Text

10 Draft Outlines
	ML22342B252
Person / Time
Site:	Grand Gulf
Issue date:	10/14/2022
From:	Heather Gepford; Operations Branch IV
To:	; Entergy Operations
References
	Download: ML22342B252 (1)
	v • d • e

Form 4.1-BWR Boiling-Water Reactor Examination Outline Facility: Grand Gulf K/A Catalog Rev. 3 Rev. 0 Date of Exam: 10/10/2022 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

Emergency and Abnormal Plant Evolutions 1

3 3

4 4

3 3

20 3

4 7

2 1

1 1

1 6

1 2

3 Tier Totals 4

4 5

5 4

4 26 4

6 10

2.

Plant Systems 1

2 2

3 2

2 3

2 2

3 3

2 26 3

2 5

2 1

1 1

1 0

11 0

2 1

3 Tier Totals 3

4 4

3 3

4 3

3 4

4 2

37 5

3 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM 6

CO EC RC EM 7

2 2

1 1

2 2

1 2

4. Theory Reactor Theory Thermodynamics 6

3 3

Notes: CO = Conduct of Operations; EC = Equipment Control; RC = Radiation Control; EM = Emergency Procedures/Plan These systems/evolutions may be eliminated from the sample when Revision 2 of the K/A catalog is used to develop the sample plan.

These systems/evolutions are only included as part of the sample (as applicable to the facility) when Revision 2 of the K/A catalog is used to develop the sample plan.

ES-4.1-BWR BWR Examination Outline (Grand Gulf)

Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

Item #

E/APE # / Name /

Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR Q#

1 (295001) (APE 1)

PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION X

(295001AK2.12) Knowledge of the relationship between the (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Recirculation flow control system 3.5 1

2 (295001) (APE 1)

PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION X

(295001AA2.03) Ability to determine or interpret the following as they apply to (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: (CFR: 41.10 / 43.5 / 45.13) Core flow 4

76 3

(295003) (APE 3)

PARTIAL OR COMPLETE LOSS OF AC POWER X

(295003AA1.06) Ability to operate or monitor the following as they apply to (APE 3) PARTIAL OR COMPLETE LOSS OF AC POWER: (CFR: 41.5 / 41.7 / 45.5 to 45.8) AC electrical loads 3.8 2

4 (295003) (APE 3)

PARTIAL OR COMPLETE LOSS OF AC POWER X (295003) (APE 3) PARTIAL OR COMPLETE LOSS OF AC POWER (G2.2.44) EQUIPMENT CONTROL Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions (CFR: 41.5 / 43.5 / 45.12) 4.4 77 5

(295004) (APE 4)

PARTIAL OR COMPLETE LOSS OF DC POWER X

(295004AK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 4) PARTIAL OR COMPLETE LOSS OF DC POWER: (CFR: 41.5 / 41.7 / 45.7 / 45.8) Battery capacity 3.9 3

6 (295005) (APE 5)

MAIN TURBINE GENERATOR TRIP X

(295005AA1.07) Ability to operate or monitor the following as they apply to (APE 5) MAIN TURBINE GENERATOR TRIP:

(CFR: 41.5 / 41.7 / 45.5 to 45.8) AC electrical distribution 3.4 4

7 (295006) (APE 6)

SCRAM X

(295006AA1.04) Ability to operate or monitor the following as they apply to (APE 6) SCRAM: (CFR: 41.5 / 41.7 / 45.5 to 45.8) Recirculation system 3.8 5

8 (295016) (APE 16)

CONTROL ROOM ABANDONMENT X

(295016AK3.04) Knowledge of the reasons for the following responses or actions as they apply to (APE 16) CONTROL ROOM ABANDONMENT: (CFR: 41.5 / 41.10 / 45.6 / 45.13)

Abandonment criteria 4.1 6

9 (295016) (APE 16)

CONTROL ROOM ABANDONMENT X (295016) (APE 16) CONTROL ROOM ABANDONMENT (G2.1.25) CONDUCT OF OPERATIONS Ability to interpret reference materials, such as graphs, curves, and tables (reference potential) (CFR: 41.10 / 43.5 / 45.12) 4.2 78 10 (295018) (APE 18)

PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW)

X (295018AA1.04) Ability to operate or monitor the following as they apply to (APE 18) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW): (CFR: 41.5 / 41.7 /

45.5 to 45.8) Reactor water cleanup system 3.4 7

11 (295019) (APE 19)

PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR X

(295019AK3.03) Knowledge of the reasons for the following responses or actions as they apply to (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: (CFR: 41.5 / 41.10

/ 45.6 / 45.13) Service Air isolations 3.3 8

12 (295019) (APE 19)

PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR X (295019) (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR (G2.4.50) EMERGENCY PROCEDURES/PLAN Ability to verify system alarm setpoints and operate controls identified in the alarm response procedure (CFR: 41.10 / 43.5 / 45.3) 4 79

13 (295021) (APE 21)

LOSS OF SHUTDOWN COOLING X

(295021AK2.02) Knowledge of the relationship between the (APE 21) LOSS OF SHUTDOWN COOLING and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Reactor water cleanup 3.2 9

14 (295023) (APE 23)

REFUELING ACCIDENTS X

(295023AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 23) REFUELING ACCIDENTS:

(CFR: 41.5 / 41.7 / 45.7 / 45.8) Radiation exposure hazards 3.9 10 15 (295024) (EPE 1)

HIGH DRYWELL PRESSURE X

(295024EA2.02) Ability to determine or interpret the following as they apply to (EPE 1) HIGH DRYWELL PRESSURE: (CFR:

41.10 / 43.5 / 45.13) Drywell temperature 4.4 11 16 (295025) (EPE 2)

HIGH REACTOR PRESSURE X (295025) (EPE 2) HIGH REACTOR PRESSURE (G2.4.49)

EMERGENCY PROCEDURES/PLAN Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (CFR: 41.10 /

43.2 / 45.6) 4.6 12 17 (295026) (EPE 3)

SUPPRESSION POOL HIGH WATER X

(295026EA2.02) Ability to determine or interpret the following as they apply to (EPE 3) SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.10 / 43.5 / 45.13)

Suppression pool level 3.6 13 18 (295026) (EPE 3)

SUPPRESSION POOL HIGH WATER TEMPERATURE X (295026) (EPE 3) SUPPRESSION POOL HIGH WATER TEMPERATURE (G2.4.23) EMERGENCY PROCEDURES/PLAN Knowledge of the bases for prioritizing emergency operating procedures implementation (CFR: 41.10 / 43.5 / 45.13) 4.4 80 19 (295027) (EPE 4)

HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

X (295027EK2.02) Knowledge of the relationship between the (EPE 4) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Components internal to the containment 3.3 14 (295028) (EPE 5)

HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) / 5 20 (295030) (EPE 7)

LOW SUPPRESSION POOL WATER LEVEL X

(295030EK3.01) Knowledge of the reasons for the following responses or actions as they apply to (EPE 7) LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.5 / 41.10 /

45.6 / 45.13) Anticipated/emergency depressurization 4.0 15 21 (295031) (EPE 8)

REACTOR LOW WATER LEVEL X (295031) (EPE 8) REACTOR LOW WATER LEVEL (G2.1.20)

CONDUCT OF OPERATIONS Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5 / 45.12) 4.6 16 22 (295031) (EPE 8)

REACTOR LOW WATER LEVEL X

(295031EA2.04) Ability to determine or interpret the following as they apply to (EPE 8) REACTOR LOW WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13) Adequate core cooling 4.7 81 23 (295037) (EPE 14)

SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN X

(295037EA2.04) Ability to determine or interpret the following as they apply to (EPE 14) SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.10 / 43.5 / 45.13) Suppression pool temperature 3.8 17

24 (295038) (EPE 15)

HIGH OFFSITE RADIOACTIVITY RELEASE RATE X

(295038EK3.04) Knowledge of the reasons for the following responses or actions as they apply to (EPE 15) HIGH OFFSITE RADIOACTIVITY RELEASE RATE: (CFR: 41.5 /

41.10 / 45.6 / 45.13) Emergency depressurization 4.1 18 25 (600000) (APE 24)

PLANT FIRE ON SITE X (600000) (APE 24) PLANT FIRE ON SITE (G2.4.12)

EMERGENCY PROCEDURES/PLAN: Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR: 41.10 / 45.12) 4.0 19 26 (700000) (APE 25)

GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES X

(700000AK1.05) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: (CFR: 41.5 / 41.7 / 45.7 /

45.8) Voltage disturbance 3.5 20 27 (700000) (APE 25)

GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES X

(700000AA2.02) Ability to determine or interpret the following as they apply to (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: (CFR:

41.10 / 43.5 / 45.13) Generator voltage limitations 3.3 82 K/A Category Totals:

3 3

4 4

6 7 Group Point Total:

27

ES-4.1-BWR BWR Examination Outline (Grand Gulf)

Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

Item #

E/APE # / Name /

Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR Q#

(295002) (APE 2)

LOSS OF MAIN CONDENSER VACUUM / 3 28 (295007) (APE 7)

HIGH REACTOR PRESSURE X

(295007AA2.04) Ability to determine or interpret the following as they apply to (APE 7) HIGH REACTOR PRESSURE: (CFR:

41.10 / 43.5 / 45.13) Bypass valve capacity 4.2 21 29 (295008) (APE 8)

HIGH REACTOR WATER LEVEL X

(295008AK2.01) Knowledge of the relationship between the (APE 8) HIGH REACTOR WATER LEVEL and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) RPS 3.9 22 (295009) (APE 9)

LOW REACTOR WATER LEVEL / 2 (295010) (APE 10)

HIGH DRYWELL PRESSURE / 5 30 (295011) (APE 11)

HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

X (295011) (APE 11) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) (G2.1.9) CONDUCT OF OPERATIONS, Ability to direct licensed personnel activities inside the control room (SRO Only) (CFR: 43.1

/ 45.5 / 45.12 / 45.13) 4.5 83 31 (295012) (APE 12)

HIGH DRYWELL TEMPERATURE X

(295012AK3.01) Knowledge of the reasons for the following responses or actions as they apply to (APE 12) HIGH DRYWELL TEMPERATURE: (CFR: 41.5 / 41.10 / 45.6 /

45.13) Increased drywell cooling 3.8 23 (295013) (APE 13)

HIGH SUPPRESSION POOL TEMPERATURE. / 5 32 (295014) (APE 14)

INADVERTENT REACTIVITY ADDITION X

(295014AK1.08) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 14) INADVERTENT REACTIVITY ADDITION: (CFR: 41.5 / 41.7 / 45.7 / 45.8) Moderator temperature 3.7 24 (295017) (APE 17)

ABNORMAL OFFSITE RELEASE RATE / 9 (295020) (APE 20)

INADVERTENT CONTAINMENT ISOLATION / 5 & 7 33 (295022) (APE 22)

LOSS OF CONTROL ROD DRIVE PUMPS X (295022) (APE 22) LOSS OF CONTROL ROD DRIVE PUMPS (G2.1.20) CONDUCT OF OPERATIONS Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5 / 45.12) 4.6 25 (295029) (EPE 6)

HIGH SUPPRESSION POOL WATER LEVEL / 5

(295032) (EPE 9)

HIGH SECONDARY CONTAINMENT AREA TEMPERATURE / 5 34 (295033) (EPE 10)

HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS X (295033) (EPE 10) HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS (G2.2.44) EQUIPMENT CONTROL Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12) 4.4 84 35 (295034) (EPE 11)

SECONDARY CONTAINMENT VENTILATION HIGH RADIATION X

(295034EA1.03) Ability to operate or monitor the following as they apply to (EPE 11) SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: (CFR: 41.5 / 41.7 / 45.5 to 45.8) Secondary containment ventilation 3.8 26 36 (295035) (EPE 12)

SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE X

(295035EA2.03) Ability to determine or interpret the following as they apply to (EPE 12) SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: (CFR:

41.10 / 43.5 / 45.13) Lights and alarms 3.3 85 (295036) (EPE 13)

SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL / 5 (500000) (EPE 16)

HIGH CONTAINMENT HYDROGEN CONCENTRATION /

5 K/A Category Totals:

1 1

2 3 Group Point Total:

9

ES-4.1-BWR BWR Examination Outline (Grand Gulf)

Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)

Item #

System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR Q#

37 (203000) (SF2, SF4 RHR/LPCI)

RHR/LPCI:

INJECTION MODE X

(203000A4.02) Ability to manually operate and/or monitor the (SF2, SF4 RHR/LPCI) RHR/LPCI:

INJECTION MODE in the control room: (CFR: 41.7 / 45.5 to 45.8)

System valves 4.2 27 38 (205000) (SF4 SCS)

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

X (205000A2.01) Ability to (a) predict the impacts of the following on the (SF4 SCS) SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6)

Recirculation loop high temperature 3.6 28 39 (205000) (SF4 SCS)

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

X (205000) (SF4 SCS) SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

(G2.3.11) RADIATION CONTROL Ability to control radiation releases (CFR: 41.11 / 43.4 /

45.10) 4.3 29 (206000) (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM (207000) (SF4 IC)

ISOLATION (EMERGENCY)

CONDENSER 40 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X

(209001A4.05) Ability to manually operate and/or monitor the (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM in the control room: (CFR: 41.7 / 45.5 to 45.8) Manual initiation controls 4.2 30 41 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM (G2.1.41) CONDUCT OF OPERATIONS Knowledge of the refueling process (CFR: 41.2 /

41.10

/ 43.6 / 45.13) 2.8 86 42 (209002) (SF2, SF4 HPCS) HIGH PRESSURE CORE SPRAY SYSTEM X

(209002K1.01) Knowledge of the physical connections and/or cause and effect relationships between the (SF2, SF4 HPCS) HIGH PRESSURE CORE SPRAY SYSTEM and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Condensate system 3.2 31

43 (211000) (SF1 SLCS) STANDBY LIQUID CONTROL SYSTEM X

(211000K6.03) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF1 SLCS) STANDBY LIQUID CONTROL SYSTEM: (CFR: 41.7 /

45.7) AC Power 3.7 32 44 (212000) (SF7 RPS)

REACTOR PROTECTION SYSTEM X

(212000A3.09) Ability to monitor automatic operation of the (SF7 RPS) REACTOR PROTECTION SYSTEM including: (CFR: 41.7 /

45.7) System actuation 4.3 33 45 (215003) (SF7 IRM)

INTERMEDIATE RANGE MONITOR SYSTEM X

(215003K2.01) (SF7 IRM)

INTERMEDIATE RANGE MONITOR SYSTEM Knowledge of electrical power supplies to the following: (CFR: 41.7) IRM channels/detectors 3.4 34 46 (215003) (SF7 IRM)

INTERMEDIATE RANGE MONITOR SYSTEM X (215003) (SF7 IRM)

INTERMEDIATE RANGE MONITOR SYSTEM (G2.4.2)

EMERGENCY PROCEDURES/PLAN Knowledge of system setpoints, interlocks and automatic actions associated with emergency and abnormal operating procedure entry conditions (CFR: 41.7 / 45.7 / 45.8) 4.6 87 47 (215004) (SF7 SRMS) SOURCE RANGE MONITOR SYSTEM X

(215004K5.01) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF7 SRMS) SOURCE RANGE MONITOR SYSTEM : (CFR: 41.5 /

45.3) Detector operation 2.8 35 48 (215005) (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X

(215005A2.12) Ability to (a) predict the impacts of the following on the (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 /

45.6) Operation of the OPRM-enabled region of the power to flow map 4

36 49 (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM X

(217000K3.01) Knowledge of the effect that a loss or malfunction of the (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM will have on the following systems or system parameters:

(CFR: 41.7 / 45.4) Reactor water level 4.2 37

50 (218000) (SF3 ADS)

AUTOMATIC DEPRESSURIZATI ON SYSTEM X

(218000A4.02) Ability to manually operate and/or monitor the (SF3 ADS) AUTOMATIC DEPRESSURIZATION SYSTEM in the control room: (CFR: 41.7 / 45.5 to 45.8) ADS logic initiation 4.2 38 51 (223002) (SF5 PCIS) PRIMARY CONTAINMENT ISOLATION SYSTEM /

NUCLEAR STEAM SUPPLY SHUTOFF X

(223002K4.05) Knowledge of (SF5 PCIS) PRIMARY CONTAINMENT ISOLATION SYSTEM / NUCLEAR STEAM SUPPLY SHUTOFF design features and/or interlocks that provide for the following: (CFR:

41.7) Single failures will not impair the function ability of the system 3.6 39 52 (239002) (SF3 SRV)

SAFETY RELIEF VALVES X

(239002K4.05) Knowledge of (SF3 SRV) SAFETY RELIEF VALVES design features and/or interlocks that provide for the following: (CFR:

41.7) Allows for SRV operation from more than one location 3.7 40 53 (239002) (SF3 SRV)

SAFETY RELIEF VALVES X

(239002A2.02) Ability to (a) predict the impacts of the following on the (SF3 SRV)

SAFETY RELIEF VALVES and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

(CFR: 41.5 / 45.6) Leaking SRV 3.6 88 54 (259002) (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM X

(259002A3.06) Ability to monitor automatic operation of the (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM including: (CFR: 41.7 / 45.7)

Reactor water level setpoint setdown following a reactor SCRAM 3.6 41 55 (259002) (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM X

(259002K3.01) Knowledge of the effect that a loss or malfunction of the (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM will have on the following systems or system parameters:

(CFR: 41.7 / 45.4) Reactor water level 4.3 42 56 (261000) (SF9 SGTS) STANDBY GAS TREATMENT SYSTEM X

(261000A1.03) Ability to predict and/or monitor changes in parameters associated with operation of the (SF9 SGTS)

STANDBY GAS TREATMENT SYSTEM including: (CFR: 41.5 /

45.5) Offsite radioactive release limits 3.7 43 57 (262001) (SF6 AC)

AC ELECTRICAL DISTRIBUTION X

(262001K5.02) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF6 AC) AC ELECTRICAL DISTRIBUTION: (CFR: 41.5 / 45.3)

Breaker control power 3.5 44

58 (262002) (SF6 UPS)

UNINTERRUPTABL E POWER SUPPLY (AC/DC)

X (262002K2.01) (SF6 UPS)

UNINTERRUPTABLE POWER SUPPLY (AC/DC) Knowledge of electrical power supplies to the following: (CFR: 41.7) Static switch/inverter 3.3 45 59 (263000) (SF6 DC)

DC ELECTRICAL DISTRIBUTION X

(263000A1.03) Ability to predict and/or monitor changes in parameters associated with operation of the (SF6 DC) DC ELECTRICAL DISTRIBUTION including: (CFR: 41.5 / 45.5)

Voltage 3.5 46 60 (263000) (SF6 DC)

DC ELECTRICAL DISTRIBUTION X

(263000A2.03) Ability to (a) predict the impacts of the following on the (SF6 DC) DC ELECTRICAL DISTRIBUTION and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6)

Abnormal battery parameters 3.2 89 61 (264000) (SF6 EGE)

EMERGENCY GENERATORS (DIESEL/JET)

X (264000A3.05) Ability to monitor automatic operation of the (SF6 EGE) EMERGENCY GENERATORS (DIESEL/JET) including: (CFR: 41.7 / 45.7) Load shedding and sequencing 3.9 47 62 (264000) (SF6 EGE)

EMERGENCY GENERATORS (DIESEL/JET)

X (264000A2.09) Ability to (a) predict the impacts of the following on the (SF6 EGE)

EMERGENCY GENERATORS (DIESEL/JET) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

(CFR: 41.5 / 45.6) Loss of safety bus 4.3 90 63 (300000) (SF8 IA)

INSTRUMENT AIR SYSTEM X

(300000K3.17) Knowledge of the effect that a loss or malfunction of the (SF8 IA) INSTRUMENT AIR SYSTEM will have on the following systems or system parameters:

(CFR: 41.7 / 45.4) Heater drain system 3.1 48 64 (300000) (SF8 IA)

INSTRUMENT AIR SYSTEM X

(300000K6.01) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 IA) INSTRUMENT AIR SYSTEM: (CFR: 41.7 / 45.7) Air compressors 3.7 49

65 (400000) (SF8 CCS)

COMPONENT COOLING WATER SYSTEM X

(400000K1.14) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 CCS) COMPONENT COOLING WATER SYSTEM and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Fuel pool cooling and cleanup system 3.8 50 66 (400000) (SF8 CCS)

COMPONENT COOLING WATER SYSTEM X

(400000K6.12) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 CCS) COMPONENT COOLING WATER SYSTEM :

(CFR: 41.7 / 45.7) Reactor water cleanup system 3.1 51 67 (510000) (SF4 SWS*) SERVICE WATER SYSTEM X (510000) (SF4 SWS*) SERVICE WATER SYSTEM (G2.2.41)

EQUIPMENT CONTROL Ability to obtain and interpret station electrical and mechanical drawings (reference potential)

(CFR: 41.10 / 45.12 / 45.13) 3.5 52 K/A Category Totals:

2 2

3 2

2 3

2 5

3 3

4 Group Point Total:

31

ES-4.1-BWR BWR Examination Outline (Grand Gulf)

Emergency and Abnormal Plant EvolutionsTier 2/Group 2 (RO/SRO)

Item #

System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR Q#

68 (201001) (SF1 CRDH) CRD HYDRAULIC SYSTEM X

(201001A4.01) Ability to manually operate and/or monitor the (SF1 CRDH) CRD HYDRAULIC SYSTEM in the control room: (CFR: 41.7 /

45.5 to 45.8) CRD pumps 3.7 53 (201002) (SF1 RMCS) REACTOR MANUAL CONTROL SYSTEM 69 (201003) (SF1 CRDM) CONTROL ROD AND DRIVE MECHANISM X

(201003A2.01) Ability to (a) predict the impacts of the following on the Control Rod and Drive Mechanism and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6)

Stuck Rod 4.0 91 (201004) (SF7 RSCS) ROD SEQUENCE CONTROL SYSTEM 70 (201005) (SF1, SF7 RCIS) ROD CONTROL AND INFORMATION SYSTEM X

(201005A3.01) Ability to monitor automatic operation of the (SF1, SF7 RCIS) ROD CONTROL AND INFORMATION SYSTEM including:

(CFR: 41.7 / 45.7) Operator control module lights 3.6 54 71 (201006) (SF7 RWMS) ROD WORTH MINIMIZER SYSTEM (202001) (SF1, SF4 RS)

RECIRCULATION SYSTEM X

(202001K3.01) Knowledge of the effect that a loss or malfunction of the Recirculation System will have on the following systems or system parameters: (CFR: 41.5 to 41.7 / 45.4) Core Flow 4.2 55 (202002) (SF1 RSCTL)

RECIRCULATION FLOW CONTROL SYSTEM

72 (204000) (SF2 RWCU) REACTOR WATER CLEANUP SYSTEM X

(204000A1.09) Ability to predict and/or monitor changes in parameters associated with operation of the (SF2 RWCU)

REACTOR WATER CLEANUP SYSTEM including: (CFR: 41.5 /

45.5) Reactor water conductivity 3.3 56 (214000) (SF7 RPIS) ROD POSITION INFORMATION SYSTEM 73 (215001) (SF7 TIP)

TRAVERSING IN CORE PROBE X

(215001K4.03) Knowledge of (SF7 TIP) TRAVERSING IN CORE PROBE design features and/or interlocks that provide for the following: (CFR: 41.7) Radiation Shielding 2.9 57 (215002) (SF7 RBMS) ROD BLOCK MONITOR 74 (216000) (SF7 NBI)

NUCLEAR BOILER INSTRUMENTATIO N

X (2160002K5.01) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Nuclear Boiler Instrumentation:

(CFR: 41.5 / 45.3) Vessel level measurement 3.9 58 75 (219000) (SF5 RHR SPC) RHR/LPCI:

TORUS/SUPPRESS ION POOL COOLING MODE X

(219000A2.05) Ability to (a) predict the impacts of the following on the (SF5 RHR SPC)

RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

(CFR: 41.5 / 45.6) AC electrical failures 3.8 92 (223001) (SF5 PCS)

PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES (226001) (SF5 RHR CSS) RHR/LPCI:

CONTAINMENT SPRAY MODE SYSTEM MODE (230000) (SF5 RHR SPS) RHR/LPCI:

TORUS/SUPPRESS ION POOL SPRAY MODE (233000) (SF9 FPCCU) FUEL POOL COOLING/CLEANU P

76 (234000) (SF8 FH)

FUEL HANDLING X

(234000K1.12) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 FH) FUEL HANDLING and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Fuel pool cooling and cleanup system 3.1 59 (239001) (SF3, SF4 MRSS) MAIN AND REHEAT STEAM SYSTEM (239003) (SF9 MSVLCS) MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM 77 (241000) (SF3 RTPRS)

REACTOR/TURBIN E PRESSURE REGULATING SYSTEM X

(241000K2.01) (SF3 RTPRS)

REACTOR/TURBINE PRESSURE REGULATING SYSTEM Knowledge of electrical power supplies to the following: (CFR: 41.7) Pumps 2.9 60 78 (245000) (SF4 MTGEN) MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS X

(245000K2.04) (SF4 MTGEN) MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS Knowledge of electrical power supplies to the following: (CFR: 41.7) Hydrogen seal oil pumps 2.9 61 79 (256000) (SF2 CDS)

CONDENSATE SYSTEM X

(256000K6.09) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF2 CDS) CONDENSATE SYSTEM: (CFR: 41.7 / 45.7) Offgas system 2.6 62 (259001) (SF2 FWS)

FEEDWATER SYSTEM (268000) (SF9 RW)

RADWASTE SYSTEM (271000) (SF9 OG)

OFFGAS SYSTEM (272000) (SF7, SF9 RMS) RADIATION MONITORING SYSTEM (286000) (SF8 FPS)

FIRE PROTECTION SYSTEM (288000) (SF9 PVS)

PLANT VENTILATION SYSTEMS (290001) (SF5 SC)

SECONDARY CONTAINMENT

(290002) (SF4 RVI)

REACTOR VESSEL INTERNALS 80 (290003) (SF9 CRV)

CONTROL ROOM VENTILATION X (290003) (SF9 CRV) CONTROL ROOM VENTILATION (G2.4.42)

EMERGENCY PROCEDURES/PLAN Knowledge of emergency response facilities (CFR: 41.10 / 45.11) 3.8 93 81 (510001) (SF8 CWS*)

CIRCULATING WATER SYSTEM X

(510001A2.02) Ability to (a) predict the impacts of the following on the (SF8 CWS*) CIRCULATING WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6)

Abnormal valve positions 3

63 K/A Category Totals:

1 2

1 1

1 3

1 1

1 Group Point Total:

14

Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Grand Gulf)

Facility: Grand Gulf Date of Exam: 10/10/2022 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)

Category K/A #

RO SRO-Only Topic Item #

IR Q#

1.

Conduct of Operations G2.1.28 (G2.1.28) CONDUCT OF OPERATIONS Knowledge of the purpose and function of major system components and controls (CFR: 41.7) 82 4.1 64 G2.1.46 (G2.1.46) CONDUCT OF OPERATIONS Ability to use integrated control systems to operate plant systems or components (CFR: 41.10/ 45.12 / 45.13) 83 4

65 G2.1.1 (G2.1.1) Knowledge of conduct of operations requirements. (CFR: 41.10 / 43.10 / 45.13) 84 3.8 94 G2.1.35 (G2.1.35) CONDUCT OF OPERATIONS Knowledge of the fuel handling responsibilities of SROs (SRO Only) (CFR:

43.7) 85 3.9 95 Subtotal N/A 2

N/A 2

2.

Equipment Control G2.2.13 (G2.2.13) EQUIPMENT CONTROL Knowledge of tagging and clearance procedures (CFR: 41.10 / 43.1 / 45.13) 86 4.1 66 G2.2.35 (G2.2.35) EQUIPMENT CONTROL Ability to determine technical specification mode of operation (CFR: 41.7 / 41.10 /

43.2 / 45.13) 87 3.6 67 G2.2.39 (G2.2.39) EQUIPMENT CONTROL Knowledge of less than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months technical specification action statements (This K/A does not include action statements of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or less that follow the expiration of a completion time for a technical specification condition for which an action statement has already been entered.) (CFR: 41.7 /

41.10 / 43.2 / 45.13) 88 4.5 96 G2.2.40 (G2.2.40) EQUIPMENT CONTROL Ability to apply technical specifications with action statements of less than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (CFR: 41.10 / 43.2 / 43.5 / 45.3) 89 4.7 97 Subtotal N/A 2

N/A 2

3.

Radiation Control G2.3.12 (G2.3.12) RADIATION CONTROL Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters (CFR: 41.12 / 43.4 / 45.9 / 45.10) 90 3.2 68 G2.3.14 (G2.3.14) RADIATION CONTROL Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures, or analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) (CFR: 43.4

/ 45.10) 91 3.8 98 Subtotal N/A 1

N/A 1

4.

Emergency Procedures / Plan G2.4.47 (G2.4.47) EMERGENCY PROCEDURES/PLAN Ability to diagnose and recognize trends in an accurate and timely manner using the appropriate control room reference material (reference potential) (CFR: 41.10 / 43.5 / 45.12) 92 4.2 69 G2.4.20 (G2.4.20) EMERGENCY PROCEDURES/PLAN Knowledge of the operational implications of emergency and abnormal operating procedures warnings, cautions, and notes (CFR: 41.10 / 43.5 / 45.13) 93 4.3 99

G2.4.38 (G2.4.38) EMERGENCY PROCEDURES/PLAN Ability to take actions required by the facility emergency plan implementing procedures, including supporting or acting as emergency coordinator (CFR: 41.10 / 43.5 / 45.11) 94 4.4 100 Subtotal N/A 1

N/A 2

Tier 3 Point Total N/A 6

N/A 7

Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Grand Gulf)

Facility: Grand Gulf Date of Exam: 10/10/2022 Theory (Tier 4) (RO)

Category K/A #

RO Topic Item #

IR Q#

Reactor Theory 292001 (292001K1.07) NEUTRONS (CFR: 41.1) Define neutron generation time 95 1.9 70 292006 (292006K1.08) FISSION PRODUCT POISONS (CFR: 41.1)

Describe the effects that xenon concentration has on flux shape and control rod patterns 96 3.2 71 292007 (292007K1.02) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1) Describe and explain distribution of burnable poisons in the core 97 2.0 72 Subtotal 3

Thermodynamics 293004 (293004K1.08) THERMODYNAMIC PROCESS (CFR: 41.14)

(TURBINES) Define turbine efficiency 98 2.1 73 293008 (293008K1.25) THERMAL HYDRAULICS (CFR: 41.14)

(RECIRCULATION SYSTEM) Explain the reason for forced core recirculation 99 3.2 74 293010 (293010K1.05) BRITTLE FRACTURE AND VESSEL THERMAL STRESS (CFR: 41.14) State the effect of fast neutron irradiation on reactor vessel metals 100 2.8 75 Subtotal 3

Tier 4 Point Total N/A 6

Form 4.1-1 Record of Rejected Knowledge and Abilities Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.

Tier/Group Randomly Selected K/A Reason for Rejection 1 / 1 295019 AK3.04 Q# - 8 295019 AK3.03 Original KA: (295019) (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR AK3.03 - Knowledge of the reasons for the following responses or actions as they apply to (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: (CFR: 41.5 / 41.10 / 45.6 / 45.13),

Dryer/filter realignment A licensed operator would not perform any of these actions, all local indications, and actions.

Randomly selected new K/A K3.03, Service Air isolations Page 1 point totals not affected by this change.

1 / 1 295027 EK2.06 Q# - 14 295027 EK2.02 Original KA: (295027) (EPE 4) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

EK2.06 - Knowledge of the relationship between the (EPE 4)

HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Reactor/Turbine pressure regulating system.

Grand Gulf Reactor Pressure Control System does not have any relationship with Containment Temperature. This KA will be added to the Rejected KA list for future use.

Randomly selected new K/A EK2.02, Components internal to the containment.

Page 1 point totals not affected by this change.

Tier/Group Randomly Selected K/A Reason for Rejection 1 / 1 600000 G2.2.36 Q# - 19 600000 G2.4.12 Original KA: (600000) (APE 24) PLANT FIRE ON SITE G2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operation (CFR: 41.10 / 43.2 / 45.13).

Analyzing maintenance activities on status of LCOs is an SRO function.

Randomly selected new K/A (G2.4.12)

EMERGENCY PROCEDURES/PLAN: Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR: 41.10 / 45.12)

Page 1 point totals not affected by this change.

1 / 2 295012 AK3.02 Q# - 23 295012 AK3.01 (295012) (APE 12) HIGH DRYWELL TEMPERATURE (295012AK3.02) Knowledge of the reasons for the following responses or actions as they apply to (APE 12) HIGH DRYWELL TEMPERATURE: (CFR: 41.5 / 41.10 / 45.6 / 45.13) Venting Grand Gulf does not have guidance to Vent the Dyrwell. This KA will be added to the Rejected KA list for future use.

Randomly selected new K/A AK3.01 Increased drywell cooling Page 1 point totals not affected by this change.

1 / 2 295022 G2.1.40 Q# - 25 295022 G2.1.20 (295022) (APE 22) LOSS OF CONTROL ROD DRIVE PUMPS (295022) (APE 22) (G2.1.40) CONDUCT OF OPERATIONS Knowledge of refueling administrative requirements (CFR: 41.10 /

43.5 / 43.6 / 45.13)

Grand Gulf does not have guidance on loss of the CRD system in the refueling administrative requirements.

Randomly selected new K/A G2.1.20 Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5 / 45.12)

Page 1 point totals not affected by this change.

Tier/Group Randomly Selected K/A Reason for Rejection 2 / 1 262002 K2.02 Q# - 45 262002 K2.01 (262002) (SF6 UPS) UNINTERRUPTABL E POWER SUPPLY (AC/DC)

(262002K2.02) (SF6 UPS) UNINTERRUPTABLE POWERSUPPLY (AC/DC) Knowledge of electrical power supplies to the following: (CFR: 41.7) Motor generator.

Grand Gulf does not have any Motor generators in the UPS system. This KA will be added to the Rejected KA list for future use.

Randomly selected new K/A K2.01, Static switch/inverter Page 1 point totals not affected by this change.

2 / 1 510000 G2.2.18 Q# - 52 510000 G2.2.41 (510000) (SF4 SWS*) SERVICE WATER SYSTEM 510000) (SF4 SWS*) SERVICE WATER SYSTEM (G2.2.18)

EQUIPMENT CONTROL Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments and work prioritization (CFR: 41.10 / 43.5 /45.13)

At Grand Gulf managing maintenance activities, risk assessments and word prioritization are SRO duties.

Randomly selected new K/A G2.2.41, Ability to obtain and interpret station electrical and mechanical drawings (reference potential)

(CFR: 41.10 / 45.12 / 45.13)

Page 1 point totals not affected by this change.

SRO 1 / 2 295011 G2.1.37 Q# - 83 295011 G2.1.9 (295011) (APE 11) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

(295011) (APE 11) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) (G2.1.37) CONDUCT OF OPERATIONS, Knowledge of procedures, guidelines, or limitations associated with reactivity management (CFR: 41.1 / 41.5 / 41.10 / 43.6 / 45.6)

Reactivity Management during a refueling outage has no guidance on Primary Containment Temperature.

Randomly selected new K/A (G2.1.9), Ability to direct licensed personnel activities inside the control room (SRO Only) (CFR: 43.1 /

45.5 / 45.12 / 45.13)

Page 1 point totals not affected by this change.

Tier/Group Randomly Selected K/A Reason for Rejection 1 / 2 295033 G2.2.15 Q# - 84 295033 G2.2.44 (295033) (EPE 10) HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS (295033) (EPE 10) HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS (G2.2.15) EQUIPMENT CONTROL Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, lineups or, tagouts (reference potential) (CFR: 41.10 / 43.3 / 45.13)

Unable to write discriminatory SRO level question for this K/A Randomly selected new K/A (G2.2.44) EQUIPMENT CONTROL Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 /

45.12)

Page 1 point totals not affected by this change.

2 / 1 215003 G2.4.52 Q# - 87 215003 G2.4.2 (215003) (SF7 IRM) INTERMEDIATE RANGE MONITOR SYSTEM 215003) (SF7 IRM) INTERMEDIATE RANGE MONITOR SYSTEM (G2.4.52) EMERGENCY PROCEDURES/PLAN Knowledge of the lines of authority during implementation of the emergency plan, emergency plan implementing procedures, emergency operating procedures, or severe accident guidelines (CFR: 41.10 / 45.13)

Unable to write discriminatory SRO level question for this K/A due to the IRM system is not covered within the Emergency Procedures/Plan Randomly selected new K/A (G2.4.2) EMERGENCY PROCEDURES/PLAN Knowledge of system setpoints, interlocks and automatic actions associated with emergency and abnormal operating procedure entry conditions (CFR: 41.7 / 45.7 / 45.8)

Page 1 point totals not affected by this change.

3 G2.1.6 Q# - 94 G2.1.1 (G2.1.6) CONDUCT OF OPERATIONS Ability to manage the control room crew during plant transients (SRO Only) (CFR: 43.5 /

45.12 / 45.13)

This K/A is better evaluated in a dynamic simulator setting.

Randomly selected new K/A (G2.1.1) CONDUCT OF OPERATIONS Knowledge of conduct of operations requirements.

(CFR: 41.10 / 43.10 / 45.13)

Page 1 point totals not affected by this change.

Form 3.2-1 Administrative Topics Outline Facility:

GRAND GULF NUCLEAR STATION Date of Examination: October 10. 2022 Examination Level:

RO SRO Operating Test Number: GGNS 2022 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations GJPM-OPS-2022AR1, Review Cooldown Record per IOI. The operator will review cooldown data recorded on 03-1-01-3 Attachment 3 and identify the Tech Spec limit of 100F/hr has been exceeded.

2.1.23 Ability to perform general or normal operating procedures during any plant condition (CFR: 41.10 / 43.5 / 45.2 / 45.6)

IMPORTANCE RO 4.3 This JPM has not been used in the last 5 NRC exams.

R, D Equipment Control GJPM-OPS-2022AR2, RPS Electrical Print Reading. The applicant will use the provided electrical prints to prove that removing C71-F14A will de-energize K14A and K14E relays inserting a Division 1 half scram. Removing C71-27D will de-energize the white light for Reactor Scram Trip Logic D.

2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, lineups or, tagouts (reference potential)

(CFR: 41.10 / 43.3 / 45.13)

IMPORTANCE RO 3.9 This JPM has not been used in the last 5 NRC exams.

R, D

Radiation Control GJPM-OPS-2022AR3, Determine Exposure Limit. The applicant will use the given room RP survey map and first determine the normal administrative dose limits are in effect. An Alert or higher would raise the limits to the federal guidelines. Determine the total amount of dose by using the survey map and the general dose at the location for 0.5 hrs.

2.3.12 Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters (CFR: 41.12 / 43.4 / 45.9 / 45.10)

IMPORTANCE RO 3.2 R, N Emergency Plan GJPM-OPS-2022AR4, Perform Emergency Notifications. This task is to review an Emergency Notification Form and then make the required notifications to state and local agencies using the Operational Hotline (OHL). This task will be simulated using a disconnected telephone.

Licensed and Non-Licensed Operators are designated to perform the duties of Control Room Communicator.

2.4.52 Knowledge of the lines of authority during implementation of the emergency plan, emergency plan implementing procedures, emergency operating procedures, or severe accident guidelines (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.0 R, D

Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

Topic Number of JPMs RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.

3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams)

(D)irect from bank (no more than three for ROs, no more than four for SROs and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)

Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics portion of the operating test (with a waiver or excusal of the other portions).

Form 3.2-1 Administrative Topics Outline Facility:

GRAND GULF NUCLEAR STATION Date of Examination: October 10. 2022 Examination Level: RO SRO Operating Test Number: GGNS 2022 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations GJPM-OPS-2022AS1 - Review Requirements for MODE change to STARTUP The candidate will use the given IOI-1 attachments and review for Mode Change restraints from Mode 4 (Cold Shutdown) to Mode 2 (Startup).

2.1.1 Knowledge of conduct of operations requirements (CFR: 41.10 / 43.10 / 45.13)

IMPORTANCE SRO 4.2 R, N Conduct of Operations GJPM-OPS-2022AS2 - Determine Shutdown Risk Levels For the stated conditions, the candidate will use the SOPP to determine the plant is in Shutdown Condition 3, then using the SOPP charts, determine the risk levels for Decay Heat Removal, Inventory Control and AC Power Control.

A similar JPM was given during the 10-2020 NRC Exam (GJPM-OPS-10-2020AS3) 2.1.41 Knowledge of the refueling process (CFR: 41.2 / 41.10 / 43.6 / 45.13)

IMPORTANCE SRO 3.7 R, M Equipment Control GJPM-OPS-2022AS3 - Tagout/LCO Determination The applicant will evaluate a tagout for the Tech Spec implications as a Tagout Approver per EN OP102 section 5.8.1. The candidate will also complete a manual LCOTR for the applicable LCO per EN-OP-115-16, Safety Function Determination, and LOCTR Processes.

This JPM was used during the 5/2017 NRC Exam.

2.2.45 Ability to determine or interpret technical specifications with action statements of greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (SRO Only) (CFR: 43.2 / 43.5 / 45.3)

IMPORTANCE SRO 4.7 R, D

Radiation Control GJPM-OPS-2022AS4 - Upgrade Classification and Determine Release Data This task is an event classification in accordance with EALs and using the Radiation data given, determines the upgrade criteria.

2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures, or analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) (CFR: 43.4 / 45.10)

IMPORTANCE SRO 3.8 R, N Emergency Plan GJPM-OPS-2022AS5 - Perform Initial Actions of the Shift Manager/ED During an Emergency Event This task is an activation of the ERO during an event in accordance with Emergency Response procedures and is required of all licensed SROs.

2.4.40 Knowledge of SRO responsibilities in emergency plan implementing procedures (SRO Only) (CFR: 43.5 / 45.11)

IMPORTANCE SRO 4.5 R, N

Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

Topic Number of JPMs RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.

3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams)

(D)irect from bank (no more than three for ROs, no more than four for SROs and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)

Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics portion of the operating test (with a waiver or excusal of the other portions).

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: GRAND GULF NUCLEAR STATION Date of Examination: October 10, 2022 Operating Test Number: GGNS 2022 Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems S1 - Operate CRD System/RCIS to bring the Reactor Critical, GJPM-OPS-2022S1, 201005 A4.01 (3.7/3.7); A4.02 (3.7/3.7)

D, L, S 1

S2 - Perform RFPT Thrust Bearing Wear Monthly Test GJPM-OPS-2022S2, 259001 A2.07 (4.1/4.1); A4.02 (4.0)

A, N, S 2

S3 - Turbine Bypass Control Valve Pressure Control Malfunction GJPM-OPS-2022S3, 241000 A4.06 (4.2); A3.08 (4.0)

N, S 3

S4 - Performing HPCS Quarterly Functional Test GJPM-OPS-2022S4, 209002 A2.01 (4.5/4.4)

A, D, EN, S 4

S5 - Incomplete NS4 Isolation GJPM-OPS-2022S5, 223002 A4.06 (4.2)

A, N, S 5

S6 - Transfer ESF Bus 17AC Power to XFMR ESF 12 GJPM-OPS-2022S6, 262001 A3.02 (3.7) (RO ONLY)

EN, N, S 6

S7 - Reactor Manual Scram Switch Test GJPM-OPS-2022S7, 212000 A1.11 (3.7); A3.09 (4.3)

A, D, EN, S 7

S8 - Perform Standby Gas Treatment System B Operability GJPM-OPS-2022S8, 212000 A1.11 (3.7); A3.09 (4.3)

A, EN, N, S 9

In-Plant Systems P1 - Manual Diesel / Generator Startup with Auto Start Signal Present GJPM-OPS-2022P1, 264000 A2.11 (4.6/4.3); A2.10 (4.7/4.4)

N, EN 6

P2 - Local Manual Fire Water Pump Start GJPM-OPS-2022P2, 286000 A2.08 (3.7/3.3); A2.01 (2.8/3.1)

N 8

P3 - Perform Attachment IV of Shutdown from Remote Shutdown Panel GJPM-OPS-2022P3, 288000 A4.01 (3.2) A4.03 (3.0)

D, E, L, R 9

JPM

Description:

S1 - Operate CRD System/RCIS to bring the Reactor Critical, GJPM-OPS-2022S1, 201005 A4.01 (3.7/3.7); A4.02 (3.7/3.7)

This task withdraws control rods per the Control Rod Movement Sequence to establish Reactor Criticality.

When the control rod Block occurs, the operator must recognize that a Data Fault has occurred per the P680-4A2-C5 ARI and will be directed to substitute position per 04-1-01-C11-2 SOI.

Bank JPM, however, not used previously on last 5 NRC Exams.

S2 - Perform RFPT Thrust Bearing Wear Monthly Test ALTERNATE PATH GJPM-OPS-2022S2, 259001 A2.07 (4.1/4.1); A4.02 (4.0)

This task is a monthly test on the Reactor Feedwater Pumps Thrust Bearing Wear detector.

During the test a RFPT B Speed Controller will fail, causing the speed to rise.

The Feedwater System Malfunctions ONEP will be entered and actions performed.

NEW JPM S3 - Turbine Bypass Control Valve Pressure Control Malfunction GJPM-OPS-2022S3, 241000 A4.06 (4.2); A3.08 (4.0)

This task has the applicant manually closing one of the three Turbine Bypass Control Valves during power operation, using the Ovation HDMI control panel

NEW JPM

S4 - Performing HPCS Quarterly Functional Test GJPM-OPS-2022S4, 209002 A2.01 (4.5/4.4)

ALTERNATE PATH

This task requires the ability to manually start the only ECCS-qualified high pressure injection system.

This task demonstrates the ability to operate HPCS in the "test return" mode, which puts HPCS flow in a loop from and to the Suppression Pool, one of its two suction sources. HPCS is operated in this mode for surveillance and post-maintenance testing.

As HPCS is placed in the test return an inadvertent initiation will occur with reactor core injection. This will require the applicant to per actions per 02-S-01-43, Transient Mitigation Strategy.

Bank JPM, however, a similar JPM was performed on 2-2020 NRC Exam (S4).

S5 - Incomplete NS4 Isolation GJPM-OPS-2022S5, 223002 A4.06 (4.2)

ALTERNATE PATH

This task is to secure A SSW system and return to Standby.

This is an Alternate Path JPM, as SSW A is being secured a small Drywell Leak will occur.

NS4 isolation will fail to occur and the applicant will be required to manually isolate the Containment/Drywell/ Auxiliary Building per Automatic Isolation ONEP.

NEW JPM S6 - Transfer ESF Bus 17AC Power to XFMR ESF 12 GJPM-OPS-2022S6, 262001 A3.02 (3.7) (RO ONLY)

This task is to transfer incoming supply power to ESF Bus 17AC from XFMR 21 to ESF XFMR 12 per SOI.

NEW JPM

S7 - Reactor Manual Scram Switch Test GJPM-OPS-2022S7, 212000 A1.11 (3.7); A3.09 (4.3)

ALTERNATE PATH

The applicant will perform 06-OP-1C71-Q-0002 (Reactor Manual Scram Switch Test).

When the operator depresses the first manual scram switch, the applicant should recognize 3 scrammed rods.

The applicant should perform 05-1-02-IV-1, Control Rod/Drive Malfunctions ONEP Immediate actions.

Bank JPM, however, not used previously on last 5 NRC Exams.

S8 - Perform Standby Gas Treatment System B Operability GJPM-OPS-2022S8, 212000 A1.11 (3.7); A3.09 (4.3)

ALTERNATE PATH

The applicant will complete 06-OP-1T48-M-0002 (Standby Gas Treatment System B Operability).

When the applicant places MOV test switch to NORM a 5 second time delay will occur then a high radiation signal from Fuel Pool Sweep/Fuel Handling Area systems will occur. Both SGBT systems will not initiate.

The applicant should perform EN-OP-120, Operator Fundamentals, and manually initiate both SGBT trains.

NEW JPM P1 - Manual Diesel / Generator Startup with Auto Start Signal Present GJPM-OPS-2022P1, 264000 A2.11 (4.6/4.3); A2.10 (4.7/4.4)

This task simulates a failure to start of the Division III, HPCS Diesel Generator, with directions to manually start locally.

NEW JPM

P2 - Local Manual Fire Water Pump Start GJPM-OPS-2022P2, 286000 A2.08 (3.7/3.3); A2.01 (2.8/3.1)

This task simulates a failure to start of ALL Fire Water Pumps, a remote start has already been attempted.

The applicant must manually start all three Fire Water Pumps locally.

NEW JPM P3 - Perform Attachment IV of Shutdown from Remote Shutdown Panel GJPM-OPS-2022P3, 288000 A4.01 (3.2) A4.03 (3.0)

This task is to align the Alternate Shutdown Panels in the Auxiliary Building per 05-1-02-II-1 Attachment IV separating the Main Control Room from the Division I equipment for safe shutdown in the event of a fire or security event in the Main Control Room.

This JPM is considered a Low Power JPM due to the requirement to scram the plant prior to manning the Remote Shutdown Panels.

This JPM is an Abnormal Operating Procedure requiring entry into the CAA.

This JPM will match several KAs due to the alignment of systems for remote shutdown.

Bank JPM, however, not used previously on last 5 NRC Exams.

Code License Level Criteria RO (A)lternate path 5

(C)ontrol room (D)irect from bank 4

(E)mergency or abnormal in-plant 1

(EN)gineered safety feature (for control room system) 5 (L)ow power/shutdown 2

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 6 (P)revious two exams (randomly selected) 0 (R)adiologically controlled area 1

(S)imulator

1. Determine the number of control room system and in-plant system job performance measures (JPMs) to develop using the following table:

License Level Control Room In-Plant Total Reactor Operator (RO) 8 3

11 Senior Reactor Operator-Instant (SRO-I) 7 3

10 Senior Reactor Operator-Upgrade (SRO-U) 2 or 3 3 or 2 5

2. Select safety functions and systems for each JPM as follows:

Refer to Section 1.9 of the applicable knowledge and abilities (K/A) catalog for the plant systems organized by safety function. For pressurized-water reactor operating tests, the primary and secondary systems listed under Safety Function 4, Heat Removal from Reactor Core, in Section 1.9 of the applicable K/A catalog, may be treated as separate safety functions (i.e., two systems, one primary and one secondary, may be selected from Safety Function 4). From the safety function groupings identified in the K/A catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicants license level (see the table in step 1).

For RO/SRO-I applicants: Each of the control room system JPMs and, separately, each of the in-plant system JPMs must evaluate a different safety function, and the same system or evolution cannot be used to evaluate more than one safety function in each location. One of the control room system JPMs must be an engineered safety feature.

For SRO-U applicants: Evaluate SRO-U applicants on five different safety functions.

One of the control room system JPMs must be an engineered safety feature, and the same system or evolution cannot be used to evaluate more than one safety function.

3. Select a task for each JPM that supports, either directly or indirectly and in a meaningful way, the successful fulfillment of the associated safety function. Select the task from the applicable K/A catalog (K/As for plant systems or emergency and abnormal plant evolutions) or the facility licensees site-specific task list. If this task has an associated K/A, the K/A should have an importance rating of at least 2.5 in the RO column. K/As that have importance ratings of less than 2.5 may be used if justified based on plant priorities; inform the NRC chief examiner if selecting K/As with an importance rating less than 2.5.

The selected tasks must be different from the events and evolutions conducted during the simulator operating test and tasks tested on the written examination. A task that is similar to a simulator scenario event may be acceptable if the actions required to complete the task are significantly different from those required in response to the scenario event.

Apply the following specific task selection criteria:

At least one of the tasks shall be related to a shutdown or low-power condition.

Four to six of the tasks for RO and SRO-I applicants shall require execution of alternative paths within the facility licensees operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensees operating procedures.

At least one alternate path JPM must be new or modified from the bank.

At least one of the tasks conducted in the plant shall evaluate the applicants ability to implement actions required during an emergency or abnormal condition.

At least one of the tasks conducted in the plant shall require the applicant to enter the radiologically controlled area. This provides an excellent opportunity for the applicant to discuss or demonstrate radiation control administrative subjects.

If it is not possible to develop or locate a suitable task for a selected system, return to step 2 and select a different system.

4. For each JPM, specify the codes for type, source, and location:

Code License Level Criteria RO SRO-I SRO-U (A)lternate path 4-6 4-6 2-3 (C)ontrol room (D)irect from bank 9

8 4

(E)mergency or abnormal in-plant 1

1 1

(EN)gineered safety feature (for control room system) 1 1

1 (L)ow power/shutdown 1

1 1

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 2 2

1 (P)revious two exams (randomly selected) 3 3

2 (R)adiologically controlled area 1

1 1

(S)imulator

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: GRAND GULF NUCLEAR STATION Date of Examination: October 10, 2022 Operating Test Number: GGNS 2022 Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems S1 - Operate CRD System/RCIS to bring the Reactor Critical, GJPM-OPS-2022S1, 201005 A4.01 (3.7/3.7); A4.02 (3.7/3.7)

D, L, S 1

S2 - Perform RFPT Thrust Bearing Wear Monthly Test GJPM-OPS-2022S2, 259001 A2.07 (4.1/4.1); A4.02 (4.0)

A, N, S 2

S3 - Turbine Bypass Control Valve Pressure Control Malfunction GJPM-OPS-2022S3, 241000 A4.06 (4.2); A3.08 (4.0)

N, S 3

S4 - Performing HPCS Quarterly Functional Test GJPM-OPS-2022S4, 209002 A2.01 (4.5/4.4)

A, D, EN, S 4

S5 - Incomplete NS4 Isolation GJPM-OPS-2022S5, 223002 A4.06 (4.2)

A, N, S 5

S7 - Reactor Manual Scram Switch Test GJPM-OPS-2022S7, 212000 A1.11 (3.7); A3.09 (4.3)

A, D, EN, S 7

S8 - Perform Standby Gas Treatment System B Operability GJPM-OPS-2022S8, 212000 A1.11 (3.7); A3.09 (4.3)

A, EN, N, S 9

In-Plant Systems P1 - Manual Diesel / Generator Startup with Auto Start Signal Present GJPM-OPS-2022P1, 264000 A2.11 (4.6/4.3); A2.10 (4.7/4.4)

N, EN 6

P2 - Local Manual Fire Water Pump Start GJPM-OPS-2022P2, 286000 A2.08 (3.7/3.3); A2.01 (2.8/3.1)

N 8

P3 - Perform Attachment IV of Shutdown from Remote Shutdown Panel GJPM-OPS-2022P3, 288000 A4.01 (3.2) A4.03 (3.0)

D, E, L, R 9

JPM

Description:

S1 - Operate CRD System/RCIS to bring the Reactor Critical, GJPM-OPS-2022S1, 201005 A4.01 (3.7/3.7); A4.02 (3.7/3.7)

This task withdraws control rods per the Control Rod Movement Sequence to establish Reactor Criticality.

When the control rod Block occurs, the operator must recognize that a Data Fault has occurred per the P680-4A2-C5 ARI and will be directed to substitute position per 04-1-01-C11-2 SOI.

Bank JPM, however, not used previously on last 5 NRC Exams.

S2 - Perform RFPT Thrust Bearing Wear Monthly Test ALTERNATE PATH GJPM-OPS-2022S2, 259001 A2.07 (4.1/4.1); A4.02 (4.0)

This task is a monthly test on the Reactor Feedwater Pumps Thrust Bearing Wear detector.

During the test a RFPT B Speed Controller will fail, causing the speed to rise.

The Feedwater System Malfunctions ONEP will be entered and actions performed.

NEW JPM S3 - Turbine Bypass Control Valve Pressure Control Malfunction GJPM-OPS-2022S3, 241000 A4.06 (4.2); A3.08 (4.0)

This task has the applicant manually closing one of the three Turbine Bypass Control Valves during power operation, using the Ovation HDMI control panel

NEW JPM

S4 - Performing HPCS Quarterly Functional Test GJPM-OPS-2022S4, 209002 A2.01 (4.5/4.4)

ALTERNATE PATH

This task requires the ability to manually start the only ECCS-qualified high pressure injection system.

This task demonstrates the ability to operate HPCS in the "test return" mode, which puts HPCS flow in a loop from and to the Suppression Pool, one of its two suction sources. HPCS is operated in this mode for surveillance and post-maintenance testing.

As HPCS is placed in the test return an inadvertent initiation will occur with reactor core injection. This will require the applicant to per actions per 02-S-01-43, Transient Mitigation Strategy.

Bank JPM, however, a similar JPM was performed on 2-2020 NRC Exam (S4).

S5 - Incomplete NS4 Isolation GJPM-OPS-2022S5, 223002 A4.06 (4.2)

ALTERNATE PATH

This task is to secure A SSW system and return to Standby.

This is an Alternate Path JPM, as SSW A is being secured a small Drywell Leak will occur.

NS4 isolation will fail to occur and the applicant will be required to manually isolate the Containment/Drywell/ Auxiliary Building per Automatic Isolation ONEP.

NEW JPM

S7 - Reactor Manual Scram Switch Test GJPM-OPS-2022S7, 212000 A1.11 (3.7); A3.09 (4.3)

ALTERNATE PATH

The applicant will perform 06-OP-1C71-Q-0002 (Reactor Manual Scram Switch Test).

When the operator depresses the first manual scram switch, the applicant should recognize 3 scrammed rods.

The applicant should perform 05-1-02-IV-1, Control Rod/Drive Malfunctions ONEP Immediate actions.

Bank JPM, however, not used previously on last 5 NRC Exams.

S8 - Perform Standby Gas Treatment System B Operability GJPM-OPS-2022S8, 212000 A1.11 (3.7); A3.09 (4.3)

ALTERNATE PATH

The applicant will complete 06-OP-1T48-M-0002 (Standby Gas Treatment System B Operability).

When the applicant places MOV test switch to NORM a 5 second time delay will occur then a high radiation signal from Fuel Pool Sweep/Fuel Handling Area systems will occur. Both SGBT systems will not initiate.

The applicant should perform EN-OP-120, Operator Fundamentals, and manually initiate both SGBT trains.

NEW JPM P1 - Manual Diesel / Generator Startup with Auto Start Signal Present GJPM-OPS-2022P1, 264000 A2.11 (4.6/4.3); A2.10 (4.7/4.4)

This task simulates a failure to start of the Division III, HPCS Diesel Generator, with directions to manually start locally.

NEW JPM

P2 - Local Manual Fire Water Pump Start GJPM-OPS-2022P2, 286000 A2.08 (3.7/3.3); A2.01 (2.8/3.1)

This task simulates a failure to start of ALL Fire Water Pumps, a remote start has already been attempted.

The applicant must manually start all three Fire Water Pumps locally.

NEW JPM P3 - Perform Attachment IV of Shutdown from Remote Shutdown Panel GJPM-OPS-2022P3, 288000 A4.01 (3.2) A4.03 (3.0)

This task is to align the Alternate Shutdown Panels in the Auxiliary Building per 05-1-02-II-1 Attachment IV separating the Main Control Room from the Division I equipment for safe shutdown in the event of a fire or security event in the Main Control Room.

This JPM is considered a Low Power JPM due to the requirement to scram the plant prior to manning the Remote Shutdown Panels.

This JPM is an Abnormal Operating Procedure requiring entry into the CAA.

This JPM will match several KAs due to the alignment of systems for remote shutdown.

Bank JPM, however, not used previously on last 5 NRC Exams.

Code License Level Criteria RO (A)lternate path 5

(C)ontrol room (D)irect from bank 4

(E)mergency or abnormal in-plant 1

(EN)gineered safety feature (for control room system) 4 (L)ow power/shutdown 2

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 5 (P)revious two exams (randomly selected) 0 (R)adiologically controlled area 1