ML14310A402
| ML14310A402 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/24/2014 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Entergy Operations |
| laura hurley | |
| References | |
| 50-416/14-008, 50-417/14-008 50-416/OL-14, 50-417/OL-14 | |
| Download: ML14310A402 (39) | |
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 5
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: Date of Exam:
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 ES-401,Attachment 1 of NUREG-1021, 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 ES-401, section D.1.b, as well as any re-sampling 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: August 8, 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 ES-401,Attachment 1 of NUREG-1021, 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 ES-401, section D.1.b, as well as any re-sampling 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
Rev 0 (2/28/12)
Page 1 of 2 ES-301 Transient and Event Checklist Form ES-301-5 Facility: GGNS Date of Exam: 10/20/2014 Operating Test No.: LOT-2014 A
P P
L I
C A
N T
E V
E N
T T
Y P
E Scenarios 1
2 3
4 T
O T
A L
M I
N I
M U
M(*)
CREW POSITION CREW POSITION CREW POSITION CREW POSITION S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P R
I U
I1 I7 I2 I8 I3 I9 I4 R2 I5 R3 I6 I10 RX 0
1 0
0 1
0 2
1 1
NOR 0
0 2
0 0
1 3
1 1
I/C 0
1 4
1 4
2 12 4
4 MAJ 1
1 1
2 2
2 9
2 2
TS 2
2 4
0 2
I1 R1 I3 R3 I10 R4 R5 R6 RX 0
2 0
0 1
0 3
1 1
NOR 0
0 2
0 0
1 3
1 1
I/C 0
2 2
0 2
3 9
4 4
MAJ 2
2 2
1 1
1 9
2 2
TS 2
2 4
0 2
I4 R1 I5 R4 I6 R5 I7 R6 I8 I9 RX 0
2 0
0 1
0 3
1 1
NOR 0
0 2
0 0
1 3
1 1
I/C 0
2 2
0 2
3 9
4 4
MAJ 2
2 2
1 1
1 9
2 2
TS 2
2 4
0 2
RX NOR I/C MAJ TS Instructions:
1.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; ()Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
Rev 0 (2/28/12)
Page 2 of 2 ES-301 Transient and Event Checklist Form ES-301-5 Facility: GGNS Date of Exam: 10/20/2014 Operating Test No.: LOT-2014 A
P P
L I
C A
N T
E V
E N
T T
Y P
E Scenarios 5
T O
T A
L M
I N
I M
U M(*)
CREW POSITION CREW POSITION CREW POSITION CREW POSITION S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P R
I U
RX 0
1 0
1 1
1 NOR 0
0 1
1 1
1 I/C 2
4 3
9 4
4 MAJ 1
1 1
3 2
2 TS 2
2 0
2 RX NOR I/C MAJ TS RX NOR I/C MAJ TS RX NOR I/C MAJ TS Instructions:
3.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; ()Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
4.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 5 Page 1 of 2 Facility: Grand Gulf Nuclear Station Scenario No.: 5 Op-Test No.: NRC LOT 2014 Examiners: ____________________________ Operators:
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
- 1. Start a Condensate Pump.
- 2. Withdraw Control Rods to Establish Main Turbine BCVs 10% open.
- 3. Inability to move Control Rod
- 4. One IRM channel fails upscale.
- 5. Loss of ESF Transformer 21.
- 6. Startup Level Control Valve Fails Open
- 7. Recirc System Line Break in Drywell
- 8. RCIC/HPCS fails to start on initiation.
Initial Conditions: Reactor startup in progress.
x Reactor pressure is 400 psig x
Reactor power is 5%
Inoperable Equipment: None Turnover:
x A reactor startup is in progress.
o Step 112b of Control Rod Movement Sequence is complete o SJAE B is in warm up 04-01-N62-1 step 4.2.2r o IRM H is INOP and Bypassed o Attachment XV step 29 of 03-1-01-1 is complete.
x The Condensate system is lined up as follows:
o CFFF is in service o Precoat Filters are not in service o 4 Deepbed demins are in service Scenario Notes:
This scenario is a modified version of the 2012 NRC Exam Scenario 2.
Validation Time:
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 5 Page 2 of 2 Event No.
Malf. No.
Event Type
Event Description 1
N (BOP)
Start a Condensate Pump (04-1-01-N19-1 Condensate System) 2 R (ATC)
Withdraw Control Rods to Establish Main Turbine BCVs 10% open (04-1-01-C11-2 Rod Control and Information System) 3 z022022_52_33 C (CREW)
A (CREW)
Inability to move Control Rod (05-1-02-IV-1, Control Rod/Drive Malfunctions) 4 c51004b I (ATC)
TS (CRS)
One IRM channel fails upscale, (TS 3.3.1.1 and TR 3.3.2.1) 5 r21180 n41140b C (BOP)
A(CREW)
TS(CRS)
Loss of ESF Transformer 21 (05-1-02-I-4, Loss of AC Power)
Division 2 LSS Failure (TS 3.8.1) 6 ai_1c34r602_sp C (ATC)
A(CREW)
Startup Level Control Valve Fails Open (05-1-02-V-7, Feedwater System Malfunctions) 7 rr192a M (Crew)
Recirc System Line Break in Drywell (EP-2, 3) 8 e51043 e22177 e21051 e12050a e12272b e12272c fw115a fw226a r21139b C (Crew)
Limited Injection sources:
RCIC fails to start on initiation (SOI 04-1-01-E51-1)
HPCS system fail to auto initiate LPCS pump trip RHR A pump trip Loss of power to E12-F042B Loss of power to E12-F042C Condensate Pump A trip Condensate Booster pump A shaft sheer Loss of bus 14AE
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)
Quantitative Attributes Table Normal Events 1
Abnormal Events 3
Reactivity Manipulations 1
Total Malfunctions 6
Instrument/Component Failures 5
EP Entries (Requiring substantive action) 1 Major Transients 1
EP Contingencies 0
Tech Spec Calls 2
Critical Tasks 2
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 1 Page 1 of 2 Facility: Grand Gulf Nuclear Station Scenario No.: 1 Op-Test No.: NRC LOT 2014 Examiners: ____________________________ Operators:
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
- 1. Raise reactor power using Recirc Flow Control.
- 2. Rotate CRD Pumps.
- 3. Respond to a CRD Pump Trip.
- 4. Respond to loss of control power to of Division 2 Diesel Generator.
- 5. Respond to LPCS Jockey Pump trip.
- 6. Respond to 15AA lockout.
- 7. Take actions for a low power ATWS.
- 8. Respond to an unisolable FW Line A Break in the Drywell.
Initial Conditions: Operating at 85% power.
Inoperable Equipment: None Turnover:
The plant is at 85% following a sequence exchange. SSW A is operating in preparation for weekly chemical addition. Planned activities for this shift are:
x Raise power to 90% (1300 Mwe) per IOI. Allow Reactor Engineering to perform preconditioning.
x Rotate CRD pumps in accordance with the C11-1 SOI in preparation for CRD pump A maintenance.
There is no out of service equipment and EOOS is GREEN. It is a division 1 work week.
Scenario Notes:
This scenario is a modified version of AUDIT 2012-1 Scenario 1.
Validation Time: 60 minutes
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 1 Page 2 of 2 Event No.
Malf. No.
Event Type
Event Description 1
N (BOP)
R (ATC)
Raise Reactor power to 90% using FCVs (IOI 03-1-01-2 Attachment VIII) 2 N (BOP)
Rotate CRD pumps (SOI 04-1-01-C11-1 section 5.5) 3 C11028b C (BOP)
A (CREW)
CRD pump Trip (CRD Malfunctions (05-1-02-IV-1) ONEP section 2.1.2) 4 n41140b C (BOP)
TS (CRS)
Division 2 DG control power fuse failure. (Alarm Response Instructions 04-1-02-1H13-P864-2A-D1 and D2, 04-1-02-1H22-P401-1A-E1, TS 3.8.1) 5 p41148c C (BOP)
TS (CRS)
LPCS Jockey Pump Trip (Alarm Response Instructions 04-1 1H13-P601-21A-C7 and H8, TS 3.5.1, TS 3.8.1, 02-S-01-17, Control of Limiting Conditions of Operability) 6 rr012a C (BOP)
A (CREW)
ESF 15AA bus lockout (05-1-02-I-4, Loss of AC Power, 05-1 I-1 Reactor Scram) 7 c11164 e51044 M (CREW)
Low power ATWS with reduced feed capability (EP-2A)
When EP-2A requires Emergency Depressurization, Crew terminates and prevents all injection except boron, CRD, and RCIC per 02-S-01-43 Transient Mitigation Strategy.
Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criterion is to give the highest priority to prevent all injection except boron, CRD, and RCIC until reaching MSCP.
Reactor pressure decreases to MSCP. Crew commences and slowly raises injection utilizing available EP-2A Table 4 and/or Table 5 systems with RPV level restored and maintained to greater than -191". Criterion is to give the highest priority to restore RPV level greater than -
191".
8 fw171a rr063a C(ATC)
Feedwater Line A rupture inside the Drywell with inability to isolate.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)
Quantitative Attributes Table Normal Events 2
Abnormal Events 2
Reactivity Manipulations 1
Total Malfunctions 6
Instrument/Component Failures 5
EP Entries (Requiring substantive action) 1 Major Transients 1
EP Contingencies 1
Tech Spec Calls 2
Critical Tasks 2
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 4 Page 1 of 2 Facility: Grand Gulf Nuclear Station Scenario No.: 4 Op-Test No.: NRC LOT-2014 Examiners: ____________________________ Operators:
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
- 1. Shutdown Standby Service Water (SSW) A following weekly chemical addition.
- 2. SSW Pump A Discharge valve breaker trip while closing
- 3. Turbine Building Cooling Water Pump B trip with failure of TBCW Pump C to auto start.
- 4. Narrow Range Level indicator C fails upscale.
- 5. Fuel leak
- 6. Hydraulic Block ATWS.
- 7. Main Steam Line Hi Rad
- 8. Standby Liquid Control System squib valves fail to open.
Initial Conditions: Plant is operating at 100% power. Standby Service Water A is aligned for chemical addition.
Inoperable Equipment: none Turnover:
x Plant is in steady state operation at 100% power.
x Standby Service Water A is aligned for chemical addition. Plant Chemistry is adding chemicals and will contact the control Room to secure SSW A immediately following turnover.
x This is a Division 1 work week.
Scenario Notes:
This is a modified version of 2013 AUDIT scenario 4.
Validation Time (60-90 min): 70 min
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 4 Page 2 of 2 Event No.
Malf. No.
Event Type
Event Description 1
N (BOP)
Secure SSW A following chemical addition. (04-1-03-P41-1 step 7.8).
2 p41f001a_i C (BOP)
TS (CRS) 1P41F001A, SSW Pump A Discharge valve, breaker trip while closing (ARI 04-1-02-1H13-P870-1A-C2, TS 3.7.1).
3 p43152b C (BOP)
A (CREW)
Turbine Building Cooling Water Pump B trip with failure of TBCW Pump C to auto start (05-1-02-V-2 Loss of Turbine Building Cooling Water, ARI 04-1-02-1H13-P870-5A-B4).
4 fw126c I (ATC)
TS (CRS)
Narrow Range Level indicator C failure upscale. (TS 6.3.7) 5 rr071 A(CREW)
R(ATC)
Fuel leak (ARI 04-1-02-1H13-P601-19A-E7; 05-1-02-II-2, Off-Gas Activity High).
6 c11164 M (CREW)
Manual Scram, hydraulic block ATWS, power > 5%,
level/power control (05-1-02-I-1 Reactor Scram, 05-1-02-I-2 Turbine and Generator Trips, EP-2A ATWS RPV Control, EP-3 Containment Control)
When Suppression Pool temperature reaches 110°F, crew terminates and prevents Condensate/ Feedwater and ECCS injection per EP-2A step L-8.
When power decreases to below 5% or reactor water level drops to -167 on compensated fuel zone, crew restores injection using Condensate/Feedwater to maintain level between the point to which level was lowered in step L-8 and -191 per EP-2A step L-9.
Following the ATWS, crew directs installation of EP Attachments 18, 19, and 20 and inserts control rods by manual scram and/or normal rod insertion per EP-2A step Q-1.
7 P601_18A_C_4 P601_19A_C_4 P601_19A_D_4 C(ATC)
MSL Hi-Hi Rad signal requiring closure of MSIVs; EP-4 8
c41f004a_a c41f004b_a C(BOP)
Standby Liquid Control System squib valves fail to open (SOI 04-1-01-C41-1 Attachment VI; EP Attachment 28)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)
Quantitative Attributes Table Normal Events 1
Abnormal Events 2
Reactivity Manipulations 1
Total Malfunctions 7
Instrument/Component Failures 5
EP Entries (Requiring substantive action) 2 Major Transients 1
EP Contingencies 1
Tech Spec Calls 2
Critical Tasks 3
Appendix D Required Operator Actions Form ES-D-1 NRC 2014 Scenario 3 Page 1 of 2 Facility: Grand Gulf Nuclear Station Scenario No.: 3 Op-Test No.: NRC LOT 2014 Examiners: ____________________________ Operators:
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
- 1. Place Suppression Pool Cooling in service.
- 2. Reactor Feed Pump A High Vibration
- 3. Trip of the 16BB3 electric bus.
- 4. Control Rod drift.
- 5. Second Control Rod drift.
- 6. Unisolable LOCA with limited injection capabilities.
- 7. Division 3 Diesel Generator failure to start.
- 8. Division 2 Diesel Generator running without cooling water.
- 9. Loss of power to E22-F004 HPCS injection valve.
Initial Conditions: Operating at 100% power.
Inoperable Equipment: None Turnover:
A plant is operating at rated power. Suppression Pool temperature is elevated due to a weeping SRV.
The Crew will start Suppression Pool Cooling on RHR B using the 04-1-01-E12-1 RHR system SOI.
Scenario Notes:
This scenario is modified from the 2012 Audit Scenario 3.
Validation Time: 55 min
Appendix D Required Operator Actions Form ES-D-1 NRC 2014 Scenario 3 Page 2 of 2 Event No.
Malf. No.
Event Type
Event Description 1
N (BOP)
TS (CRS)
Place Suppression Pool Cooling in Service (SOI 04-1 E12-1 section 5.2, TS 3.5.1 Condition A) 2 c86013x C (ATC)
Reactor Feed Pump A High Vibration (04-1-02-1H13-P680-2A-E2) 3 R (ATC)
N (BOP)
Lower reactor power from 100% to 90% using Recirc FCVs (03-1-01-2) 4 r21142z TS (CRS)
A (CREW)
Trip of the 16BB3 electric bus (480V LCC 16BB3 UNDERVOLT ARI (04-1-02-1H13-P864-2A-E3), TS 3.6.1.3 Condition A, TS 3.5.1 Condition C, TS 3.6.4.3 Condition A, TS 3.6.3.2 Condition A) 5 z161161_20_49 R (ATC)
A (Crew)
Control Rod Drift (Control Rod/Drive Malfunctions (05-1 IV-1) ONEP) 6 z021021_20_33 M (CREW)
Second Control Rod Drift (Control Rod/Drive Malfunctions (05-1-02-IV-1) ONEP) 7 rr063a r21139e xml1r21191 xml1r21192 e12050c M (Crew)
Unisolable LOCA with limited injection capabilities (Scram (05-1-02-I-1) and Turbine Trip (05-1-02-I-2) ONEPs, EP-2, EP-3) 8 n41140c C (BOP)
Division 3 Diesel Generator failure to start (Loss of AC Power (05-1-02-I-4) ONEP) 9 p41f018b_i C (BOP)
Division 2 Diesel Generator running without cooling water (02-S-01-43 Transient Mitigation Strategy section 6.1.1.c) 10 e22648 C (ATC)
Loss of power to E22-F004 HPCS injection valve (02-S 43 Transient Mitigation Strategy section 6.1.1.d)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)
Quantitative Attributes Table Normal Events 1
Abnormal Events 2
Reactivity Manipulations 1
Total Malfunctions 8
Instrument/Component Failures 4
EP Entries (Requiring substantive action) 1 Major Transients 2
EP Contingencies 1
Tech Spec Calls 2
Critical Tasks 3
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 2 Page 1 of 2 Revision 0 Facility: Grand Gulf Nuclear Station Scenario No.: 2 Op-Test No.: NRC LOT 2014 Examiners: ____________________________ Operators:
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
- 1. Lower reactor power from 100% to 85% using Recirc FCVs.
- 2. Recognize and respond to APRM Channel 2 fails upscale.
- 3. Recognize and respond to SBGT Filter Train Fan A trip.
- 4. Recognize and respond to Reactor Feed Pump B Controller failure - increasing speed.
- 5. Respond to a Circ Water Pump A trip.
- 6. RPS Motor Generator Set B trip with inadvertent scram of nine Control Rods.
- 7. Respond to failure of Service Transformer 21.
- 8. Respond to a MSL steam line break in the Aux Building Steam Tunnel, high room temps in Steam Tunnel and RCIC room with failure/inability to isolate RCIC steam supply.
Initial Conditions: Operating at 100% power.
Inoperable Equipment: None Turnover:
The plant is at 100% power preparing for a temporary down power for a control rod pattern adjustment.
Power is to be reduced to 85% slowly within IOI limitations. SBGT A is operating per surveillance, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> into a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> run. APRM Channel 4 is Bypassed for I&C. EOOS is green. A Division 1 work week is in effect.
Scenario Notes:
This scenario is a new scenario.
Validation Time:
Appendix D Scenario Outline Form ES-D-1 NRC 2014 Scenario 2 Page 2 of 2 Revision 0 Event No.
Malf. No.
Event Type*
Event Description 1
N(BOP)
R(ATC)
Lower reactor power from 100% to 85% using Recirc FCVs (03-1-01-2) 2 C51009_2 C(ATC)
TS(CRS)
APRM Channel 2 fails full upscale. (Tech Specs 3.3.1.1 Condition A, TR3.3.2.1 Condition A) 3 ct155a C(BOP)
TS(CRS)
SBGT Filter Train Fan trips. (Tech Specs 3.6.4.3 Condition A) 4 fw121b C(ATC)
A(CREW)
Reactor Feed Pump B Controller failure - increasing speed (Feedwater System malfunctions ONEP, 05-1 V-7) 5 n71114a C(ATC)
A(CREW)
Circ Water Pump A Trip. (Loss of Condenser Vacuum ONEP, 05-1-02-V-8) 6 c71077b z025025 A (CREW)
M (ALL)
RPS MG Set B trip with inadvertent scram of nine control rods (Reactor Scram ONEP 05-1-02-I-1 and Turbine and Generator Trips ONEP 05-1-02-I-2) 7 r21113b C (ALL)
A (CREW)
Respond to trip of Service Transformer 21 (Loss of AC Power ONEP 05-1-02-I-4, EP-2) 8 ms066a e51050 M (ALL)
Respond to a MSL steam line break in the Aux Building Steam Tunnel, high room temps in Steam Tunnel and RCIC room with failure/inability to isolate RCIC steam supply.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)
Quantitative Attributes Table Normal Events 1
Abnormal Events 3
Reactivity Manipulations 1
Total Malfunctions 7
Instrument/Component Failures 5
EP Entries (Requiring substantive action) 2 Major Transients 2
EP Contingencies 1
Tech Spec Calls 2
Critical Tasks 2