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{{#Wiki_filter:ES*401 PWR Examination Outline Form ES*401*2 NRC Exam Facility:
{{#Wiki_filter:ES*401                                                 PWR Examination Outline                                             Form ES*401*2 NRC Exam Facility: Watts Bar                   Date of Exam: May 2009                                                                 RO Tier                                           RO KIA Category Points                                         SRO-Only Points 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
Watts Bar Date of Exam: May 2009 RO Tier RO KIA Category Points SRO-Only Points 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
* 3   3   3                     3   3               3       18
* 1. 1 3 3 3 3 3 3 18 Emergency 2 2 1 N/A 1 2 N/A 1 9 & Abnormal 2 Plant 5 5 4 4 5 4 27 Evolutions Tier Totals 1 3 2 2 3 3 3 2 3 2 2 3 28 2. 1 1 1 1 1 1 1 1 1 0 1 10 Plant 2 Systems 4 3 3 4 4 4 3 4 3 2 4 38 Tier Totals 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 2 2 3 3 10 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
: 1.            1 Emergency                                         N/A                     N/A 2    2    1                     1    2              1      9
The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions 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 KIA statements.  
& Abnormal         2 Plant Tier Totals 5   5   4                     4   5               4     27 Evolutions 3   2   2     3   3     3   2   3     2   2   3     28 1
: 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.  
2.
: 5. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.
1   1   1     1   1     1   1   1     1   0   1     10 Plant           2 Systems Tier Totals 4   3   3     4   4     4   3   4     3   2   4     38
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.  
: 3. Generic Knowledge and Abilities             1         2         3         4                 1     2     3     4 10 2         2         3         3 Note:     1.     Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
: 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.
7.* The generic (G)
: 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/evolutions 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 KIA statements.
KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KlAs. s. On the following pages, enter the KIA 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.
: 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.
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-onlyexams.  
: 5.     Absent a plant-specific priority, only those KlAs 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.
: 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
: 6.     Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
Limit SRO selections to KlAs that are linked to 10 CFR 55.43. Note: This outline was provided by the Chief Examiner.
7.*     The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KlAs.
Watts Bar Nuclear Plant NRC Exam March 2009 ES-401 2 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emeraenc and Abnormal Plant Evolutions
: s.     On the following pages, enter the KIA 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-onlyexams.
-Tier 1/GrouD 1 eRO) E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KIA Tooic(s) IR # 000008 Pressurizer Vapor Space 2.2.20 Knowledge of the process for managing 2.6 1 Accident/3 troublestiooting activities.
: 9.     For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals
000009 Small Break LOCA / 3 03 Interrelations between SBLOCA and S/Gs. 3.0 1 000011 Large Break LOCA / 3 05 Operate/monitor man/auto transfer of charging suction to borated source. 4.3 1 000015/17 RCP Malfunctions / 4 10 Interrelations between RCP malfunctions and 2.8 1 indicators/controls.
(#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
000025 Loss of RHR System /4 01 Reasons for shift to alternate flowpath as it applies to LossofRHR.
Note: This outline was provided by the Chief Examiner.
3.1 1 000026 Loss of Component Cooling 04 Reasons for effect on CCW flow header of a loss of 3.5 1 Water /8 CCW. 000027 Pressurizer Pressure Control 03 Op implications of latent heat of vaporization.
Watts Bar Nuclear Plant NRC Exam                                                                                 March 2009
2.6 1 System Malfunction / 3 000029 ATWS /1 12 Operate/monitor M/G set pwr supply & Rx trip brkrs. 4.1 1 000038 Steam Gen. Tube Rupture /3 03 Op implications of natural circulation.
3.9 1 000054 (CE/E06) Loss of Main 2.2.22 Knowledge of LCOs and safety limits. 4.0 1 Feedwater
/4 000056 Loss of Offsite Power / 6 04 Implication of saturation conditions for the systems. 3.1 1 000057 Loss of Vital AC Elec. Inst. Bus 19 Determinelinterpret auto actions that occur. 4.0 1 /6 000058 Loss of DC Power / 6 02 Operate/monitor dc input brkr, freq. meter, ac output detector and ground fault detector.
3.1 1 000062 Loss of Nuclear Service Water 01 Determinelinterpret location of a leak in the SWS 2.9 1 /4 000065 Loss of Instrument Air /8 03 Reasons for effects on plant ops of isolating certain equipment from instrument air. 2.9 1 W /E04 LOCA Outside Containment / 3 Interrelations between LOCA outside containment 01 and comp'onents and functions of control and safety 3.5 1 inc!. instrumentation, signals, interlocks, failure modes and auto and manual features.
W/E11 Loss of Emergency Coolant 01 Determine/interpret facility conditions and select 3.4 1 Recirc./4 appropriate procedures.
000040 (W/E12) Steam Line Rupture-2.2.36 Analyze effect of maintenance activities on status of 3.1 1 Excessive Heat Transfer /4 LCOs. KIA Category Point Totals: 3 3 3 3 3 3 Group Point Total: 18 Watts Bar Nuclear Plant NRC Exam March 2009 ES-401 3 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emel encv and Abnormal Plant Evolutions
-Tier 1/GrouD 2 IRQ) E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KIA TODicls) IR # 000001 Continuous Rod Withdrawal/1 01 petermine/interpret reactor tripped brkr IndIcator.
4.2 1 000003 Dropped Control Rod /1 2.2.44 Interpret indications to verify status and operation of a and actions 4.2 1 and directives a ecting con Itions. 000028 Pressurizer Level Malfunction / 2 01 Op implications of PZR ref. leak abnormalities 2.8 1 000033 Loss of Intermediate Range NI/ 7 01 Determine/interpret equivalency between source range, intermeaiate range, and power 3.0 1 range channel readings 000059 Accidental Liquid RadWaste ReI. / 9 02 Interrelations with radioactive gas monitors 2.7 1 000076 High Reactor Coolant Activity /9 05 Reasons for corrective actions as a result of 2.9 1 high fission product rad level in RCS W/E08 RCS Overcooling
-PTS /4 03 Operate/monitor desired operating results. 3.6 1 (W/E14) High Containment Pressure /5 Interrelations between Loss of CTMT and components and functions of control an 01 safety systems, incl. instrumentation, signals, 3.4 1 interloci(s, failure modes and auto and manual features.
W/E15 Containment Flooding /5 02 Op implications of procedures 2.7 1 KIA Category Point Totals: 2 2 1 1 2 1 Group Point Total: 9 Watts Bar Nuclear Plant NRC Exam March 2009 ES-401 4 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Fonn ES-401-2 Plant Systems-Tier 2/Group 1 (RO System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic(s) IR # 003 Reactor Coolant Pump 02 Knowledge of pwr supplies to CCW pumps. 2.5 1 004 Chemical and Volume Control of RCP seal 05 fai ures on CVCS, and 4.0 1 procedures.
Imp of Keff by' means other 08 than 6-factor formula: 2.6 1 of count rate to reactivity c anges. 005 Residual Heat Removal 06 Effect of loss on CSS. 3.1 1 006 Emergency Core Cooling 05 Manually


===3.9 transfer===
ES-401                                                              2                                                               Form ES-401-2 NRC Exam ES-401                                                PWR Examination Outline                                                    Form ES-401-2 Emeraenc and Abnormal Plant Evolutions - Tier 1/GrouD 1 eRO)
of CCS flowpaths 1 prior to recirculation.
E/APE # / Name / Safety Function        K1    K2  K3  A1    A2      G                              KIA Tooic(s)                        IR  #
007 Pressurizer Relief/Quench Tank 01 Design/interlocks for quench tank cooling 2.6 1 02 Method of steam bubble in the PZ . 3.1 1 008 Component Cooling Water 2.4.2 Sys. se4>Oints, interlocks, 4.5 1 auto actions associated with EOP entry conditions.
000008 Pressurizer Vapor Space                                          2.2.20      Knowledge of the process for managing                      2.6  1 Accident/3                                                                          troublestiooting activities.
010 Pressurizer Pressure Control 04 Effect of loss/malf.
000009 Small Break LOCA / 3                       03                                Interrelations between SBLOCA and S/Gs.                   3.0  1 000011 Large Break LOCA / 3                                05                      Operate/monitor man/auto transfer of charging            4.3  1 suction to borated source.
of PRT. 2.9 1 01 Impacts of and rerocedures for faulty bistab e operation.
000015/17 RCP Malfunctions / 4                    10                                Interrelations between RCP malfunctions and              2.8   1 indicators/controls.
3.1 1 012 Reactor Protection 2.4.35 Local AO tasks during emerg., including effects. 3.8 1 013 Engineered Safety Features 01 Power supplies to ESFAS 3.6 1 Actuation equipment control. Monitor auto 0fes. of 022 Containment Cooling 01 initiation of sa eguards 4.1 1 mode. 02 Connections/cause
000025 Loss of RHR System /4                          01                           Reasons for shift to alternate flowpath as it applies to  3.1   1 LossofRHR.
& effect 2.7 1 with refrigerant systems. 025 Ice Condenser Features/interlocks for 02 system control. 2.8 1 026 Containment Spray Featureslinterlocks for rad 09 release (interlock on RWST 3.7 1 isol. after swapover).
000026 Loss of Component Cooling                      04                            Reasons for effect on CCW flow header of a loss of        3.5  1 CCW.
039 Main and Reheat Steam 02 Monitor auto operation of MRSS isolation.
Water /8 000027 Pressurizer Pressure Control        03                                      Op implications of latent heat of vaporization.           2.6  1 System Malfunction / 3 000029 ATWS /1                                              12                      Operate/monitor M/G set pwr supply & Rx trip brkrs.       4.1  1 000038 Steam Gen. Tube Rupture /3         03                                       Op implications of natural circulation.                   3.9  1 000054 (CE/E06) Loss of Main                                            2.2.22    Knowledge of LCOs and safety limits.                       4.0   1 Feedwater /4 000056 Loss of Offsite Power / 6          04                                      Implication of saturation conditions for the systems.     3.1   1 000057 Loss of Vital AC Elec. Inst. Bus                            19              Determinelinterpret auto actions that occur.              4.0  1
3.1 1 059 Main Feedwater 03 Impacts of and procedures for overfeeding event. 2.7 1 061 Auxiliary/Emergency Feedwater 03 of pp. head 2.6 1 e ects when control vlv shut. 062 AC Electrical Distribution 2.4.11 Knowledge of abnormal procedures.
/6 000058 Loss of DC Power / 6                                02                      Operate/monitor dc input brkr, freq. meter, ac output      3.1   1 detector and ground fault detector.
4.0 1 063 DC Electrical Distribution 01 Effects on battery capacity of discharge rate. 2.5 1 07 Effects of loss of air rcvrs. 2.7 1 064 Emergency Diesel Generator 08 Effects of loss of fuel tanks. 3.2 1 073 Process Radiation Monitoring 01 Effect of loss/malf.
000062 Loss of Nuclear Service Water                              01               Determinelinterpret location of a leak in the SWS          2.9  1
on 3.6 1 .. releases . 076 Service Water Predict associated 02 with reactor turbo bldg. 2.6 1 closed cooling water temps. 01 Monitor pressure gauges. 3.1 1 078 Instrument Air 01 Relations with sensor air. 2.8 1 103 Containment 01 Relations with CCS 3.6 1 KIA Category Point Totals: 3 2 2 3 3 3 2 3 2 2 3 Group Point Total: 28 Watts Bar Nuclear Plant NRC Exam March 2009 ES-401 5 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems-Tier 2/Grouo 2 (RO SYStem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Tooic(s) IR # 001 Control Rod Drive 03 Effect of loss on reactor trip 3.7 1 breakers.
/4 000065 Loss of Instrument Air /8                      03                          Reasons for effects on plant ops of isolating certain      2.9  1 equipment from instrument air.
002 Reactor Coolant 03 Effect of loss/malf.
W /E04 LOCA Outside Containment / 3                                                Interrelations between LOCA outside containment 01                                and comp'onents and functions of control and safety        3.5  1 s~tems, inc!. instrumentation, signals, interlocks, failure modes and auto and manual features.
on 4.2 1 containment.
W/E11 Loss of Emergency Coolant                                  01                Determine/interpret facility conditions and select        3.4  1 appropriate procedures.
016 Non-nuclear 01 Separation of control and 2.7 1 Instrumentation protection circuits.
Recirc./4 000040 (W/E12) Steam Line Rupture-                                      2.2.36    Analyze effect of maintenance activities on status of      3.1   1 LCOs.
017 In-Core Temperature Monitor 01 Relationship with plant computer.
Excessive Heat Transfer /4 3      3    3    3    3        3                                                                       18 KIA Category Point Totals:                                                         Group Point Total:
3.2 1 027 Containment Iodine 01 3.1 1 Removal Power supplies to fans. 033 Spent Fuel Pool Cooling 01 Design features for spent fuel level. 2.9 1 034 Fuel Handling Equipment 02 Monitor water level in refuel canal 2.9 1 045 Main Turbine Generator 2.2.37 Determine operability/availability 3.6 1 of safety related equipment.
Watts Bar Nuclear Plant NRC Exam                                                                                                 March 2009
068 Liquid Radwaste 02 Monitor automatic isolation.
 
3.6 1 072 Area Radiation Monitoring 01 of erratic or fai ed power supply. 2.7 1 KIA Category Point Totals: 1 1 1 1 1 1 1 1 1 0 1 Group Point Total: 10 Watts Bar Nuclear Plant NRC Exam March 2009 ES*401 Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3 NRC EXAM Facility:
ES-401                                                       3                                                                Form ES-401-2 NRC Exam ES-401                                             PWR Examination Outline                                                 Form ES-401-2 Emel encv and Abnormal Plant Evolutions - Tier 1/GrouD 2 IRQ)
Watts Bar Date of Exam: May 2009 RO Category KIA # Topic RO SRO-Only IR # IR # 2.1.4 Operator responsibilities for shift staffing.
E/APE # / Name / Safety Function    K1   K2   K3   A1   A2       G                           KIA TODicls)                     IR #
3.3 1 1. 2.1.42 New and spent fuel movement procedures.
000001 Continuous Rod Withdrawal/1                                01              petermine/interpret reactor tripped brkr            4.2  1 IndIcator.
2.5 1 Conduct of Operations Subtotal 2 2.2.20 Process for managing troubleshooting activities.
000003 Dropped Control Rod /1                                                      Interpret indications to verify status and 2.2.44    operation of a s~tem, and ~erator actions            4.2 1 and directives a ecting con Itions.
2.6 1 2.2.21 Pre-and post-maintenance operability requirements.
000028 Pressurizer Level Malfunction / 2    01                                     Op implications of PZR ref. leak abnormalities      2.8  1 000033 Loss of Intermediate Range NI/ 7                                           Determine/interpret equivalency between 01              source range, intermeaiate range, and power          3.0 1 range channel readings 000059 Accidental Liquid RadWaste ReI. / 9      02                                Interrelations with radioactive gas monitors        2.7 1 000076 High Reactor Coolant Activity /9                05                          Reasons for corrective actions as a result of        2.9 1 high fission product rad level in RCS W/E08 RCS Overcooling - PTS /4                              03                    Operate/monitor desired operating results.           3.6 1 (W/E14) High Containment Pressure /5                                              Interrelations between Loss of CTMT Integri~
2.9 1 2. Equipment Control Subtotal 2 2.3.12 Radiological safety principles pertaining to licensed operator 3.2 1 duties. 3. 2.3.14 Knowledge of radiation or contamination hazards. 3.4 1 Radiation 2.3.15 Radiation monitoring systems. 2.9 1 Control Subtotal 3 2.4.9 Low power/shutdown implications in accident mitigation.
and components and functions of control an 01                                safety systems, incl. instrumentation, signals,      3.4 1 interloci(s, failure modes and auto and manual features.
3.8 1 4. 2.4.19 EOP layout, symbols and icons. 3.4 1 Emergency 2.4.27 Knowledge of fire in the plant procedures.
W/E15 Containment Flooding /5              02                                    Op implications of procedures                        2.7 1 KIA Category Point Totals:                 2    2    1   1     2        1     Group Point Total:                                       9 Watts Bar Nuclear Plant NRC Exam                                                                                             March 2009
3.4 1 Procedures
 
/ Plan Subtotal 3 Tier 3 Point Total 10 Note: This outline was provided by the Chief Examiner.
ES-401                                                     4                                                        Form ES-401-2 NRC Exam ES-401                                        PWR Examination Outline                                            Fonn ES-401-2 Plant Systems- Tier 2/Group 1 (RO System # / Name          K1 K2 K3 K4    K5    K6    A1    A2    A3  A4    G              KIA Topic(s)            IR  #
ES-401 PWR Examination Outline Form ES-401-2 Facility:
02                                                    Knowledge of pwr supplies        2.5   1 003 Reactor Coolant Pump                                                                    to CCW pumps.
Watts Bar Date of Exam: May 2009 SRO Tier RO KIA Category Points SRO-Only Points 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
Im~acts of RCP seal 004 Chemical and Volume Control                                        05                    fai ures on CVCS, and            4.0    1 procedures.
* 1. 1 3 3 6 Emergency N/A N/A 2 2 4 & Abnormal 2 Plant 5 5 10 Evolutions Tier Totals 1 2 3 5 2. 1 2 3 Plant 2 Systems 3 5 8 Tier Totals 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that speCified in the table based on NRC revisions.
Imp of Keff by' means other 08                                      than 6-factor formula:          2.6   1 relationshi~ of count rate to reactivity c anges.
The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutjons 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 KIA statements.
005 Residual Heat Removal                06                                                Effect of loss on CSS.           3.1    1 Manually o~erate/monitor 006 Emergency Core Cooling                                                      05        transfer of CCS flowpaths        3.9   1 prior to recirculation.
: 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.  
01                                              Design/interlocks for            2.6  1 007 Pressurizer Relief/Quench Tank                                                          quench tank cooling 02                                      Method of fonnin~ steam          3.1  1 bubble in the PZ .
: 5. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.
Sys. se4>Oints, interlocks, 008 Component Cooling Water                                                          2.4.2 auto actions associated with      4.5  1 EOP entry conditions.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.  
04                                Effect of loss/malf. of PRT.     2.9   1 010 Pressurizer Pressure Control 01                    Impacts of and rerocedures        3.1  1 for faulty bistab e operation.
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
012 Reactor Protection                                                                      Local AO tasks during 2.4.35  emerg., including effects.       3.8  1 013 Engineered Safety Features        01                                                  Power supplies to ESFAS          3.6  1 Actuation                                                                                  equipment control.
7.* The generic (G) KlAs in Tiers 1.and 2 shall be selected from Section 2 of the KIA 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 KlAs. B. On the following pages, enter the KIA 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.
Monitor auto 0fes. of 022 Containment Cooling                                                    01              initiation of sa eguards          4.1  1 mode.
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-onlyexams.
02                                                      Connections/cause & effect        2.7  1 with refrigerant systems.
: 9. For Tier 3, select topiCS from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
025 Ice Condenser 02                                            Features/interlocks for          2.8  1 system control.
Limit SRO selections to KlAs that are linked to 10 CFR 55.43. Note: This outline was provided by the Chief Examiner.
Featureslinterlocks for rad 026 Containment Spray                        09                                            release (interlock on RWST        3.7  1 isol. after swapover).
Watts Bar Nuclear Plant NRC Exam May 2009 Page 1 of 5 ES-401 2 Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Emenencv and Abnormal Plant Evolutions
02              Monitor auto operation of         3.1  1 039 Main and Reheat Steam                                                                  MRSS isolation.
-Tier 1/GrouD 1 (SRQ) E/APE # I Name I Safetv Function K1 K2 K3 A1 A2 G KIA TODicls) IR # 000008 Pressurizer Vapor Space 2.1.20 Interpret and execute procedure steps. 4.6 1 Accident I 3 000011 Large Break LOCA I 3 01 Determine actions, based on RCS temperature and 4.7 1 pressure.
03                    Impacts of and procedures        2.7  1 059 Main Feedwater                                                                          for overfeeding event.
000025 Loss of RHR System 14 06 DetelTT!ine existence of proper RHR overpressure protection.
I~lications of pp. head 061 Auxiliary/Emergency Feedwater                  03                                      e ects when control vlv          2.6  1 shut.
3.4 1 000056 Loss of Offsite Power I 6 2.4.45 Prioritize and interpret the significance of each annunciator or alarm. 4.3 1 000065 Loss of Instrument Air I 8 03 Location and isolation of leaks. 2.9 1 W IE04 LOCA Outside Containment I 3 2.4.21 Parameters and logic used to assess the status of safety functions.
2.4.11  Knowledge of abnormal            4.0  1 062 AC Electrical Distribution                                                              procedures.
4.6 1 KIA Category Point Totals: 3 3 Group Point Total: 6 Watts Bar Nuclear Plant Exam May 2009 Page 2 of5 ES*401 3 Form ES*401*2 ES-401 PWR Examination Outline Emeraencyand Abnormal Plant Evolutions
01                          Effects on battery capacity      2.5   1 063 DC Electrical Distribution                                                              of discharge rate.
-Tier 1/GrouD 2 (SRQ) Form ES-401-2 E/APE # 1 Name 1 Safety Function K1 K2 K3 A1 A2 G KIA TODic(s) IR # 0000028 Pressurizer Level Malfunction 12 01 Interpret PZR level indicators and alarms. 3.6 1 000076 High Reactor Coolant Activity 1 9 02 Determine corrective actions for high reactor coolant activity.
07                                Effects of loss of air rcvrs. 2.7   1 064 Emergency Diesel Generator 08                                Effects of loss of fuel tanks. 3.2   1 073 Process Radiation Monitoring          01                                                Effect of loss/malf. on          3.6  1
3.4 1 W IE03 LOCA Cooldown -Depress. 1 4 2.4.30 Events that must be reported to internal organizations or external agencies.
                                                                                          .. releases .
4.1 1 W/E10 Natural Circ. With Steam Void 14 2.2.37 Determine op.erability and/or availability of safety relatea equipment.
076 Service Water                                                                          Predict chan~es associated 02                          with reactor turbo bldg.          2.6  1 closed cooling water temps.
4.6 1 KIA Category Point Totals: 2 2 Group Point Total: 4 Watts Bar Nuclear Plant Exam May 2009 Page 3 of5 ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S\ stems-Tier 2/Grou 1 (SRO) SYStem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Tooic(s) IR # 005 Residual Heat Removal 03 " ""/ Impacts of and procedures 3.1 1 for motor/pump malf. 008 Component Cooling 2.4.41 Obtain and inter:pret 4.6 1 station electrical and Water mechanical drawings.
01        Monitor pressure gauges.          3.1  1 078 Instrument Air                01                                                      Relations with sensor air.        2.8  1 103 Containment                    01                                                      Relations with CCS                3.6  1 3  2  2  3      3    3    2      3    2    2    3                                          28 KIA Category Point Totals:                                                                  Group Point Total:
026 Containment Spray 2.2.38 Conditions and limitations 4.5 1 in the facility license. 062 AC Electrical Distribution 06 safeguards buses ele rically separate.
Watts Bar Nuclear Plant NRC Exam                                                                                March 2009
3.9 1 063 DC Electrical Distribution 2.2.37 Determine 0p.erabiliJ:y 4.6 1 and/or availability of safety related equipment.
 
KIA Category Point Totals: 2 3 Group Point Total: Watts Bar Nuclear Plant Exam May 2009 Page 4 of 5 ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline F Plant Systems-Tier 2/Group 2 (SRO) System # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic(s) IR # 028 Hydrogen Recombiner Perform without reference to and Purge Control 2.4.49 procedures immediate 4.4 1 operation of components and controls.
ES-401                                                5                                                        Form ES-401-2 NRC Exam ES-401                                    PWR Examination Outline                                            Form ES-401-2 Plant Svstems- Tier 2/Grouo 2 (RO SYStem # / Name        K1 K2 K3 K4 K5    K6    A1    A2    A3  A4    G                KIA Tooic(s)              IR  #
055 Condenser Air Removal Use plant computers to 2.1.19 evaluate system or component 3.8 1 status. 079 Station Air 01 Cross connection with lAS. 3.2 1 KIA Category Point Totals: 1 2 Group Point Total: 3 Watts Bar Nuclear Plant Exam May 2009 Page 5 of 5 ES*401 Generic Knowledge and Abilities Outline (Tier 3) NRC EXAM Facility:
001 Control Rod Drive                          03                                Effect of loss on reactor trip        3.7  1 breakers.
Watts Bar Date of Exam: May 2009 Category KIA # Topic 1. Conduct of Operations
002 Reactor Coolant                03                                            Effect of loss/malf. on              4.2  1 containment.
: 2. Equipment Control 2.1.8 Subtotal 2.2.15 2.2.42 Coordinate activities outside the control room. Determine expected plant configuration using documents.
016 Non-nuclear                          01                                      Separation of control and            2.7  1 Instrumentation                                                                    protection circuits.
System parameters that are Tech Spec entry conditions.
017 In-Core Temperature      01                                                                                        3.2  1 Monitor                                                                            Relationship with plant computer.
Form ES*401*3 SRO SRO-Only IR # 4.1 4.6 Subtotal 2 3. Radiation Control 2.3.4 Radiation exposure limits. 2.3.15 Knowledge of radiation monitoring systems. 3.1 Subtotal 2 4. Emergency Procedures
027 Containment Iodine          01                                                                                      3.1 1 Removal                                                                            Power supplies to fans.
/ Plan Tier 3 Point Total 2.4.35 Local AO emergency tasks and operational effects. 2.4.38 Take actions of EPlan, inc!. emergency coordinator.
033 Spent Fuel Pool Cooling            01                                          Design features for spent fuel        2.9  1 level.
Subtotal Note: This outline was provided by the Chief Examiner.
034 Fuel Handling Equipment                          02                          Monitor water level in refuel canal  2.9  1 045 Main Turbine Generator                                                  2.2.37 Determine operability/availability    3.6  1 of safety related equipment.
4.4 2 7 ES-301 Administrative Topics Outline Form ES-301-1 Facility:
068 Liquid Radwaste                                                02              Monitor automatic isolation.         3.6  1 072 Area Radiation Monitoring                              01                    Im~acts/procedures of erratic or      2.7  1 fai ed power supply.
Watts Bar Date of Examination:
1  1 1  1  1      1    1    1      1    0    1                                              10 KIA Category Point Totals:                                                        Group Point Total:
05/18/2009 Examination Level: SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code* 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating Conduct of Operations R,M characteristics, reactor behavior, and instrument interpretation.
Watts Bar Nuclear Plant NRC Exam                                                        March 2009
Calculate Shutdown Margin 2.1.25 Ability to interpret reference materials, such as Conduct of Operations R,M graphs, curves, tables, etc. Calculate Target Boron Concentration for Load Escalation Using Appendix E of 501-62.02.
 
2.2.40 Ability to apply Technical Specifications for a Equipment Control R,M system. Perform a QPTR Calculation per 0-51-0-21.
ES*401                            Generic Knowledge and Abilities Outline (Tier 3)                   Form ES*401*3 NRC EXAM Facility: Watts Bar                    Date of Exam:      May 2009                                        RO Category            KIA #                                 Topic                                RO        SRO-Only IR    #    IR      #
Radiation Control ----2.4.39 Knowledge of RO responsibilities in emergency Emergency Procedures 1 R,D plan implementation.
2.1.4    Operator responsibilities for shift staffing.                  3.3    1 2.1.42  New and spent fuel movement procedures.                        2.5    1 1.
Plan Perform Control Room Operator Medical Response Checklist.
Conduct of Operations Subtotal                                                                        2 2.2.20   Process for managing troubleshooting activities.               2.6     1 2.2.21  Pre- and post-maintenance operability requirements.            2.9    1 2.
Equipment Control Subtotal                                                                        2 2.3.12    Radiological safety principles pertaining to licensed operator 3.2    1 duties.
2.3.14    Knowledge of radiation or contamination hazards.              3.4     1 3.
Radiation          2.3.15    Radiation monitoring systems.                                  2.9     1 Control Subtotal                                                                        3 2.4.9    Low power/shutdown implications in accident mitigation.        3.8    1 2.4.19    EOP layout, symbols and icons.                                3.4    1 4.
Emergency          2.4.27    Knowledge of fire in the plant procedures.                    3.4    1 Procedures /
Plan Subtotal                                                                        3 Tier 3 Point Total                                                                                10 Note: This outline was provided by the Chief Examiner.
 
ES-401                                                 PWR Examination Outline                                             Form ES-401-2 Facility: Watts Bar                    Date of Exam: May 2009                                                                  SRO Tier                                          RO KIA Category Points                                        SRO-Only Points 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
* 3            3                 6
: 1.            1 Emergency                                          N/A                      N/A                        2            2                  4
& Abnormal          2 Plant 5            5                10 Evolutions    Tier Totals 2            3                 5 1
2.
2 1           2                 3 Plant Systems Tier Totals 3            5                  8
: 3. Generic Knowledge and Abilities            1         2        3          4                  1     2    3      4              7 1      2    2     2 Note:    1.     Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
: 2.      The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that speCified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
: 3.     Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutjons 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 KIA statements.
: 4.     Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
: 5.      Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 6.      Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*    The generic (G) KlAs in Tiers 1.and 2 shall be selected from Section 2 of the KIA 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 KlAs.
B.     On the following pages, enter the KIA 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-onlyexams.
: 9.     For Tier 3, select topiCS from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals
(#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
Note: This outline was provided by the Chief Examiner.
Watts Bar Nuclear Plant NRC Exam                                                                                  May 2009 Page 1 of 5
 
ES-401                                                          2                                                              Form ES-401-2 I ES-401                                              PWR Examination Outline                                                   Form ES-401-2 Emenencv and Abnormal Plant Evolutions - Tier 1/GrouD 1 (SRQ)
E/APE # I Name I Safetv Function  K1  K2    K3  A1    A2        G                                KIA TODicls)                         IR  #
000008 Pressurizer Vapor Space                                  2.1.20      Interpret and execute procedure steps.                       4.6  1 Accident I 3 000011 Large Break LOCA I 3                              01                Determine actions, based on RCS temperature and              4.7  1 pressure.
000025 Loss of RHR System 14                              06                DetelTT!ine existence of proper RHR overpressure            3.4  1 protection.
000056 Loss of Offsite Power I 6                                2.4.45      Prioritize and interpret the significance of each            4.3  1 annunciator or alarm.
000065 Loss of Instrument Air I 8                        03                Location and isolation of leaks.                            2.9  1 W IE04 LOCA Outside Containment I 3                              2.4.21      Parameters and logic used to assess the status of            4.6  1 safety functions.
3        3                                                                          6 KIA Category Point Totals:                                                  Group Point Total:
Watts Bar Nuclear Plant Exam                                                                                                            May 2009 Page 2 of5
 
ES*401                                                        3                                                                Form ES*401*2 ES-401                                              PWR Examination Outline                                                  Form ES-401-2 Emeraencyand Abnormal Plant Evolutions - Tier 1/GrouD 2 (SRQ)
E/APE # 1 Name 1 Safety Function    K1  K2  K3  A1    A2      G                        KIA TODic(s)                          IR  #
0000028 Pressurizer Level Malfunction 12                      01                Interpret PZR level indicators and alarms.            3.6  1 000076 High Reactor Coolant Activity 1 9                      02                Determine corrective actions for high reactor        3.4  1 coolant activity.
W IE03 LOCA Cooldown - Depress. 1 4                                  2.4.30    Events that must be reported to internal              4.1  1 organizations or external agencies.
W/E10 Natural Circ. With Steam Void 14                              2.2.37    Determine op.erability and/or availability of        4.6  1 safety relatea equipment.
KIA Category Point Totals:                                    2        2      Group Point Total:                                          4 Watts Bar Nuclear Plant Exam                                                                                                          May 2009 Page 3 of5
 
ES-401                                                    4                                                          Form ES-401-2 ES-401                                        PWR Examination Outline                                                Form ES-401-2 Plant S\ stems- Tier 2/Grou 1 (SRO)
SYStem # / Name          K1 K2 K3 K4 K5    K6      A1    A2    A3  A4      G                KIA Tooic(s)            IR    #
                                                                                    " ""/
03                        Impacts of and procedures        3.1  1 005 Residual Heat Removal                                                                for motor/pump malf.
Obtain and inter:pret 008 Component Cooling                                                          2.4.41    station electrical and          4.6  1 Water                                                                                    mechanical drawings.
2.2.38    Conditions and limitations      4.5  1 026 Containment Spray                                                                    in the facility license.
06                        Ke~ing safeguards buses          3.9  1 062 AC Electrical Distribution                                                            ele rically separate.
Determine 0p.erabiliJ:y 063 DC Electrical Distribution                                                  2.2.37    and/or availability of safety  4.6    1 related equipment.
KIA Category Point Totals:
2                  3 Group Point Total:
                                                                                                                                  ~I Watts Bar Nuclear Plant Exam                                                                                                  May 2009 Page 4 of 5
 
ES-401                                                5                                                      Form ES-401-2
                                                                                                                ~,..
ES-401                                    PWR Examination Outline                                            F Plant Systems- Tier 2/Group 2 (SRO)
System # I Name      K1 K2 K3 K4 K5  K6    A1    A2    A3    A4      G              KIA Topic(s)            IR #
028 Hydrogen Recombiner                                                        Perform without reference to and Purge Control                                                        2.4.49 procedures immediate            4.4 1 operation of components and controls.
055 Condenser Air Removal                                                      Use plant computers to 2.1.19 evaluate system or component    3.8 1 status.
079 Station Air                                        01                      Cross connection with lAS.      3.2 1 1                  2                                        3 KIA Category Point Totals:                                                      Group Point Total:
Watts Bar Nuclear Plant Exam                                                                      May 2009 Page 5 of 5
 
ES*401                          Generic Knowledge and Abilities Outline (Tier 3)    Form ES*401*3 NRC EXAM Facility: Watts Bar                    Date of Exam:      May 2009                          SRO Category            KIA #                              Topic                            SRO-Only IR      #
2.1.8  Coordinate activities outside the control room.              4.1 1.
Conduct of Operations Subtotal 2.2.15  Determine expected plant configuration using documents.
2.2.42  System parameters that are Tech Spec entry conditions.      4.6 2.
Equipment Control Subtotal                                                                      2 2.3.4    Radiation exposure limits.
2.3.15  Knowledge of radiation monitoring systems.                  3.1 3.
Radiation Control Subtotal                                                                      2 2.4.35  Local AO emergency tasks and operational effects.
2.4.38  Take actions of EPlan, inc!. emergency coordinator.          4.4 4.
Emergency Procedures /
Plan Subtotal                                                                      2 Tier 3 Point Total                                                                                7 Note: This outline was provided by the Chief Examiner.
 
ES-301                            Administrative Topics Outline                            Form ES-301-1 Facility: Watts Bar                                                  Date of Examination: 05/18/2009 Examination Level: RO~ SRO          0                                Operating Test Number: 1 Administrative Topic          Type Describe activity to be performed (See Note)              Code*
2.1.7  Ability to evaluate plant performance and make operational judgments based on operating Conduct of Operations            R,M                characteristics, reactor behavior, and instrument interpretation.
Calculate Shutdown Margin 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Conduct of Operations            R,M Calculate Target Boron Concentration for Load Escalation Using Appendix E of 501-62.02.
2.2.40 Ability to apply Technical Specifications for a Equipment Control                R,M                system.
Perform a QPTR Calculation per 0-51-0-21.
Radiation Control                  -                                        ---
2.4.39 Knowledge of RO responsibilities in emergency Emergency Procedures 1                                plan implementation.
R,D Plan                                         Perform Control Room Operator Medical Response Checklist.
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.
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 for ROs; 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams 1; randomly selected)
* Type Codes & Criteria:             (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank   (~3  for ROs; ~ 4 for SROs & RO retakes)
ES 301, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 Facility:
(N)ew or (M)odified from bank     (~ 1)
Watts Bar Date of Examination:
(P)revious 2 exams   (~ 1; randomly selected)
05/18/2009 Examination Level: ROO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code* 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating Conduct of Operations R,M characteristics, reactor behavior, and instrument interpretation.
ES 301, Page 22 of 27
Perform Technical Review of Shutdown Margin Calcu lation. 2.1.25 Ability to interpret reference materials, such as Conduct of Operations R,M graphs, curves, tables, etc. Perform Independent Verification of Target Boron Concentration for Load Escalation Calculation.
 
2.2.24 Knowledge of the process used to track Equipment Control R,N inoperable alarms. Review/Approve Disabled Alarm Checklist.  
ES-301                             Administrative Topics Outline                             Form ES-301-1 Facility: Watts Bar                                                   Date of Examination: 05/18/2009 Examination Level: ROO SRO ~                                          Operating Test Number: 1 Administrative Topic           Type Describe activity to be performed (See Note)             Code*
2.1.7   Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument Conduct of Operations            R,M                  interpretation.
Perform Technical Review of Shutdown Margin Calcu lation.
2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Conduct of Operations            R,M Perform Independent Verification of Target Boron Concentration for Load Escalation Calculation.
2.2.24 Knowledge of the process used to track Equipment Control                 R,N                 inoperable alarms.
Review/Approve Disabled Alarm Checklist.
2.3.6    Ability to approve release permits.
Radiation Control                R,N Review/Approve Liquid Release Permit.
2.4.41 Knowledge of the emergency action level Emergency Procedures /                                thresholds and classifications.
R,D Plan Classify an Event (High RCS Activity, SGTRlFauited SG).
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)
ES 301, Page 22 of 27
 
ES-301                            Control Room/In-Plant Systems Outline                            Form ES-301-2 Facility: Watts Bar                                                    Date of Examination: May 2009 Exam Level: RO ~ SRO-I          0  SRO-U    0                        Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety System I JPM Title                                      Type Code*
Function
: a. Withdraw Shutdown Banks.                                                                  ALMS              1
: b. Place Excess Letdown in Service.                                                            DC              2
: c. Isolate Cold Leg Accumulators.                                                            AENS              3
: d. Place RHR Spray in Service.                                                                ADLS            4P
: e. Place the Containment H2 Recombiner in Service.                                            DLS            5
: f. Synchronize DIG from Main Control Room.                                                    MS              6
: g. Return Power Range Monitor to Service.                                                    ADS              7
: h. Shutdown A Train Emergency Gas Treatment System.                                            OS              8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Perform Local Boration of RCS.                                                          AELMR            1
: j. Local Isolation of Steam Lines Following a SGTR.                                            MEL            3
: k. Place Cation Bed in Service for High RCS Activity.                                        MER            9
  @        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 I SRO-I I SRO-U (A)lternate path                                                            4-6 I  4-6 I 2-3 (C)ontrol room (D)irect from bank                                                          ~91    ~8    I ~4 (E)mergency or abnormal in-plant                                            ~ 1 I  ~1 I ~ 1 (EN)gineered safety feature                                                  - I    - I ~1 (L)ow-Power I Shutdown                                                      ~1 I    ~1 I ~ 1 (N)ew or (M)odified from bank including 1(A)                                ~21    ~2 I ~ 1 (P)revious 2 exams                                                          ~3      ~ 3 I ~ 2 (randomly selected)
(R)CA                                                                        ~1  I  ~1 I ~ 1 (S)imulator ES-301, Page 23 of 27
 
ES-301                            Control Roomlln-Plant Systems Outline                            Form ES-301-2 Facility: Watts Bar                                                    Date of Examination: May 2009 Exam Level: RO      0    SRO-I [gI SRO-U      0                        Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety System / JPM Title                                      Type Code*
Function
: a. Withdraw Shutdown Banks.                                                                  ALMS              1
: b. Place Excess Letdown in Service.                                                            DC              2
: c. Isolate Cold Leg Accumulators.                                                            AENS              3
: d. Place RHR Spray in Service.                                                                ADLS            4P
: e. Place the Containment H2 Recombiner in Service.                                            DLS            5
: f. (Not required for I-SRO).                                                                    -              -
: g. Return Power Range Monitor to Service.                                                    ADS              7
: h. Shutdown A Train Emergency Gas Treatment System.                                            DS              8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Perform Local Boration of RCS.                                                          AELMR            1
: j. Local Isolation of Steam Lines Following a SGTR.                                            MEL            3
: k. Place Cation Bed in Service for High RCS Activity.                                        MER            9
  @        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 (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 ES-301, Page 23 of 27


====2.3.6 Ability====
ES-301                           Control Room/In-Plant Systems Outline                             Form ES-301-2 Facility: Watts Bar                                                     Date of Examination: May 2009 Exam Level: RO       0    SRO-I 0   SRO-U ~                            Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
to approve release permits. Radiation Control R,N Review/Approve Liquid Release Permit. 2.4.41 Knowledge of the emergency action level Emergency Procedures
Safety System / JPM Title                                       Type Code*
/ R,D thresholds and classifications.
Function
Plan Classify an Event (High RCS Activity, SGTRlFauited SG). 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.
: a. (Not required for U - SRO).                                                                   -             -
* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank for ROs; 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams 1; randomly selected)
: b. (Not required for U - SRO).                                                                   -             -
ES 301, Page 22 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
: c. Isolate Cold Leg Accumulators.                                                           AENS             3
Watts Bar Date of Examination:
: d. (Not required for U - SRO).                                                                   -             -
May 2009 Exam Level: RO SRO-I 0 SRO-U 0 Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. Withdraw Shutdown Banks. ALMS 1 b. Place Excess Letdown in Service. DC 2 c. Isolate Cold Leg Accumulators.
: e. Place the Containment H2 Recombiner in Service.                                           DLS             5
AENS 3 d. Place RHR Spray in Service. ADLS 4P e. Place the Containment H2 Recombiner in Service. DLS 5 f. Synchronize DIG from Main Control Room. MS 6 g. Return Power Range Monitor to Service. ADS 7 h. Shutdown A Train Emergency Gas Treatment System. OS 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Perform Local Boration of RCS. AELMR 1 j. Local Isolation of Steam Lines Following a SGTR. MEL 3 k. Place Cation Bed in Service for High RCS Activity.
: f. (Not required for U - SRO).                                                                   -             -
MER 9 @ 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 I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank I (E)mergency or abnormal in-plant 1 I I 1 (EN)gineered safety feature -I -I 1 (L)ow-Power I Shutdown 1 I I 1 (N)ew or (M)odified from bank including 1 (A) I 1 (P)revious 2 exams 3 I 2 (randomly selected) (R)CA 1 I I 1 (S)imulator ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:
: g. Return Power Range Monitor to Service.                                                     ADS             7
Watts Bar Date of Examination:
: h. (Not required for U - SRO).                                                                   -             -
May 2009 Exam Level: RO 0 SRO-I [gI SRO-U 0 Operating Test Number: 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 a. Withdraw Shutdown Banks. ALMS 1 b. Place Excess Letdown in Service. DC 2 c. Isolate Cold Leg Accumulators.
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
AENS 3 d. Place RHR Spray in Service. ADLS 4P e. Place the Containment H2 Recombiner in Service. DLS 5 f. (Not required for I-SRO). --g. Return Power Range Monitor to Service. ADS 7 h. Shutdown A Train Emergency Gas Treatment System. DS 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Perform Local Boration of RCS. AELMR 1 j. Local Isolation of Steam Lines Following a SGTR. MEL 3 k. Place Cation Bed in Service for High RCS Activity.
: i. Perform Local Boration of RCS.                                                           AELMR             1
MER 9 @ 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 / 4 (E)mergency or abnormal in-plant 1 / / 1 (EN)gineered safety feature -/ -/ 1 (L)ow-Power
: j. (Not required for U - SRO).                                                                   -           -
/ Shutdown 1 / / 1 (N)ew or (M)odified from bank including 1 (A) / 1 (P)revious 2 exams 3 / 2 (randomly selected) (R)CA 1 / / 1 (S)imulator ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
: k. Place Cation Bed in Service for High RCS Activity.                                         MER             9
Watts Bar Date of Examination:
  @       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.
May 2009 Exam Level: RO 0 SRO-I 0 SRO-U Operating Test Number: 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 a. (Not required for U -SRO). --b. (Not required for U -SRO). --c. Isolate Cold Leg Accumulators.
                    *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 (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)
AENS 3 d. (Not required for U -SRO). --e. Place the Containment H2 Recombiner in Service. DLS 5 f. (Not required for U -SRO). --g. Return Power Range Monitor to Service. ADS 7 h. (Not required for U -SRO). --In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Perform Local Boration of RCS. AELMR 1 j. (Not required for U -SRO). --k. Place Cation Bed in Service for High RCS Activity.
(R)CA                                                                       ~ 1 /   ~1    / ~1 (S)imulator ES-301, Page 23 of 27}}
MER 9 @ 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 / (E)mergency or abnormal in-plant 1 / / 1 (EN)gineered safety feature -/ -/ 1 (L)ow-Power  
/ Shutdown 1 / / 1 (N)ew or (M)odified from bank including 1 (A) / 1 (P)revious 2 exams / 2 (randomly selected) (R)CA 1 / / 1 (S)imulator ES-301, Page 23 of 27}}

Latest revision as of 02:39, 14 November 2019

Initial Exam 2009-301 Draft Administrative Documents
ML092810413
Person / Time
Site: Watts Bar  Tennessee Valley Authority icon.png
Issue date: 10/08/2009
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-390/09-301, 50-391/09-301
Download: ML092810413 (17)
v • d • e


Text

ES*401 PWR Examination Outline Form ES*401*2 NRC Exam Facility: Watts Bar Date of Exam: May 2009 RO Tier RO KIA Category Points SRO-Only Points 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

  • 3 3 3 3 3 3 18
1. 1 Emergency N/A N/A 2 2 1 1 2 1 9

& Abnormal 2 Plant Tier Totals 5 5 4 4 5 4 27 Evolutions 3 2 2 3 3 3 2 3 2 2 3 28 1

2.

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 2 2 3 3 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions 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 KIA statements.
4. Select topiCS from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KlAs.

s. On the following pages, enter the KIA 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-onlyexams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals

(#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

Note: This outline was provided by the Chief Examiner.

Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 2 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emeraenc and Abnormal Plant Evolutions - Tier 1/GrouD 1 eRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KIA Tooic(s) IR #

000008 Pressurizer Vapor Space 2.2.20 Knowledge of the process for managing 2.6 1 Accident/3 troublestiooting activities.

000009 Small Break LOCA / 3 03 Interrelations between SBLOCA and S/Gs. 3.0 1 000011 Large Break LOCA / 3 05 Operate/monitor man/auto transfer of charging 4.3 1 suction to borated source.

000015/17 RCP Malfunctions / 4 10 Interrelations between RCP malfunctions and 2.8 1 indicators/controls.

000025 Loss of RHR System /4 01 Reasons for shift to alternate flowpath as it applies to 3.1 1 LossofRHR.

000026 Loss of Component Cooling 04 Reasons for effect on CCW flow header of a loss of 3.5 1 CCW.

Water /8 000027 Pressurizer Pressure Control 03 Op implications of latent heat of vaporization. 2.6 1 System Malfunction / 3 000029 ATWS /1 12 Operate/monitor M/G set pwr supply & Rx trip brkrs. 4.1 1 000038 Steam Gen. Tube Rupture /3 03 Op implications of natural circulation. 3.9 1 000054 (CE/E06) Loss of Main 2.2.22 Knowledge of LCOs and safety limits. 4.0 1 Feedwater /4 000056 Loss of Offsite Power / 6 04 Implication of saturation conditions for the systems. 3.1 1 000057 Loss of Vital AC Elec. Inst. Bus 19 Determinelinterpret auto actions that occur. 4.0 1

/6 000058 Loss of DC Power / 6 02 Operate/monitor dc input brkr, freq. meter, ac output 3.1 1 detector and ground fault detector.

000062 Loss of Nuclear Service Water 01 Determinelinterpret location of a leak in the SWS 2.9 1

/4 000065 Loss of Instrument Air /8 03 Reasons for effects on plant ops of isolating certain 2.9 1 equipment from instrument air.

W /E04 LOCA Outside Containment / 3 Interrelations between LOCA outside containment 01 and comp'onents and functions of control and safety 3.5 1 s~tems, inc!. instrumentation, signals, interlocks, failure modes and auto and manual features.

W/E11 Loss of Emergency Coolant 01 Determine/interpret facility conditions and select 3.4 1 appropriate procedures.

Recirc./4 000040 (W/E12) Steam Line Rupture- 2.2.36 Analyze effect of maintenance activities on status of 3.1 1 LCOs.

Excessive Heat Transfer /4 3 3 3 3 3 3 18 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 3 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emel encv and Abnormal Plant Evolutions - Tier 1/GrouD 2 IRQ)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KIA TODicls) IR #

000001 Continuous Rod Withdrawal/1 01 petermine/interpret reactor tripped brkr 4.2 1 IndIcator.

000003 Dropped Control Rod /1 Interpret indications to verify status and 2.2.44 operation of a s~tem, and ~erator actions 4.2 1 and directives a ecting con Itions.

000028 Pressurizer Level Malfunction / 2 01 Op implications of PZR ref. leak abnormalities 2.8 1 000033 Loss of Intermediate Range NI/ 7 Determine/interpret equivalency between 01 source range, intermeaiate range, and power 3.0 1 range channel readings 000059 Accidental Liquid RadWaste ReI. / 9 02 Interrelations with radioactive gas monitors 2.7 1 000076 High Reactor Coolant Activity /9 05 Reasons for corrective actions as a result of 2.9 1 high fission product rad level in RCS W/E08 RCS Overcooling - PTS /4 03 Operate/monitor desired operating results. 3.6 1 (W/E14) High Containment Pressure /5 Interrelations between Loss of CTMT Integri~

and components and functions of control an 01 safety systems, incl. instrumentation, signals, 3.4 1 interloci(s, failure modes and auto and manual features.

W/E15 Containment Flooding /5 02 Op implications of procedures 2.7 1 KIA Category Point Totals: 2 2 1 1 2 1 Group Point Total: 9 Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 4 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Fonn ES-401-2 Plant Systems- Tier 2/Group 1 (RO System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic(s) IR #

02 Knowledge of pwr supplies 2.5 1 003 Reactor Coolant Pump to CCW pumps.

Im~acts of RCP seal 004 Chemical and Volume Control 05 fai ures on CVCS, and 4.0 1 procedures.

Imp of Keff by' means other 08 than 6-factor formula: 2.6 1 relationshi~ of count rate to reactivity c anges.

005 Residual Heat Removal 06 Effect of loss on CSS. 3.1 1 Manually o~erate/monitor 006 Emergency Core Cooling 05 transfer of CCS flowpaths 3.9 1 prior to recirculation.

01 Design/interlocks for 2.6 1 007 Pressurizer Relief/Quench Tank quench tank cooling 02 Method of fonnin~ steam 3.1 1 bubble in the PZ .

Sys. se4>Oints, interlocks, 008 Component Cooling Water 2.4.2 auto actions associated with 4.5 1 EOP entry conditions.

04 Effect of loss/malf. of PRT. 2.9 1 010 Pressurizer Pressure Control 01 Impacts of and rerocedures 3.1 1 for faulty bistab e operation.

012 Reactor Protection Local AO tasks during 2.4.35 emerg., including effects. 3.8 1 013 Engineered Safety Features 01 Power supplies to ESFAS 3.6 1 Actuation equipment control.

Monitor auto 0fes. of 022 Containment Cooling 01 initiation of sa eguards 4.1 1 mode.

02 Connections/cause & effect 2.7 1 with refrigerant systems.

025 Ice Condenser 02 Features/interlocks for 2.8 1 system control.

Featureslinterlocks for rad 026 Containment Spray 09 release (interlock on RWST 3.7 1 isol. after swapover).

02 Monitor auto operation of 3.1 1 039 Main and Reheat Steam MRSS isolation.

03 Impacts of and procedures 2.7 1 059 Main Feedwater for overfeeding event.

I~lications of pp. head 061 Auxiliary/Emergency Feedwater 03 e ects when control vlv 2.6 1 shut.

2.4.11 Knowledge of abnormal 4.0 1 062 AC Electrical Distribution procedures.

01 Effects on battery capacity 2.5 1 063 DC Electrical Distribution of discharge rate.

07 Effects of loss of air rcvrs. 2.7 1 064 Emergency Diesel Generator 08 Effects of loss of fuel tanks. 3.2 1 073 Process Radiation Monitoring 01 Effect of loss/malf. on 3.6 1

.. releases .

076 Service Water Predict chan~es associated 02 with reactor turbo bldg. 2.6 1 closed cooling water temps.

01 Monitor pressure gauges. 3.1 1 078 Instrument Air 01 Relations with sensor air. 2.8 1 103 Containment 01 Relations with CCS 3.6 1 3 2 2 3 3 3 2 3 2 2 3 28 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 5 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems- Tier 2/Grouo 2 (RO SYStem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Tooic(s) IR #

001 Control Rod Drive 03 Effect of loss on reactor trip 3.7 1 breakers.

002 Reactor Coolant 03 Effect of loss/malf. on 4.2 1 containment.

016 Non-nuclear 01 Separation of control and 2.7 1 Instrumentation protection circuits.

017 In-Core Temperature 01 3.2 1 Monitor Relationship with plant computer.

027 Containment Iodine 01 3.1 1 Removal Power supplies to fans.

033 Spent Fuel Pool Cooling 01 Design features for spent fuel 2.9 1 level.

034 Fuel Handling Equipment 02 Monitor water level in refuel canal 2.9 1 045 Main Turbine Generator 2.2.37 Determine operability/availability 3.6 1 of safety related equipment.

068 Liquid Radwaste 02 Monitor automatic isolation. 3.6 1 072 Area Radiation Monitoring 01 Im~acts/procedures of erratic or 2.7 1 fai ed power supply.

1 1 1 1 1 1 1 1 1 0 1 10 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam March 2009

ES*401 Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3 NRC EXAM Facility: Watts Bar Date of Exam: May 2009 RO Category KIA # Topic RO SRO-Only IR # IR #

2.1.4 Operator responsibilities for shift staffing. 3.3 1 2.1.42 New and spent fuel movement procedures. 2.5 1 1.

Conduct of Operations Subtotal 2 2.2.20 Process for managing troubleshooting activities. 2.6 1 2.2.21 Pre- and post-maintenance operability requirements. 2.9 1 2.

Equipment Control Subtotal 2 2.3.12 Radiological safety principles pertaining to licensed operator 3.2 1 duties.

2.3.14 Knowledge of radiation or contamination hazards. 3.4 1 3.

Radiation 2.3.15 Radiation monitoring systems. 2.9 1 Control Subtotal 3 2.4.9 Low power/shutdown implications in accident mitigation. 3.8 1 2.4.19 EOP layout, symbols and icons. 3.4 1 4.

Emergency 2.4.27 Knowledge of fire in the plant procedures. 3.4 1 Procedures /

Plan Subtotal 3 Tier 3 Point Total 10 Note: This outline was provided by the Chief Examiner.

ES-401 PWR Examination Outline Form ES-401-2 Facility: Watts Bar Date of Exam: May 2009 SRO Tier RO KIA Category Points SRO-Only Points 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

  • 3 3 6
1. 1 Emergency N/A N/A 2 2 4

& Abnormal 2 Plant 5 5 10 Evolutions Tier Totals 2 3 5 1

2.

2 1 2 3 Plant Systems Tier Totals 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that speCified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutjons 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 KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1.and 2 shall be selected from Section 2 of the KIA 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 KlAs.

B. On the following pages, enter the KIA 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-onlyexams.

9. For Tier 3, select topiCS from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals

(#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

Note: This outline was provided by the Chief Examiner.

Watts Bar Nuclear Plant NRC Exam May 2009 Page 1 of 5

ES-401 2 Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Emenencv and Abnormal Plant Evolutions - Tier 1/GrouD 1 (SRQ)

E/APE # I Name I Safetv Function K1 K2 K3 A1 A2 G KIA TODicls) IR #

000008 Pressurizer Vapor Space 2.1.20 Interpret and execute procedure steps. 4.6 1 Accident I 3 000011 Large Break LOCA I 3 01 Determine actions, based on RCS temperature and 4.7 1 pressure.

000025 Loss of RHR System 14 06 DetelTT!ine existence of proper RHR overpressure 3.4 1 protection.

000056 Loss of Offsite Power I 6 2.4.45 Prioritize and interpret the significance of each 4.3 1 annunciator or alarm.

000065 Loss of Instrument Air I 8 03 Location and isolation of leaks. 2.9 1 W IE04 LOCA Outside Containment I 3 2.4.21 Parameters and logic used to assess the status of 4.6 1 safety functions.

3 3 6 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant Exam May 2009 Page 2 of5

ES*401 3 Form ES*401*2 ES-401 PWR Examination Outline Form ES-401-2 Emeraencyand Abnormal Plant Evolutions - Tier 1/GrouD 2 (SRQ)

E/APE # 1 Name 1 Safety Function K1 K2 K3 A1 A2 G KIA TODic(s) IR #

0000028 Pressurizer Level Malfunction 12 01 Interpret PZR level indicators and alarms. 3.6 1 000076 High Reactor Coolant Activity 1 9 02 Determine corrective actions for high reactor 3.4 1 coolant activity.

W IE03 LOCA Cooldown - Depress. 1 4 2.4.30 Events that must be reported to internal 4.1 1 organizations or external agencies.

W/E10 Natural Circ. With Steam Void 14 2.2.37 Determine op.erability and/or availability of 4.6 1 safety relatea equipment.

KIA Category Point Totals: 2 2 Group Point Total: 4 Watts Bar Nuclear Plant Exam May 2009 Page 3 of5

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S\ stems- Tier 2/Grou 1 (SRO)

SYStem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Tooic(s) IR #

" ""/

03 Impacts of and procedures 3.1 1 005 Residual Heat Removal for motor/pump malf.

Obtain and inter:pret 008 Component Cooling 2.4.41 station electrical and 4.6 1 Water mechanical drawings.

2.2.38 Conditions and limitations 4.5 1 026 Containment Spray in the facility license.

06 Ke~ing safeguards buses 3.9 1 062 AC Electrical Distribution ele rically separate.

Determine 0p.erabiliJ:y 063 DC Electrical Distribution 2.2.37 and/or availability of safety 4.6 1 related equipment.

KIA Category Point Totals:

2 3 Group Point Total:

~I Watts Bar Nuclear Plant Exam May 2009 Page 4 of 5

ES-401 5 Form ES-401-2

~,..

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

System # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic(s) IR #

028 Hydrogen Recombiner Perform without reference to and Purge Control 2.4.49 procedures immediate 4.4 1 operation of components and controls.

055 Condenser Air Removal Use plant computers to 2.1.19 evaluate system or component 3.8 1 status.

079 Station Air 01 Cross connection with lAS. 3.2 1 1 2 3 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant Exam May 2009 Page 5 of 5

ES*401 Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3 NRC EXAM Facility: Watts Bar Date of Exam: May 2009 SRO Category KIA # Topic SRO-Only IR #

2.1.8 Coordinate activities outside the control room. 4.1 1.

Conduct of Operations Subtotal 2.2.15 Determine expected plant configuration using documents.

2.2.42 System parameters that are Tech Spec entry conditions. 4.6 2.

Equipment Control Subtotal 2 2.3.4 Radiation exposure limits.

2.3.15 Knowledge of radiation monitoring systems. 3.1 3.

Radiation Control Subtotal 2 2.4.35 Local AO emergency tasks and operational effects.

2.4.38 Take actions of EPlan, inc!. emergency coordinator. 4.4 4.

Emergency Procedures /

Plan Subtotal 2 Tier 3 Point Total 7 Note: This outline was provided by the Chief Examiner.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: 05/18/2009 Examination Level: RO~ SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating Conduct of Operations R,M characteristics, reactor behavior, and instrument interpretation.

Calculate Shutdown Margin 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Operations R,M Calculate Target Boron Concentration for Load Escalation Using Appendix E of 501-62.02.

2.2.40 Ability to apply Technical Specifications for a Equipment Control R,M system.

Perform a QPTR Calculation per 0-51-0-21.

Radiation Control - ---

2.4.39 Knowledge of RO responsibilities in emergency Emergency Procedures 1 plan implementation.

R,D Plan Perform Control Room Operator Medical Response Checklist.

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)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: 05/18/2009 Examination Level: ROO SRO ~ Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument Conduct of Operations R,M interpretation.

Perform Technical Review of Shutdown Margin Calcu lation.

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Operations R,M Perform Independent Verification of Target Boron Concentration for Load Escalation Calculation.

2.2.24 Knowledge of the process used to track Equipment Control R,N inoperable alarms.

Review/Approve Disabled Alarm Checklist.

2.3.6 Ability to approve release permits.

Radiation Control R,N Review/Approve Liquid Release Permit.

2.4.41 Knowledge of the emergency action level Emergency Procedures / thresholds and classifications.

R,D Plan Classify an Event (High RCS Activity, SGTRlFauited SG).

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)

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2009 Exam Level: RO ~ SRO-I 0 SRO-U 0 Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System I JPM Title Type Code*

Function

a. Withdraw Shutdown Banks. ALMS 1
b. Place Excess Letdown in Service. DC 2
c. Isolate Cold Leg Accumulators. AENS 3
d. Place RHR Spray in Service. ADLS 4P
e. Place the Containment H2 Recombiner in Service. DLS 5
f. Synchronize DIG from Main Control Room. MS 6
g. Return Power Range Monitor to Service. ADS 7
h. Shutdown A Train Emergency Gas Treatment System. OS 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Perform Local Boration of RCS. AELMR 1
j. Local Isolation of Steam Lines Following a SGTR. MEL 3
k. Place Cation Bed in Service for High RCS Activity. MER 9

@ 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 I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~91 ~8 I ~4 (E)mergency or abnormal in-plant ~ 1 I ~1 I ~ 1 (EN)gineered safety feature - I - I ~1 (L)ow-Power I Shutdown ~1 I ~1 I ~ 1 (N)ew or (M)odified from bank including 1(A) ~21 ~2 I ~ 1 (P)revious 2 exams ~3 ~ 3 I ~ 2 (randomly selected)

(R)CA ~1 I ~1 I ~ 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2009 Exam Level: RO 0 SRO-I [gI SRO-U 0 Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Withdraw Shutdown Banks. ALMS 1
b. Place Excess Letdown in Service. DC 2
c. Isolate Cold Leg Accumulators. AENS 3
d. Place RHR Spray in Service. ADLS 4P
e. Place the Containment H2 Recombiner in Service. DLS 5
f. (Not required for I-SRO). - -
g. Return Power Range Monitor to Service. ADS 7
h. Shutdown A Train Emergency Gas Treatment System. DS 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Perform Local Boration of RCS. AELMR 1
j. Local Isolation of Steam Lines Following a SGTR. MEL 3
k. Place Cation Bed in Service for High RCS Activity. MER 9

@ 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 (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 ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2009 Exam Level: RO 0 SRO-I 0 SRO-U ~ Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. (Not required for U - SRO). - -
b. (Not required for U - SRO). - -
c. Isolate Cold Leg Accumulators. AENS 3
d. (Not required for U - SRO). - -
e. Place the Containment H2 Recombiner in Service. DLS 5
f. (Not required for U - SRO). - -
g. Return Power Range Monitor to Service. ADS 7
h. (Not required for U - SRO). - -

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Perform Local Boration of RCS. AELMR 1
j. (Not required for U - SRO). - -
k. Place Cation Bed in Service for High RCS Activity. MER 9

@ 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 (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 ES-301, Page 23 of 27

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