Text

08 Draft Outlines
	ML23285A295
Person / Time
Site:	Waterford
Issue date:	08/30/2023
From:	Heather Gepford; Operations Branch IV
To:	; Entergy Operations
References
	05000382/2023301
	Download: ML23285A295 (1)
	v • d • e

Facility: Waterford K/A Catalog Rev. 3 Rev. dd/mm/yyyy Date of Exam: 8/30/2023 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

18 3

3 6

2 1

1 1

2 1

2 8

2 2

4 Tier Totals 4

4 4

5 4

5 26 5

5 10

2.

Plant Systems 1

2 2

3 2

2 3

3 3

3 2

3 28 3

2 5

2 1

0 1

1 1

0 1

1 1

9 0

2 1

3 Tier Totals 3

2 4

3 3

3 4

4 4

3 4

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

Page 2 of 17 Item #

E/APE # / Name /

Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR Q#

1 (000007) (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery X (000007) (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery (G2.4.16) EMERGENCY PROCEDURES/PLAN: Knowledge of emergency and abnormal operating procedures implementation hierarchy and coordination with other support procedures or guidelines, such as operating procedures, abnormal operating procedures, or severe accident management guidelines (CFR: 41.10 / 43.5 / 45.13) 3.5 1

2 (000008) (APE 8)

Pressurizer Vapor Space Accident X

(000008AK2.07) Knowledge of the relationship between (APE 8)

PRESSURIZER VAPOR Space Accident and the following systems or components (CFR: 41.8 / 41.10 / 45.3): PZR LCS 3.6 2

3 (000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture - Excessive Heat Transfer X (040) (CE E05) EXCESS STEAM DEMAND (G2.1.9) CONDUCT OF OPERATIONS: Ability to direct licensed personnel activities inside the control room(CFR: 43.1 / 45.5 / 45.12 /

45.13)$

4.5 76 4

(000009) (EPE 9)

Small Break LOCA X

(000009EA1.07) Ability to operate and/or monitor the following as they apply to (EPE 9) SMALL-Break LOCA (CFR: 41.5 / 41.7 /

45.5 to 45.8): CCS 3.5 3

5 (000011) (EPE 11)

Large Break LOCA X

(000011EK2.03) Knowledge of the relationship between (EPE

11) LARGE-Break LOCA and the following systems or components (CFR: 41.8 / 41.10 / 45.3): RCS 4.3 4

6 (000015) (APE 15)

Reactor Coolant Pump Malfunctions X

(000015AK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 15) REACTOR COOLANT Pump Malfunctions (CFR: 41.5 / 41.7 / 45.7 / 45.8): Consequences of an RCP failure$

3.9 5

7 (000022) (APE 22)

Loss of Reactor Coolant Makeup X

(000022AA2.02) Ability to determine and/or interpret the following as they apply to (APE 22) LOSS OF REACTOR Coolant Makeup (CFR: 41.10 / 43.5 / 45.13): Charging pump problems$

3.7 77 8

(000025) (APE 25)

Loss of Residual Heat Removal System X (000025) (APE 25) Loss of Residual Heat Removal System (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) 4.0 78 9

(000026) (APE 26)

Loss of Component Cooling Water X

(000026AK3.08) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 26) LOSS OF Component Cooling Water (CFR: 41.5 / 41.10 / 45.6 / 45.13):

Verifying CCW adequate surge tank level 3.4 6

10 (000027) (APE 27)

Pressurizer Pressure Control System Malfunction X

(000027AA1.01) Ability to operate and/or monitor the following as they apply to (APE 27) PRESSURIZER PRESSURE Control System Malfunction (CFR: 41.5 / 41.7 / 45.5 to 45.8): PZR heaters, sprays, and PORVs 3.8 7

11 (000029) (EPE 29)

Anticipated Transient Without Scram X

(000029EK1.03) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (EPE 29) ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) (CFR: 41.5 / 41.7 / 45.7 / 45.8):

Addition of negative reactivity$

4.2 8

12 (000038) (EPE 38)

Steam Generator Tube Rupture X

(000038EA2.15) Ability to determine and/or interpret the following as they apply to (EPE 38) STEAM GENERATOR Tube Rupture (CFR: 41.10 / 43.5 / 45.13): RCS pressure 4.0 9

Page 3 of 17 13 (000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture - Excessive Heat Transfer X

(CE05EK3.07) Knowledge of the reasons for the following responses and/or actions as they apply to (CE E05) EXCESS STEAM DEMAND (CFR: 41.5 / 41.10 / 45.6 / 45.13): Operating RCPs within operating limits 3.7 10 14 (000054) (APE 54; CE E06) Loss of Main Feedwater X (000054) (APE 54; CE E06) Loss of Main Feedwater (G2.1.20)

CONDUCT OF OPERATIONS: Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)$

4.6 11 15 (000055) (EPE 55)

Station Blackout X

(000055EA2.01) Ability to determine and/or interpret the following as they apply to (EPE 55) Station Blackout (CFR: 41.10

/ 43.5 / 45.13): Existing valve positioning 3.5 12 16 (000056) (APE 56)

Loss of Offsite Power X

(000056AK1.07) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 56) Loss of Offsite Power (CFR: 41.5 /

41.7 / 45.7 / 45.8): Long term core cooling 4.0 13 17 (000056) (APE 56)

Loss of Offsite Power X (000056) (APE 56) Loss of Offsite Power (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) 4.8 79 18 (000057) (APE 57)

Loss of Vital AC Instrument Bus X

(000057AA1.06) Ability to operate and/or monitor the following as they apply to (APE 57) LOSS OF VITAL AC ELECTRICALINSTRUMENT BUS (CFR: 41.5 / 41.7 / 45.5 to 45.8): Manual control of components for which automatic control is lost 3.8 14 19 (000058) (APE 58)

Loss of DC Power X (000058) (APE 58) Loss of DC Power (G2.1.19) CONDUCT OF OPERATIONS: Ability to use available indications to evaluate system or component status (CFR: 41.10 / 45.12) 3.9 15 20 (000058) (APE 58)

Loss of DC Power X

(000058AA2.03 Ability to determine and/or interpret the following as they apply to (APE 58) LOSS OF DC Power (CFR: 41.10 / 43.5 / 45.13): Impact on ability to operate and monitor plant systems 4.0 80 21 (000062) (APE 62)

Loss of Nuclear Service Water X

(000062AK2.09) Knowledge of the relationship between (APE

62) LOSS OF SERVICE WATER and the following systems or components (CFR: 41.8 / 41.10 / 45.3): AFW System$

3.3 16 22 (000065) (APE 65)

Loss of Instrument Air X

(000065AK3.03) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 65) LOSS OF Instrument Air (CFR: 41.5 / 41.10 / 45.6 / 45.13): Knowing effects on plant operation of isolating certain equipment from instrument air 3.6 17 23 (000077) (APE 77)

Generator Voltage and Electric Grid Disturbances X

(000077AA2.04) Ability to determine and/or interpret the following as they apply to (APE 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances (CFR: 41.10 / 43.5 / 45.13):

VAR$

3.6 18 24 (000077) (APE 77)

Generator Voltage and Electric Grid Disturbances X

(000077AA2.05) Ability to determine and/or interpret the following as they apply to (APE 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances (CFR: 41.5 / 43.5 / 45.5 /

45.7 / 45.8): Status of grid$

3.6 81 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4

Page 4 of 17 (BW E04; W E05)

Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 K/A Category Totals:

3 3

6 6 Group Point Total:

24 ES-4.1-PWR Waterford 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#

25 (000001) (APE 1)

Continuous Rod Withdrawal X (000001) (APE 1) Continuous Rod Withdrawal (G2.4.12)

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

4.0 19 26 (000003) (APE 3)

Dropped Control Rod X

(000003AA2.09) Ability to determine and/or interpret the following as they apply to (APE 3) DROPPED Control Rod (CFR:

41.10 / 43.5 / 45.13): Reactor Power$

3.8 20 000005 (APE 5)

Inoperable/Stuck Control Rod / 1 32 000024 (APE 24)

Emergency Boration

/ 1 X

(000024AA2.05) Ability to determine and/or interpret the following as they apply to (024) Emergency Boration (CFR:

43.5 / 45.13): Amount of boric acid to achieve required SDM$

3.9 84 27 (000028) (APE 28)

Pressurizer (PZR)

Level Control Malfunction X

(000028AA2.06) Ability to determine and/or interpret the following as they apply to (APE 28) PRESSURIZER (PZR)

Level Control Malfunction (CFR: 41.10 / 43.5 / 45.13):

Letdown flow 3.6 82 28 (000032) (APE 32)

Loss of Source Range Nuclear Instrumentation X

(000032AK3.02) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 32) LOSS OF SOURCE RANGE Nuclear Instrumentation (CFR: 41.5 / 41.10 /

45.6 / 45.13): Guidance contained in procedures for loss of source range NI$

3.5 21 29 (000033) (APE 33)

Loss of Intermediate Range Nuclear Instrumentation X

(000033AA1.02) Ability to operate and/or monitor the following as they apply to (APE 33) LOSS OF INTERMEDIATE RANGE Nuclear Instrumentation (CFR: 41.5 / 41.7 / 45.5 to 45.8): Level trip bypass$

3.3 22 000036 (APE 36; BW/A08) Fuel-Handling Incidents /

8 30 (000037) (APE 37)

Steam Generator Tube Leak X (000037) (APE 37) Steam Generator Tube Leak (G2.2.22)

EQUIPMENT CONTROL: Knowledge of limiting condition for operation and safety limits (CFR: 41.5 / 43.2 / 45.2)$

4.0 23 000051 (APE 51)

Loss of Condenser Vacuum / 4 000059 (APE 59)

Accidental Liquid Radwaste Release /

9

Page 5 of 17 000060 (APE 60)

Accidental Gaseous Radwaste Release /

9 000061 (APE 61)

Area Radiation Monitoring System Alarms / 7 31 (000067) (APE 67)

Plant Fire On Site X (000067) (APE 67) Plant Fire On Site (G2.1.8) CONDUCT OF OPERATIONS: Ability to coordinate activities outside the control room (CFR: 41.10 /43.1 / 45.5/ 45.12 /45.13)$

4.1 83

Page 6 of 17 X

APE 69; W 000069 (

E14) Loss of Containment Integrity / 5 33 EPE 74; (000074) (

W E06 & E07)

Inadequate Core Cooling Knowledge of the relationship between (EPE (000074EK2.07)

Inadequate Core Cooling and the following systems or

74) components (CFR: 41.8 / 41.10 / 45.3): Main Steam system$

3.4 24 (000068) ( APE 68; BW A06) Control Room Evacuation

( W E01 & E02)

Rediagnosis & SI Termination / 3

( W E13) Steam Generator Overpressure / 4 (000076) ( APE 76)

High Reactor Coolant Activity APE 78*)

000078 (

RCS Leak / 3

( BW A01) Plant Runback / 1

( BW A02 & A03)

Loss of NNI-X/Y/7

( W E15)

Containment Flooding / 5

( W E16) High Containment Radiation /9

( BW A07) Flooding /

8

( BW E03)

Inadequate Subcooling Margin /

4

( BW A04) Turbine Trip / 4 BW A05)

(

Emergency Diesel Actuation / 6

( BW E13 & E14)

EOP Rules and Enclosures

( CE A11**; W E08)

RCS Overcooling -

Pressurized Thermal Shock / 4

( BW E08; W E03)

LOCA Cooldown -

Depressurization / 4 BW E09; CE

(

A13**; W E09 &

E10) Natural Circulation/4

Page 7 of 17 35 (CE A16) Excess RCS Leakage X

(CA16AK1.06) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (CE A16) EXCESS RCS Leakage (CFR: 41.5 / 41.7 / 45.7 / 45.8): Methods for quantifying an RCS leak$

3.8 25 34 (CE E09) Functional Recovery X (CE E09) Functional Recovery (G2.4.22) EMERGENCY PROCEDURES/PLAN: Knowledge of the basis for prioritizing safety functions during abnormal and emergency operations (CFR: 41.7 / 41.10 / 43.5 to 45.12$

4.4 85 36 (CE E13*) Loss of Forced Circulation/LOOP/Blackout X

(CE13EA1.14) Ability to operate and/or monitor the following as they apply to (CE E13) LOSS OF FORCED CIRCULATION AND/OR LOOP AND/OR A BLACKOUT (CFR: 41.5 / 41.7 / 45.5 to 45.8): MFW system 2.7 26 K/A Category Totals:

1 1

1 2

3 4 Group Point Total:

12

Page 8 of 17 ES-4.1-PWR Waterford Plant SystemsTier 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 (003) (SF4P RCP)

REACTOR COOLANT PUMP SYSTEM X

(003A1.05) Ability to predict and/or monitor changes in parameters associated with operation of the (SF4P RCP) REACTOR COOLANT PUMP SYSTEM, including (CFR:

41.5 / 45.5): RCS flow 3.4 27 38 (003) (SF4P RCP)

REACTOR COOLANT PUMP SYSTEM X (003) (SF4P RCP) REACTOR COOLANT PUMP SYSTEM (G2.1.28) CONDUCT OF OPERATIONS: Knowledge of the purpose and function of major system components and controls (CFR: 41.7) 4.1 28 39 (004) (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X

(004A2.22) Ability to (a) predict the impacts of the following on the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL 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): Mismatch of letdown and charging flows$

3.4 29 40 (004) (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X

(004K6.07) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM (CFR: 41.7 /

45.7): Regenerative and nonregenerative heat exchangers 3.4 30 41 (005) (SF4P RHR)

RESIDUAL HEAT REMOVAL SYSTEM X

(005K6.16) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF4P RHR)

RESIDUAL HEAT REMOVAL SYSTEM (CFR: 41.7 / 45.7):

Injection and/or recirculation valves 3.9 31 42 (005) (SF4P RHR)

RESIDUAL HEAT REMOVAL SYSTEM X

(005A2.02) Ability to (a) predict the impacts of the following on the (SF4P RHR) RESIDUAL HEAT REMOVAL 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): Pressure transient protection during cold shutdown 3.9 86

Page 9 of 17 43 (006) (SF2; SF3 ECCS)

EMERGENCY CORE COOLING SYSTEM X

(006A2.02) Ability to (a) predict the impacts of the following on the (SF2; SF3 ECCS) EMERGENCY CORE COOLING 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): Loss of flowpath$

3.9 32 44 (007) (SF5 PRTS)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM X

(007A2.02) Ability to (a) predict the impacts of the following on the (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK 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 pressure in the PRT/quench tank 3.6 33 45 (007) (SF5 PRTS)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM X

(007A3.01)

Ability to monitor automatic features of the (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM, including (CFR: 41.7 / 45.7):

Components that discharge to the PRT/quench tank 3.4 34 46 (008) (SF8 CCW)

COMPONENT COOLING WATER SYSTEM X

(008A4.04) Ability to manually operate and/or monitor the (SF8 CCW) COMPONENT COOLING WATER SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): Startup of a CCW pump when the system is shut down 2.8 35 47 (010) (SF3 PZR PCS)

PRESSURIZER PRESSURE CONTROL SYSTEM X

(010A3.03) Ability to monitor automatic features of the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM, including (CFR: 41.7 / 45.7): PZR heater operation 3.3 36 48 (010) (SF3 PZR PCS)

PRESSURIZER PRESSURE CONTROL SYSTEM X (010) (SF3 PZR PCS)

PRESSURIZER PRESSURE CONTROL SYSTEM (G2.4.31)

EMERGENCY PROCEDURES/PLAN: Knowledge of annunciator alarms, indications, or response procedures (CFR: 41.10 / 45.3) 4.1 87 49 (012) (SF7 RPS)

REACTOR PROTECTION SYSTEM X

(012K2.01) Knowledge of electrical power supplies to the following (CFR:

41.7): (SF7 RPS) REACTOR PROTECTION SYSTEM RPS channels, components, and interconnections 4.0 37

Page 10 of 17 50 (012) (SF7 RPS)

REACTOR PROTECTION SYSTEM X

(012A2.01) Ability to (a) predict the impacts of the following on the (SF7 RPS) REACTOR PROTECTION 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): Faulty bistable operation$

3.6 88 51 (013) (SF2 ESFAS)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X

(013A1.16) Ability to predict and/or monitor changes in parameters associated with operation of the (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, including (CFR: 41.5 / 45.5): Auxiliary building HVAC system status 2.9 38 52 (013) (SF2 ESFAS)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X

(013K4.06) Knowledge of (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):

Recirculation actuation/reset 4.1 39 53 (022) (SF5 CCS)

CONTAINMENT COOLING SYSTEM X

(022A1.01) Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 CCS) CONTAINMENT COOLING SYSTEM, including (CFR: 41.5 /

45.5): Containment temperature 3.8 40 025 (SF5 ICE) ICE CONDENSER SYSTEM 54 (026) (SF5 CSS)

CONTAINMENT SPRAY SYSTEM X

(026K2.01) Knowledge of electrical power supplies to the following (CFR:

41.7): (SF5 CSS) CONTAINMENT SPRAY SYSTEM Containment spray pumps 3.9 41 55 (039) (SF4S MSS)

MAIN AND REHEAT STEAM SYSTEM X (039) (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM (G2.1.23) CONDUCT OF OPERATIONS: Ability to perform general and/or normal operating procedures during any plant condition$

4.3 42 053 (SF1; SF4P ICS*)

INTEGRATED 56 CONTROL (059)

(SF4S MFW)

MAIN FEEDWATER SYSTEM X

(059K1.14) Knowledge of the physical connections and/or cause and effect relationships between the (SF4S MFW) MAIN FEEDWATER SYSTEM and the following systems (CFR: 41.2 to 41.9 / 45.7 to 45.8):

ESFAS 3.8 43

Page 11 of 17 57 (059) (SF4S MFW)

MAIN FEEDWATER SYSTEM X

(059K3.05) Knowledge of the effect that a loss or malfunction of the (SF4S MFW) MAIN FEEDWATER SYSTEM will have on the following systems or system parameters (CFR:

41.7 / 45.4): Extraction steam 2.7 44 58 (061) (SF4S AFW)

AUXILIARY /

EMERGENCY FEEDWATER SYSTEM X

(061K4.11) Knowledge of (SF4S AFW) AUXILIARY/EMERGENCY FEEDWATER SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):

Automatic level control$

3.6 45 59 (062) (SF6 ED AC)

AC ELECTRICAL DISTRIBUTION SYSTEM X

(062K3.02) Knowledge of the effect that a loss or malfunction of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4): EDG 4.4 46 60 (063) (SF6 ED DC)

DC ELECTRICAL DISTRIBUTION SYSTEM X

(063A4.03) Ability to manually operate and/or monitor the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): Battery discharge rate 3.5 47 61 (063) (SF6 ED DC)

DC ELECTRICAL DISTRIBUTION SYSTEM X (063) (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM (G2.1.32) CONDUCT OF OPERATIONS: Ability to explain and apply system precautions, limitations, notes, or cautions (CFR: 41.10 / 43.2 / 45.12) 4.0 89 62 (064) (SF6 EDG)

EMERGENCY DIESEL GENERATOR SYSTEM X

(064K5.07) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (CFR: 41.5 /

45.3): Loading the EDG$

3.7 48 63 (064) (SF6 EDG)

EMERGENCY DIESEL GENERATOR SYSTEM X

(064A2.24) Ability to (a) predict the impacts of the following on the (SF6 EDG) EMERGENCY DIESEL GENERATOR 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): Fuel oil storage system failure 3.7 90

Page 12 of 17 64 (073) (SF7 PRM)

PROCESS RADIATION MONITORING SYSTEM X

(073K1.05) Knowledge of the physical connections and/or cause and effect relationships between the (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM and the following systems (CFR: 41.2 to 41.9

/ 45.7 to 45.8): CCWS$

3.1 49 65 (076) (SF4S SW)

SERVICE WATER SYSTEM X

(076K5.05) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF4S SW) SERVICE WATER SYSTEM (CFR: 41.5 / 45.3): Radiation alarms on SWS 3.1 50 66 (078) (SF8 IAS)

INSTRUMENT AIR SYSTEM X

(078A3.03) Ability to monitor automatic features of the (SF8 IAS)

INSTRUMENT AIR SYSTEM, including (CFR: 41.7 / 45.7): Isolation of instrument air to containment$

3.3 51 67 (078) (SF8 IAS)

INSTRUMENT AIR SYSTEM X

(078K6.06) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 IAS)

INSTRUMENT AIR SYSTEM (CFR:

41.7 / 45.7): Cross-tie valve 3.0 52 68 (103) (SF5 CNT)

CONTAINMENT SYSTEM X (103) (SF5 CNT) CONTAINMENT SYSTEM (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) 4.4 53 69 (103) (SF5 CNT)

CONTAINMENT SYSTEM X

(103K3.04) Knowledge of the effect that a loss or malfunction of the (SF5 CNT) CONTAINMENT SYSTEM will have on the following systems or system parameters (CFR: 41.7 /

45.4): Shield building vent system 3.0 54 K/A Category Totals:

2 2

3 2

2 3

3 6

3 2

5 Group Point Total:

33 ES-4.1-PWR Waterford Plant SystemsTier 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#

70 (001) (SF1 CRDS)

CONTROL ROD DRIVE SYSTEM X

(001A4.01) Ability to manually operate and/or monitor the (SF1 CRDS) CONTROL ROD DRIVE SYSTEM in the control room (CFR:

41.7 / 45.5 to 45.8): CRDM cooling 2.9 55

Page 13 of 17 71 (002) (SF2; SF4P RCS) REACTOR COOLANT SYSTEM 72 (011) (SF2 PZR LCS)

PRESSURIZER LEVEL CONTROL SYSTEM X

(011A2.01) Ability to (a) predict the impacts of the following on the (SF2 PZR LCS) PRESSURIZER LEVEL CONTROL 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): Excessive Letdown$

3.5 91 73 (014) (SF1 RPI)

ROD POSITION INDICATION SYSTEM X (014) (SF1 RPI) ROD POSITION INDICATION SYSTEM (G2.4.4)

EMERGENCY PROCEDURES/PLAN: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures$

(CFR: 41.10 / 43.2 / 45.6) 4.7 92 015 (SF7 NI)

NUCLEAR INSTRUMENTATIO N SYSTEM 74 (016) (SF7 NNI)

NONNUCLEAR INSTRUMENTATIO N SYSTEM X

(016A3.01) Ability to monitor automatic features of the (SF7 NNI)

NONNUCLEAR INSTRUMENTATION SYSTEM, including (CFR: 41.7 / 45.7):

Automatic selection of NNI system inputs to control systems 3.3 57 017 (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM 027 (SF5 CIRS)

CONTAINMENT IODINE REMOVAL SYSTEM 75 (028) (SF5 HRPS)

HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM X

(028K3.01) Knowledge of the effect that a loss or malfunction of the (SF5 HRPS) HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM will have on the following systems or system parameters (CFR: 41.7 /

45.4): Hydrogen concentration in containment 3.1 58

Page 14 of 17 76 (029) (SF8 CPS)

CONTAINMENT PURGE SYSTEM X

(029A2.06) Ability to (a) predict the impacts of the following on the (SF8 CPS) CONTAINMENT PURGE 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): CPS component malfunction$

3.0 93 033 (SF8 SFPCS)

SPENT FUEL POOL COOLING SYSTEM X

(033K5.06) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF8)

SPENT FUEL POOL COOLING SYSTEM (CFR: 41.5 / 45.7):

Shielding (water level)$

3.7 56 77 (034) (SF8 FHS)

FUEL HANDLING EQUIPMENT SYSTEM X

(034A2.07) Ability to (a) predict the impacts of the following on the (SF8 FHS) FUEL HANDLING EQUIPMENT 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): Loss of refueling cavity or Spent Fuel pool level.$

3.7 59 035 (SF4P SG)

STEAM GENERATOR SYSTEM 041 (SF4S SDS)

STEAM DUMP /

TURBINE BYPASS CONTROL SYSTEM 045 (SF4S MTG)

MAIN TURBINE GENERATOR SYSTEM 050 (SF9 CRV*)

CONTROL ROOM VENTILATION 78 (055) (SF4S CARS)

CONDENSER AIR REMOVAL SYSTEM X

(055K1.02) Knowledge of the physical connections and/or cause and effect relationships between the (SF4S CARS) CONDENSER AIR REMOVAL SYSTEM and the following systems (CFR: 41.2 to 41.9

/ 45.7 to 45.8): Main condenser 3.5 60 79 (056) (SF4S CDS)

CONDENSATE SYSTEM X

(056K4.14) Knowledge of (SF4S CDS) CONDENSATE SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):

MFW pump NPSH$

3.6 61

Page 15 of 17 80 (068) (SF9 LRS)

LIQUID RADWASTE SYSTEM X (068) (SF9 LRS) LIQUID RADWASTE SYSTEM (G2.3.11) Radiation Control: Ability to control radiation releases (41.11 /43.4

/45.10)$

3.8 62 81 (071) (SF9 WGS)

WASTE GAS DISPOSAL SYSTEM X

(071A1.09) Ability to predict and/or monitor changes in parameters associated with operation of the (SF9 WGS) WASTE GAS DISPOSAL SYSTEM, including (CFR: 41.5 /

45.5): Waste gas tank discharge radiation levels 3.2 63 072 (SF7 ARM)

AREA RADIATION MONITORING SYSTEM 075 (SF8 CW)

CIRCULATING WATER SYSTEM 079 (SF8 SAS**)

STATION AIR SYSTEM 086 (SF8 FPS)

FIRE PROTECTION SYSTEM K/A Category Totals:

1 0

1 1

1 0

1 3

1 1

2 Group Point Total:

12

Page 16 of 17 Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Waterford)

Facility: Waterford Date of Exam: 8/30/2023 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)

Category K/A #

RO SRO-Only Topic Item #

IR Q#

1.

Conduct of Operations G2.1.17 (G2.1.17) CONDUCT OF OPERATIONS: Ability to make accurate, clear, and concise verbal reports (CFR: 41.10 /

45.12 / 45.13) 82 4.0 94 G2.1.31 (G2.1.31) CONDUCT OF OPERATIONS: Ability to locate control room switches, controls, and indications and to determine whether they correctly reflect the desired plant lineup (CFR: 41.10 / 45.12) 83 4.3 95 G2.1.47 (G2.1.47) CONDUCT OF OPERATIONS: Ability to direct nonlicensed personnel activities inside the control room (CFR:

41.10 / 43.5 / 45.5 / 45.12 / 45.13) 84 3.2 65 G2.1.8 (G2.1.8) CONDUCT OF OPERATIONS: Ability to coordinate personnel activities outside the control room (CFR: 41.10 / 43.1

/ 45.5 / 45.12 / 45.13) 85 3.4 64 Subtotal N/A 2

N/A 2

2.

Equipment Control G2.2.12 (G2.2.12) EQUIPMENT CONTROL: Knowledge of surveillance procedures (CFR: 41.10 / 43.2 / 45.13) 86 3.7 66 G2.2.13 (G2.2.13) EQUIPMENT CONTROL: Knowledge of tagging and clearance procedures (CFR: 41.10 / 43.1 / 45.13) 87 4.1 67 G2.2.25 (G2.2.25) EQUIPMENT CONTROL: Knowledge of the bases in TS for limiting conditions for operation and safety limits (CFR: 43.2)$

88 4.2 96 G2.2.37 (G2.2.37) EQUIPMENT CONTROL: Ability to determine operability or availability of safety-related equipment(CFR:

43.2 / 43.5 / 45.12)$

89 4.6 97 Subtotal N/A 2

N/A 2

3.

Radiation Control G2.3.5 (G2.3.5) RADIATION CONTROL: Ability to use RMSs, such as fixed radiation monitors and alarms or personnel monitoring equipment (CFR: 41.11 / 41.12 / 43.4 / 45.9) 90 2.9 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 to 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 G2.4.21 (G2.4.21) EMERGENCY PROCEDURES/PLAN: Knowledge of the parameters and logic used to assess the status of emergency operating procedures critical safety functions or shutdown critical safety functions (CFR: 41.7 / 43.5 / 45.12) 92 4

69

Page 17 of 17 G2.4.29 (G2.4.29) EMERGENCY PROCEDURES/PLAN: Knowledge of the emergency plan implementing procedures (CFR:

41.10 / 43.5 / 45.11) 93 4.4 99 G2.4.40 (G2.4.40) EMERGENCY PROCEDURES/PLAN: Knowledge of SRO responsibilities in emergency plan implementing procedures (SRO Only) (CFR: 43.5 / 45.11) 94 4.5 100 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 (Waterford)

Facility: Waterford Date of Exam: 8/30/2023 Theory (Tier 4) (RO)

Category K/A #

RO Topic Item #

IR Q#

Reactor Theory 192006 (192006K1.04) FISSION PRODUCT POISONS (CFR: 41.1):

Describe the removal of xenon 135 95 2.8 70 192007 (192007K1.04) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1): Describe how and why boron concentration changes over core life 96 3.4 71 192008 (192008K1.13) REACTOR OPERATIONAL PHYSICS (CFR:

41.1): (INTERMEDIATE RANGE OPERATION) Discuss the concept of the POAH and its impact on reactor power 97 3.6 72 Subtotal N/A 3

Thermodynamics 193003 (193003K1.24) STEAM (CFR: 41.14): Explain the usefulness of steam tables to the control room operator 98 3.1 73 193004 (193004K1.15) THERMODYNAMIC PROCESS (CFR: 41.14):

(THROTTLING AND THE THROTTLING PROCESS)

Determine the exit conditions for a throttling process based on the use of steam and/or water 99 2.8 74 193009 (193009K1.01) CORE THERMAL LIMITS (CFR: 41.14):

Explain radial peaking factor 100 2.8 75 Subtotal N/A 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 Tier 1 Group 1 Question

5 015 AK1.02 015 AK1.01 rejected. The only question that could be written regarding natural circulation criteria was too close to the question written for RO13. One of these two K/As had to be rejected. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

8 029 EK1.03 029 EK1.01 rejected. No guidance found on reactor nucleonic and thermo hydraulic behavior during an ATWS that could be developed into an RO question that did not resemble a theory question. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

11 054 G2.1.20 An RO question involving the criteria for plant announcements that involve a loss of Main Feedwater could not be developed with existing W3 procedures. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

16 062 AK2.09 062 AK2.08 rejected. Three different K/As in this outline involve the relationship between service water and radiation monitoring. They are questions 16, 49 and 50. Question on this subject was written for question 50 and the K/As are rejected for questions 16 and 49.

This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

18 077 A2.04 077 A2.03 rejected. There is no guidance in any of the W3 procedures on the effect of an Electrical Grid Disturbance and Generator Current. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

19 001 G2.4.12 001 G2.4.18 rejected. Continuous rod withdrawal is not discussed in the W3 EOPs and W3 abnormal operating procedures do not have basis documents. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

20 003 A2.09 003 A2.08 rejected. W3 abnormal operating procedures for a dropped rod do not discuss incore temperature monitoring. All actions are based on cold leg temperatures. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

21 032 AK3.02 032 AK3.01 rejected. All TS actions and procedure guidance for the startup channels at W3 pertain to core alterations. The startup channels de-energize early in the startup (5.3x10-6 power). This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

22 033 A1.02 033 A1.03 rejected. There is no guidance in any W3 procedure for manual restoration of power to the intermediate range nuclear instrumentation. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

23 037 G2.2.22 037 2.2.35 rejected. Could not develop a question that would link a Steam Generator Tube leak with the ability to determine TS mode for operation This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

24 074 EK2.07 074 EK2.03 rejected. The discussion in W3 Tech Spec basis for inadequate core cooling involves HPSI flow and ADVs. (not EFW flow). This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

25 CE A16 AK1.06 CE A16 AK1.05 rejected. The guidance for detecting and isolating an RCS leak inside containment only involves taking temperatures of inlet piping to the reactor drain tank. An RO question could not be developed from this. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 1 Question

29 004 A2.22 004 A2.23 rejected. The only guidance for high filter DP is in RCS watch logs. A reading is taken on this D/P and the RCA watch must inform the CRS if it is too high. An RO question could not be developed on this information.

Tier 2 Group 1 Question

32 006 A2.01 006 A2.02 rejected. There is no guidance in the W3 procedures for a high bearing temperature on ECCS pumps. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 1 Question

42 039 G2.1.23 039 191008K1.09 rejected. This is a theory question K/A. An RO question could not be developed on losing control power to main or reheat steam components. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 1 Question

45 061 K4.11 061 K4.08 rejected. Not enough guidance or information in W3 procedures on EFW pump recirc to develop an RO question. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 1 Question

48 064 K5.07 064 K5.13 rejected. Not enough guidance on the consequences of a high VAR on EDG integrity to develop an RO question. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 1 Question

49 073 K1.05 073 K1.08 rejected. Three different K/As in this outline involve the relationship between service water and radiation monitoring. They are questions 16, 49 and 50. Question on this subject was written for question 50 and the K/As are rejected for questions 16 and 49.

This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 1 Question

51 078 A3.03 078 A3.04 rejected. Instrument air is always isolated from station air at W3. This made it impossible to write a question on isolating instrument air from station air. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 2 Question

56 002 K5.05 rejected. Could not develop an RO level question on rise in reactor drain tank pressure during water inventory operations with the RCS system. This is not an evolution that is performed at W3.

Tier 2 Group 2 Question

59 034 A2.07 034 A2.05 rejected. There is no impact on Fuel Handling equipment due to high radiation at W3, other than leaving the area. No question could be written for this K/A. This change does not affect any of the numbers on the first page of the outline.

Tier Group 2 Question

61 056 K4.14 056 K4.01 rejected. There are no design features or interlocks that provide for feedwater heating at W3. No question could be written for this K/A. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 2 Question

62 068 G2.3.11 068 191006K1.09 rejected. This is a theory question K/A. An RO question could not be developed on the effects of water hammer in the heat exchangers of the LWM system. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

76 CE E05 G2.1.9 008 2.1.37 rejected. Could not develop and SRO question that related a Pressurizer Vapor Accident with reactivity management that seemed valid. W3 does not have specific guidance for vapor space accident. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

77 022 AA2.09 022 AA2.06 rejected. No guidance in W3 procedures for monitoring charging pump ammeters. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

81 077 AA2.05 077 AA2.11 rejected. No guidance in W3 procedures for interpret excessive step up transformer neutral DC ground current. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

83 067 G2.1.8 067 G2.1.44 rejected. This K/A is N/A for an SRO. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 1 Question

84 024 A2.05 068 AA2.01 rejected. Question 83 is a Control Room Evacuation question. This would have made back to back Control Room Evacuation questions. Also, could not write a SRO level question pertaining to CRE and steam generator level. This change does not affect any of the numbers on the first page of the outline.

Tier1 Group 1 Question

85 CE09 G2.4.22 076 G2.4.35 rejected. Could not write an SRO level question on non-licensed operator duties during High RCS activity. This change does not affect any of the numbers on the first page of the outline.

Tier 1 Group 2 Question

88 012 A2.01 012 A2.04 rejected. Could not develop and SRO question on erratic power supply operation to the RPS due to limited guidance. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 2 Question

91 011 A2.01 011 A2.08 rejected. No guidance at W3 for loss of level compensation to the pressurizer level control system. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 2 Question

92 014 G2.4.4 014 G2.4.49 rejected. Could not develop an SRO question that involved immediate actions as required by this K/A. Additionally, there are no immediate actions at W3 for the Rod Position indicating system. This change does not affect any of the numbers on the first page of the outline.

Tier 2 Group 2 Question

93 029 A2.06 029 A2.02 rejected. An SRO question could not be developed for the effects of adverse environmental conditions on containment purge. It would involve giving the SRO a flowchart but would then be considered a direct lookup. This change does not affect any of the numbers on the first page of the outline.

Tier 3 Question

96 G2.2.25 G2.2.2 rejected. Could not write an SRO question on manipulating the console controls. It is also hard to keep this K/A in the generic category. This change does not affect any of the numbers on the first page of the outline.

Tier 3 Question #

97 G2.2.37 2.2.44 rejected. Could not write an SRO question on interpreting control indications to verify the status and operation of a system while keeping the question generic. This change does not affect any of the numbers on the first page of the outline.

Form 3.2-1 Administrative Topics Outline Facility: ___ Waterford 3___________________________

Date of Examination: 8/21/2023 Examination Level:

RO SRO Operating Test Number: ____1____

Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

A1 Conduct of Operations Complete calculations to determine available Feedwater and maximum time remaining to Shutdown Cooling in accordance with OP-902-009, Attachment 2-G.

2.1.25 Ability to interpret reference materials, such as graphs, curves, and tables RO-3.9 R,M(2018)

A2 Conduct of Operations Determine Acceptability of Containment Temperature in accordance with OP-903-001, Technical Specifications Surveillance Logs 2.1.19 Ability to use available indications to evaluate system or component status RO-3.9 R,D(2015)

A3 Equipment Control Calculate Keff in accordance with OP-903-090, Shutdown Margin, Section 7.5, Keff Calculation.

2.2.12 Knowledge of surveillance procedures RO-3 R,M(2017)

A4 Radiation Control Evaluate Meteorological conditions for gaseous release from the Gaseous Waste Management System in accordance with OP-007-003, Gaseous Waste Management.

2.3.11 Ability to control radiation releases RO-3.8 R,D(2017)

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: ___ Waterford 3___________________________

Date of Examination: 8/21/2023 Examination Level:

RO SRO Operating Test Number: ____1____

Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

A5 Conduct of Operations Review and approve a completed calculation for determining the amount of pure water that may be added to the Refuel Cavity without dilution to below shutdown margin requirements in accordance with OP-010-006, Outage Operations, section 9.24, Refueling Cavity Boron Concentration.

2.1.23, Ability to perform specific system and integrated plant procedures during any plant condition SRO-4.4 R,N A6 Conduct of Operations Perform SM/CRS review of OP-901-501, PMC or Core Operating Limit Supervisory System Malfunction, Attachments 1, 2 and 3 following a PMC failure.

2.1.20 Ability to interpret and execute procedure steps. SRO-4.6 P,R,D(2020)

A7 Equipment Control Review Keff Calculation in accordance with OP-903-090, Shutdown Margin, Section 7.5, Keff Calculation. Applicant determines Keff does not meet Tech Spec 3.1.2.9 requirements and identifies required corrective actions.

2.2.12, Knowledge of Surveillance Procedures SRO-4.1 R,M A8 Radiation Control Authorize Emergency Exposure as the Emergency Director in accordance with EP-002-030, Emergency Radiation Exposure Guidelines and Controls.

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 to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits(SRO Only) SRO-3.8 R,M A9 Emergency Plan Determine the appropriate emergency action level in accordance with EP-001-001, Recognition and Classification of Emergency Conditions(SRO Only) SRO-4.6 2.4.41, Knowledge of the emergency action level thresholds and classifications 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: _Waterford 3_________________ Date of Examination: __8/21/2023_

Operating Test Number: ____1______

Exam Level: X RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems S1 APE 001 Continuous Rod Withdrawal Operator will withdraw CEAs to support plant startup per OP-010-003, Plant Startup.

Alt. Path: During CEA withdrawal, the selected CEA group will continue to withdraw after the CEA Shim switch is released. The operator is required to manually trip the reactor per OP-901-102, CEA or CEDMCS Malfunction.

AA2.05 Uncontrolled rod withdrawal RO-4.2 SRO-4.1 N,A,E,S 1

S2 006 ECCS Emergency Core Cooling System Adjust HPSI Flow to Maintain Pressurizer Level after HPSI Throttle Criteria Met per OP-902-004, Excess Steam Demand Recovery A1.18 PZR level and pressure RO/SRO-3.8 N,EN,L,S 2

S3 010 PZR RCS Pressurizer Pressure Control System Operate Pressurizer Vents to lower RCS Pressure to maintain P-T Limits per Appendix 38, Pressurizer Vent Operations A2.04 Loss of charging flow to auxiliary spray valves RO-3.4 SRO-3.1 E,L,N,S 3

S4 003 Reactor Coolant Pump System (2017 Exam)

Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation. (2014 NRC Exam)

Alt. Path: Reactor Coolant pump reverse rotates requiring stopping of remaining Reactor Coolant Pumps. (W3 OE)

A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP RO - 3.5 SRO - 3.8 A,D,L,S 4P S5 059 MFW Main Feedwater System Emergency Feedwater Actuation Signal reset in accordance with OP-902-006, Loss of Feedwater, step 29.b.2) and OP-902-009, Appendix 5C.

A2.01 Actuation of AFW system RO-4.0 SRO-4.1 N,EN,S 4S S6 022 CCS Containment Cooling System Change running Containment Cooling Fan configuration per OP-008-003, Containment Cooling System, sections 6.1 and 7.1.

A4.01 Ability to manually operate and/or monitor in the control room: CCS fans RO/SRO-3.7 N,S 5

S7 062 ED AC AC Electrical Distribution System Transfer 3A from EDG A to 2A in accordance with OP-902-009, Standard Appendices, Attachment 12C A4.07 Synchronizing and paralleling of different AC supplies RO/SRO-3.7 N,E,L,S 6

S8 068 Liquid Radwaste System Discharging a Boric Acid Condensate Tank to Circulating Water in accordance with OP-007-001, Boron Management Alt. Path: After flow is established, the flow controller will fail and flow will exceed the release permit allowed value.

A4.03 Stoppage of release if limits exceeded RO/SRO-3.5 M,A,S 9

In-Plant Systems P1 013 Engineered Safety Features Actuation System (ESFAS) (2020 Exam)

Actuate a Recirculation Actuation Signal (RAS) manually in accordance with OP-902-009 Appendix 34, RAS Manual Actuation.

Fault: The RAS will not actuate using the manual pushbuttons and will actuate by opening the breakers.

A4.03 ESFAS Initiation RO/SRO-4.4 A,D,EN,P 2

P2 045 MT/G Main Turbine Generator System Transfer Operating Stator Cooling Water Pump in accordance with OP-003-022, Stator Cooling Water, section 6.2.

Fault: The stopped stator cooling water pump will experience reverse rotation requiring the pump to be restarted to prevent loss of stator cooling water flow to the main generator.

A2.02 Loss of Stator Cooling Water RO - 3.4 SRO - 3.6 A,N 4S P3 064 Electrical Diesel Generators (2017 Exam)

Reset EDG A following an overspeed trip with a LOOP in accordance with OP-009-002, Emergency Diesel Generator, section 8.8.

EPE 055 EA1.06 Restoration of power with one EDG RO/SRO-4.3 D,E,L,R 6

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: _Waterford 3_________________ Date of Examination: __8/21/2023_

Operating Test Number: ____1______

Exam Level:

RO X SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems S1 APE 001 Continuous Rod Withdrawal Operator will withdraw CEAs to support plant startup per OP-010-003, Plant Startup.

Alt. Path: During CEA withdrawal, the selected CEA group will continue to withdraw after the CEA Shim switch is released. The operator is required to manually trip the reactor per OP-901-102, CEA or CEDMCS Malfunction.

AA2.05 Uncontrolled rod withdrawal RO-4.2 SRO-4.1 N,A,E,S 1

S2 006 ECCS Emergency Core Cooling System Adjust HPSI Flow to Maintain Pressurizer Level after HPSI Throttle Criteria Met per OP-902-004, Excess Steam Demand Recovery.

A1.18 PZR level and pressure RO/SRO-3.8 N,EN,L,S 2