ML14310A423
| ML14310A423 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/24/2014 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Entergy Operations |
| laura hurley | |
| References | |
| Download: ML14310A423 (29) | |
Text
ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Grand Gulf Date of Exam: October 17, 2014 Tier Group RO K/A Category Points SRO-Only Points K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total
- 1.
Emergency &
Abnormal Plant Evolutions 1
2 1
5 N/A 3
3 N/A 6
20 7
2 2
3 0
0 2
0 7
3 Tier Totals 4
4 5
3 5
6 27 10
- 2.
Plant Systems 1
2 2
4 3
3 3
3 2
1 1
2 26 5
2 2
0 1
1 2
2 1
0 1
1 1
12 3
Tier Totals 4
2 5
4 5
5 4
2 2
2 3
38 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
4 3
3 3
Note:
- 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/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 K/A statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.*
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X
AK1.04 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Limiting cycle oscillation: Plant Specific 2.5 1
295003 Partial or Complete Loss of AC / 6 X
2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
4.6 2
295004 Partial or Total Loss of DC Pwr / 6 X
2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.5 3
295005 Main Turbine Generator Trip / 3 X
AK2.02 Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: Feedwater Temperature 2.9 4
295006 SCRAM / 1 295016 Control Room Abandonment / 7 X 2.2.12 Knowledge of surveillance procedures.
3.7 5
295018 Partial or Total Loss of CCW / 8 X
AK3.07 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Cross-connecting with backup systems.
3.1 6
295019 Partial or Total Loss of Inst. Air / 8 X 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.
3.5 7
295021 Loss of Shutdown Cooling / 4 X
AA2.01 Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING : Reactor water heatup/cooldown rate.
3.5 8
295023 Refueling Acc / 8 X
AA2.01 Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS
- Area radiation levels 3.6 9
295024 High Drywell Pressure / 5 X
EA1.04 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: RHR/LPCI 4.1 10 295025 High Reactor Pressure / 3 X
EA2.01 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor pressure 4.3 11 295026 Suppression Pool High Water Temp. / 5 X
EK3.05 Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor SCRAM 3.9 12 295027 High Containment Temperature / 5 X
EK3.02 Knowledge of the reasons for the following responses as they apply to HIGH CONTAINMENT TEMPERATURE MARK III CONTAINMENT ONLY)
- Containment spray: Plant specific 3.2 13 295028 High Drywell Temperature / 5 X
2.1.28 Knowledge of the purpose and function of major system components and controls.
4.1 14 295030 Low Suppression Pool Wtr Lvl / 5 X
EK3.06 Knowledge of the reasons for the following responses as they apply to LOW SUPPRESSION POOL WATER LEVEL: Reactor SCRAM 3.6 15 295031 Reactor Low Water Level / 2 X
EK3.01 Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL : Automatic depressurization system actuation 3.9 16 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X 2.4.6 Knowledge of EOP mitigation strategies.
3.7 17 295038 High Off-site Release Rate / 9 X
EK2..02 Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following:
Offgas System 3.6 18
600000 Plant Fire On Site / 8 X
AA1.06 Ability to operate and / or monitor the following as they apply to PLANT FIRE ON SITE:
Fire Alarm 3.0 19 700000 Generator Voltage and Electric Grid Disturbances / 6 X
AA1.03 Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Voltage regulator controls 3.8 20 K/A Category Totals:
2 1
5 3
3 6
Group Point Total:
20
ES-401 3
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295002 Loss of Main Condenser Vac / 3 X
AK2.07 Knowledge of the interrelations between LOSS OF MAIN CONDENSER VACUUM and the following:
Offgas system 3.1 21 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X
AK2.04 Knowledge of the interrelations between LOW REACTOR WATER LEVEL and the following: Reactor water cleanup 2.6 22 295010 High Drywell Pressure / 5 X
AA1.01 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE :
Drywell ventilation/cooling 3.4 23 295011 High Containment Temp / 5 X
AK2.01 Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following:
Containment ventilation/cooling: Mark-III.
3.7 24 295012 High Drywell Temperature / 5 X
AK1.01Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE : Pressure/temperature relationship 3.3 25 295013 High Suppression Pool Temp. / 5 X
AA1.01 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE : Suppression pool cooling 3.9 26 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 X
AK1.01 Knowledge of the operational implications of the following concepts as they apply to INCOMPLETE SCRAM : Shutdown margin 3.6 27 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:
2 3
2 Group Point Total:
7
ES-401 4
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 203000 RHR/LPCI: Injection Mode X
K4.14 Knowledge of RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) design feature(s) and/or interlocks which provide for the following: Operation from remote shutdown panel 3.6 28 205000 Shutdown Cooling X
K5.02 Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) :Valve operation 2.8 29 X
K4.04 Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which provide for the following: Adequate pump NPSH 2.6 30 206000 HPCI NA GGNS 207000 Isolation (Emergency)
Condenser NA GGNS 209001 LPCS X
K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSTEM : A.C. power 3.4 31 X
2.1.19 Ability to use plant computers to evaluate system or component status.
3.9 32 209002 HPCS X
A1.09 Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) controls including:
Condensate storage tank level: BWR-5,6 2.6 33 211000 SLC X
K5.05 Knowledge of the operational implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM : Accumulator operation: Plant-Specific 2.5 34 212000 RPS X
K3.01 Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on following: Process radiation monitoring 3.0 35 215003 IRM X
K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM : Detectors 3.0 36 X
A3.01 Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM including: Meters and recorders 3.3 37 215004 Source Range Monitor X
Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.01 Power supply degraded 2.7 38
K1.13 Knowledge of the physical connections and/or causeeffect relationships between AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following:
Traversing incore probe system 2.6 39 217000 RCIC X
2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
4.4 40 218000 ADS X
K5.01 Knowledge of the operational implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM :ADS logic operation 3.8 41 223002 PCIS/Nuclear Steam Supply Shutoff X
Ability to manually operate and/or monitor in the control room:A4.01 Valve closures 3.6 42 239002 SRVs X
K4.01 Knowledge of RELIEF/SAFETY VALVES design feature(s) and/or interlocks which provide for the following: Insures that only one or two safety/relief valves reopen following the initial portion of a reactor isolation event (LLS logic): Plant-Specific 3.9 43 259002 Reactor Water Level Control X
K6.08 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM :Loss of dP across startup level control bypass valve: Plant-Specific 2.7 44 261000 SGTS X
K3.02 Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following: Off-site release rate 3.6 45 262001 AC Electrical Distribution X
A1.03 Ability to predict and/or monitor changes in parameters associated with operating the A.C. ELECTRICAL DISTRIBUTION controls including: Bus voltage 2.9 46 X
K3.02 Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following:
Emergency generators 3.8 47 262002 UPS (AC/DC)
X A1.02 A1. Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs 2.5 48 263000 DC Electrical Distribution X
A2.02 Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of ventilation during charging 2.6 49 X
K2.01 Knowledge of electrical power supplies to the following: Major D.C. loads 3.1 50 264000 EDGs X
K3.02 Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following: A.C. electrical distribution 3.9 51 300000 Instrument Air X
K1.04 Knowledge of the connections and / or cause effect relationships between INSTRUMENT AIR SYSTEM and the following: Cooling water to compressor 2.8 52 400000 Component Cooling Water X
K2.02 Knowledge of electrical power supplies to the following: CCW valve 2.9 53 K/A Category Point Totals:
2 2
4 3
3 3
3 2
1 1
2 Group Point Total:
26
ES-401 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 201001 CRD Hydraulic X
K1.05 Knowledge of the physical connections and/or cause-effect relationships between CONTROL ROD DRIVE HYDRAULIC SYSTEM and the following: Feedwater (or reactor water cleanup)-CRD return to vessel: Plant-Specific 2.7 54 201002 RMCS 201003 Control Rod and Drive Mechanism X
K5.01 Knowledge of the operational implications of the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM :Hydraulics 2.6 55 201004 RSCS 201005 RCIS X
A1.01 First stage shell pressure/turbine load: BWR-6 3.2 56 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU X
A4.02 Ability to manually operate and/or monitor in the control room: Valve controllers 2.9 57 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.
219000 RHR/LPCI: Torus/Pool Cooling Mode X
2.1.28 Knowledge of the purpose and function of major system components and lcontrols.
4.1 58 223001 Primary CTMT and Aux.
226001 RHR/LPCI: CTMT Spray Mode X
K5.06 Knowledge of the operational implications of the following concepts as they apply to RHR/LPCI:
cONTAINMENT SPRAY SYSTEM MODE :Vacuum breaker operation 2.6 59 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup X
K4.08 Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature(s) and/or interlocks which provide for the following: Pool cooling during loss of coolant accident: BWR-6 2.6 60 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator
245000 Main Turbine Gen. / Aux.
X K6.08 Knowledge of the effect that a loss or malfunction of the following will have on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS : Main steam 3.0 61 256000 Reactor Condensate 259001 Reactor Feedwater X
K6.07 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR FEEDWATER SYSTEM : Reactor water level control system 3.8 62 268000 Radwaste X
K3.04 Knowledge of the effect that a loss or malfunction of the RADWASTE will have on following: Drain sumps 2.7 63 271000 Offgas X
K1.07 Knowledge of the physical connections and/or cause-effect relationships between OFFGAS SYSTEM and the following: Plant air systems 2.7 64 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC X
A3.02 Ability to monitor automatic operations of the CONTROL ROOM HVAC including: Initiation/failure of fire protection system 3.0 65 290002 Reactor Vessel Internals K/A Category Point Totals:
2 0
1 1
2 2
1 0
1 1
1 Group Point Total:
12
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Grand Gulf Date of Exam:
October 17, 2014 Category K/A #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
4.6 66 2.1.41 Knowledge of the refueling process.
2.8 67 2.1.1 Knowledge of conduct of operations requirements.
3.8 68 2.1.43 Knowledge of the process used to track inoperable alarms.
3.0 69 Subtotal 4
- 2.
Equipment Control 2.2.37 Ability to determine operability and/or availability of safety related equipment.
3.6 70 2.2.23 Ability to track Technical Specification limiting conditions for operations.
3.1 71 Subtotal 2
- 3.
Radiation Control 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
2.9 72 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
2.9 73 Subtotal 2
- 4.
Emergency Procedures /
Plan 2.4.1 Knowledge of EOP entry conditions and immediate action steps.
4.6 74 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.
3.5 75 Subtotal 2
Tier 3 Point Total 10
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 2/1 215004 K6.06 Importance rating < 2.5 (2.2) 2/2 245000 K6.07 Importance rating < 2.5 (2.4) 2/2 259001 K6.08 Importance rating < 2.5 (2.1) 2/1 263000 K1.03 De-selected for exam balance. K1 was oversampled.
2/1 400000 K1.04 De-selected for exam balance. K1 was oversampled.
2/1 215005 K6.05 De-selected for exam balance. K6 was oversampled.
2/1 211000 K5.05 De-selected, N/A for GGNS 2/1 205000 K4.04 De-selected due to lack of training material 2/2 201001 K1.05 De-selected, N/A for GGNS 1/1 295018 AK3.07 De-selected due to a lack of adequate distractors 3
2.1.31 De-selected due to difficulty in writing generic question 2/1 259002 K6.08 De-selected, N/A for GGNS 1/1 295003 2.1.31 De-selected due to difficulty in writing generic question 1/1 295028 2.1.28 De-selected due to difficulty in writing generic question 2/1 209001 2.1.19 De-selected due to lack of familiarity 2/1 262002 A1.02 De-selected due to lack of training material (Changed to Knowledge) 1/1 295016 2.2.12 De-selected due to a lack of adequate distracters 2/2 201005 A1.01 De-selected No longer used at GGNS Ref, EC-49891, 49880 2/2 226001 K5.06 De-selected N/A for GGNS SYSTEMS DELETED 201002 Reactor Manual Control System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.
201004 Rod Sequence Control System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.
201006 Rod Worth Minimizer System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.
214000 Rod Position Information System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.
215002 Rod Block Monitor System - This system is not incorporated into the BWR-6 design.
The functions of this system are incorporated into the Rod Control and Information System.
206000 High Pressure Core Injection (HPCI) - This system is not incorporated into the BWR 6 design.
207000 Isolation (Emergency) Condenser - This system is not incorporated into the BWR 6 design. This was replaced by the Mark III Containment Suppression Pool.
230000 RHR/LPCI: Torus/Pool Spray Mode - This system is not incorporated into the BWR 6 Mark III Containment design.
Written Exam Sample Plan: This sampling plan was developed using the manual sampling method described in ES401,Attachment 1 of NUREG1021, Revision 9, Supplement 1. It applies this same manual method throughout the sampling process, including the sampling of the Generic KAs listed on page 4 of ES401, section D.1.b, as well as any resampling that is required for rejected KAs (i.e., KA swaps).
Instead of tokens, the plan was developed using the web site random.org to generate the random number associated with each decision. Instead of bounding the possible selections by the number of tokens, the web site allows the user to specify the range of possible numbers for each choice.
ES-401 BWR Examination Outline - SRO Form ES-401-1 Facility: Grand Gulf Date of Exam:
October 17, 2014 Tier Group RO K/A Category Points SRO-Only Points K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total
- 1.
Emergency &
Abnormal Plant Evolutions 1
N/A N/A 20 6
1 7
2 7
1 2
3 Tier Totals 27 7
3 10
- 2.
Plant Systems 1
26 4
1 5
2 12 2
1 3
Tier Totals 38 6
2 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
2 2
1 2
Note:
- 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
- 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 K/A statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.*
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 295019 Partial or Total Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 X
AA2.04 Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING : Reactor water temperature 3.6 76 295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Temp. / 5 X
EA2.01 Ability to operate and/or monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression Pool Water Temperature 4.1 77 295027 High Containment Temperature / 5 X
EA2.04 Ability to determine and/or interpret the following as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) : Containment radiation levels: Mark-III 3.7 78 295028 High Drywell Temperature / 5 X
EA2.03 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE : Reactor water level 3.9 79 295030 Low Suppression Pool Wtr Lvl / 5 X
2.4.6 Knowledge of EOP mitigation strategies 4.7 80 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X
EA2.07 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :
Containment conditions/isolations 4.2 81 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 700000 Generator Voltage and Electric Grid Disturbances / 6 X
AA2.05 Ability to determine and/or interpret the following as l they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Operational Status of offsite circuit 3.6 82 K/A Category Totals:
6 1
Group Point Total:
7
ES-401 3
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295002 Loss of Main Condenser Vac / 3 X
2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.
4.4 83 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 X
AA2.03 Ability to determine and/or interpret the following as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) :
Containment humidity: Mark-II 3.2 84 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 X
2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
4.6 85 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:
1 2
Group Point Total:
3
ES-401 4
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 203000 RHR/LPCI: Injection Mode X 2.4.1 Knowledge of EOP entry conditions and immediate action steps.
4.8 86 205000 Shutdown Cooling 206000 HPCI 207000 Isolation (Emergency)
Condenser 209001 LPCS 209002 HPCS 211000 SLC 212000 RPS X
A2.02 Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RPS bus power supply failure 3.9 87 215003 IRM X
A2.05 Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Faulty or erratic operation of detectors/system 3.5 88 215004 Source Range Monitor 215005 APRM / LPRM 217000 RCIC 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control X
A2.04 Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RFP runout condition: Plant-Specific 3.1 89 261000 SGTS X
A2.07 Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C.
electrical failure 2.7 90 262001 AC Electrical Distribution
262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals:
4 1
Group Point Total:
5
ES-401 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.
219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam X 2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
4.2 91 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator X
A2.08 Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE PEGULATING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Main Turbine Overspeed 3.3 92 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate
259001 Reactor Feedwater X
A2.04 Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of extraction steam 3.4 93 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals:
2 1
Group Point Total:
3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Grand Gulf Date of Exam: October 17, 2014 Category K/A #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements.
3.9 94 2.1.44 Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
3.8 95 Subtotal 2
- 2.
Equipment Control 2.2.5 Knowledge of the process for making changes to procedures.
3.6 96 2.2.11 Knowledge of the process for controlling temporary design changes.
3.3 97 Subtotal 2
- 3.
Radiation Control 2.3.11 Ability to control radiation releases.
4.3 98 Subtotal 1
- 4.
Emergency Procedures / Plan 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.7 99 2.4.25 Knowledge of fire protection procedures 3.7 100 Subtotal 2
Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 700000, AA2.04 Not conducive to SRO only question.
2/2 241000, 2.1.25 Not conducive to SRO only question.
Written Exam Sample Plan: This sampling plan was developed using the manual sampling method described in ES401,Attachment 1 of NUREG1021, Revision 9, Supplement
- 1. It applies this same manual method throughout the sampling process, including the sampling of the Generic KAs listed on page 4 of ES401, section D.1.b, as well as any resampling that is required for rejected KAs (i.e., KA swaps). Instead of tokens, the plan was developed using the web site random.org to generate the random number associated with each decision. Instead of bounding the possible selections by the number of tokens, the web site allows the user to specify the range of possible numbers for each choice.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 10/20/2014 Examination Level: RO SRO Operating Test Number: LOT-2014 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations Conduct of Operations R - D Review Cooldown Record GJPM-OPS-2014AR2 2.1.25 (3.9/4.2) 2.1.23 (4.3/4.4)
Equipment Control R - D Electrical Print Reading GJPM-OPS-2014AR3 2.2.41 (3.5/3.9) 2.1.25 (3.9/4.2)
Radiation Control R - N Emergency Exposure Limits GJPM-OPS-2014AR4 2.3.4 (3.2/3.7)
Emergency Procedures/Plan R - D Emergency Notifications GJPM-OPS-2014AR5 2.4.43 (3.2/3.8)
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 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 10/20/2014 Examination Level: RO SRO Operating Test Number: LOT-2014 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R - D Inadequate Decay Heat Removal Required Actions GJPM-OPS-2014AS1 2.1.20 (4.6/4.6)
Conduct of Operations R - D Determine Reportability GJPM-OPS-2014AS2 2.1.20 (4.6/4.6); 2.1.25 (3.9/4.2)
Equipment Control R - D Determine Shutdown Risk Levels GJPM-OPS-2014AS3 2.2.18 (2.6/3.9)
Radiation Control R - N Authorize Emergency Exposure GJPM-OPS-2014AS4 2.3.4 (3.2/3.7)
Emergency Procedures/Plan R - N Protective Action Recommendation Determination GJPM-OPS-2014AS5 2.4.44 (2.4/4.4)
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 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 10/20/2014 Exam Level: RO SRO-I SRO-U Operating Test No.:
LOT-2014 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. 201005 A4.01 (3.7/3.7), Control Rod Operability Surveillance, GJPM-OPS-2014CR1 A-D-S 1
- b. 217000 A4.04 (3.6/3.6), RCIC Manual Startup, GJPM-OPS-2014CR2 A-D-S 2
- c. 245000 A4.02 (3.1/2.9), Place Main Generator Voltage Regulator in AUTO, GJPM-OPS-2014CR4 N-S 4
- d. 223002 A4.03 (3.6/3.5), Defeat MSIV/MSL Drain Level 1 Isolation Interlocks, GJPM-OPS-2014CR5 C-D-E-L 5
- e. 264000 A4.01 (3.3/3.4), Start and Parallel D/G 13 with Offsite, GJPM-OPS-2014CR6 A-N-S 6
- f.
212000: A2.02 (3.7/3.9); A4.14 (3.8/3.8), Transfer RPS B to Normal Power Source and RPS A to Alternate Power Source, GJPM-OPS-2014CR7 M-S 7
- g. 400000: A4.01 (3.1/3.0); A2.01 (3.3/3.4), Rotate CCW Pumps GJPM-OPS-2014CR8 A-D-S 8
- h. 290003 A4.01 (3.2/3.2):A2.01 (3.1/3.2), Secure Control Room Standby Fresh Air Unit, GJPM-OPS-2014CR9 C-D 9
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
218000 A2.03 (3.4/3.6), Install Nitrogen Bottles on ADS Air Supply, GJPM-OPS-2014PS1 D-E-L-R 3
- j.
219000 A4.01 (3.8/3.7),Startup RHR in Suppression Pool Cooling from the Remote Shutdown Panels, GJPM-OPS-2014PS2 D-E-L 5
- k. 262002 A4.01 (2.8/3.1), Startup Static Inverter 1Y81, GJPM-OPS-2014PS3 D
6 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 10/20/2014 Exam Level: RO SRO-I SRO-U Operating Test No.:
LOT-2014 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. 201005 A4.01 (3.7/3.7), Control Rod Operability Surveillance, GJPM-OPS-2014CR1 A-D-S 1
- b. 217000 A4.04 (3.6/3.6), RCIC Manual Startup, GJPM-OPS-2014CR2 A-D-S 2
- d. 223002 A4.03 (3.6/3.5), Defeat MSIV/MSL Drain Level 1 Isolation Interlocks, GJPM-OPS-2014CR5 C-D-E-L 5
- e. 264000 A4.01 (3.3/3.4), Start and Parallel D/G 13 with Offsite, GJPM-OPS-2014CR6 A-N-S 6
- f.
212000: A2.02 (3.7/3.9); A4.14 (3.8/3.8), Transfer RPS B to Normal Power Source and RPS A to Alternate Power Source, GJPM-OPS-2014CR7 N-S 7
- g. 400000: A4.01 (3.1/3.0); A2.01 (3.3/3.4), Rotate CCW Pumps GJPM-OPS-2014CR8 A-D-S 8
- h. 290003 A4.01 (3.2/3.2):A2.01 (3.1/3.2), Secure Control Room Standby Fresh Air Unit, GJPM-OPS-2014CR9 C-D 9
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
218000 A2.03 (3.4/3.6), Install Nitrogen Bottles on ADS Air Supply, GJPM-OPS-2014PS1 D-E-L-R 3
- j.
219000 A4.01 (3.8/3.7),Startup RHR in Suppression Pool Cooling from the Remote Shutdown Panels, GJPM-OPS-2014PS2 D-E-L 5
- k. 262002 A4.01 (2.8/3.1), Startup Static Inverter 1Y81, GJPM-OPS-2014PS3 D
6 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
Following this page is the As-Given SRO Administrative JPM Outline
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 10/20/2014 Examination Level: RO SRO Operating Test Number: LOT-2014 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R - D Inadequate Decay Heat Removal Required Actions GJPM-OPS-2014AS1 2.1.20 (4.6/4.6)
Conduct of Operations R - D Determine Reportability GJPM-OPS-2014AS2 2.1.20 (4.6/4.6); 2.1.25 (3.9/4.2)
Equipment Control R - D Determine Shutdown Risk Levels GJPM-OPS-2014AS3 2.2.18 (2.6/3.9)
Radiation Control R - N Authorize Emergency Exposure GJPM-OPS-2014AS4 2.3.4 (3.2/3.7)
Emergency Procedures/Plan R - N Emergency Event Classification GJPM-OPS-2014AS5 2.4.41 (2.9/4.6)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)