/R      ANO-2-JPM-NRC-AMDIN-TTBCSRO 2.1.23 SRO (4.4)
Supervisory review of maintenance activities for configuration control A7. Equipment Control                  D/R ANO-2-JPM-NRC-ADMIN-MAINT 2.2.14 SRO (4.3)
Calculate expected dose for Re-entry during an emergency and determine if entry is allowed.
A8. Radiation Control                  N/R ANO-2-JPM-NRC-ADMIN-EMGRESPSRO 2.3.4 SRO (3.7)
Determine Emergency Action Level for given conditions.
A9. Emergency                        D/P/R      ANO-2-JPM-NRC-ADMIN-EAL11 Procedures/Plan 2.4.41 SRO (4.6)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
Revision 0
 
ES-301                                Control Room/In-Plant Systems Outline                        Form ES-301-2 Facility: Arkansas Nuclear One Unit 2                                    Date of Examination: 08/27/2012 Exam Level: RO                  SRO-I            SRO-U X                Operating Test No.: 2012-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                Type Code*            Safety Function S1. ANO-2-JPM-NRC-SIT09                                                                                    2 006 A4.02 RO-4.0/SRO-3.8                                                      A/D/EN/L/S      Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05                                                                                  6 062 A4.01 RO3.3/SRO3.1                                                            N/S              Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2                                                                                    4 041 A4.05 RO-3.1/SRO-3.3                                                        A/L/N/S          Heat Removal Manually Operate SDBCS valves In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P2. ANO-2-JPM-NRC-MGSU                                                                                    1 001 A4.08 RO-3.7/SRO-3.4                                                          D/L          Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1                                                                                    8 033 A2.03 RO-3.1/SRO-3.5                                                        D/E/R          Plant service Perform emergency SW make up to SFP systems
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                                9/ 8/ 4 (E)mergency or abnormal in-plant                                                  1/ 1/ 1 (EN)gineered safety feature                                                      - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                            1/ 1/ 1 (N)ew or (M)odified from bank including 1(A)                                      2/ 2/ 1 (P)revious 2 exams                                                                3 / 3 / 2 (randomly selected)
(R)CA                                                                              1/ 1/ 1 (S)imulator Revision 0
 
ES-301                                Control Room/In-Plant Systems Outline                        Form ES-301-2 Facility: Arkansas Nuclear One Unit 2                                    Date of Examination: 08/27/2012 Exam Level: RO                  SRO-I X          SRO-U                  Operating Test No.: 2012-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                Type Code*            Safety Function S1. ANO-2-JPM-NRC-SIT09                                                                                    2 006 A4.02 RO-4.0/SRO-3.8                                                      A/D/EN/L/S      Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05                                                                                    6 062 A4.01 RO3.3/SRO3.1                                                            N/S              Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2                                                                                    4 041 A4.05 RO-3.1/SRO-3.3                                                        A/L/N/S          Heat Removal Manually Operate SDBCS valves S4. ANO-2-JPM-NRC-CCW01                                                                                    8 008 A4.01 RO-3.3/SRO-3.1 Secure CCW system using EOP D/L/S            Plant service systems S5. ANO-2-JPM-NRC-CNMT2                                                                                    5 103 A3.01 RO-3.9/SRO-4.2                                                        A/D/P/S Containment Drain the containment sump                                                                          Integrity S6. ANO-2-JPM-NRC-CEA01                                                                                    1 001 A4.03 RO-4.0/SRO-3.7                                                        D/P/S Perform a CEA exercise                                                                        Reactivity control S7. ANO-2-JPM-NRC-CPC06                                                                                    7 012 A4.02 RO-3.3/SRO-3.4                                                          D/S          Instrumentation Place #1 CEAC to inop on B CPC In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1. ANO-2-JPM-NRC-EDDCB                                                                                    6 064 A4.01 RO-4.0/SRO-4.3                                                        A/D/E/L Electrical Start EDG 2K-4B without DC P2. ANO-2-JPM-NRC-MGSU                                                                                      1 001 A4.08 RO-3.7/SRO-3.4                                                          D/L          Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1                                                                                    8 033 A2.03 RO-3.1/SRO-3.5                                                        D/E/R            Plant service Perform emergency SW make up to SFP systems
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                                9/ 8/ 4 (E)mergency or abnormal in-plant                                                  1/ 1/ 1 (EN)gineered safety feature                                                      - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                            1/ 1/ 1 (N)ew or (M)odified from bank including 1(A)                                      2/ 2/ 1 (P)revious 2 exams                                                                3 / 3 / 2 (randomly selected)
(R)CA                                                                              1/ 1/ 1 (S)imulator Revision 0


===3.5 000055===
ES-301                                    Transient and Event Checklist                              Form ES-301-5 Facility: Arkansas Nuclear One                    Date of Exam:        8-27-12        Operating Test No.: 2012-1 A          E                                                    Scenarios P          V                1                   2                                      4          T      M 3(currently selected P          E                                                      as spare)                       O        I L          N                                                                                      T      N CREW                CREW                  CREW            CREW                    I I        T                                                                                      A POSITION            POSITION              POSITION          POSITION                M C                                                                                                  L      U A          T        S      A    B    S      A     B      S        A     B  S    A     B M(*)
Station Blackout / 6 0 1Existing valve positioning on a loss of instrument air system 3.4 1 000056 Loss of Off-site Power / 6 04.03Ability to identify post-accident instrumentation.
R      T    O    R      T    O      R        T    O  R    T      O N          Y                                                                                            R    I U O      C    P    O      C    P      O        C    P  O    C      P T          P E
3.7 1 000057 Loss of Vital AC Inst. Bus / 6 2 0Interlocks in effect on loss of ac vital electrical instrument bus thatmust be bypassed to restore normal equipment operation 3.6 1 000058 Loss of DC Power / 6 04.02Knowledge of system set points, interlocks and automatic actionsassociated with EOP entry conditions.
RO          RX                                    3                     1                           1     1   1 0 NOR      1                                                                               1     1   1 1 SRO-I X          I/C      2,3,4,                      6,9                    3,6                          7      4    4 2 5,8 SRO-U MAJ      6,7                        5,7                    5                            4     2   2 1 TS        2,5                                                                            2     0   2 2 RX                3                                                                       1     1   1 0 RO NOR                          1                     1                                     1     1   1 1 SRO-I                        4,5         2,3,4,               2,3,4, I/C                                                                                      8      4    4 2 X                                        6,8,9                 6,7 SRO-U                        6,7        5,7                   5 MAJ                                                                                      4     2    2 1 TS                            2,4                   2,4                                  2     0   2 2 RO          RX                                                                                              1   1 0 NOR                                                                                              1   1 1 SRO-I I/C                                                                                              4   4 2 SRO-U      MAJ                                                                                              2   2 1 TS                                                                                              0    2 2 RO          RX                                                                                              1   1 0 NOR                                                                                              1   1 1 SRO-I I/C                                                                                              4   4 2 SRO-U      MAJ                                                                                              2   2 1 TS                                                                                              0    2 2 Instructions:
4.5 1 000062 Loss of Nuclear Svc Water / 4 0 4Effect on the nuclear service water discharge flow header of a loss of CCW 3.5 1 000065 Loss of Instrument Air / 8 0 3Restoration of systems served by instrument air when pressure is regained 2.9 1 000077 Generator Voltage and Electric Grid Disturbances / 6 0 2 Breakers, relays 3.1 1 K/A Category Totals:
: 1.       Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
3333 3 3 18 ES-401, 22 of 33 Group Point Total:
: 2.       Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
1 1 1 ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
: 3.       Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)
Revision 0                                                                                         Page 2 of 2
IR#000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 02Signal inputs to rod control system 2.7 1 000005 Inoperable/Stuck Control Rod / 1 04.20Knowledge of the operational implications of EOP warnings, cautions, and notes.
3.8 1 000024 Emergency Boration / 1 02Relationship between boron addition and reactor power 3.6 1 000028 Pressurizer Level Malfunction / 2 02 CVCS 3.4 1 000032 Loss of Source Range NI / 7 01 Manual restoration of power 3.1 1 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 0 000037 Steam Generator Tube Leak / 3 08Criteria for securing RCP 4.1 1 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 000067 Plant Fire On-site / 9 8 16Vital equipment and control systems to be maintained and operated during a fire 3.3 1 000068 Control Room Evac. / 8 02 Reactor trip system 3.7 1 000069  Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 000076 High Reactor Coolant Activity / 9 06Actions contained in EOP for high reactor coolant activity 3.2 1 CE/A13 Natural Circ. / 4 0 CE/A11 RCS Overcooling / 4 0 CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 0 0 0 0 0 0 0 0 0 K/A Category Totals:
1 1 2 2 2 1 9 ES-401, 23 of 33 Group Point Total:
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)
IR#003 Reactor Coolant Pump 0 2 S/G 3.5 1 004 Chemical and Volume Control 01.27 Knowledge of system purpose and/or function.
3.9 1 005 Residual Heat Removal 0 1 0 7 RHR pumps; System protection logics, including high-pressure interlock, reset controls, and valve interlocks 3; 3.2 2 006 Emergency Core Cooling 0 4 ESFAS-operated valves 3.6 1 007 Pressurizer Relief/Quench Tank 0 2 Method of forming a steam bubble in the PZR 3.1 1 008 Component Cooling Water 0 2 01.28 CCW temperature; Knowledge of the purpose and function of major system components and controls.
2.9;4.1 2 010 Pressurizer Pressure Control 0 2 0 1 Constant enthalpy expansion through a valve; Pressure detection systems 2.6;2.7 2 012 Reactor Protection 0 1 RPS channels, components, and interconnections 3.3 1 013 Engineered Safety Features Actuation 0 1 Sensors and detectors 2.7 1 022 Containment Cooling 0 1 Initiation of safeguards mode of operation 4.1 1 025 Ice Condenser 0 026 Containment Spray 02.44 Ability 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 4.2 1 039 Main and Reheat Steam 0 4 Utilization of steam pressure program control when steam dumping through atmospheric relief/dump valves, including T-ave. limits 2.9 1 059 Main Feedwater 1 1 Failure of feedwater control system 3.0 1 061 Auxiliary/Emergency Feedwater 0 2 Pumps 2.6 1 062 AC Electrical Distribution 0 7 Synchronizing and paralleling of different ac supplies 3.1 1 063 DC Electrical Distribution 0 1 0 1 Battery capacity as it is affected by discharge rate; Meters, annunciators, dials, recorders, and indicating lights 2.5;2.7 2 064 Emergency Diesel Generator 0 1 ED/G lube oil temperature and pressure 3.0 1 073 Process Radiation Monitoring 0 1 0 1 Radiation theory, including sources, types, units, and effects; Erratic or failed power supply 2.5;2.5 2 076 Service Water 0 5 0 2 RHR components, controls, sensors, indicators, and alarms, including rad monitors; Automatic start features associated with SWS pump controls 3; 2.9 2 078 Instrument Air 0 5 0 1 MSIV air; Air pressure 3.4;3.1 2 103 Containment 0 1 CCS 3.6 1 K/A Category Totals:23233332313 28 ES-401, 24 of 33 Group Point Total:
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)
IR#001 Control Rod Drive 0 002 Reactor Coolant 1 1 Relationship between effects of the primary coolant system and the secondary coolant system 4.0 1 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 1 NIS channels, components, and interconnections 3.3 1 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 1 Sensors and detectors 2.7 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0 033 Spent Fuel Pool Cooling 0 3 Spent fuel temperature 3.0 1 034 Fuel Handling Equipment 0 035 Steam Generator 0 8 Recognition that increasing radiation levels in secondary systems may mean leaking and possibly ruptured S/G tubes 4.1 1 041 Steam Dump/Turbine Bypass Control 0 2 Steam pressure 3.1 1 045 Main Turbine Generator 0 055 Condenser Air Removal 0 6 PRM system 2.6 1 056 Condensate 0 068 Liquid Radwaste 0071 Waste Gas Disposal 01.28 Knowledge of the purpose and function of major system components and controls.
4.1 1 072 Area Radiation Monitoring 0 2 Detector failure 2.8 1 075 Circulating Water 0 1 Heat sink 2.5 1 079 Station Air 0 086 Fire Protection 0 K/A Category Totals:11111111011 10 ES-401, 25 of 33 Group Point Total:
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)
IR#000007 Reactor Trip / 1 0 2Proper actions to be taken if the automatic safety functions have not taken place 4.6 CE/E02 Reactor Trip Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 0 000009 Small Break LOCA / 3 0 000011 Large Break LOCA / 3 0 000015 RCP Malfunctions / 4 000017 RCP Malfunctions (Loss of RC Flow) / 4 0 000022 Loss of Rx Coolant Makeup / 2 02.36Ability to analyze the effect of maintenance activities, such asdegraded power sources, on the status of limiting conditions for operations.
4.2 1 000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System Malfunction / 3 0 4Tech-Spec limits for RCS pressure 4.3 1 000029 ATWS / 1 0 000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture / 4 CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 CE/E06 Loss of Feedwater / 4 000055 Station Blackout / 6 0 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0 000058 Loss of DC Power / 6 04.47Ability to diagnose and recognize trends in an accurate and timelymanner utilizing the appropriate control room reference material.
4.2 1 000062 Loss of Nuclear Svc Water / 4 0 5The normal values for SWS-header flow rate and the flow rates to the components cooled by the SWS 2.5 1 000065 Loss of Instrument Air / 8 02.42Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
4.6 1 000077 Generator Voltage and Electric Grid Disturbances / 6 0 K/A Category Totals:
0000 3 3 6 ES-401, 22 of 33 Group Point Total:
0 1 0 ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)
IR#000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 03 Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements 3.8 1 000005 Inoperable/Stuck Control Rod / 1 0 000024 Emergency Boration / 1 0 000028 Pressurizer Level Malfunction / 2 02.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
4.2 1 000032 Loss of Source Range NI / 7 04.11 Knowledge of abnormal condition procedures.
4.2 1 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 02 Occurrence of a fuel handling incident 4.1 1 000037 Steam Generator Tube Leak / 3 0 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 000067 Plant Fire On-site / 9 8 0 000068 Control Room Evac. / 8 0 000069  Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 000076 High Reactor Coolant Activity / 9 0 CE/A13 Natural Circ. / 4 0 CE/A11 RCS Overcooling / 4 0CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 K/A Category Totals:
0 0 0 0 2 2 4 ES-401, 23 of 33 Group Point Total:
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)
IR#003 Reactor Coolant Pump 0 004 Chemical and Volume Control 0 005 Residual Heat Removal 0 006 Emergency Core Cooling 0 007 Pressurizer Relief/Quench Tank 0 2 Abnormal pressure in the PRT 3.2 1 008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 012 Reactor Protection 0 013 Engineered Safety Features Actuation 0 022 Containment Cooling 0 025 Ice Condenser 0 026 Containment Spray 02.12 Knowledge of surveillance procedures.
4.1 1 039 Main and Reheat Steam 0 059 Main Feedwater 01.30 Ability to locate and operate components, including local controls.4.0 1 061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0 063 DC Electrical Distribution 0 2 Loss of ventilation during battery charging 3.1 1 064 Emergency Diesel Generator 04.06 Knowledge of EOP mitigation strategies.
4.7 1 073 Process Radiation Monitoring 0 076 Service Water 0 078 Instrument Air 0 103 Containment 0 K/A Category Totals:00000002003 5 ES-401, 24 of 33 Group Point Total:
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)
IR#001 Control Rod Drive 0 002 Reactor Coolant 0 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 2 Core damage 4.1 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0 033 Spent Fuel Pool Cooling 02.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
4.6 1 034 Fuel Handling Equipment 0 035 Steam Generator 0 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0 055 Condenser Air Removal 01.13 Knowledge of facility requirements for controlling vital/controlled access.
3.2 1 056 Condensate 0 068 Liquid Radwaste 0071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 086 Fire Protection 0 K/A Category Totals:00000001002 3 ES-401, 25 of 33 Group Point Total:
ES-401Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3Facility Name:ANO Unit 2      Date of Exam:6/24/2012 IR#IR#2.1.20 Ability to interpret and execute procedure steps.
4.6 12.1.03 Knowledge of shift or short-term relief turnover practices.
3.7 12.1.03 Knowledge of shift or short-term relief turnover practices.
3.9 12.1.13 Knowledge of facility requirements for controlling vital/controlled access.
3.2 1 2.1.2.1.Subtotal 2 22.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.
3.9 12.2.40 Ability to apply Technical Specifications for a system.
3.4 12.2.11 Knowledge of the process for controlling temporary design changes.
3.3 12.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.
3.9 1 2.2.2.2.Subtotal 2 22.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such ascontainment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.2 12.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
2.9 12.3.07 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
3.5 12.3.06 Ability to approve release permits.
3.8 1 2.3.2.3.Subtotal 3 12.4.01 Knowledge of EOP entry conditions and immediate action steps.
4.6 12.4.42 Knowledge of emergency response facilities.
2.6 12.4.47Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
4.2 12.4.14 Knowledge of general guidelines for EOP usage.
4.5 12.4.08 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
4.5 1 2.4.Subtotal 3 2 10 7 ES-401, Page 26 of 33 1.Conduct of Operations RO SRO-Only K/A #Tier 3 Point Total 3.Radiation Control 4.Emergency Procedures
/ Plan 2.Equipment Control Category Topic ES-401Record of Rejected K/AsForm ES-401-4ES-401, Page 27 of 33Tier /GroupRandomlySelected K/AReason for Rejection1/2 (RO)003/AA2.05 A TC map for Unit 2 (simulator) does not show an appreciable differencebetween the location for a dropped CEA as compared to other corelocations. Selected 003 AA2.02 as the replacement KA.1/2 (RO)028/AA1.01 This KA states "Ability to operate and/or monitor the following as they applyto the Pressurizer Level Control Malfunctions: PZR level reactor protectionbistables" Unit 2 does not have reactor protection bistables for PZR level.Selected KA 028 AA1.022/1 (RO)073/A2.02This KA is too close to the other KA selected for this system. Selected KA073 K 5.01 as a replacement.2/1 (RO)076/K4.03Unit 2 does not have an auto opening feature for SWS valves to CCW heatexchangers. Selected 076 K4.02 as the replacement KA.2/2 (RO)071/2.4.3This KA was also chosen in T1G1 for system 056 and is thereforeredundant. Selected 071 2.1.28 as the replacement KA.3 (RO)G/2.2.5This KA has too low of a KA value for the RO position to be used for thissystem (KA 2.2.5), replaced with KA 2.2.40 (RO rating 3.4).
1/2 (SRO)005/AA2.04 A TC map for Unit 2 (simulator) does not show an appreciable differencebetween the location for a dropped CEA as compared to other corelocations. Selected 003 AA2.03 as the replacement KA.
1/2 (SRO)032/2.1.19This generic KA states: "Ability to use plant computer to evaluate system orcomponent status."  This KA is best evaluated on the operating exam vs.the written exam. Selected 2.4.11 as the replacement KA.
2/2 (SRO)055/2.2.3This KA applies to multi-unit sites with similar units, ANO is a multi-unit sitebut with dissimilar units. A KA with a value >2.5 could not be selected fromthe CARS system (055) for the SRO so KA 055 2.1.13 was selected.
3 (SRO)2.1.6This KA states: "Ability to manage the control room crew during planttransients."  This KA does not lend itself to written exam evaluation butshould be reserved for the operating exam. Replaced with KA 2.1.13.
Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility:  Arkansas Nuclear One Unit 2                                        Date of Examination:  08/27/2012Exam Level:  RO X      SRO-I      SRO-UOperating Test No.:  2012-1Control Room Systems
@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-SIT09006 A4.02 RO-4.0/SRO-3.8Isolate SITs following SIAS with SIAS resetA/D/EN/L/S 2Inventory Control S2.ANO-2-JPM-NRC-ELEC05062 A4.01 RO3.3/SRO3.1Transfer Auxiliaries from SU#2 to SU#3 for 2A-1N/S 6Electrical S3.ANO-2-JPM-NRC-SDBC2041 A4.05 RO-3.1/SRO-3.3Manually Operate SDBCS valvesA/L/N/S 4Heat RemovalS4.ANO-2-JPM-NRC-CCW01008 A4.01 RO-3.3/SRO-3.1Secure CCW system using EOPD/L/S 8Plant servicesystems S5.ANO-2-JPM-NRC-CNMT2103 A3.01 RO-3.9/SRO-4.2Drain the containment sumpA/D/P/S 5ContainmentIntegrity S6.ANO-2-JPM-NRC-CEA01001 A4.03 RO-4.0/SRO-3.7Perform a CEA exerciseD/P/S 1Reactivity control S7.ANO-2-JPM-NRC-CPC06012 A4.02 RO-3.3/SRO-3.4Place #1 CEAC to inop on "B" CPCD/S 7Instrumentation S8.ANO-2-JPM-NRC-AOP3010 A2.02 RO-3.9/SRO-3.9Isolate failed PZR spray valveA/D/P/S 3Pressure ControlIn-Plant Systems
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1.ANO-2-JPM-NRC-EDDCB064 A4.01 RO-4.0/SRO-4.3Start EDG 2K-4B without DCA/D/E/L 6ElectricalP2.ANO-2-JPM-NRC-MGSU001 A4.08 RO-3.7/SRO-3.4Start the First MG setD/L 1Reactivity controlP3.ANO-2-JPM-NRC-FPEM1033 A2.03 RO-3.1/SRO-3.5Perform emergency SW make up to SFPD/E/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 /  8 /  4 1 /  1 /  1  -  /  -  /  1 (control room system) 1 /  1 /  1 2 /  2 /  1 3 /  3 /  2 (randomly selected) 1 /  1 /  1 Revision 0ES-301Administrative Topics OutlineForm ES-301-1Facility:  Arkansas Nuclear One Unit 2Date of Examination: 08/27/2012Examination Level:  RO        SRO XOperating Test Number:  2012-1Administrative Topic (see Note)Type Code*Describe activity to be performedA5. Conduct of Operations2.1.32 SRO (4.0)D/RReview performing transferring Unit AuxiliaryCalculation and determine if it they can be transferred.ANO-2-JPM-NRC-ADMIN-SU2LOADSROA6. Conduct of Operations2.1.23 SRO (4.4)D/RReview Time to Boil Calculation.ANO-2-JPM-NRC-AMDIN-TTBCSROA7. Equipment Control2.2.14 SRO (4.3)D/RSupervisory review of maintenance activities forconfiguration controlANO-2-JPM-NRC-ADMIN-MAINTA8. Radiation Control2.3.4 SRO (3.7)N/RCalculate expected dose for Re-entry during anemergency and determine if entry is allowed.ANO-2-JPM-NRC-ADMIN-EMGRESPSROA9. EmergencyProcedures/Plan2.4.41 SRO (4.6)D/P/RDetermine Emergency Action Level for given conditions.ANO-2-JPM-NRC-ADMIN-EAL11NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)


Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: Arkansas Nuclear One Unit 2                                        Date of Examination: 08/27/2012Exam Level:  RO    SRO-I      SRO-U XOperating Test No.:   2012-1Control Room Systems
ES-301                                    Transient and Event Checklist                              Form ES-301-5 Facility: Arkansas Nuclear One                     Date of Exam:       8-27-12          Operating Test No.: 2012-1 A          E                                                    Scenarios P          V                1                    2                                       4           T      M 3(currently selected P          E                                                      as spare)                         O        I L         N                                                                                        T      N CREW                CREW                CREW              CREW                    I I         T                                                                                        A POSITION              POSITION            POSITION            POSITION                M C                                                                                                   L       U A         T        S       A     B    S      A    B     S       A      B   S     A     B M(*)
@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-SIT09006 A4.02 RO-4.0/SRO-3.8Isolate SITs following SIAS with SIAS resetA/D/EN/L/S 2Inventory Control S2.ANO-2-JPM-NRC-ELEC05062 A4.01 RO3.3/SRO3.1Transfer Auxiliaries from SU#2 to SU#3 for 2A-1N/S 6Electrical S3.ANO-2-JPM-NRC-SDBC2041 A4.05 RO-3.1/SRO-3.3Manually Operate SDBCS valvesA/L/N/S 4Heat RemovalIn-Plant Systems
R       T      O     R      T     O     R        T      O  R     T     O N         Y                                                                                             R     I U O       C     P     O       C     P     O       C       P   O     C     P T         P E
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)P2.ANO-2-JPM-NRC-MGSU001 A4.08 RO-3.7/SRO-3.4Start the First MG setD/L 1Reactivity controlP3.ANO-2-JPM-NRC-FPEM1033 A2.03 RO-3.1/SRO-3.5Perform emergency SW make up to SFPD/E/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 /  8 /  4 1 /  1 /  1  -  /  -  /  1 (control room system) 1 /  1 /  1 2 /  2 /  1 3 /  3 /  2 (randomly selected) 1 /  1 /  1 Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility:  Arkansas Nuclear One Unit 2                                        Date of Examination:  08/27/2012Exam Level:  RO     SRO-I X     SRO-UOperating Test No.:  2012-1Control Room Systems
RO          RX               3                                                                         1     1   1 0 X                                                      1                       1 SRO-I       NOR                                                                                        1     1   1 1 I/C               4,5                       2,3,8                   2,4,7                 5      4    4 2 SRO-U                        6,7                       5,7                     5 MAJ                                                                                        4     2   2 1 TS                                                                                          0      0    2 2 RO          RX                                    4                     1                             1     1   1 0 X         NOR                      1                                                                 1      1   1 1 SRO-I I/C                     2,3,8         6,9                   3,6                           5      4    4 2 SRO-U      MAJ                     6,7           5,7                   5                             4      2    2 1 TS                                                                                         0      0    2 2 RO          RX                                                                                         0      1   1 0 NOR      1                                                                                 1     1    1 1 SRO-I I/C       2,3,4,                                                                           5      4    4 2 5,8 SRO-U MAJ       6,7                                                                               2      2    2 1 X
@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-SIT09006 A4.02 RO-4.0/SRO-3.8Isolate SITs following SIAS with SIAS resetA/D/EN/L/S 2Inventory Control S2.ANO-2-JPM-NRC-ELEC05062 A4.01 RO3.3/SRO3.1Transfer Auxiliaries from SU#2 to SU#3 for 2A-1N/S 6Electrical S3.ANO-2-JPM-NRC-SDBC2041 A4.05 RO-3.1/SRO-3.3Manually Operate SDBCS valvesA/L/N/S 4Heat RemovalS4.ANO-2-JPM-NRC-CCW01008 A4.01 RO-3.3/SRO-3.1Secure CCW system using EOPD/L/S 8Plant servicesystems S5.ANO-2-JPM-NRC-CNMT2103 A3.01 RO-3.9/SRO-4.2Drain the containment sumpA/D/P/S 5ContainmentIntegrity S6.ANO-2-JPM-NRC-CEA01001 A4.03 RO-4.0/SRO-3.7Perform a CEA exerciseD/P/S 1Reactivity control S7.ANO-2-JPM-NRC-CPC06012 A4.02 RO-3.3/SRO-3.4Place #1 CEAC to inop on "B" CPCD/S 7InstrumentationIn-Plant Systems
TS       2,5                                                                               2     0    2 2 RO          RX                                                                                         0      1    1 0 NOR                            1                    1                                       1     1   1 1 SRO-I I/C                           2,3,4,               2,3,4,                                 6      4    4 2 6,8,9                6,7 SRO-U MAJ                           5,7                 5                                       2      2    2 1 X
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
TS                             2,4                 2,4                                     2      0    2 2 Instructions:
P1.ANO-2-JPM-NRC-EDDCB064 A4.01 RO-4.0/SRO-4.3Start EDG 2K-4B without DCA/D/E/L 6ElectricalP2.ANO-2-JPM-NRC-MGSU001 A4.08 RO-3.7/SRO-3.4Start the First MG setD/L 1Reactivity controlP3.ANO-2-JPM-NRC-FPEM1033 A2.03 RO-3.1/SRO-3.5Perform emergency SW make up to SFPD/E/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 /  8 /  4 1 /  1 /  1  -  /  -  /  1 (control room system) 1 /  1 /  1 2 /  2 /  1 3 /  3 /  2 (randomly selected) 1 /  1 /  1 Revision 0Page 2 of 2ES-301Transient and Event ChecklistForm ES-301-5Facility: Arkansas Nuclear OneDate of Exam: 8-27-12Operating Test No.: 2012-1Scenarios 1 2 3(currently selectedas spare)4 CREWPOSITION CREWPOSITION CREWPOSITION CREWPOSITION     M      I     N     I     M     U    M(*)A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX 3 1 11 1 0NOR 1 11 1 1 I/C 2,3,4, 5,8 6,9 3,6 74 4 2 MAJ 6,7 5,7 5 42 2 1 ROSRO-I XSRO-U TS 2,5 20 2 2 RX 3 11 1 0NOR 1 1 11 1 1 I/C 4,5 2,3,4, 6,8,9 2,3,4, 6,7 84 4 2 MAJ 6,7 5,7 5 42 2 1 ROSRO-I XSRO-U TS 2,4 2,4 20 2 2 RX1 1 0NOR1 1 1 I/C4 4 2 MAJ2 2 1 ROSRO-ISRO-U TS0 2 2 RX1 1 0NOR1 1 1 I/C4 4 2 MAJ2 2 1 ROSRO-ISRO-U TS0 2 2Instructions:
: 1.       Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for eachevent type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions,including at least two instrument or component (I/C) malfunctions and one major transient, in the ATCposition. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.
: 2.       Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
2.Reactivity manipulations may be conducted under normal orcontrolled abnormal conditions (refer toSection D.5.d) but must be significant per Section C.2.a of Appendix D.  (*) Reactivity and normalevolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.3.         Whenever practical, both instrument and component malfunctions should be included; only thosethat require verifiable actions that provide insight to the applicant's competence count toward the minimumrequirements specified for the applicant's license level in the right-hand columns.
: 3.       Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
Revision 0Page 1 of 2ES-301Transient and Event ChecklistForm ES-301-5Facility: Arkansas Nuclear OneDate of Exam: 8-27-12Operating Test No.: 2012-1Scenarios 1 2 3(currently selectedas spare)4 CREWPOSITION CREWPOSITION CREWPOSITION CREWPOSITION    M      I    N     I    M    U    M(*)A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX 3 11 1 0NOR 1 1 11 1 1 I/C 4,5 2,3,8 2,4,7 54 4 2 MAJ 6,7 5,7 5 42 2 1 RO XSRO-ISRO-U TS 00 2 2 RX 4 1 11 1 0NOR 1 11 1 1 I/C 2,3,8 6,9 3,6 54 4 2 MAJ 6,7 5,7 5 42 2 1 RO XSRO-ISRO-U TS 00 2 2 RX 01 1 0NOR 1 11 1 1 I/C 2,3,4, 5,8 54 4 2 MAJ 6,7 22 2 1 ROSRO-ISRO-U X TS 2,5 20 2 2 RX 01 1 0NOR 1 1 11 1 1 I/C 2,3,4, 6,8,9 2,3,4, 6,7 64 4 2 MAJ 5,7 5 22 2 1 ROSRO-ISRO-U X TS 2,4 2,4 20 2 2Instructions:
Revision 0                                                                                            Page 1 of 2}}
1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for eachevent type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions,including at least two instrument or component (I/C) malfunctions and one major transient, in the ATCposition. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.
2.Reactivity manipulations may be conducted under normal orcontrolled abnormal conditions (refer toSection D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normalevolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.3.         Whenever practical, both instrument and component malfunctions should be included; only thosethat require verifiable actions that provide insight to the applicant's competence count toward the minimumrequirements specified for the applicant's license level in the right-hand columns.}}

Latest revision as of 11:31, 6 February 2020

ANO2-2012-08 Draft Outlines
ML12285A291
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/27/2012
From:
Operations Branch IV
To:
Osterholtz C
References
Download: ML12285A291 (22)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Examination Level: RO X SRO Operating Test Number: 2012-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine any limits for CEA positions using the COLR PDIL A1. Conduct of Operations D/P/R ANO-2-JPM-NRC-ADMIN-PDIL 2.1.25 RO (3.9)

Calculate Time to Boil using computer program A2. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-TTBCRO 2.1.23 RO (4.3)

Review 2P-89B surveillance to determine operability A3. Equipment Control D/R ANO-2-JPM-NRC-ADMIN-2P89BSURV 2.2.42 RO (3.9)

Calculate expected dose for Re-entry during emergency and if applicable limits will be exceeded A4. Radiation Control N/R ANO-2-JPM-NRC-ADMIN-EMGRESP 2.3.4 RO (3.2)

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Revision 0

ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:ANO Unit 2 Date of Exam:6/24/2012 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. Emergency 1 3 3 3 3 3 3 18 3 3 6 Abnormal 2 1 1 2 N/A 2 2 N/A 1 9 2 2 4 Plant Evolutions 5 5 Tier Totals 4 4 5 5 5 4 27 10 1 2 3 2 3 3 3 3 2 3 1 3 28 2 3 5 2.

2 1 1 1 1 1 1 1 1 0 1 1 10 0 1 2 3 Plant Systems Tier Totals 3 4 3 4 4 4 4 3 3 2 4 38 3 5 8 1 2 3 4 1 2 3 4

3. Generic Knowledge and Abilities 10 7 Categories 2 2 3 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, 21 of 33

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

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

1 2 3 1 2 0 Reasons for closing the main turbine governor valve and the main 000007 Reactor Trip / 1 3.7 3 turbine stop valve after a reactor trip 1

CE/E02 Reactor Trip Recovery / 1 0

000008 Pressurizer Vapor Space Accident / 3 Control of PZR level 3.6 1 6

3 000009 Small Break LOCA / 3 RCS water inventory balance and Tech-Spec limits 3.3 1 3

0 000011 Large Break LOCA / 3 Flowpath for sump recirculation 3.9 1 8

000015 RCP Malfunctions / 4 0 Natural circulation in a nuclear reactor power plant 4.4 1 000017 RCP Malfunctions (Loss of RC Flow) / 4 1 0

000022 Loss of Rx Coolant Makeup / 2 CVCS charging pump ammeters and running indicators 2.9 1 6

000025 Loss of RHR System / 4 0 Ability to interpret control room indications to verify the status and 02.

000026 Loss of Component Cooling Water / 8 operation of a system, and understand how operator actions and 4.2 1 44 directives affect plant and system conditions.

000027 Pressurizer Pressure Control System 0

Malfunction / 3 0 definition of negative temperature coefficient as applied to large 000029 ATWS / 1 2.8 1 5 PWR coolant systems 0

000038 Steam Gen. Tube Rupture / 3 Criteria for securing RCP 4.1 1 8

0 000040 Steam Line Rupture / 4 Sensors and detectors 2.6 2

1 CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 1

Facilitys heat removal systems, including primary coolant, 0

CE/E06 Loss of Feedwater / 4 emergency coolant, the decay heat removal systems, and 3.5 2 relations between the proper operation of these systems to the 0

000055 Station Blackout / 6 Existing valve positioning on a loss of instrument air system 3.4 1 1

04.

000056 Loss of Off-site Power / 6 Ability to identify post-accident instrumentation. 3.7 1 03 2 Interlocks in effect on loss of ac vital electrical instrument bus that 000057 Loss of Vital AC Inst. Bus / 6 3.6 1 0 must be bypassed to restore normal equipment operation

04. Knowledge of system set points, interlocks and automatic actions 000058 Loss of DC Power / 6 4.5 1 02 associated with EOP entry conditions.

0 Effect on the nuclear service water discharge flow header of a 000062 Loss of Nuclear Svc Water / 4 3.5 1 4 loss of CCW 0 Restoration of systems served by instrument air when pressure is 000065 Loss of Instrument Air / 8 2.9 1 3 regained 000077 Generator Voltage and Electric 0 Breakers, relays 3.1 1 Grid Disturbances / 6 2 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 ES-401, 22 of 33

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

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 02 Signal inputs to rod control system 2.7 1

04. Knowledge of the operational implications of EOP warnings, 000005 Inoperable/Stuck Control Rod / 1 cautions, and notes.

3.8 1 20 000024 Emergency Boration / 1 02 Relationship between boron addition and reactor power 3.6 1 000028 Pressurizer Level Malfunction / 2 02 CVCS 3.4 1 000032 Loss of Source Range NI / 7 01 Manual restoration of power 3.1 1 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 0 000037 Steam Generator Tube Leak / 3 08 Criteria for securing RCP 4.1 1 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 Vital equipment and control systems to be maintained and 000067 Plant Fire On-site / 9 8 16 operated during a fire 3.3 1 000068 Control Room Evac. / 8 02 Reactor trip system 3.7 1 000069 Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 000076 High Reactor Coolant Activity / 9 06 Actions contained in EOP for high reactor coolant activity 3.2 1 CE/A13 Natural Circ. / 4 0 CE/A11 RCS Overcooling / 4 0 CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 0

0 0

0 0

0 0

0 0

K/A Category Totals: 1 1 2 2 2 1 Group Point Total: 9 ES-401, 23 of 33

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

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

1 2 3 4 5 6 1 2 3 4 0

003 Reactor Coolant Pump S/G 3.5 1 2

01.

004 Chemical and Volume Control Knowledge of system purpose and/or function. 3.9 1 27 0 0 RHR pumps; System protection logics, including high-005 Residual Heat Removal pressure interlock, reset controls, and valve interlocks 3; 3.2 2 1 7 0

006 Emergency Core Cooling ESFAS-operated valves 3.6 1 4

0 007 Pressurizer Relief/Quench Tank Method of forming a steam bubble in the PZR 3.1 1 2

0 01. CCW temperature; Knowledge of the purpose and function 2.9; 008 Component Cooling Water of major system components and controls.

2 2 28 4.1 0 0 Constant enthalpy expansion through a valve; Pressure 2.6; 010 Pressurizer Pressure Control detection systems 2

2 1 2.7 0

012 Reactor Protection RPS channels, components, and interconnections 3.3 1 1

013 Engineered Safety Features 0 Sensors and detectors 2.7 1 Actuation 1 0

022 Containment Cooling Initiation of safeguards mode of operation 4.1 1 1

025 Ice Condenser 0 Ability to interpret control room indications to verify the 02.

026 Containment Spray status and operation of a system, and understand how 4.2 1 44 operator actions and directives affect plant and system Utilization of steam pressure program control when steam 0

039 Main and Reheat Steam dumping through atmospheric relief/dump valves, including 2.9 1 4 T-ave. limits 1

059 Main Feedwater Failure of feedwater control system 3.0 1 1

0 061 Auxiliary/Emergency Feedwater Pumps 2.6 1 2

0 062 AC Electrical Distribution Synchronizing and paralleling of different ac supplies 3.1 1 7

0 0 Battery capacity as it is affected by discharge rate; Meters, 2.5; 063 DC Electrical Distribution annunciators, dials, recorders, and indicating lights 2

1 1 2.7 0

064 Emergency Diesel Generator ED/G lube oil temperature and pressure 3.0 1 1

0 0 Radiation theory, including sources, types, units, and 2.5; 073 Process Radiation Monitoring effects; Erratic or failed power supply 2

1 1 2.5 RHR components, controls, sensors, indicators, and alarms, 0 0 076 Service Water including rad monitors; Automatic start features associated 3; 2.9 2 5 2 with SWS pump controls 0 0 3.4; 078 Instrument Air MSIV air; Air pressure 2 5 1 3.1 0

103 Containment CCS 3.6 1 1

K/A Category Totals: 2 3 2 3 3 3 3 2 3 1 3 Group Point Total: 28 ES-401, 24 of 33

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

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

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0 1 Relationship between effects of the primary coolant system and 002 Reactor Coolant 1 the secondary coolant system 4.0 1 011 Pressurizer Level Control 0 014 Rod Position Indication 0 0

015 Nuclear Instrumentation 1

NIS channels, components, and interconnections 3.3 1 016 Non-nuclear Instrumentation 0 0

017 In-core Temperature Monitor 1

Sensors and detectors 2.7 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0 0

033 Spent Fuel Pool Cooling 3

Spent fuel temperature 3.0 1 034 Fuel Handling Equipment 0 0 Recognition that increasing radiation levels in secondary 035 Steam Generator 8 systems may mean leaking and possibly ruptured S/G tubes 4.1 1 0

041 Steam Dump/Turbine Bypass Control 2

Steam pressure 3.1 1 045 Main Turbine Generator 0 0

055 Condenser Air Removal 6

PRM system 2.6 1 056 Condensate 0 068 Liquid Radwaste 0

01. Knowledge of the purpose and function of major system 071 Waste Gas Disposal 4.1 1 28 components and controls.

0 072 Area Radiation Monitoring 2

Detector failure 2.8 1 0

075 Circulating Water 1

Heat sink 2.5 1 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 1 1 1 1 1 1 1 1 0 1 1 Group Point Total: 10 ES-401, 25 of 33

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

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

1 2 3 1 2 0 Proper actions to be taken if the automatic safety functions have 000007 Reactor Trip / 1 4.6 2 not taken place 1

CE/E02 Reactor Trip Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 0 000009 Small Break LOCA / 3 0 000011 Large Break LOCA / 3 0 000015 RCP Malfunctions / 4 0

000017 RCP Malfunctions (Loss of RC Flow) / 4 Ability to analyze the effect of maintenance activities, such as 02.

000022 Loss of Rx Coolant Makeup / 2 degraded power sources, on the status of limiting conditions for 4.2 1 36 operations.

000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System 0 Tech-Spec limits for RCS pressure 4.3 1 Malfunction / 3 4 000029 ATWS / 1 0 000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture / 4 0

CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 0

CE/E06 Loss of Feedwater / 4 000055 Station Blackout / 6 0 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0

04. Ability to diagnose and recognize trends in an accurate and timely 000058 Loss of DC Power / 6 4.2 1 47 manner utilizing the appropriate control room reference material.

0 The normal values for SWS-header flow rate and the flow rates to 000062 Loss of Nuclear Svc Water / 4 2.5 1 5 the components cooled by the SWS

02. Ability to recognize system parameters that are entry-level 000065 Loss of Instrument Air / 8 4.6 1 42 conditions for Technical Specifications.

000077 Generator Voltage and Electric 0

Grid Disturbances / 6 K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 ES-401, 22 of 33

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

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 Dropped rod, using in-core/ex-core instrumentation, in-core or 000003 Dropped Control Rod / 1 03 loop temperature measurements 3.8 1 000005 Inoperable/Stuck Control Rod / 1 0 000024 Emergency Boration / 1 0 Ability to analyze the effect of maintenance activities, such as 02.

000028 Pressurizer Level Malfunction / 2 degraded power sources, on the status of limiting conditions for 4.2 1 36 operations.

04.

000032 Loss of Source Range NI / 7 Knowledge of abnormal condition procedures. 4.2 1 11 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 02 Occurrence of a fuel handling incident 4.1 1 000037 Steam Generator Tube Leak / 3 0 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 000067 Plant Fire On-site / 9 8 0 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 000076 High Reactor Coolant Activity / 9 0 CE/A13 Natural Circ. / 4 0 CE/A11 RCS Overcooling / 4 0 CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401, 23 of 33

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

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

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0 004 Chemical and Volume Control 0 005 Residual Heat Removal 0 006 Emergency Core Cooling 0 0

007 Pressurizer Relief/Quench Tank Abnormal pressure in the PRT 3.2 1 2

008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 012 Reactor Protection 0 013 Engineered Safety Features 0

Actuation 022 Containment Cooling 0 025 Ice Condenser 0 02.

026 Containment Spray Knowledge of surveillance procedures. 4.1 1 12 039 Main and Reheat Steam 0

01. Ability to locate and operate components, including local 059 Main Feedwater controls.

4.0 1 30 061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0 0

063 DC Electrical Distribution Loss of ventilation during battery charging 3.1 1 2

04.

064 Emergency Diesel Generator Knowledge of EOP mitigation strategies. 4.7 1 06 073 Process Radiation Monitoring 0 076 Service Water 0 078 Instrument Air 0 103 Containment 0 K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 3 Group Point Total: 5 ES-401, 24 of 33

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

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

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0 002 Reactor Coolant 0 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 0

017 In-core Temperature Monitor 2

Core damage 4.1 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0

02. Ability to recognize system parameters that are entry-level 033 Spent Fuel Pool Cooling 4.6 1 42 conditions for Technical Specifications.

034 Fuel Handling Equipment 0 035 Steam Generator 0 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0

01. Knowledge of facility requirements for controlling 055 Condenser Air Removal 3.2 1 13 vital/controlled access.

056 Condensate 0 068 Liquid Radwaste 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 0 0 0 0 0 0 0 1 0 0 2 Group Point Total: 3 ES-401, 25 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:ANO Unit 2 Date of Exam:6/24/2012 RO SRO-Only Category K/A # Topic IR # IR #

2.1. 20 Ability to interpret and execute procedure steps. 4.6 1 2.1. 03 Knowledge of shift or short-term relief turnover practices. 3.7 1

1. 2.1. 03 Knowledge of shift or short-term relief turnover practices. 3.9 1 Conduct of 2.1. 13 Knowledge of facility requirements for controlling vital/controlled access. 3.2 1 Operations 2.1.

2.1.

Subtotal 2 2 Ability to determine the expected plant configuration using design and configuration 2.2. 15 control documentation, such as drawings, line-ups, tag-outs, etc. 3.9 1 2.2. 40 Ability to apply Technical Specifications for a system. 3.4 1

2. 2.2. 11 Knowledge of the process for controlling temporary design changes. 3.3 1 Equipment Knowledge of the process for managing maintenance activities during shutdown 2.2. 18 operations, such as risk assessments, work prioritization, etc. 3.9 1 Control 2.2.

2.2.

Subtotal 2 2 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 2.3. 12 containment entry requirements, fuel handling responsibilities, access to locked high- 3.2 1 radiation areas, aligning filters, etc.

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 Ability to comply with radiation work permit requirements during normal or abnormal

3. 2.3. 07 conditions. 3.5 1 Radiation Control 2.3. 06 Ability to approve release permits. 3.8 1 2.3.

2.3.

Subtotal 3 1 2.4. 01 Knowledge of EOP entry conditions and immediate action steps. 4.6 1 2.4. 42 Knowledge of emergency response facilities. 2.6 1

4. Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 2.4. 47 appropriate control room reference material. 4.2 1 Emergency Procedures 2.4. 14 Knowledge of general guidelines for EOP usage. 4.5 1

/ Plan 2.4. 08 Knowledge of how abnormal operating procedures are used in conjunction with EOPs. 4.5 1 2.4.

Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/2 (RO) 003/AA2.05 A TC map for Unit 2 (simulator) does not show an appreciable difference between the location for a dropped CEA as compared to other core locations. Selected 003 AA2.02 as the replacement KA.

1/2 (RO) 028/AA1.01 This KA states "Ability to operate and/or monitor the following as they apply to the Pressurizer Level Control Malfunctions: PZR level reactor protection bistables" Unit 2 does not have reactor protection bistables for PZR level.

Selected KA 028 AA1.02 2/1 (RO) 073/A2.02 This KA is too close to the other KA selected for this system. Selected KA 073 K 5.01 as a replacement.

2/1 (RO) 076/K4.03 Unit 2 does not have an auto opening feature for SWS valves to CCW heat exchangers. Selected 076 K4.02 as the replacement KA.

2/2 (RO) 071/2.4.3 This KA was also chosen in T1G1 for system 056 and is therefore redundant. Selected 071 2.1.28 as the replacement KA.

3 (RO) G/2.2.5 This KA has too low of a KA value for the RO position to be used for this system (KA 2.2.5), replaced with KA 2.2.40 (RO rating 3.4).

1/2 005/AA2.04 A TC map for Unit 2 (simulator) does not show an appreciable difference (SRO) between the location for a dropped CEA as compared to other core locations. Selected 003 AA2.03 as the replacement KA.

1/2 032/2.1.19 This generic KA states: Ability to use plant computer to evaluate system or (SRO) component status. This KA is best evaluated on the operating exam vs.

the written exam. Selected 2.4.11 as the replacement KA.

2/2 055/2.2.3 This KA applies to multi-unit sites with similar units, ANO is a multi-unit site (SRO) but with dissimilar units. A KA with a value >2.5 could not be selected from the CARS system (055) for the SRO so KA 055 2.1.13 was selected.

3 (SRO) 2.1.6 This KA states: Ability to manage the control room crew during plant transients. This KA does not lend itself to written exam evaluation but should be reserved for the operating exam. Replaced with KA 2.1.13.

ES-401, Page 27 of 33

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Exam Level: RO X SRO-I SRO-U Operating Test No.: 2012-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1. ANO-2-JPM-NRC-SIT09 2 006 A4.02 RO-4.0/SRO-3.8 A/D/EN/L/S Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05 6 062 A4.01 RO3.3/SRO3.1 N/S Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2 4 041 A4.05 RO-3.1/SRO-3.3 A/L/N/S Heat Removal Manually Operate SDBCS valves S4. ANO-2-JPM-NRC-CCW01 8 008 A4.01 RO-3.3/SRO-3.1 Secure CCW system using EOP D/L/S Plant service systems S5. ANO-2-JPM-NRC-CNMT2 5 103 A3.01 RO-3.9/SRO-4.2 A/D/P/S Containment Drain the containment sump Integrity S6. ANO-2-JPM-NRC-CEA01 1 001 A4.03 RO-4.0/SRO-3.7 D/P/S Reactivity control Perform a CEA exercise S7. ANO-2-JPM-NRC-CPC06 7 012 A4.02 RO-3.3/SRO-3.4 D/S Place #1 CEAC to inop on B CPC Instrumentation S8. ANO-2-JPM-NRC-AOP3 3 010 A2.02 RO-3.9/SRO-3.9 A/D/P/S Pressure Control Isolate failed PZR spray valve In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1. ANO-2-JPM-NRC-EDDCB 6 064 A4.01 RO-4.0/SRO-4.3 A/D/E/L Electrical Start EDG 2K-4B without DC P2. ANO-2-JPM-NRC-MGSU 1 001 A4.08 RO-3.7/SRO-3.4 D/L Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1 8 033 A2.03 RO-3.1/SRO-3.5 D/E/R Plant service Perform emergency SW make up to SFP systems

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Revision 0

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Examination Level: RO SRO X Operating Test Number: 2012-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Review performing transferring Unit Auxiliary Calculation and determine if it they can be transferred.

A5. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-SU2LOADSRO 2.1.32 SRO (4.0)

Review Time to Boil Calculation.

A6. Conduct of Operations D/R ANO-2-JPM-NRC-AMDIN-TTBCSRO 2.1.23 SRO (4.4)

Supervisory review of maintenance activities for configuration control A7. Equipment Control D/R ANO-2-JPM-NRC-ADMIN-MAINT 2.2.14 SRO (4.3)

Calculate expected dose for Re-entry during an emergency and determine if entry is allowed.

A8. Radiation Control N/R ANO-2-JPM-NRC-ADMIN-EMGRESPSRO 2.3.4 SRO (3.7)

Determine Emergency Action Level for given conditions.

A9. Emergency D/P/R ANO-2-JPM-NRC-ADMIN-EAL11 Procedures/Plan 2.4.41 SRO (4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Exam Level: RO SRO-I SRO-U X Operating Test No.: 2012-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1. ANO-2-JPM-NRC-SIT09 2 006 A4.02 RO-4.0/SRO-3.8 A/D/EN/L/S Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05 6 062 A4.01 RO3.3/SRO3.1 N/S Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2 4 041 A4.05 RO-3.1/SRO-3.3 A/L/N/S Heat Removal Manually Operate SDBCS valves In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P2. ANO-2-JPM-NRC-MGSU 1 001 A4.08 RO-3.7/SRO-3.4 D/L Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1 8 033 A2.03 RO-3.1/SRO-3.5 D/E/R Plant service Perform emergency SW make up to SFP systems

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Exam Level: RO SRO-I X SRO-U Operating Test No.: 2012-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1. ANO-2-JPM-NRC-SIT09 2 006 A4.02 RO-4.0/SRO-3.8 A/D/EN/L/S Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05 6 062 A4.01 RO3.3/SRO3.1 N/S Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2 4 041 A4.05 RO-3.1/SRO-3.3 A/L/N/S Heat Removal Manually Operate SDBCS valves S4. ANO-2-JPM-NRC-CCW01 8 008 A4.01 RO-3.3/SRO-3.1 Secure CCW system using EOP D/L/S Plant service systems S5. ANO-2-JPM-NRC-CNMT2 5 103 A3.01 RO-3.9/SRO-4.2 A/D/P/S Containment Drain the containment sump Integrity S6. ANO-2-JPM-NRC-CEA01 1 001 A4.03 RO-4.0/SRO-3.7 D/P/S Perform a CEA exercise Reactivity control S7. ANO-2-JPM-NRC-CPC06 7 012 A4.02 RO-3.3/SRO-3.4 D/S Instrumentation Place #1 CEAC to inop on B CPC In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1. ANO-2-JPM-NRC-EDDCB 6 064 A4.01 RO-4.0/SRO-4.3 A/D/E/L Electrical Start EDG 2K-4B without DC P2. ANO-2-JPM-NRC-MGSU 1 001 A4.08 RO-3.7/SRO-3.4 D/L Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1 8 033 A2.03 RO-3.1/SRO-3.5 D/E/R Plant service Perform emergency SW make up to SFP systems

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator Revision 0

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Arkansas Nuclear One Date of Exam: 8-27-12 Operating Test No.: 2012-1 A E Scenarios P V 1 2 4 T M 3(currently selected P E as spare) O I L N T N CREW CREW CREW CREW I I T A POSITION POSITION POSITION POSITION M C L U A T S A B S A B S A B S A B M(*)

R T O R T O R T O R T O N Y R I U O C P O C P O C P O C P T P E

RO RX 3 1 1 1 1 0 NOR 1 1 1 1 1 SRO-I X I/C 2,3,4, 6,9 3,6 7 4 4 2 5,8 SRO-U MAJ 6,7 5,7 5 4 2 2 1 TS 2,5 2 0 2 2 RX 3 1 1 1 0 RO NOR 1 1 1 1 1 1 SRO-I 4,5 2,3,4, 2,3,4, I/C 8 4 4 2 X 6,8,9 6,7 SRO-U 6,7 5,7 5 MAJ 4 2 2 1 TS 2,4 2,4 2 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Revision 0 Page 2 of 2

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Arkansas Nuclear One Date of Exam: 8-27-12 Operating Test No.: 2012-1 A E Scenarios P V 1 2 4 T M 3(currently selected P E as spare) O I L N T N CREW CREW CREW CREW I I T A POSITION POSITION POSITION POSITION M C L U A T S A B S A B S A B S A B M(*)

R T O R T O R T O R T O N Y R I U O C P O C P O C P O C P T P E

RO RX 3 1 1 1 0 X 1 1 SRO-I NOR 1 1 1 1 I/C 4,5 2,3,8 2,4,7 5 4 4 2 SRO-U 6,7 5,7 5 MAJ 4 2 2 1 TS 0 0 2 2 RO RX 4 1 1 1 1 0 X NOR 1 1 1 1 1 SRO-I I/C 2,3,8 6,9 3,6 5 4 4 2 SRO-U MAJ 6,7 5,7 5 4 2 2 1 TS 0 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2,3,4, 5 4 4 2 5,8 SRO-U MAJ 6,7 2 2 2 1 X

TS 2,5 2 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 1 SRO-I I/C 2,3,4, 2,3,4, 6 4 4 2 6,8,9 6,7 SRO-U MAJ 5,7 5 2 2 2 1 X

TS 2,4 2,4 2 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Revision 0 Page 1 of 2

Retrieved from "https://kanterella.com/w/index.php?title=ML12285A291&oldid=2460382"