ML22147A184

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04 Draft Outlines
ML22147A184
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 04/13/2022
From: Heather Gepford
Operations Branch IV
To:
Entergy Operations
References
Download: ML22147A184 (39)
v • d • e


Text

Page 1 of 16 Facility:

ANO 1 K/A Catalog Rev. 2 Rev. 0 Date of Exam: 04/05/2022 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

2 3

3 4

3 3

18 3

3 6

2 2

2 1

1 2

1 9

2 2

4 Tier Totals 4

5 4

5 5

4 27 5

5 10

2.

Plant Systems 1

3 2

3 4

2 2

2 3

2 2

3 28 3

2 5

2 0

0 2

1 1

0 1

3 0

1 1

10 0

1 2

3 Tier Totals 3

2 5

5 3

2 3

6 2

3 4

38 4

4 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

2 3

2 3

2 2

1 2

Note: 1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

2.

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4.

Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

Page 2 of 16 ES-401 PWR Examination Outline (ANO 1)

Form ES-401-2 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 000007 (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery / 1 X

(000007EA2.04) Ability to determine and interpret the following as they apply to (EPE 7) REACTOR TRIP, STABILIZATION, RECOVERY / 1 (CFR: 43.5 / 45.13): If reactor should have tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP 4.6 76 1316 New 2

000008 (APE 8)

Pressurizer Vapor Space Accident / 3 X

(000008AK2.03) Knowledge of the interrelations between the (APE 8) PRESSURIZER VAPOR SPACE ACCIDENT / 3 and the following (CFR 41.7 / 45.7): Controllers and positioners 2.5 1

1317 New 3

000009 (EPE 9)

Small Break LOCA /

3 X

(000009EK1.01) Knowledge of the operational implications of the following concepts as they apply to (EPE 9) SMALL BREAK LOCA / 3 (CFR: 41.8 / 41.10 / 45.3): Natural circulation and cooling, including reflux boiling 4.2 2

1333 New 4

000009 (EPE 9)

Small Break LOCA

/ 3 X (000009 (EPE 9) Small Break LOCA / 3) (G2.4.30)

Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 / 43.5 / 45.11) 4.1 77 1331 New 5

000011 (EPE 11)

Large Break LOCA /

3 X

(000011EK2.02) Knowledge of the interrelations between (EPE

11) LARGE BREAK LOCA / 3 and the following (CFR: 41.7 /

45.7): Pumps 2.6 3

491 Bank 6

000015 (APE 15)

Reactor Coolant Pump Malfunctions /

4 X

(000015AA2.11) Ability to determine and interpret the following as they apply to the (APE 15) REACTOR COOLANT PUMP MALFUNCTIONS / 4 (CFR: 43.5 / 45.13): When to jog RCPs during ICC (000015AA2.10) Ability to determine and interpret the following as they apply to the (APE 15) REACTOR COOLANT PUMP MALFUNCTIONS / 4 (CFR: 43.5 / 45.13): When to secure RCPs on loss of cooling or seal injection 3.4 3.7 REJECT 4

1373 New 7

000022 (APE 22)

Loss of Reactor Coolant Makeup / 2 X

(000022AK1.04) Knowledge of the operational implications of the following concepts as they apply to (APE 22) LOSS OF REACTOR COOLANT MAKEUP / 2 (CFR 41.8 / 41.10 / 45.3):

Reason for changing from manual to automatic control of charging flow valve controller 2.9 5

1338 Bank 8

000025 (APE 25)

Loss of Residual Heat Removal System / 4 X (000025 (APE 25) Loss of Residual Heat Removal System /

4) (G2.2.22) Knowledge of limiting conditions for operations and safety limits. (CFR: 43.2 / 45.2) 4.0 6

1340 New 9

000026 (APE 26)

Loss of Component Cooling Water / 8 X

(000026AA2.01) Ability to determine and interpret the following as they apply to the (APE 26) LOSS OF COMPONENT COOLING WATER / 8 (CFR: 43.5 / 45.13): Location of a leak in the CCWS 2.9 7

8 Bank 10 000027 (APE 27)

Pressurizer Pressure Control System Malfunction

/ 3 X

(000027AK3.01) Knowledge of the reasons for the following responses as they apply to the (APE 27) PRESSURIZER PRESSURE CONTROL SYSTEM MALFUNCTION / 3 (CFR 41.5,41.10 / 45.6 / 45.13): Isolation of PZR spray following loss of PZR heaters (000027AK3.03) Knowledge of the reasons for the following responses as they apply to the (APE 27) PRESSURIZER PRESSURE CONTROL SYSTEM MALFUNCTION / 3 (CFR 41.5,41.10 / 45.6 / 45.13): Actions contained in EOP for PZR PCS malfunction 3.5 3.7 REJECT 8

1374 New

Page 3 of 16 11 000029 (EPE 29)

Anticipated Transient Without Scram / 1 X

(000029EK2.06) Knowledge of the interrelations between (EPE

29) ANTICIPATED TRANSIENT WITHOUT SCRAM / 1 and the following (CFR: 41.7 / 45.7): Breakers, relays, and disconnects 2.9 9

509 Bank 12 000038 (EPE 38)

Steam Generator Tube Rupture / 3 X

(000038EK3.01) Knowledge of the reasons for the following responses as they apply to (EPE 38) STEAM GENERATOR TUBE RUPTURE / 3 (CFR: 41.5 / 41.10 / 45.6 / 45.13):

Equalizing pressure on primary and secondary sides of ruptured S/G 4.1 10 37 Bank 13 000040 (APE 40; BW E05; CE E05; W E12) Steam Line Rupture -

Excessive Heat Transfer / 4 X

(000040AA1.01) Ability to operate and / or monitor the following as they apply to (APE 040) the Steam Line Rupture (CFR 41.7 / 45.5 / 45.6): Manual and automatic ESFAS initiation 4.6 11 1341 Mod 14 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X

(000054AA2.03) Ability to determine and interpret the following as they apply to the (APE 54) LOSS OF MAIN FEEDWATER /4 (CFR: 43.5 / 45.13): Conditions and reasons for AFW pump startup 4.1 12 1342 New 15 000055 (EPE 55)

Station Blackout / 6 X

(000055EA1.01) Ability to operate and / or monitor the following as they apply to (EPE 55) STATION BLACKOUT / 6 (CFR:

41.7 / 45.5 / 45.6): In-core thermocouple temperatures 3.7 13 1343 New 16 000055 (EPE 55)

Station Blackout /

6 X (000055 (EPE 55) Station Blackout / 6) (G2.4.20) Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13) 4.3 78 1319 Bank 17 000056 (APE 56)

Loss of Offsite Power / 6 X (000056 (APE 56) Loss of Offsite Power / 6) (G2.1.32) Ability to explain and apply system limits and precautions. (CFR: 41.10 /

43.2 / 45.12) 3.8 14 1344 New 18 000056 (APE 56)

Loss of Offsite Power / 6 X

(000056AA2.19) Ability to determine and interpret the following as they apply to the (APE 56) LOSS OF OFFSITE POWER / 6 (CFR: 43.5 / 45.13): T-cold and T-hot indicators (wide range) 4.0 79 1320 New 19 000057 (APE 57)

Loss of Vital AC Instrument Bus / 6 X (000057 (APE 57) Loss of Vital AC Instrument Bus / 6)

(G2.4.18) Knowledge of the specific bases for EOPs. (CFR:

41.10 / 43.1 / 45.13)

(000057 (APE 57) Loss of Vital AC Instrument Bus / 6)

(G2.4.6) Knowledge of symptom based EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13) 4.0 4.7 REJECT 80 TBD 20 000058 (APE 58)

Loss of DC Power /

6 X (000058 (APE 58) Loss of DC Power / 6) (G2.1.20) Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 /

45.12) 4.6 15 41 Bank 21 000062 (APE 62)

Loss of Nuclear Service Water / 4 X

(000062AA1.01) Ability to operate and / or monitor the following as they apply to the (APE 62) LOSS OF NUCLEAR SERVICE WATER / 4 (CFR 41.7 / 45.5 / 45.6): Nuclear service water temperature indications 3.1 16 625 Mod 22 000065 (APE 65)

Loss of Instrument Air / 8 X

(000065AA2.05) Ability to determine and interpret the following as they apply to the (APE 65) LOSS OF INSTRUMENT AIR / 8 (CFR: 43.5 / 45.13): When to commence plant shutdown if instrument air pressure is decreasing 4.1 81 1114 Mod 23 000077 (APE 77)

Generator Voltage and Electric Grid Disturbances / 6 X

(000077AA1.02) Ability to operate and / or monitor the following as they apply to the (APE 77) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES / 6 (CFR 41.7 / 45.5 /

45.6): Turbine / generator controls.

3.8 17 891 Bank

Page 4 of 16 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 24 (BW E04; W E05)

Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X

(BE04EK3.1) Knowledge of the reasons for the following responses as they apply to (BW E04) INADEQUATE HEAT TRANSFER / 4 (CFR: 41.5 / 41.10 / 45.6 / 45.13): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

3.5 18 556 Bank K/A Category Totals:

2 3

3 4

6 6

Group Point Total:

24

Page 5 of 16 ES-401 PWR Examination Outline (ANO 1)

Form ES-401-2 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 000003 (APE 3)

Dropped Control Rod / 1 X

(000003AK3.09) Knowledge of the reasons for the following responses as they apply to the (APE 3) DROPPED CONTROL ROD / 1 (CFR 41.5,41.10 / 45.6 / 45.13): Recording of group bank position for dropped rod (reference point used to withdraw dropped rod to equal height with other rods in the bank)

(000003AK3.04) Knowledge of the reasons for the following responses as they apply to the (APE 3) DROPPED CONTROL ROD / 1 (CFR 41.5,41.10 / 45.6 / 45.13): Actions contained in EOP for dropped control rod 3.0 3.8 REJECT 19 1127 Bank 000024 (APE 24)

Emergency Boration

/ 1 26 000028 (APE 28)

Pressurizer (PZR)

Level Control Malfunction / 2 X

(000028AK1.01) Knowledge of the operational implications of the following concepts as they apply to (APE 28)

PRESSURIZER (PZR) LEVEL CONTROL MALFUNCTION / 2 (CFR 41.8 / 41.10 / 45.3): PZR reference leak abnormalities 2.8 20 1359 New 27 000032 (APE 32)

Loss of Source Range Nuclear Instrumentation / 7 X

(000032AK1.01) Knowledge of the operational implications of the following concepts as they apply to (APE 32) LOSS OF SOURCE RANGE NUCLEAR INSTRUMENTATION / 7 (CFR 41.8 / 41.10 / 45.3): Effects of voltage changes on performance 2.5 21 1360 New 28 000033 (APE 33)

Loss of Intermediate Range Nuclear Instrumentation / 7 X

(000033AA2.10) Ability to determine and interpret the following as they apply to the (APE 33) LOSS OF INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION /

7 (CFR: 43.5 / 45.13): Tech-Spec limits if both intermediate-range channels have failed (000033AA2.04) Ability to determine and interpret the following as they apply to the (APE 33) LOSS OF INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION /

7 (CFR: 43.5 / 45.13): Satisfactory overlap between source-range, intermediate-range and power-range instrumentation 3.8 3.6 REJECT 82 TBD 29 000036 (APE 36; BW/A08) Fuel-Handling Incidents /

8 X

(BA08AK2.1) Knowledge of the interrelations between the (BW A08) REFUELING CANAL LEVEL DECREASE / 8 and the following (CFR 41.7 / 45.7): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

4.0 22 1361 New 30 000037 (APE 37)

Steam Generator Tube Leak / 3 X

(000037AA2.05) Ability to determine and interpret the following as they apply to the (APE 37) STEAM GENERATOR TUBE LEAK / 3 (CFR: 43.5 / 45.13): Past history of leakage with current problem 2.8 23 1362 New 000051 (APE 51)

Loss of Condenser Vacuum / 4 31 000059 (APE 59)

Accidental Liquid Radwaste Release / 9 X

(000051 (APE 59) Accidental Liquid Radwaste Release / 9 (G2.2.25) Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 43.2)

(000051 (APE 59) Accidental Liquid Radwaste Release / 9 (G2.2.38) Knowledge of conditions and limitations in the facility license. (CFR: 43.2) 4.2 4.5 REJECT 83 1086 Bank

Page 6 of 16 000060 (APE 60)

Accidental Gaseous Radwaste Release /

9 000061 (APE 61)

Area Radiation Monitoring System Alarms / 7 32 000067 (APE 67)

Plant Fire On Site /

8 X

(000067AA2.16) Ability to determine and interpret the following as they apply to the (APE 67) PLANT FIRE ON SITE / 8 (CFR: 43.5 / 45.13): Vital equipment and control systems to be maintained and operated during a fire 4.0 84 116 Bank 000068 (APE 68; BW A06) Control Room Evacuation /

8 33 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X

(000069AA2.01) Ability to determine and interpret the following as they apply to the (APE 69) LOSS OF CONTAINMENT INTEGRITY / 5 (CFR: 43.5 / 45.13): Loss of containment integrity.

3.7 24 499 Bank 000074 (EPE 74; W E06 & E07)

Inadequate Core Cooling / 4 34 000076 (APE 76)

High Reactor Coolant Activity / 9 X (000076 (APE 76) High Reactor Coolant Activity / 9) (G2.4.45)

Ability to prioritize and interpret the significance of each annunciator or alarm. (CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.1 25 1363 New 000078 (APE 78*)

RCS Leak / 3 (W E01 & E02)

Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15)

Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03)

Loss of NNI-X/Y/7 35 (BW A04) Turbine Trip / 4 X

(BA04AK2.1) Knowledge of the interrelations between the (BW A04) TURBINE TRIP / 4 and the following (CFR 41.7 / 45.7):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

3.5 26 1364 Mod (BW A05)

Emergency Diesel Actuation / 6 36 (BW A07) Flooding

/ 8 X ((BW A07) Flooding / 8) (G2.1.19) Ability to use plant computers to evaluate system or component status. (CFR:

41.10 / 45.12) 3.8 85 TBD (BW E03)

Inadequate Subcooling Margin /

4

Page 7 of 16 (BW E08; W E03)

LOCA Cooldown -

Depressurization / 4 37 (BW E09; CE A13**;

W E09 & E10)

Natural Circulation/4 X

(BE09EA1.2) Ability to operate and / or monitor the following as they apply to (BW E09) NATURAL CIRCULATION COOLDOWN / 4 (CFR: 41.7 / 45.5 / 45.6): Operating behavior characteristics of the facility.

                    • REPLACE WITH TIER 4 GFE QUESTION**********

3.2 27 TBD (BW E13 & E14)

EOP Rules and Enclosures (CE A11**; W E08)

RCS Overcooling -

Pressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation /

LOOP / Blackout / 4 K/A Category Totals:

2 2

1 1

4 3

Group Point Total:

13

Page 8 of 16 ES-401 PWR Examination Outline (ANO 1)

Form ES-401-2 Plant Systems Tier 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#

38 003 (SF4P RCP)

REACTOR COOLANT PUMP SYSTEM X

(003K2.02) (SF4P RCP) REACTOR COOLANT PUMP SYSTEM Knowledge of electrical power supplies to the following (CFR:

41.7): CCW pumps (NCC)

(003K2.01) (SF4P RCP) REACTOR COOLANT PUMP SYSTEM Knowledge of electrical power supplies to the following (CFR:

41.7): RCPS 2.5 3.1 REJECT 28 1375 New 39 004 (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X

(004K4.04) Knowledge of (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR:

41.7): Manual/automatic transfers of control 3.2 29 1335 New 40 004 (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X (004 (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM) (G2.1.25) Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10 / 43.5 / 45.12) 4.2 86 1324 New 41 005 (SF4P RHR)

RESIDUAL HEAT REMOVAL SYSTEM X

(005K1.06) Knowledge of the physical connections and/or cause-effect relationships between (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM and the following (CFR:

41.2 to 41.9 / 45.7 to 45.8): ECCS 3.5 30 1336 New 42 006 (SF2; SF3 ECCS)

EMERGENCY CORE COOLING SYSTEM X

(006A4.07) (SF2; SF3 ECCS)

EMERGENCY CORE COOLING SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8): ECCS Pumps and valves 4.4 31 1337 New 43 006 (SF2; SF3 ECCS)

EMERGENCY CORE COOLING SYSTEM X

(006A4.11) (SF2; SF3 ECCS)

EMERGENCY CORE COOLING SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8):

Overpressure protection system 4.2 32 1339 Mod 44 007 (SF5 PRTS)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM X

(007K5.02) Knowledge of the operational implications of the following concepts as they apply to the (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM (CFR: 41.5 / 45.7): Method of forming a steam bubble in the PZR 3.1 33 561 Mod 45 008 (SF8 CCW)

COMPONENT COOLING WATER SYSTEM X

(008K2.02) (SF8 CCW)

COMPONENT COOLING WATER SYSTEM Knowledge of electrical power supplies to the following (CFR: 41.7): CCW pump, including emergency backup 3.0 34 1334 New

Page 9 of 16 46 008 (SF8 CCW)

COMPONENT COOLING WATER SYSTEM X (008 (SF8 CCW) COMPONENT COOLING WATER SYSTEM)

(G2.4.41) Knowledge of the emergency action level thresholds and classifications.

(CFR: 41.10 / 43.5 / 45.11) 4.6 87 1325 New 47 010 (SF3 PZR PCS)

PRESSURIZER PRESSURE CONTROL SYSTEM X

(010A3.02) Ability to monitor automatic operations of the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM including (CFR: 41.7 / 45.5): PZR pressure 3.6 35 1149 Bank 48 012 (SF7 RPS)

REACTOR PROTECTION SYSTEM X (012 (SF7 RPS) REACTOR PROTECTION SYSTEM) (G2.4.47)

Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 / 43.5 / 45.12) 4.2 36 1371 New 49 012 (SF7 RPS)

REACTOR PROTECTION SYSTEM X

(012K6.06) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF7 RPS)

REACTOR PROTECTION SYSTEM (CFR: 41.7 / 45.7): Sensors and detectors 2.7 37 155 Bank 50 013 (SF2 ESFAS)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X

(013K4.03) Knowledge of (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): Main Steam Isolation System (013K4.04) Knowledge of (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): Auxiliary feed actuation signal 3.9 4.3 REJECT 38 908 Bank 51 022 (SF5 CCS)

CONTAINMENT COOLING SYSTEM X

(022K1.01) Knowledge of the physical connections and/or cause-effect relationships between (SF5 CCS) CONTAINMENT COOLING SYSTEM and the following (CFR:

41.2 to 41.9 / 45.7 to 45.8): SWS/

cooling system 3.5 39 2

Bank 52 022 (SF5 CCS)

CONTAINMENT COOLING SYSTEM X

(022K4.04) Knowledge of (SF5 CCS) CONTAINMENT COOLING SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): Cooling of control rod drive motors 2.8 40 1345 New 025 (SF5 ICE) ICE CONDENSER SYSTEM

Page 10 of 16 53 026 (SF5 CSS)

CONTAINMENT SPRAY SYSTEM X

(026A1.03) Ability to predict and/or monitor changes in parameters associated with operating the (SF5 CSS) CONTAINMENT SPRAY SYSTEM controls including (CFR:

41.5 / 45.5): Containment sump level 3.5 41 1075 Bank 54 026 (SF5 CSS)

CONTAINMENT SPRAY SYSTEM X

(026A2.09) Ability to (a) predict the impacts of the following on the (SF5 CSS) CONTAINMENT SPRAY SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/

45.3/45.13): Radiation hazard potential of BWST 2.5 42 TBD 55 039 (SF4S MSS)

MAIN AND REHEAT STEAM SYSTEM X

(039A3.02) Ability to monitor automatic operations of the (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM including (CFR: 41.7 /

45.5): Isolation of the MRSS 3.1 43 1346 New 56 039 (SF4S MSS)

MAIN AND REHEAT STEAM SYSTEM X

(039A2.04) Ability to (a) predict the impacts of the following on the (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:

41.5 /43.5/ 45.3/45.13):

Malfunctioning steam dump 3.7 88 1327 New 053 (SF1; SF4P ICS*) INTEGRATED CONTROL 57 059 (SF4S MFW)

MAIN FEEDWATER SYSTEM X

(059A1.07) Ability to predict and/or monitor changes in parameters associated with operating the (SF4S MFW) MAIN FEEDWATER SYSTEM controls including (CFR:

41.5 / 45.5): Feed Pump speed, including normal control speed for ICS 2.5 44 1347 New 58 059 (SF4S MFW)

MAIN FEEDWATER SYSTEM X

(059K3.02) Knowledge of the effect that a loss or malfunction of the (SF4S MFW) MAIN FEEDWATER SYSTEM will have on the following (CFR: 41.7 / 45.6): AFW system (059K3.04) Knowledge of the effect that a loss or malfunction of the (SF4S MFW) MAIN FEEDWATER SYSTEM will have on the following (CFR: 41.7 / 45.6): RCS 3.6 3.6 REJECT 45 TBD 59 061 (SF4S AFW)

AUXILIARY /

EMERGENCY FEEDWATER SYSTEM X

(061K4.01) Knowledge of (SF4S AFW) AUXILIARY / EMERGENCY FEEDWATER SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR:

41.7): Water sources and priority of use 4.1 46 1348 New

Page 11 of 16 60 062 (SF6 ED AC)

AC ELECTRICAL DISTRIBUTION SYSTEM X

(062A2.15) Ability to (a) predict the impacts of the following on the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5

/43.5/ 45.3/45.13): Consequence of paralleling out-of-phase/mismatch in volts (062A2.04) Ability to (a) predict the impacts of the following on the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5

/43.5/ 45.3/45.13): Effect on plant of de-energizing a bus 2.8 3.1 REJECT 47 TBD 61 062 (SF6 ED AC)

AC ELECTRICAL DISTRIBUTION SYSTEM X

(062A2.16) Ability to (a) predict the impacts of the following on the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:

41.5 /43.5/ 45.3/45.13): Degraded system voltages 2.9 89 1328 Bank 62 063 (SF6 ED DC)

DC ELECTRICAL DISTRIBUTION SYSTEM X (063 (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM) (G2.4.3) Ability to identify post-accident instrumentation.

(CFR: 41.6 / 45.4)

(063 (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM) (G2.4.11) Knowledge of abnormal condition procedures.

(CFR: 41.10 / 43.5 / 45.4) 3.7 4.0 REJECT 48 TBD 63 063 (SF6 ED DC)

DC ELECTRICAL DISTRIBUTION SYSTEM X

(063K3.01) Knowledge of the effect that a loss or malfunction of the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM will have on the following (CFR: 41.7 / 45.6):

ED/G 3.7 49 975 Bank 64 064 (SF6 EDG)

EMERGENCY DIESEL GENERATOR SYSTEM X

(064K6.08) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (CFR: 41.7

/ 45.7): Fuel oil storage tanks 3.2 50 1349 New 65 073 (SF7 PRM)

PROCESS RADIATION MONITORING SYSTEM X

(073A2.02) Ability to (a) predict the impacts of the following on the (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5

/43.5/ 45.3/45.13): Detector failure 2.7 51 1366 New

Page 12 of 16 66 073 (SF7 PRM)

PROCESS RADIATION MONITORING SYSTEM X

(073K5.01) Knowledge of the operational implications of the following concepts as they apply to the (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM (CFR: 41.5 / 45.7):

Radiation theory, including sources, types, units, and effects 2.5 52 672 Bank 67 076 (SF4S SW)

SERVICE WATER SYSTEM X

(076K3.07) Knowledge of the effect that a loss or malfunction of the (SF4S SW) SERVICE WATER SYSTEM will have on the following (CFR: 41.7 / 45.6): ESF loads 3.7 53 1350 New 68 076 (SF4S SW)

SERVICE WATER SYSTEM X

(076A2.02) Ability to (a) predict the impacts of the following on the (SF4S SW) SERVICE WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/

45.3/45.13): Service water header pressure (076A2.01) Ability to (a) predict the impacts of the following on the (SF4S SW) SERVICE WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/

45.3/45.13): Loss of SWS 3.1 3.7 REJECT 90 1329 New 69 078 (SF8 IAS)

INSTRUMENT AIR SYSTEM X

(078K1.04) Knowledge of the physical connections and/or cause-effect relationships between (SF8 IAS) INSTRUMENT AIR SYSTEM and the following (CFR: 41.2 to 41.9

/ 45.7 to 45.8): Cooling water to compressor (078K1.05) Knowledge of the physical connections and/or cause-effect relationships between (SF8 IAS) INSTRUMENT AIR SYSTEM and the following (CFR: 41.2 to 41.9

/ 45.7 to 45.8): MSIV air 2.6 3.4 REJECT 54 TBD 70 103 (SF5 CNT)

CONTAINMENT SYSTEM X (103 (SF5 CNT) CONTAINMENT SYSTEM) (G2.4.50) Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 /

43.5 / 45.3) 4.2 55 1351 New K/A Category Totals:

3 2

3 4

2 2

2 6

2 2

5 Group Point Total:

33

Page 13 of 16 ES-401 PWR Examination Outline (ANO 1)

Form ES-401-2 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#

001 (SF1 CRDS)

CONTROL ROD DRIVE SYSTEM 002 (SF2; SF4P RCS) REACTOR COOLANT 011 (SF2 PZR LCS)

PRESSURIZER LEVEL CONTROL SYSTEM 71 014 (SF1 RPI) ROD POSITION INDICATION SYSTEM X

(014A4.02) (SF1 RPI) ROD POSITION INDICATION SYSTEM Ability to manually operate and/or monitor in the control room (CFR:

41.7 / 45.5 to 45.8): Control rod mode-select switch 3.4 56 1352 Mod 72 015 (SF7 NI)

NUCLEAR INSTRUMENTATIO N SYSTEM X

(015A2.01) Ability to (a) predict the impacts of the following on the (SF7 NI) NUCLEAR INSTRUMENTATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/

45.3/45.13): Power supply loss or erratic operation 3.9 91 1332 New 016 (SF7 NNI)

NONNUCLEAR INSTRUMENTATIO N SYSTEM 017 (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM 027 (SF5 CIRS)

CONTAINMENT IODINE REMOVAL SYSTEM 73 028 (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 (CFR: 41.7 / 45.6):

Hydrogen concentration in containment 3.3 57 1353 New 74 029 (SF8 CPS)

CONTAINMENT PURGE SYSTEM X (029 (SF8 CPS) CONTAINMENT PURGE SYSTEM) (G2.2.44) 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 92 1328 Bank

Page 14 of 16 033 (SF8 SFPCS)

SPENT FUEL POOL COOLING 75 034 (SF8 FHS)

FUEL HANDLING EQUIPMENT SYSTEM X

(034A2.01) 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 operation (CFR: 41.5

/43.5/ 45.3/45.13): Dropped fuel element 3.6 58 1354 New 76 035 (SF4P SG)

STEAM GENERATOR SYSTEM X

(035K5.01) Knowledge of the operational implications of the following concepts as they apply to the (SF4P SG) STEAM GENERATOR SYSTEM (CFR: 41.5

/ 45.7): Effect of secondary parameters, pressure, and temperature on reactivity 3.4 59 1355 Bank 77 041 (SF4S SDS)

STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM X

(041A1.02) Ability to predict and/or monitor changes in parameters associated with operating the (SF4S SDS) STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM controls including (CFR: 41.5 /

45.5): Steam pressure 3.1 60 1080 Bank 78 045 (SF4S MTG)

MAIN TURBINE GENERATOR SYSTEM X (045 (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM) (G2.2.12)

Knowledge of surveillance procedures. (CFR: 41.7 / 41.10 /

43.2 / 43.3 / 45.3) 3.7 61 1356 New 050 (SF9 CRV*)

CONTROL ROOM VENTILATION 055 (SF4S CARS)

CONDENSER AIR REMOVAL 056 (SF4S CDS)

CONDENSATE SYSTEM 79 068 (SF9 LRS)

LIQUID RADWASTE SYSTEM X

(068K4.01) Knowledge of (SF9 LRS) LIQUID RADWASTE SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): Safety and environmental precautions for handling hot, acidic, and radioactive liquids 3.4 62 1357 New 80 071 (SF9 WGS)

WASTE GAS DISPOSAL SYSTEM X

(071K3.04) Knowledge of the effect that a loss or malfunction of the (SF9 WGS) WASTE GAS DISPOSAL SYSTEM will have on the following (CFR: 41.7 / 45.6):

Ventilation system 2.7 63 272 Bank 072 (SF7 ARM)

AREA RADIATION MONITORING SYSTEM

Page 15 of 16 81 075 (SF8 CW)

CIRCULATING WATER SYSTEM X (075 (SF8 CW) CIRCULATING WATER SYSTEM) (G2.4.4)

Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. (CFR:

41.10 / 43.2 / 45.6) 4.7 93 TBD 82 079 (SF8 SAS**)

STATION AIR SYSTEM X

(079A2.01) Ability to (a) predict the impacts of the following on the (SF8 SAS**) STATION AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5

/43.5/ 45.3/45.13): Cross-connection with IAS 2.9 64 1358 New 83 086 (SF8 FPS)

FIRE PROTECTION SYSTEM X

(086A2.01) Ability to (a) predict the impacts of the following on the (SF8 FPS) FIRE PROTECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:

41.5 /43.5/ 45.3/45.13): Manual shutdown of the FPS

                    • REPLACE WITH TIER 4 GFE QUESTION**********

2.9 65 TBD K/A Category Totals:

0 0

2 1

1 0

1 4

0 1

3 Group Point Total:

13

Page 16 of 16 ES-401 PWR Examination Outline (ANO 1)

Form ES-401-3 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)

Facility: ANO 1 Date of Exam: 04/05/2022 Category K/A #

RO SRO-Only Topic Item #

IR Q#

IR Q#

1. Conduct of Operations G2.1.26 (G2.1.26) Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen). (CFR: 41.10 / 45.12) 84 3.4 66 1367 Bank G2.1.45 (G2.1.45) Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 / 43.5 /

45.4) 85 4.3 67 883 Bank G2.1.21 G2.1.14 (G2.1.21) Ability to verify the controlled procedure copy.

(CFR: 41.10 / 45.10 / 45.13)

(G2.1.14) Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

86 3.6 3.1 REJECT 94 1372 Bank G2.1.36 (G2.1.36) Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10 / 43.6 / 45.7) 87 4.1 95 1250 Repeat Subtotal 2

2

2. Equipment Control G2.2.12 (G2.2.12) Knowledge of surveillance procedures. (CFR: 41.10 /

45.13) 88 3.7 68 1368 Mod G2.2.13 (G2.2.13) Knowledge of tagging and clearance procedures.

(CFR: 41.10 / 45.13) 89 4.1 69 1369 Bank G2.2.36 (G2.2.36) Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 / 43.2 / 45.13)

                    • REPLACE WITH TIER 4 GFE QUESTION**********

90 3.1 70 TBD G2.2.20 (G2.2.20) Knowledge of the process for managing troubleshooting activities. (CFR: 41.10 / 43.5 / 45.13) 91 3.8 96 1326 New G2.2.43 (G2.2.43) Knowledge of the process used to track inoperable alarms. (CFR: 41.10 / 43.5 / 45.13) 92 3.3 97 1323 New Subtotal 3

2

3. Radiation Control G2.3.13 (G2.3.13) Knowledge of radiological safety 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, aligning filters, etc. (CFR: 41.12 / 43.4 / 45.9 / 45.10) 93 3.4 71 1081 Bank G2.3.5 (G2.3.5) Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11

/ 41.12 / 43.4 / 45.9)

                    • REPLACE WITH TIER 4 GFE QUESTION**********

94 2.9 72 TBD G2.3.6 (G2.3.6) Ability to approve release permits. (CFR: 41.13 /

43.4 / 45.10) 95 3.8 98 1322 New Subtotal 2

1

4. Emergency Procedures/Plan G2.4.11 (G2.4.11) Knowledge of abnormal condition procedures. (CFR:

41.10 / 43.5 / 45.13) 96 4.0 73 1370 New G2.4.25 (G2.4.25) Knowledge of fire protection procedures. (CFR:

41.10 / 43.5 / 45.13)

                    • REPLACE WITH TIER 4 GFE QUESTION**********

97 3.3 74 TBD G2.4.29 (G2.4.29) Knowledge of the emergency plan. (CFR: 41.10 /

43.5 / 45.11)

                    • REPLACE WITH TIER 4 GFE QUESTION**********

98 3.1 75 TBD G2.4.42 (G2.4.42) Knowledge of emergency response facilities.

(CFR: 41.10 / 45.11) 99 3.8 99 1321 Bank G2.4.44 (G2.4.44) Knowledge of emergency plan protective action recommendations. (CFR: 41.10 / 41.12 / 43.5 / 45.11) 100 4.4 100 1162 Bank Subtotal 3

2

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection RO T1 015 AA2.11 (3.4)

(Q#4) 015 AA2.10 (3.7)

It is not possible (without expending an unreasonable amount of resources) to prepare a psychometrically sound question related to the subject K/A. The original K/A concerns when to jog RCPs during ICC. While there is EOP guidance to on how to perform jogging the RCPs, there is no EOP/AOP guidance on when to perform jogging. In an emergency, this task would be directed based on input and guidance from the TSC. Randomly selected 015 AA2.10 which concerns when to secure RCPs on loss of cooling or seal injection.

RO T1 027 AK3.01 (3.5)

(Q#8) 027 AK3.03 (3.7)

The subject K/A is not relevant at the subject facility. The original K/A concerns isolating PZR spray during a loss of PZR heaters. The only time ANO1 isolates PZR spray is when the PZR spray valve fails open. There is no procedural guidance to isolate PZR spray during a loss of heaters. Randomly selected 027 AK3.03 which concerns actions contained in the EOP for PZR PCS malfunction.

RO T1 003 AK3.09 (3.0)

(Q#19) 003 AK3.04 (3.8)

The subject K/A is not relevant at the subject facility. The original K/A was the knowledge for the reasons that group bank position for a dropped rod is recorded when withdrawing the dropped rod to equal height with the other rods in the bank.

For a dropped rod event at ANO1, an automatic plant runback occurs to 40% power by the Integrated Control System (ICS). ICS will then control bank position in automatic to maintain power at the runback setpoint. When the rod is ready to be recovered, it is simply leveled with the other rods in the group. No position data is recorded. The AOP even recognizes that group position might need to be changed to keep power less than 40% when withdrawing the single rod which would be accomplished by moving control rod group position. Randomly selected AK3.04 which is actions contained in the EOP for dropped control rod.

RO T2 003 K2.02 (2.5)

(Q#28) 003 K2.01 (3.1)

The original K/A was knowledge of electrical supplies to CCW pumps. This is sampling the same knowledge required to answer Q34 (008 K2.02). Randomly selected K2.01 which is knowledge of the power supplies to RCPS.

RO T2 013 K4.03 (3.9)

(Q#38) 013 K4.04 (4.3)

The subject K/A is not relevant at the subject facility. The original K/A was knowledge of ESFAS interlocks which provide Main Steam Isolation. The ESAS system does not initiate MSLI. This is performed by the Emergency Feedwater and Actuation Control System (EFIC). Randomly selected 013 K4.04 which is the knowledge of ESFAS interlocks which provide AFW actuation signal.

RO T2 059 K3.02 (3.6)

(Q#45) 059 K3.04 (3.6)

The original K/A concerned the knowledge of the effect that a loss of malfunction of MFW will have on the AFW system. This is sampling the same knowledge required to answer Q12 (054 AA2.03). Randomly selected 059 K3.04 which is the effect a malfunction of MFW has on the RCS.

RO T2 062 A2.15 (2.8)

(Q#47) 062 A2.04 (3.1)

The subject K/A is not relevant at the subject facility. The original K/A concerned the impact of paralleling out-of-phase or mismatch in volts on the Electrical Distribution System and using procedures to correct, control, or mitigate the consequences.

There is no guidance at ANO1 for this situation. If the system was EDGs, it would be more applicable as EDG voltage and frequency can be controlled by procedure, however for the Electrical Distribution System, no guidance exists. Randomly selected A2.04 which concerns the effect on the plant of de-energizing a bus.

RO T2 063 2.4.3 (3.7)

(Q#48) 063 2.4.11 (4.0)

The subject K/A is not relevant at the subject facility. The original K/A was the generic K/A concerning the ability to identify post-accident instrumentation in the Tier 2 section for the DC electrical system. There are no DC parameters that are considered post-accident instrumentation at ANO1. Randomly selected K/A 2.4.11 which is the knowledge of abnormal condition procedures.

RO T2 078 K1.04 (2.6)

(Q#54) 078 K1.05 (3.4)

The subject K/A is not relevant at the subject facility. The original K/A concerned the physical or cause effect relationships between IAS and Cooling Water to the Compressor. ANO1 no longer utilizes cooling water to the IA compressors. Both air compressors are air cooled. Randomly selected K1.05 which concerns the relationship between IAS and MSIV air.

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection SRO T1 057 2.4.18 (4.0)

(Q#80) 057 2.4.6 (4.7)

It is not possible to prepare a question at the correct license level related to the subject K/A. The original K/A concerned knowledge of the specific bases for EOPs as a generic K/A within the T1 SRO section of the exam. There is no bases document for the Loss of Vital AC Instrument Bus procedure at ANO1. During research within the procedure, notes and cautions were reviewed but any potential question would have been better suited as a RO question, not SRO. Randomly selected K/A 2.4.6 which concerns the knowledge of symptom based EOP mitigation strategies.

SRO T1 033 AA2.10 (3.8)

(Q#82) 033 AA2.04 (3.6)

It is not possible to prepare a question at the correct license level related to the subject K/A. The original K/A concerned tech spec limits if both intermediate range channels have failed. At ANO1, these TS action times are all 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less so this question would be RO knowledge not SRO knowledge. Randomly selected K/A 003 AA2.04 which concerns the satisfactory overlap between source-range, intermediate-range, and power range instrumentation.

SRO T1 059 2.2.25 (4.2)

(Q#83) 059 2.2.38 (4.5)

It is not possible (without expending an unreasonable amount of resources) to prepare a psychometrically sound question related to the subject K/A. The original K/A concerns knowledge of TS bases for LCOs and safety limits as it pertains to an Accidental Liquid Radwaste Release. There is nothing in TS that concerns an accidental liquid radwaste release. All the license basis requirements are controlled in the ODCM. The ODCM bases contains a level of detail that is not operationally relevant and would be considered minutia for a senior licensed operator. Randomly selected K/A 2.2.38 which is the knowledge of conditions and limitations in the facility license.

SRO T2 076 A2.02 (3.1)

(Q#90) 076 A2.01 (3.7)

The subject K/A is not relevant at the subject facility. The original K/A concerns the ability to predict the impact of service water header pressure on the service water system and use procedures to correct, control or mitigate the consequences. There are no TS or procedural actions based on the service water pressure parameter.

Randomly selected K/A 076 A2.01 which is the same A2 category but concerns a loss of SWS, not service water pressure.

SRO T3 2.1.21 (3.6)

(Q#94) 2.1.14 (3.1)

It is not possible to prepare a question at the correct license level related to the subject K/A. The subject K/A is ability to verify controlled procedure copy. This is performed by all procedure users on site, not a specific SRO task. Randomly selected K/A 2.1.14 which is the knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Form 3.2-1 Administrative Topics Outline

Facility: ___ANO UNIT 1___________________

Date of Examination: ___4/4/2020__

Examination Level:

RO SRO Operating Test Number: _2022-04___

Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations Estimate RCS Leak Rate.

2.1.20 Ability to interpret and execute procedure steps.

N, R Conduct of Operations Calculate SFP Time to Boil.

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

D, R Equipment Control Determine the mechanical and electrical boundary isolations for P-36B Makeup Pump seal leak. (Do not need to drain the pump) 2.2.13 Knowledge of tagging and clearance procedures.

D, R Radiation Control Review RWP and survey map to calculate maximum stay time.

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

D, R Emergency Plan

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: ____ANO UNIT 1___________________________ Date of Examination: __4/4/2022____

Examination Level:

RO SRO Operating Test Number: _2022-04___

Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations Determine acceptable control room loading.

2.1.9 Ability to direct personnel activities inside the control room.

N, R Conduct of Operations Door breech requirements, determine need for a firewatch.

2.1.8 Ability to direct personnel activities outside the control room.

D, R Equipment Control Review and approve the tagout provided for P-36B Makeup Pump seal leak. If not approved, provide the reasons why.

2.2.13 Knowledge of tagging and clearance procedures.

D, R Radiation Control Potassium Iodine administration determination.

2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

N, R Emergency Plan Classify an Emergency Event.

2.4.41 Knowledge of emergency action level thresholds and classifications.

D, R

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: ____ ANO UNIT 1________________________ Date of Examination: ___4/4/2022 ___

Operating Test Number: __2022-04___

Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems

a. Respond to continuous rod withdrawl.

001 A2.11 (RO 3.3/SRO 3.3)

RO/SRO-I S, D 1

b. Perform actions for ESAS Actuation (Shift RB Sump Suction) 006 A4.02 (RO 4.0/SRO 3.8)

RO/SRO-I/SRO-U S, D, EN 2

c. Transfer of Service Water suction from the Lake to the ECP.

076 A2.01 (RO 3.5/SRO 3.7)

RO/SRO-I S, D 4S

d. Respond to simultaneous loss of seal injection and seal cooling.

003 A4.08 (RO 3.2/SRO 2.9)

RO/ SRO-I S, A, M 4P

e. Secure RB Spray after ES Actuation.

026 A2.08 (RO 3.2/SRO 3.7)

RO S, D 5

f. Transfer from SU1-Unit Aux.

062 A4.07 (RO 3.1/SRO 3.1)

RO/SRO-I/SRO-U S, A, M 6

g. RX Tripped Check NNI and ICS Power Available.

A02 AA1.1 (B&W EPEs/APEs) (RO 4.0/SRO 3.8)

RO/SRO-I S, A, D 7

h. Respond to Pressurizer ERV failure.

010 A3.02 (RO 3.6/SRO/3.5)

RO/SRO-I/SRO-U S, A, P, L, D

3 In-Plant Systems

i. Perform Restoring SW to ICW following ES Actuation 008 A3.08 (RO 3.6/SRO 3.7)

RO/SRO-I/SRO-U D

8

j. Take manual control of P-7A EFW Pump at 061 A2.05 (RO 3.1/SRO 3.4)

RO/SRO-I/SRO-U R, D, P, E 4S

k. Align T-16A (Treated Waste Monitoring Tank) for Recirc/Sample 068 A2.02 (RO2.7/SRO 2.8)

RO/SRO-I D, A, P, R 9

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 3.3-1 Scenario Outline Facility:

ANO-1 Scenario #:

1 Scenario Source:

NEW Op. Test #:

2022-04 Examiners:

Applicants/

Operators:

Initial Condition:

- 100% Power

- CV-2670 isolation to A SG From P-7A failed open

- CV-2646 EFW Control to A SG from P-7A failed open

- RPS Failed, Will not automatically trip the reactor.

Turnover:

- Plant is at 100% Power

- 450 EFPD

- Need to rotate operating EH Oil Pumps P-14A in service Secure P-14B.

Critical Tasks:

CT-1 IAW 1015.050, Time Critical Operator Actions, operators are required to trip the RX within 1 minute if RPS fails and the main reactor trip pushbutton fails.

CT-2 Manual SG isolation or MSLI manual actuation should occur prior to violating 100F/HR cooldown per TS 3.4.3 RCS Pressure/Temperature Limits.

Event No.

Malf. No.

Event Type*

Event Description 1

NA N-(BOP)

N-(SRO)

Rotate operating EH Oil Pumps P-14A in service Secure P-14B.

2 TR049 I-(ATC)

I-(SRO)

TS, AOP LT-1001 Pressurizer Level Fails High (T.S. 3.3.15 Condition A - Function 11 Pressurizer Level) 3 ED180 C-(BOP)

C-(SRO)

TS Startup 1 Transformer is deenergized due to Lockout caused by sudden pressure. (T.S. 3.8.1 Condition A).

4 K05C1 DO_P3CLUB CW084 C-(BOP)

C-(ATC)

C-(SRO)

Circ Water Pump Motor Cooling Flow Low 5

MC088 SW087 R-(ATC)

C-(BOP)

C-(SRO)

MC-(BOP)

AOP Condenser Vacuum Leak (5000 SCFM)

C-5B Condenser Vacuum Pump will fails to autostart.

6 DI_PB9201 RP246 RP247 RP248 RP249 C-(ATC)

MC-(ATC)

C-(SRO)

Main Generator Trips at 25.5 Vac. RPS Failed.

DI_ICC0020 C-(ATC)

C-(SRO)

CT-1 CO3 Manual Trip Pushbutton Failed 7

MS141 M-(ALL)

MSSV Stuck Open transition to overcooling.

8 FW621 C-(ALL)

CT-2 Half Trip of MSLI.

(TS 3.7.5 Condition B)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

OBJECTIVES FOR SCENARIO

1)

Evaluate individual ability to perform rotation of plant equipment.

2)

Evaluate individual ability to recognize and respond to a failed pressurizer level transmitter

3)

Evaluate individual ability to recognize and respond to failure of Circulating Water Pump.

4)

Evaluate individual ability to recognize and respond to failure of the Startup 1 Transformer.

5)

Evaluate individual ability to recognize when conditions require the entry into Technical Specifications conditions.

6)

Evaluate individual ability to respond to Lowering Main Condenser Vacuum.

7)

Evaluate individual ability to reduce plant power.

8)

Evaluate individual ability to respond to failure of RPS Trip.

9)

Evaluate individual ability to respond to a Reactor Trip.

10) Evaluate individual ability to respond to Overcooling.
11) Evaluate individual ability to respond to EFIC System Failures.
12) Evaluate individual ability to perform EOP Repetitive Tasks.

SCENARIO 1 NARRATIVE The crew will assume the watch with the plant at 100% power.

The turnover sheet will direct the crew to swap operating turbine electro-hydraulic pumps per 1106.012 Electro-Hydraulic Oil System Operation Section 15 for a 30 minute run PMT.

(SRO-N) (BOP-N).

After the P-14B EH Oil Pump is placed into service and P-14A EH Oil Pump is secured, LT-1001 - Pressurizer Level Transmitter will fail high causing two alarms (Hi Level and Hi HI Level) and results in the RCS Makeup Valve being demanded closed due to the false high level.

The ATC / BOP will determine which transmitter has failed and the ATC will select a good signal for pressurizer level control. The SRO will also enter T.S. 3.3.15 Condition A (PAM) for the failed transmitter.

(SRO-TS) (ATC-I) (TS)

SU 1 L.O. RELAY TRIP alarm (K02-A1) will come in, indicating the Startup 1 transformer is deenergized. 1203.012B, Annunciator K02 Corrective Action should be entered. An Auxiliary Operator should be dispatched to investigate the transformer locally. The AO will report that the cause of the lockout is due to a Sudden Gas Pressure alarm. Per the ACA, the Startup 2 hand switches should be removed from Pull-to-Lock (coordinated with Unit 2). The SRO should declare one required offsite power source inoperable and enter TS 3.8.1. Condition A.

(BOP-C) (SRO-C) (TS)

Circ Water Pump Motor Cooling Water Flow Low annunciator K05-C1 will alarm for the C CW Pump. The Outside AO should be dispatched to investigate. The AO will report that Seal Flow Sight Glass FI-3620 is broken and will need to be isolated. The crew should secure the C CW Pump per 1104.008 Circulating Water and Water Box Vacuum System Operation, section 10.0 Stopping a Circ Water Pump.

(SRO-C) (BOP-C) (ATC-N)

A condenser vacuum leak will occur. The SRO should direct actions per 1203.016 Loss of Condenser Vacuum. The ATC should place SG/RX to hand and ensure power is less than 100%. BOP should enter the transient low vacuum alarm setpoints in the plant computer and start the standby Condenser Vacuum Pump (C-5B). SRO should then enter 1203.045 Rapid Plant shutdown and decrease turbine load to stabilize vacuum.

(ATC-R) (BOP-C) (SRO-C)

At 25.5 inches or 65% power the main turbine will trip, due to a failure of RPS the team should recognize the failure of the RX trip and trip the RX and perform immediate actions.

(ATC-MC) (ATC-C) (SRO-C)

The backup pushbuttons on CO3 will be required due to failure of the Rx Trip pushbutton to work. (CT-1 IAW 1015.050, Time Critical Operator Actions, operators are required to trip the RX within 1 minute if RPS fails and the main reactor trip pushbutton fails.) When the reactor trips, a main steam safety valve on the A Steam Generator (SG) will fail open and will not reseat. This will result in an overcooling of the RCS. When A SG pressure is <900 psig, the Overcooling EOP, 1203.003 will be entered to address the event. HPI will be aligned if required.

(ATC-C) (SRO-C)

CONTINUED ON NEXT PAGE

The crew should identify the MSSV Open annunciator remains in alarm and recognize the lowering steam pressure (<900 psig) in the A SG. The SRO should transition to1202.003, the Overcooling EOP.

(ALL-M)

Actuation of HPI will be required to maintain RCS pressure and Pressurizer level during Overcooling event. Repetitive task 2 (RT-2) will be utilized to initiate and control HPI flow. The Overcooling EOP directs that HPI be initiated if Pressurizer Level drops below 30 or RCS pressure is < 1700 psig. During the depressurization of the A SG, the crew will identify the failure of the MSLI to fully actuate. The ATC should diagnose this and the SRO should direct actuating EFW and MSLI for the A SG. The SRO should reference Technical Specification 3.7.5.B, for One EFW train inoperable. (CT-2 Manual SG isolation or MSLI manual actuation should occur prior to violating 100F/HR cooldown per TS 3.4.3 RCS Pressure/Temperature Limits.)

(ALL-C)

The scenario can be terminated when MSLI has been actuated to the A SG and the SG is dry.

Crew has taken actions to stabilize RCS temperature, pressure and inventory. B Turbine Bypass Valves utilized to stabilize RCS temperature. HPI is secured if initiated to limit RCS pressure and pressurizer level.

Form 3.3-1 Scenario Outline Facility:

ANO-1 Scenario #:

2 Scenario Source:

FEB 2018 ANO-1 Op. Test #:

2022-04 Examiners:

Applicants/

Operators:

Initial Condition:

- 100% Power

- 12 EFPD

- #1 EDG SW cooling valve is failed closed.

- #2 EDG will not Auto-Start but will manually start

- ICS Reactor Demand AUTO button is failed.

Turnover:

- Unit 2 is in Cold Shutdown (forced outage)

- Chemistry request sample alignment for T-2A CFT. WCO has been briefed and is standing by in the Aux building.

No tank makeup has been performed and no recirc is desired.

Critical Tasks:

CT-1 #2 EDG must be started within 15 minutes of entering Blackout conditions.

CT-2 Primary to secondary heat transfer must be established prior to a loss of adequate SCM ( 30 deg), OR HPI cooling initiated when required conditions are met.

Eve nt No.

Malf. No.

Event Type*

Event Description 1

N/A N(BOP)

N(SRO)

TS Align T-2A Sample to the Hot Lab as directed in 1104.001 Section 16.0. (Technical Specification 3.6.3, RB Isol. Valves, & 3.5.1, Core Flood Tanks) 2 NI236 DI_RPSA59 I-(BOP)

I-(SRO)

TS, AOP Power Range NI (NI-5) fails low.

(Technical Specification 3.3.1, RPS Instrumentation and 3.3.11, EFIC System Instrumentation) 3 B5148 B5122 R-(ATC)

N-(SRO)

Loss of 500kV transmission line. Dispatcher orders power reduction to 700MW in 20 minutes (ICS in HAND).

4 RX150 I-(ATC)

I-(BOP)

MC-(ATC/BOP)

I-(SRO)

Main Turbine EHC fails to respond to ICS signal requiring MANUAL control of the Main Turbine.

5 CV062 C-(SRO)

C-(BOP)

C-(ATC)

Trip of the running Makeup Pump (P-36B) 6 ED183 M-(ALL)

Loss of Offsite Power/Reactor Trip (Technical Specification 3.8.1, AC Sources - Operating) 7 DG176 CV3806 C-(BOP)

C-(SRO)

(CT)

  1. 1 EDG Service Water Cooling valve (CV-3806) fails to open
  1. 2 EDG doesnt auto-start. Must depress the manual start button.

(Technical Specification 3.8.1, AC Sources - Operating) 8 FW076 C-(ALL)

(CT)

P-7A EFW pump trips after approx. 5 min.

A3 powered from A4 or the AAC Diesel Generator(power to P-7B) to provide primary to secondary heat removal or HPI Cooling Initiated.

(Technical Specification 3.7.5, Emergency Feedwater (EFW) System)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

OBJECTIVES FOR SCENARIO

1)

Evaluate individual ability to perform sampling of Core Flood Tanks.

2)

Evaluate individual ability to recognize and respond to a Power Range Nuclear Instrument failure.

3)

Evaluate individual ability to perform a controlled power reduction as directed by the system dispatcher to maintain grid stability.

4)

Evaluate individual ability to recognize and respond to a failure of the main turbine control system to respond to ICS demand.

5)

Evaluate individual ability to respond to loss of Makeup Pump.

6)

Evaluate individual ability to respond to an automatic Reactor Trip.

7)

Evaluate individual ability to respond to a loss of offsite power (Degraded Power).

8)

Evaluate individual ability to identify and respond to failure of an EDG cooling water valve.

9)

Evaluate individual ability to identify and respond to failure if an EDG to auto-start.

10) Evaluate individual ability to identify and respond to loss of primary to secondary cooling (Overheating).
11) Evaluate individual ability to restore AC power to vital equipment.
12) Evaluate individual ability to ensure core cooling by various means.

SCENARIO 2 NARRATIVE The crew will be allowed to brief aligning Core Flood Tank sample.

The crew will assume the watch with the plant at 100% power near the beginning of core. There is no out of service equipment.

The SRO will direct the BOP operator to align T-2A Core Flood Tank sample. Alignment is perform as directed in 1104.001 Section 16.0. Sampling requires stationing a dedicated operator in the auxiliary building for the duration of the alignment. Note 1 of Technical Specification 3.6.3, Reactor Building Isolation Valves must be applied. Additionally, Technical Specification 3.5.1, Core Flood Tanks, Condition B must be entered (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) due to sample lines not being seismically qualified. Sample alignment requires opening one manual valve (CF-

2) (Category E) and one MOV (CV-2416). Both valves must be logged in the Containment Penetration Valve Log prior to opening.

(N-SRO) (N-BOP) (TS)

Power range nuclear instrument NI-5 will fail downscale. Due to this signal being fed through a high auctioneer, the input to ICS will be unaffected, but the failure will result in inoperability of the A RPS channel and A EFIC channel. A momentary RPS TROUBLE annunciator (K08-C3) will be received as well as REACTOR TRIP ON LOSS OF FEEDWATER BYP/TROUBLE (K15-B1) and REACTOR TRIP ON MAIN TURBINE TRIP BYPASS TROUBLE (K15-C1) will be locked in alarm. The SRO should enter 1203.021, Loss of Neutron Flux Indication AOP, Section 1 for Loss of One or More Power Range NI Channels. The SRO should reference TS.3.3.1 (Reactor Protection System Instrumentation) for the A RPS Channel and TS 3.3.11 (Emergency Feedwater Initiation and Control System Instrumentation) for the A EFIC Channel. A RPS and EFIC channels should be immediately declared inoperable and placed in bypass or trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the inoperability.

(I-BOP) (I-SRO) (TS)

A loss of a 500 kV transmission line will occur, and the system dispatcher will notify the control room that a load reduction to 700 MW is required to maintain grid stability. Power must be lowered within 20 minutes to prevent transmission line overheat. The SRO should enter 1203.045, Rapid Plant Shutdown AOP, Section 1 (No Tube Leak). The SRO will direct the ATC to adjust the rate of change to a value that will ensure that the target value (700MW) will be reached within the 20-minute time frame. The ATC will lower the Unit Load Demand (ULD) station to <735 MW (NOTE: House loads are ~35MW. Gross output of 735MW will result in net output of 700MW). (R-ATC) (N-SRO)

When to power reduction is started, the main turbine will fail to respond to changing ICS demand which will result in lowering steam header pressure and generator output not lowering as desired. The SRO will enter 1203.001 ICS Abnormal Operation AOP, Section 2, Undesired Power Change. The SRO should direct the ATC place the SG/RX Master demand into HAND and then direct the BOP operator to place the main turbine controls in MAN. The ATC will then lower reactor power by means of the SG/RX Demand station and the BOP will maintain steam header pressure in the band designated by the SRO (usually 880 to 910 psig). The ATC and BOP will coordinate and lower power until gross generation is 735MW. The AUTO pushbutton on the SG/RX demand station is failed so restoration back to auto will not be possible.

(I-ATC) (I-BOP) (I-SRO) (MC-ATC/BOP)

CONTINUED ON NEXT PAGE

During or after the power reduction is complete, the running Makeup Pump (P-36A) will trip due to an instantaneous overcurrent condition as reported from the field operator upon request to investigate. The SRO will enter AOP 1203.026, Loss of Reactor Coolant Makeup. Actions will be performed by both the ATC and BOP for this failure.

(ATC-C) (BOP-C) (SRO-C)

Once actions are complete for loss of the Makeup Pump, a loss of all offsite power will occur which will result in a reactor trip. The SRO will enter 1202.00, Reactor Trip EOP and direct completion of the Reactor Trip Immediate Actions.

(Technical Specification 3.8.1, AC Sources - Operating)

(M-ALL)

After reactor trip immediate actions are complete, the SRO should enter 1202.007, Degrade Power EOP. The SRO will direct performance of RT-21 to verify proper operation of both EDGs.

The crew should identify that CV-3806 is not open to supply the #1 EDG with cooling water. An Auxiliary Operator should be dispatch to open CV-3806 (CV-3806 will not open manually).

When the AO reports that CV-3806 will not open, #1 EDG should be shutdown by placing it in Lockout. Technical Specification 3.8.1, AC Sources - Operating) RT-21 will direct that the manual pushbutton on the #2 EDG be depressed (CT #2 EDG must be started within 15 minutes of entering Blackout conditions.) and the #2 EDG will start and energize vital bus A4. The SRO should direct the Unit 2 control room to start the Alternate AC (AAC) Generator and align its output to Unit 1. After a short delay, Unit 2 will report that the AAC Generator is running and ready for loading.

(C-BOP) (C-SRO)

P-7A EFW pump will trip after startup and will not be able to be reset. Per the Degraded Power EOP, the EFW should be realigned for restart. Vital bus A3 should be energized from the A4 bus or AAC Generator to provide power to P-7B electric EFW pump to supply feedwater to the SGs for primary-to-secondary cooling. (Technical Specification 3.7.5, Emergency Feedwater (EFW) System) (SRO-CT) (BOP-CT) If conditions exist that require HPI cooling (ERV opens in AUTO, RCS pressure 2450 psig, RCS press approaches NDTT limit, or Overheating causes SCM to become inadequate) then HPI Cooling is established using RT-4. (CT-2 Primary to secondary heat transfer must be established prior to a loss of adequate SCM ( 30 deg),

OR HPI cooling initiated when required conditions are met.)

(C-ALL)

The scenario may be terminated when RCS cooling has been established via Primary-to-Secondary Heat Transfer OR HPI Cooling OR both OR at the direction the lead evaluator.

Form 3.4-1 Events and Evolutions Checklist Facility: ANO Unit 1 Date of Exam: 04/04/2022 Operating Test No.: 2022-04 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

2 3

4 T

O T

A L

M I

N I

M U

M*

POSITION POSITION POSITION POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

I1 RX 5

1 1

1 0

NOR 1,3 2

1 1

1 I/C 2,4,6

,8 2,4, 5,7, 8

9 4

4 2

MAJ 7

6 2

2 2

1 Man. Ctrl 6

1 1

1 0

TS 1,2 2

0 2

2 U1 RX 0

1 1

0 NOR 1

1 1

1 1

I/C 2,3, 4,5, 6,8 6

4 4

2 MAJ 7

1 2

2 1

Man. Ctrl 0

1 1

0 TS 2,3 2

0 2

2 U2 RX 0

1 1

0 NOR 1,3 2

1 1

1 I/C 2,4, 5,7, 8

5 4

4 2

MAJ 6

1 2

2 1

Man. Ctrl 0

1 1

0 TS 1,2 2

0 2

2 R1 RX 5

1 1

1 0

NOR 1

1 1

1 1

I/C 2,4,6

,8 2,4,5

,7,8 9

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 6

4 2

1 1

0 TS 0

0 2

2 R2 RX 3

1 1

1 0

NOR 1

1 1

1 1

I/C 3,4,5

,8 4,5,8 7

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 6

4 2

1 1

0 TS 0

0 2

2

Form 3.4-1 Events and Evolutions Checklist Facility: ANO Unit 1 Date of Exam: 04/04/2022 Operating Test No.: 1 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

2 3

4 T

O T

A L

M I

N I

M U

M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

U3 RX 0

1 1

0 NOR 1

1 1

1 1

I/C 2,3,4

,5,6, 8

6 4

4 2

MAJ 7

1 2

2 1

Man. Ctrl 0

1 1

0 TS 2,3 2

0 2

2 U4 RX 0

1 1

0 NOR 1,3 2

1 1

1 I/C 2,4, 5,7, 8

5 4

4 2

MAJ 6

1 2

2 1

Man. Ctrl 0

1 1

0 TS 1,2 2

0 2

2 R3 RX 5

1 1

1 0

NOR 1

1 1

1 1

I/C 2,4,6

,8 2,4,5

,7,8 9

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 6

4 2

1 1

0 TS 0

0 2

2 R4 RX 3

1 1

1 0

NOR 1

1 1

1 1

I/C 3,4,5

,8 4,5,8 7

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 6

4 2

1 1

0 TS 0

0 2

2

Form 3.4-1 Events and Evolutions Checklist Facility: ANO Unit 1 Date of Exam: 04/04/2020 Operating Test No.: 1 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

2 3

4 T

O T

A L

M I

N I

M U

M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

U5 RX 0

1 1

0 NOR 1

1 1

1 1

I/C 2,3,4

,5,6, 8

6 4

4 2

MAJ 7

1 2

2 1

Man. Ctrl 0

1 1

0 TS 2,3 2

0 2

2 U6 RX 0

1 1

0 NOR 1

1 2

1 1

1 I/C 2,3,4

,5,6, 8

2,4,5

,7,8 11 4

4 2

MAJ 7

6 2

2 2

1 Man. Ctrl 4

1 1

1 0

TS 2,3 2

0 2

2 R5 RX 5

1 1

1 0

NOR 1

1 1

1 1

I/C 2,4,6

,8 2,4,5

,7,8 9

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 6

4 2

1 1

0 TS 0

0 2

2 R6 RX 3

1 1

1 0

NOR 1

1 1

1 1

I/C 3,4,5

,8 4,5,8 7

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 6

4 2

1 1

0 TS 0

0 2

2 R7 RX 3

1 1

1 0

NOR 1

1 1

1 1

I/C 3,4,5

,8 4,5,8 7

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 6

4 2

1 1

0 TS 0

0 2

2

Form 3.4-1 Events and Evolutions Checklist Form 3.4-1 Instructions for the Events and Evolutions Checklist

1.

Mark the applicant license level for each simulator operating test number.

2.

For the set of scenario columns, fill in the associated event number from Form 3.3-1, Scenario Outline, to show the specific event types being used for the applicant while in the assigned crew position for that scenario.

  • Minimums are subject to the instructions in Section C.2, License Level Criteria.

KEY: RX = Reactivity Manipulation; NOR = Normal Evolution; I/C = Instrument/Component Failure; MAJ = Major Transient; Man. Ctrl = Manual Control of Automatic Function; TS = Technical Specification Evaluation; RO = Reactor Operator; SRO-I or I = Instant Senior Reactor Operator; SRO-U or U = Upgrade Senior Reactor Operator; SRO = Senior Reactor Operator; ATC = At the Controls; and BOP = Balance of Plan

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