ML22250A451

Initial Exam 2022-08 Final Outlines

ML22250A451
Person / Time
Site:	South Texas
Issue date:	09/08/2022
From:	Heather Gepford NRC/RGN-IV/DORS/OB
To:	South Texas
References
Download: ML22250A451 (1)

Text

Form 3.2-1 Administrative Topics Outline Rev. 2 Page 1 of 5 Facility: South Texas Project Date of Examination: 8-22-2022 Examination Level: RO SRO Operating Test Number: LOT 26 NRC Exam Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations A1 KA Importance:

Record Operator Logs 2.1.18 RO 3.6 Ability to make accurate, clear, and concise logs, records, status boards, and reports.

D, R Conduct of Operations A2 KA Importance:

Calculate RCS Refill Volume (With Vacuum) 2.1.25 RO 3.9 Ability to interpret reference materials, such as graphs, curves tables, etc.

D, R Equipment Control A3 KA Importance:

Prepare an ECO for Reactor Coolant Filter 1B 2.2.13 RO 4.1 Knowledge of tagging and clearance procedures.

N, R Radiation Control A4 KA Importance:

Determine RWP Requirements for work in RRA (SFP) 2.3.7 RO 3.5 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

D, P, R

Form 3.2-1 Administrative Topics Outline Rev. 2 Page 2 of 5 Facility: South Texas Project Date of Examination: 8-22-2022 Examination Level: RO SRO Operating Test Number: LOT 26 NRC Exam Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations A5 KA Importance:

Determine Close Contact Fuel Assembly Movement 2.1.42 SRO 3.4 Knowledge of new and spent fuel movement procedures.

D, R Conduct of Operations A6 KA Importance:

Review ESF Power Availability 2.1.25 SRO 4.2 Ability to interpret reference materials, such as graphs, curves tables, etc.

D, R Equipment Control A7 KA Importance:

Review an ECO for SFP Skimmer Pump 2.2.13 SRO 4.3 Knowledge of tagging and clearance procedures.

D, R Radiation Control A8 KA Importance:

Approve a Completed Liquid Waste Release Permit 2.3.6 SRO 3.8 Ability to approve release permits.

D, R Emergency Plan A9 KA Importance:

Determine PAR 2.4.44 SRO 4.4 Knowledge of Emergency Plan Protective Action Recommendations.

M, R

Form 3.2-1 Administrative Topics Outline Rev. 2 Page 3 of 5 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

• 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).

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)

Form 3.2-1 Administrative Topics Outline Rev. 2 Page 4 of 5 STP LOT-26 NRC Admin JPM Description RO (A1)

Record Operator Logs Demonstrate the ability to properly record Operator Logs and determine necessary actions for out of specification readings IAW 0PSP03-ZQ-0028, Operator Logs, and 0POP01-ZQ-0022, Plant Operator Shift Routines.

Last Used LOT 23 (A2)

Calculate RCS Refill Volume (With Vacuum)

Demonstrate the ability to determine the amount of water needed to refill the RCS from mid-loop conditions under a vacuum IAW 0POP03-RC-0100, RCS Vacuum Fill, Addendum 3, Determination of RCS Volume to be Filled.

Last Used LOT 21 (A3)

Prepare an ECO for Reactor Coolant Filter 1B Demonstrate the ability to prepare Equipment Clearance Order for Reactor Coolant Filter 1B IAW 0PGP03-ZO-ECO1A, Equipment Clearance Order Instructions.

New (A4)

Determine RWP Requirements for work in RRA (SFP)

Demonstrate the ability to determine Radiation Worker requirements given an RWP & Survey Map and using Reactor Operator knowledge of Fuel Handling activities performed in the Fuel Handling Building.

Last Used LOT 24

Form 3.2-1 Administrative Topics Outline Rev. 2 Page 5 of 5 SRO (A5)

Determine Close Contact Fuel Assembly Movement Demonstrate the ability to determine Close Contact Fuel Assembly movement IAW 0POP02-FH-0001, Refueling Machine Operating Instruction, Addendum 4, Instructions For Close Contact Fuel Assembly Movements, and Addendum 5, Instructions For Moving TO Open Water.

Last Used LOT 23 (A6)

Review ESF Power Availability Demonstrate the ability to perform a proper review of a given surveillance, 0PSP03-EA-0002, ESF Power Availability.

Last Used LOT 22 (A7)

Review an ECO for SFP Skimmer Pump Demonstrate the ability to perform a proper review of an Equipment Clearance Order IAW 0PGP03-ZO-ECO1A, Equipment Clearance Order Instructions.

Last Used Audit 23 (A8)

Approve a Completed Liquid Waste Release Permit Demonstrate the ability to review and approve a Liquid Waste Release Permit IAW 0PSP07-WL-LDP1, Emergency Exposure Controls.

Last Used LOT 23 (A9)

Determine Emergency Plan Protective Action Recommendations Demonstrate the ability to correctly determine an Emergency Plan Protective Action Recommendation given set of conditions and IAW 0EPR03-FM-ALL06, Protective Action Recommendation Decision Flowcharts.

Modified from LOT-23

Form 3.2-2 Control Room/In-Plant Systems Outline Rev. 2 Page 1 of 7 Facility: South Texas Project Date of Examination: 8-22-2022 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 26 NRC System / JPM Title Type Code*

Safety Function Control Room Systems

a. (S1) Reestablish Letdown during ES-11 KA: 004 A4.06 (3.6/3.1)

L,M,S 1

b. (S2) Perform CS Pump Performance Test (CS flow can not be maintained greater than minimum needed, requiring stopping the CS Pump) KA: 026 A2.08 (3.2/3.7)

A,D,S 5

c. (S3) Start RCP & Respond to High Motor Temperature KA: 003 A1.03 (2.6/2.6)

A,D,L,S 4P

d. (S4) Transfer 13.8KV Electrical Bus KA: 062 K4.06 (3.6/3.1)

D,L,S 6

e. (S5) Transfer to Hot Leg Recirculation (LHSI Hot Leg Flow can not be verified requiring realignment to cold leg recirculation) KA: 006 A4.05 (3.9/3.8)

A,L,M,S 3

f. (S6) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8)

EN,L,M,S 2

g. (S7) Respond to FHB Rad Monitor Alarm RT-8035 & 8036 KA:

072 A3.01 (2.9/3.1)

A,D,EN,S 7

h. (S8) Perform CCW Valve Operability Test KA: 008 A4.01 (3.3/3.1)

D,S 8

In-Plant Systems

i. (P1) Fill AFWST using Fire Water KA: 061 A1.04 (3.9/3.9)

E,EN,L,N 4S

j. (P2) Place a 1E Battery Charger in Service (Charger Output Voltage goes high when AC Input Bkr is closed requiring re-opening Bkr) KA: 063 A3.01 (2.7/3.1)

A,M 6

k. (P3) Perform Local Channel Check of RT-8038 KA: 068 A3.02 (3.6/3.6)

A,D,R 9

Form 3.2-2 Control Room/In-Plant Systems Outline Rev. 2 Page 2 of 7 Facility: South Texas Project Date of Examination: 8-22-2022 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 26 NRC System / JPM Title Type Code*

Safety Function Control Room Systems

a. (S1) Reestablish Letdown during ES-11 KA: 004 A4.06 (3.6/3.1)

L,M,S 1

b. (S2) Perform CS Pump Performance Test (CS flow can not be maintained greater than minimum needed, requiring stopping the CS Pump) KA: 026 A2.08 (3.2/3.7)

A,D,S 5

c. (S3) Start RCP & Respond to High Motor Temperature KA: 003 A1.03 (2.6/2.6)

A,D,L,S 4P

d. (S4) Transfer 13.8KV Electrical Bus KA: 062 K4.06 (3.6/3.1)

D,L,S 6

e. (S5) Transfer to Hot Leg Recirculation KA (LHSI Hot Leg Flow can not be verified requiring realignment to cold leg recirculation): 006 A4.05 (3.9/3.8)

A,L,M,S 3

f.

g. (S7) Respond to FHB Rad Monitor Alarm RT-8035 & 8036 KA:

072 A3.01 (2.9/3.1)

A,D,EN,S 7

h. (S8) Perform CCW Valve Operability Test KA: 008 A4.01 (3.3/3.1)

D,S 8

In-Plant Systems

i. (P1) Fill AFWST using Fire Water KA: 061 A1.04 (3.9/3.9)

E,EN,L,N 4S

j. (P2) Place a 1E Battery Charger in Service (Charger Output Voltage goes high when AC Input Bkr is closed requiring re-opening Bkr) KA: 063 A3.01 (2.7/3.1)

A,M 6

k. (P3) Perform Local Channel Check of RT-8038 KA: 068 A3.02 (3.6/3.6)

A,D,R 9

Form 3.2-2 Control Room/In-Plant Systems Outline Rev. 2 Page 3 of 7 Form 3.2-2 Instructions for Control Room/In-Plant Systems Outline

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:

Form 3.2-2 Control Room/In-Plant Systems Outline Rev. 2 Page 4 of 7 Form 3.2-2 Instructions for Control Room/In-Plant Systems Outline (continued)

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 Rev. 2 Page 5 of 7 STP LOT-26 NRC Systems JPM Description Control Room Systems JPMs (S1)

Reestablish Letdown during ES-11 Demonstrate the ability to establish normal letdown flow after an SI in accordance with 0POP05-EO-ES11, SI Termination.

Modified from LOT-23 (S2)

Perform Containment Spray Pump Performance Test Demonstrate the ability to operate the Containment Spray Pumps in accordance with 0POP07-CS-0001, Containment Spray Pump 1A(2A) Functional Test. This is an Alternate Path JPM.

Last used on LOT-22 (S3)

Start RCP and Respond to High Temperature Demonstrate the ability to start a Reactor Coolant Pump and take appropriate action when a Reactor Coolant Pump critical parameter is not within band in accordance with 0POP02-RC-0004, Operation of Reactor Coolant Pumps, and 0POP04-RC-0002, Reactor Coolant Pump Off Normal. This is an Alternate Path JPM.

Last used on LOT-22 (S4)

Transfer 13.8KV Electrical Bus Demonstrate the ability to transfer 13.8KV electrical power from one source of power to another in accordance with 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup.

Last used on LOT-23 (S5)

Transfer to Hot Leg Recirculation Demonstrate the ability to align ECCS Hot Leg Recirculation in accordance with 0POP05-EO-ES14, Transfer to Hot Leg Recirculation. This is an Alternate Path JPM.

Modified from LOT-23 (S6)

Isolate SI Accumulators Demonstrate the ability to isolate SI Accumulators from the RCS by closing the discharge isolation valve and/or depressurizing the accumulator in accordance with 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant. (ROs only)

Modified from LOT-23 (S7)

Respond to FHB Radiation Monitor Alarm Demonstrate the ability to properly align and control FHB HVAC after a high radiation actuation in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response. This is an Alternate Path JPM.

Last used on LOT-21 (S8)

Perform CCW Valve Operability Test Demonstrate the ability to perform a CCW System Valve Operability Surveillance in accordance with 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B) Valve Operability Test.

Last used on LOT-22

Form 3.2-2 Control Room/In-Plant Systems Outline Rev. 2 Page 6 of 7 In Plant Systems JPMs (P1)

Fill AFWST using Fire Water Demonstrate the ability to fill the AFWST from the Fire Water system during a Control Room evacuation with a loss of offsite power in accordance with 0POP04-ZO-0001, Control Room Evacuation, Addendum 9, Filling the AFWST using Fire Water.

New (P2)

Place A 1E Battery Charger in Service Demonstrate the ability to start up a Class 1E Battery Charger in accordance with 0POP02-EE-0001 and respond to a malfunction of the Battery Charger. This is an Alternate Path JPM.

Modified from LOT-21.

(P3)

Perform Local Channel Check of RT-8038 Demonstrate ability to perform a radiation monitor channel check on RT-8038, Liquid Radwaste Release Monitor, in accordance with 0POP02-WL-0100, Liquid Waste Release. This is an Alternate Path JPM.

Last used on LOT-13

Form 3.2-2 Control Room/In-Plant Systems Outline Rev. 2 Page 7 of 7 Scheduling NOTE: All Control Room JPMs will be performed dynamically in the Simulator. JPMs will be performed as follows:

• S1 and S2 one student at a time with S2 going first. All Students

• S3 and S4 performed together with S3 going first. All Students

• S5 and S6 performed by one RO at a time with S6 going first. SROI Only perform S5.

• S7 and S8 performed together with S7 going first. All Students

• P1 - All Students.

• P2 - All Students

• P3 - All Students. RCA

Rev. 1 Page 1 of 10 Form 3.3-1 Scenario Outline Facility: South Texas Project Scenario No.: 1 Op-Test No.: LOT 26 NRC Examiners:

Operators:

Initial Conditions: IC-196

• Mode 1 at 100% Power (IC 196)

Turnover:

• Swap CRE HVAC from Train C to Train A; AFW Pump 11 OOS Critical Tasks:

CT - 16: Trip RCPs CT - 8: Start CCW Pumps Event No.

Malf.

No.

Event Type*

Event Description 1

(0 min)

N/A BOP (N)

SRO (TS,N)

Shift Control Room Envelope HVAC from Train C to Train A. After starting Train A, SPLY AHU 11A trips. (1 minute delay) 2 (10 min) 05-12-04 0

BOP (I,MC)

SRO (I,TS)

SG 1D Controlling NR level channel fails low. LT-0549 3

(30 min) 02-17-01 1

RO (C,MC)

SRO (C)

Pressurizer Pressure Controller setpoint fails -30 psi 4

(45 min) 07-04-03 1

08-12-04 1

RO (R)

BOP (R)

SRO (R)

SGFPT #13 Trips and SGFP #14 fails to start. Crew will down power to 80%.

5 (50 min) 08-12-02 1

RO (C)

SRO (C)

SGFPT #12 trips on overspeed. With two SGFPTs tripped >

85% power the crew is required to trip the Reactor.

6 (N/A)

N/A RO (C,MC)

SRO (C)

Pressurizer PORV 655A leaking and intermediate position 7

(N/A) 02-01-02 0.007 All (M)

SBLOCA on Loop B Cold Leg (Critical Task) (Inserts 30 seconds after SGFPT #11 is tripped in ES01) 8 (N/A) 50-KA-05 1

50-KA-06 1

BOP (C,MC)

SRO (C)

CCW Pumps 1B and 1C fail to Auto Start (Critical Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec, (MC)Manual Control Target Quantitative Attributes (Per Scenario; See ES 3.3.B.2 and Table 3.4-1)

Actual Attributes

1.

Events after EOP entry (1-2) 2

2.

Abnormal events (2-4) 4

3.

Major transients (1-2) 1

4.

EOPs entered/requiring substantive actions (1-2) 1

5.

Entry into a contingency EOP with substantive actions (1 per scenario set) 0

6.

Preidentified critical tasks (>2) 2

Rev. 1 Page 2 of 10 STP LOT-26 NRC Scenario #1 Description Initial Conditions: Unit 1 is in Mode 1 at 100% power. AFW Pump #11 is out of service. The crew will swap Control Room Envelope HVAC from Train C to Train A.

Event 1: As a normal evolution the crew will swap Control Room Envelope HVAC from Train C to Train A using 0POP02-HE-0001, Electrical Auxiliary Building HVAC System.

After starting Train A CRE HVAC, SPLY AHU Fan 11A trips. The crew will secure Train A CRE HVAC and the SRO will address Tech Spec implications (Technical Specification 3.7.7)

Event 2: SG 1D Level Channel, LT-0549, fails low. The crew will respond by taking manual control of SG 1D MFRV using 0POP04-FW-0001, Loss of Steam Generator Level Control. The SRO will address Tech Spec implications. (Technical Specification 3.3.1 & 3.3.2)

Event 3: Pressurizer Pressure Controller setpoint fails -30 psi. PZR pressure will begin to slowly lower. If the crew does not notice the lowering pressure, the low pressure alarm takes 7 minutes. The crew will take manual control of PZR pressure using 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control or Conduct of Operations Chapter 2 step 12.1.10.

Event 4: SGFPT #13 Trips and SGFP #14 fails to start. The crew will begin to lower reactor power to restore feedwater flow using 0POP04-FW-0002, Steam Generator Feed Pump Trip.

Event 5: While reducing Reactor Power, SGFPT #12 trips on overspeed. With two SGFPTs tripped > 85% power the crew will be required to trip the Reactor. The crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection and 0POP05-EO-ES01, Reactor Trip Response.

Event 6: When the reactor trips PZR PORV 655A develops a leak and indicates intermediate. The crew will manually close the PORV and the leak will be isolated.

Event 7:) A SBLOCA will occur on Loop B Cold Leg. The event will insert 30 seconds after SGFPT #11 is tripped in ES01. The leak will require SI to be actuated. The crew will re-enter 0POP05-EO-EO00, Reactor Trip or Safety Injection, and the RCPs will have to be tripped. (Critical Task - 16)

Event 8: When SI is actuated, CCW Pumps 1B and 1C will fail to auto start. The crew will have to manually start CCW Pumps 1B and 1C per 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5. (Critical Task - 8).

Rev. 1 Page 3 of 10 STP LOT-26 NRC Scenario #1 Description Termination: Completion of 0POP05-EO-EO00, Reactor Trip or Safety Injection addendum 5 and 0POP05-EO-EO10 Loss of Reactor or Secondary Coolant Step 1.

Critical Tasks:

• CT - 16; Trip RCPs so that an Orange Path on Core Cooling (CET temperatures

> 707°F) does not occur when forced circulation in the RCS stops.

• CT - 8; Start CCW Pump 1B and CCW Pump 1C prior to completion of 0POP05-EO-EO00 addendum 5.

Source: New NOTE: Detailed description of Critical Tasks will be included in ES Form 3.3-2 Required Operator Actions.

Rev. 1 Page 8 of 10 Form 3.3-1 Scenario Outline Facility: South Texas Project Scenario No.: 4 Op-Test No.: LOT 26 NRC Examiners:

Operators:

Initial Conditions: IC-199

• 95% Power BOL, AFW Pump 11 OOS Turnover:

• Raise power from 95% to 98%

Critical Tasks:

CT13; Manually Trip Main Turbine CT46; Establish RCS Bleed and Feed Event No.

Malf.

No.

Event Type*

Event Description 1

(0 min)

N/A ALL (R)

Raise power from 95% to 98%

2 (15 min) 11-01-02 1

11-01-04 BOP (C,MC)

Open Loop ACW (OLACW) Pump 12 trips, OLACW Pump 11 fails to Auto start 3

(25 min) 02-18-01 1.0 RO (I, MC)

SRO (I)

PZR Level Controller LK-0665 fails to 100%.

4 (35 min) 05-22-02 0.0 BOP (I, MC)

SRO (I, TS)

SG 1B MS-PT-0524 fails low, affecting the in-service steam flow channel for SGWLC 5

(50 min) 02-28-02 1.0 RO(I)

SRO (I, TS)

Cold Leg 1D TT-440B fails high 6

(60 min) 10-06-01 1

ALL (M)

Main Generator Output Breaker trips open causing an automatic or manual reactor trip 7

N/A 06-02-01 1

50-L2-12 1

RO (C)

SRO (C)

Main Turbine fails to auto trip on reactor trip and inadvertent FWI.

(Critical Task) 8 NA 10-11-02 1

RO (C)

SRO (C)

Train B 4160V bus lockout. (On Reactor Trip) 9 N/A 08-02-01 1

08-03-06 1

ALL (M)

AFW Pump 11 OOS, Pump 12 No Power, Pump 13 Trips, Pump 14 over speeds resulting in Loss of Heat Sink and entry into FRH1 (Critical Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec, (MC)Manual Control Target Quantitative Attributes (Per Scenario; See ES 3.3.B.2 and Table 3.4-1)

Actual Attributes

1.

Events after EOP entry (1-2) 3

2.

Abnormal events (2-4) 4

3.

Major transients (1-2) 2

4.

EOPs entered/requiring substantive actions (1-2) 1

5.

Entry into a contingency EOP with substantive actions (1 per scenario set) 1

6.

Preidentified critical tasks (>2) 2

Rev. 1 Page 9 of 10 STP LOT-26 NRC Scenario #4 Description Initial Conditions: 95% power BOL. AFW Pump 11 out of service.

Event 1: After taking the shift, the crew will raise power to 98% using 0POP03-ZG-0005, Plant Startup to 100%, starting at step 7.67.

Event 2: After the reactivity manipulation is satisfied, Open Loop ACW Pump 12 trips and Open Loop Pump 11 fails to auto start. The crew will respond using 0POP09-AN-9M01-D3 or 0POP04-OC-0001, Loss of Open Loop Auxiliary Cooling System. The crew will manually start OLACW Pump 11.

Event 3: After OLACW Pump 11 is started or at examiners discretion, PZR level controller LK-0665 output fails to 100%. The crew will respond using 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control. The crew will take manual control of pressurizer level and adjust to return level to setpoint.

Event 4: After the crew has control of PZR level or at examiners discretion, MS-PT-0524 fails low. This transmitter provides density compensation to the selected channel of Steam Flow for SGWLC for S/G 1B which will indicate low. The crew will respond to the failure using 0POP04-FW-0001, Loss of Steam Generator Level Control. The crew will take manual control of S/G 1 B level control and restore 1B level select an operable steam flow channel and then place level control back in auto. The SRO will address TS implications (TS 3.3.1, 3.3.2)

Event 5: After Technical Specifications have been addressed or at the examiners discretion, Cold Leg 1D RTD TT-440B fails high. This affects the 1B loop Tavg and Delta T indications. The crew will respond using 0POP04-RP-0004, Failure of RCS Loop RTD Protection Channel. The crew will deselect the failed channel. The SRO will address Technical Specification implications (TS 3.3.1, 3.3.2)

Event 6-9: The Main Generator Output breaker opens causing an automatic or manual reactor trip. The Main Turbine fails to Auto trip on the Generator breaker opening or the reactor trip requiring manual actions to trip the turbine. An inadvertent FWI occurs on the reactor trip. 4160 V Bus E1B also deenergizes and locks out on the reactor trip.

When AFW is initiated AFW Pump 13 trips on overcurrent and AFW Pump 14 trip on overspeed. When immediate actions have been verified the crew should transition to ES01, Reactor Trip Response and commence monitoring Critical Safety Functions. The crew should note a red path condition on Heat Sink and transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink. (Critical Task 13, 46)

Rev. 1 Page 10 of 10 STP LOT 26 NRC Scenario #4 Description Termination: Scenario may be terminated after RCS Bleed and Feed has been established.

Critical Tasks:

• CT-13; Manually Trip the Main Turbine

• CT-46; Initiate RCS Feed and Bleed Source: New NOTE: Detailed description of Critical Tasks will be included in ES Form 3.3-2 Required Operator Actions.

STPNOC LOT 26 NRC Written Exam Outline - RO Page 1 of 12 Rev 2 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 Facility: South Texas Project Date of Exam: 9/8/2022 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Total A2 G

Total

1.

Emergency and Abnormal Plant Evolutions 1

3 2 3

N/A 3 4 N/A 3

18 2

1 1 2

2 1 1

8 Tier Totals 4 3 5

5 5 4

26

2.

Plant Systems 1

3 3 3

3 2 2 2 2 2 3

3 28 2

1 1 1

1 1 1 1 0 1 0

1 9

Tier Totals 4 4 4

4 3 3 3 2 3 3

4 37

3.

Generic Knowledge and Abilities Categories CO EC RC EM 6

CO EC RC EM 2

2 1

1

4. Theory Reactor Theory Thermodynamics 6

3 3

STPNOC LOT 26 NRC Written Exam Outline - RO Page 2 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 1 E/APE # / Name K1 K2 K3 A1 A2 G

K/A IR 000007 (EPE 7) Reactor Trip / 1 X

Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7 / 45.7)

EK2.02 Breakers, relays and disconnects 2.6 1

000008 (APE 8) Pressurizer Vapor Space Accident / 3 X

Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space Accident: (CFR 41.7 / 45.5 / 45.6)

AA1.03 Turbine bypass in manual control to maintain header pressure 2.8 2

000009 (EPE 9) Small Break LOCA / 3 X

Knowledge of the operational implications of the following concepts as they apply to the small break LOCA: (CFR 41.8 / 41.10 / 45.3)

EK1.01 Natural circulation and cooling, including reflux boiling 4.2 3

000011 (EPE 11) Large Break LOCA / 3 X

Ability to determine or interpret the following as they apply to a Large Break LOCA: (CFR 43.5 / 45.13)

EA2.05 Significance of charging pump operation 3.3 4

000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X

Ability to operate and / or monitor the following as they apply to l the Loss of Reactor Coolant Makeup:

(CFR 41.7 / 45.5 / 45.6)

AA1.03 PZR level trend 3.2 5

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

Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: (CFR 41.5,41.10 / 45.6 /

45.13)

AK3.03 Immediate actions contained in EOP for Loss of RHRS 3.9 6

000026 (APE 26) Loss of Component Cooling Water / 8 X

2.4.47 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 7

000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X

Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.5,41.10 /

45.6 / 45.13)

AK3.03 Actions contained in EOP for Pzr PCS malfunction 3.7 8

000029 (EPE 29) Anticipated Transient Without Scram / 1 X

Knowledge of the operational implications of the following concepts as they apply to the ATWS:

(CFR 41.8 / 41.10 / 45.3)

EK1.03 Effects of boron on reactivity 3.6 9

000038 (EPE 38) Steam Generator Tube Rupture / 3 X

Ability to determine or interpret the following as they apply to a SGTR: (CFR 43.5 / 45.13)

EA2.01 When to isolate one or more S/Gs 4.1 10 000040 (APE 40) Steam Line Rupture / 4 X

2.2.44 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) 4.2 11

STPNOC LOT 26 NRC Written Exam Outline - RO Page 3 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 1 E/APE # / Name K1 K2 K3 A1 A2 G

K/A IR (W E12) Uncontrolled Depressurization of All Steam Generators / 4 X

Knowledge of the interrelations between the (Uncontrolled Depressurization of all Steam Generators) and the following: (CFR: 41.7 / 45.7)

EK2.2 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

3.6 12 000054 (APE 54) Loss of Main Feedwater

/4 X

Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW):

(CFR 41.7 / 45.5 / 45.6)

AA1.01 AFW controls, including the use of alternate AFW sources 4.5 13 000055 (EPE 55) Station Blackout / 6 X

Ability to determine or interpret the following as they apply to a Station Blackout: (CFR 43.5 / 45.13)

EA2.04 Instruments and controls operable with only dc battery power available 3.7 14 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X 2.4.1 Knowledge of EOP entry conditions and immediate action steps. (CFR: 41.10 / 43.5 / 45.13) 4.6 15 000058 (APE 58) Loss of DC Power / 6 X

Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 /

45.13)

AA2.01 That a loss of dc power has occurred; verification that substitute power sources have come on line 3.7 16 000062 (APE 62) Loss of Nuclear Service Water / 4 X

Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4, 41.8 / 45.7 )

AK3.04 Effect on the nuclear service water discharge flow header of a loss of CCW 3.5 17 000065 (APE 65) Loss of Instrument Air / 8 000077 (APE 77) Generator Voltage and (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 X

Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation)

(CFR: 41.8 / 41.10 / 45.3)

EK1.1 Components, capacity, and function of emergency systems.

3.7 18 (W E05) Loss of Secondary Heat Sink / 4 K/A Category Totals:

3 2

3 3

4 3

Group Point Total:

18

STPNOC LOT 26 NRC Written Exam Outline - RO Page 4 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 2 E/APE # / Name K1 K2 K3 A1 A2 G

K/A Topic(s)

IR 000001 (APE 1) Continuous Rod Withdrawal / 1 X

Knowledge of the interrelations between the Continuous Rod Withdrawal and the following: (CFR 41.7 / 45.7)

AK2.06 T-ave./ref. deviation meter 3.0*

19 000003 (APE 3) Dropped Control Rod /

1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration /

1 000028 (APE 28)

Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 X

Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: (CFR 41.5,41.10 / 45.6 / 45.13)

AK3.07 Actions contained in EOP for S/G tube leak 4.2 20 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 000067 (APE 67) Plant Fire on Site / 8 000068 (APE 68 A06) Control Room Evacuation / 8 000069 (APE 69) Loss of Containment Integrity / 5 X

Ability to operate and / or monitor the following as they apply to the Loss of Containment Integrity:

(CFR 41.7 / 45.5 / 45.6)

AA1.01 Isolation valves, dampers, and electropneumatic devices 3.5 21 (W E14) High Containment Pressure /

5 000074 (EPE 74) Inadequate Core Cooling / 4 (W E06) Degraded Core Cooling / 4 X

Knowledge of the reasons for the following responses as they apply to the (Degraded Core Cooling) (CFR: 41.5 / 41.10, 45.6,45.13)

EK3.3 Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

4.0 22 (W E07) Saturated Core Cooling / 4 000076 (APE 76) High Reactor Coolant Activity / 9 X 2.4.11 Knowledge of abnormal condition procedures. 4.0 23 000078 (APE 78*) RCS Leak / 3

STPNOC LOT 26 NRC Written Exam Outline - RO Page 5 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 2 E/APE # / Name K1 K2 K3 A1 A2 G

K/A Topic(s)

IR (W E01) Rediagnosis / 3 (W E02) SI Termination / 3 X

Knowledge of the operational implications of the following concepts as they apply to the (SI Termination) (CFR: 41.8 / 41.10, 45.3)

EK1.1 Components, capacity, and function of emergency systems.

3.2 24 (W E13) Steam Generator Overpressure / 4 X

Ability to determine and interpret the following as they apply to the (Steam Generator Overpressure)

(CFR: 43.5 / 45.13)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

2.9 25 (W E15) Containment Flooding / 5 X

Ability to operate and / or monitor the following as they apply to the (Containment Flooding) (CFR:

41.7 / 45.5 / 45.6)

EA1.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

2.9 26 (W E16) High Containment Radiation /9 (W E03) LOCA Cooldown and Depressurization / 4 (W E09) Natural Circulation Operations /

4 (W E10) Natural Circulation with Steam Void in Vessel with/without Reactor Vessel Level Indicating System / 4 (W E08) Pressurized Thermal Shock / 4 K/A Category Point Totals:

1 1

2 2

1 1

Group Point Total:

8

STPNOC LOT 26 NRC Written Exam Outline - RO Page 6 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 003 (SF4P RCP) Reactor Coolant Pump X

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

A4.02 RCP motor parameters 2.9 27 004 (SF1; SF2 CVCS) Chemical and Volume Control X

Knowledge of the operational implications of the following concepts as they apply to the CVCS: (CFR: 41.5/45.7)

K5.37 Effects of boron saturation on ion exchanger behavior 2.6 28 005 (SF4P RHR) Residual Heat Removal X

Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.01 Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation 2.7 29 006 (SF2; SF3 ECCS)

Emergency Core Cooling X

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5 / 45.5)

A1.02 Boron concentration in accumulator, boron storage tanks 3.0 30 007 (SF5 PRTS)

Pressurizer Relief/Quench Tank X

Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: (CFR: 41.7 / 45.6)

K3.01 Containment 3.3 31 008 (SF8 CCW) Component Cooling Water X

Ability to monitor automatic operation of the CCWS, including: (CFR: 41.7 / 45.5)

A3.04 Requirements on and for the CCWS for different conditions of the power plant 2.9 32 010 (SF3 PZR PCS)

Pressurizer Pressure Control X

Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.06 CVCS 2.9 33 012 (SF7 RPS) Reactor Protection X

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.1 34 013 (SF2 ESFAS)

Engineered Safety Features Actuation X

Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7 / 45.5 to 45.8)

K6.01 Sensors and detectors 2.7*

35 022 (SF5 CCS) Containment Cooling X

Knowledge of power supplies to the following:

(CFR: 41.7)

K2.01 Containment cooling fans 3.0*

36 026 (SF5 CSS) Containment Spray X

Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9

/ 45.7 to 45.8)

K1.01 ECCS 4.2 37 039 (SF4S MSS) Main and Reheat Steam X

Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5 / 45.7)

K5.08 Effect of steam removal on reactivity 3.6 38

STPNOC LOT 26 NRC Written Exam Outline - RO Page 7 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 059 (SF4S MFW) Main Feedwater X

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including: (CFR: 41.5 / 45.5)

A1.03 Power level restrictions for operation of MFW pumps and valves 2.7*

39 061 (SF4S AFW)

Auxiliary/Emergency Feedwater X

Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: (CFR: 41.7 / 45.7)

K6.01 Controllers and positioners 2.5 40 062 (SF6 ED AC) AC Electrical Distribution X

Knowledge of bus power supplies to the following: (CFR: 41.7)

K2.01 Major system loads 3.3 41 063 (SF6 ED DC) DC Electrical Distribution X

Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 /

45.3 / 45.13)

A2.01 Grounds 2.5 42 064 (SF6 EDG) Emergency Diesel Generator X

Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

K4.08 ED/G fuel isolation valves 2.9*

43 073 (SF7 PRM) Process Radiation Monitoring X

Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

K4.01 Release termination when radiation exceeds setpoint 4.0 44 076 (SF4S SW) Service Water X

2.2.39 Knowledge of less than or equal to one-hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2 / 45.13) 3.9 45 078 (SF8 IAS) Instrument Air X

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

A4.01 Pressure gauges 3.1 46 103 (SF5 CNT) Containment X

Knowledge of the effect that a loss or malfunction of the containment system will have on the following: (CFR: 41.7 / 45.6)

K3.03 Loss of containment integrity under refueling operations 3.7 47 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X

Ability to monitor automatic operation of the PRTS, including: (CFR: 41.7 / 45.5)

A3.01 Components which discharge to the PRT 2.7*

48 026 (SF5 CSS) Containment Spray X

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

A4.01 CSS controls 4.5 49 039 (SF4S MSS) Main and Reheat Steam X 2.1.27 Knowledge of system purpose and/or function. (CFR: 41.7) 3.9 50 062 (SF6 ED AC) AC Electrical Distribution X

Knowledge of the physical connections and/or cause-effect relationships between the ac distribution system and the following systems:

(CFR: 41.2 to 41.9)

K1.03 DC distribution 3.5 51

STPNOC LOT 26 NRC Written Exam Outline - RO Page 8 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 064 (SF6 EDG) Emergency Diesel Generator X

Knowledge of bus power supplies to the following: (CFR: 41.7)

K2.03 Control power 3.2*

52 076 (SF4S SW) Service Water X

Knowledge of the effect that a loss or malfunction of the SWS will have on the following: (CFR: 41.7 / 45.6)

K3.07 ESF loads 3.7 53 078 (SF8 IAS) Instrument Air X

Knowledge of IAS design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7)

K4.01 Manual/automatic transfers of control 2.7 54 K/A Category Point Totals:

3 3

3 3

2 2

2 2

2 3

3 Group Point Total:

28

STPNOC LOT 26 NRC Written Exam Outline - RO Page 9 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant X

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including: (CFR: 41.5 / 45.7)

A1.04 Subcooling Margin 3.9 55 011 (SF2 PZR LCS)

Pressurizer Level Control X

Knowledge of bus power supplies to the following: (CFR: 41.7)

K2.02 PZR heaters 3.1 56 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation X

Knowledge of the operational implications of the following concepts as they apply to the NIS: (CFR: 41.5 / 45.7)

K5.05 Criticality and its indications 4.1 57 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) InCore Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control X

Knowledge of the effect that a loss or malfunction of the HRPS will have on the following: (CFR: 41.7 / 45.6)

K3.01 Hydrogen concentration in containment 3.3 58 029 (SF8 CPS) Containment Purge X

Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.01 Maintenance or other activity taking place inside containment 2.9 59 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS)

FuelHandling Equipment 035 (SF 4P SG) Steam Generator X

2.2.38 Knowledge of conditions and limitations in the facility license. (CFR: 41.7 /

41.10 / 43.1 / 45.13) 3.6 60 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X

Knowledge of the effect of a loss or malfunction on the following will have on the SDS: (CFR: 41.7 / 45.7)

K6.03 Controller and positioners, including ICS, S/G, CRDS 2.7 61 045 (SF 4S MTG) Main Turbine Generator X

Knowledge of the physical connections and/or cause-effect relationships between the MT/G system and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.18 RPS 3.6 62 055 (SF4S CARS) Condenser Air Removal

STPNOC LOT 26 NRC Written Exam Outline - RO Page 10 of 12 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste X

Knowledge of design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7)

K4.01 Safety and environmental precautions for handling hot, acidic, and radioactive liquids 3.4 63 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:

1 1 1 1 1 1 1 0 1 0 1 Group Point Total:

9

STPNOC LOT 26 NRC Written Exam Outline - RO Page 11 of 12 Rev 2 Facility: South Texas Project Date of Exam: 9/8/2022 Form 4.1-COMMON Generic Knowledge and Abilities - Tier 3 Category K/A #

Topic RO SRO-Only IR IR

1.

Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all modes of plant operation. (CFR: 41.10 / 45.13) 4.1 64 2.1.5 Ability to use procedures related to shift staffing, such as minimum shift complement, overtime limitations, etc. (CFR: 41.10 / 43.5 / 45.12) 3.3 65 Subtotal N/A 2

N/A

2.

Equipment Control 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. (CFR: 41.10 /

43.5 / 45.13) 2.6 66 2.2.43 Knowledge of the process used to track inoperable alarms. (CFR: 41.10 / 43.5 / 45.13) 3.0 67 Subtotal N/A 2

N/A

3.

Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.(CFR: 41.12 / 43.4 / 45.10) 3.2 68 Subtotal N/A 1

N/A

4.

Emergency Procedures/

Plan 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 69 Subtotal N/A 1

N/A Tier 3 Point Total 6

Theory - Tier 4 Category K/A #

Topic RO IR Reactor Theory 6

192002 Neutron Life Cycle - K1.13 Calculate shutdown margin using procedures and given plant parameters.

3.5*

70 6

192005 Control Rods (Full and/or Part Length) - K1.03 Predict direction of change in reactor power for a change in control rod position.

3.5 71 6

192007 Fuel Depletion and Burnable Poisons - K1.04 Describe how and why boron concentration changes over core life.

3.1 72 Subtotal N/A 3

Thermodynamics 6

193001 Thermodynamic Units and Properties - K1.03 Describe how pressure and level sensing instruments work.

2.6 73 6

193005 Thermodynamic Cycles - K1.03 Describe how changes in secondary system parameter affect thermodynamic efficiency.

2.5 74 6

193006 Fluid Statics and Dynamics - K1.12 Explain why flow measurements must be corrected for density changes.

2.5 75 Subtotal N/A 3

Tier 4 Point Total 6

STPNOC LOT 26 NRC Written Exam Outline - RO Page 12 of 12 Rev 2 Form 4.1-1 Record of Rejected Knowledge and Abilities Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.

Tier/Group Randomly Selected K/A Reason for Rejection 1/1 000054 AA1.03 Could not write an operationally relevant question against this K/A.

Replaced with K/A 00054 AA1.01 1/2 000076 2.1.30 Could not write an operationally relevant question against this K/A.

Replaced with K/A 2.4.11.

1/2 CE E06 EK3.3 K/A does not apply to a Westinghouse plant. STP is a Westinghouse plant. Replaced with K/A W E06 EK3.3.

3/1 2.1.45 K/A does not allow for writing an operationally relevant question that is generic in nature (administrative vs. Tier 1, 2, or 4. Replaced with K/A 2.1.5.

4 1920005 K1.05 K/A had low operational validity. Tested definitions of Integral and differential rod worth. Replaced with K/A 192005 K1.03.

3/3 2.3.7 Question created for this topic had overlap with an admin JPM.

Could not write an operationally valid question outside of the original question. Replaced with K/A 2.3.4.

1/1 027 AK3.04 027 AK3.04 is a Tier 4 type K/A. Replaced K/A as requested by the Chief Examiner. Replaced with K/A 027 AK3.03.

1/1 038 EA2.04 Could not write an operationally valid question on theis K/A that wouldnt be an LOD 1. Replaced with K/A 038 A2.01.

STPNOC LOT 26 NRC Written Exam Outline - RO Page 13 of 12 Rev 2

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 1 of 11 Rev 2 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 Facility: South Texas Project Date of Exam: 9/8/2022 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

N/A N/A 3

3 6

2 2

2 4

Tier Totals 5

5 10

2.

Plant Systems 1

3 2

5 2

1 1

1 3

Tier Totals 5

3 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM CO EC RC EM 7

2 2

1 2

4. Theory Reactor Theory Thermodynamics

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 2 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 1 E/APE # / Name K1 K2 K3 A1 A2 G

K/A IR 000007 (EPE 7;) Reactor Trip / 1 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X

Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): (CFR 43.5 / 45.13)

AA2.10 When to secure RCPs on loss of cooling or seal injection 3.7 76 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 000025 (APE 25) Loss of Residual Heat Removal System / 4 000026 (APE 26) Loss of Component Cooling Water / 8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 000040 (APE 40) Steam Line Rupture / 4 (W E12) Uncontrolled Depressurization of All Steam Generators / 4 000054 (APE 54) Loss of Main Feedwater

/4 000055 (EPE 55) Station Blackout / 6 000056 (APE 56) Loss of Offsite Power / 6 X

Ability to determine and interpret the following as they apply to the Loss of Offsite Power: (CFR: 43.5

/ 45.13)

AA2.24 CCW pump ammeter, flowmeter and run indicator 3.1 77 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 000062 (APE 62) Loss of Nuclear Service Water / 4 000065 (APE 65) Loss of Instrument Air / 8 X

Ability to determine and interpret the following as they apply to the Loss of Instrument Air: (CFR: 43.5

/ 45.13)

AA2.08 Failure modes of air-operated equipment 3.3 78 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X 2.1.32 Ability to explain and apply system limits and precautions.(CFR: 41.10 / 43.2 / 45.12) 4.0 79

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 3 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 1 E/APE # / Name K1 K2 K3 A1 A2 G

K/A IR (W E04) LOCA Outside Containment / 3 X

2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. (CFR: 41.10 / 43.5 / 45.13) 4.2 80 (W E11) Loss of Emergency Coolant Recirculation / 4 (W E05) Loss of Secondary Heat Sink / 4 X

2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 /

43.5 / 45.13) 4.3 81 K/A Category Totals:

0 0

0 0

3 3

Group Point Total:

6

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 4 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 2 E/APE # / Name K1 K2 K3 A1 A2 G

K/A Topic(s)

IR 000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod /

1 X

Ability to determine and interpret the following as they apply to the Dropped Control Rod: (CFR: 43.5 /

45.13)

AA2.03 Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements 3.8 82 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration /

1 000028 (APE 28)

Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 X

2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2) 4.2 83 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 X

Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: (CFR: 43.5 / 45.13)

AA2.04 Satisfactory overlap between source-range, intermediate-range and power-range instrumentation 3.6 84 000036 (APE 36; BW/A08) Fuel Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 000067 (APE 67) Plant Fire on Site / 8 000068 (APE 68 A06) Control Room Evacuation / 8 000069 (APE 69) Loss of Containment Integrity / 5 (W E14) High Containment Pressure /

5 000074 (EPE 74) Inadequate Core Cooling / 4 (W E06) Degraded Core Cooling / 4 (W E07) Saturated Core Cooling / 4 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01) Rediagnosis / 3 (W E02) SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 5 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Emergency and Abnormal Plant EvolutionsTier 1/Group 2 E/APE # / Name K1 K2 K3 A1 A2 G

K/A Topic(s)

IR (W E16) High Containment Radiation /9 (W E03) LOCA Cooldown and Depressurization / 4 (W E09) Natural Circulation Operations /

4 X 2.4.18 Knowledge of the specific bases for EOPs.

(CFR: 41.10 / 43.1 / 45.13) 4.0 85 (W E10) Natural Circulation with Steam Void in Vessel with/without Reactor Vessel Level Indicating System / 4 (W E08) Pressurized Thermal Shock / 4 K/A Category Point Totals:

0 0

0 0

2 2

Group Point Total:

4

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 6 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 003 (SF4P RCP) Reactor Coolant Pump X

Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5/ 45.3 / 45/13)

A2.01 Problems with RCP seals, especially rates of seal leak-off 3.9 86 004 (SF1; SF2 CVCS) Chemical and Volume Control 005 (SF4P RHR) Residual Heat Removal 006 (SF2; SF3 ECCS)

Emergency Core Cooling 007 (SF5 PRTS)

Pressurizer Relief/Quench Tank 008 (SF8 CCW) Component Cooling Water X

2.2.37 Ability to determine operability and/or availability of safety related equipment. (CFR:

41.7 / 43.5 / 45.12) 4.6 87 010 (SF3 PZR PCS)

Pressurizer Pressure Control 012 (SF7 RPS) Reactor Protection 013 (SF2 ESFAS)

Engineered Safety Features Actuation X

Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 /

45.3 / 45.13)

A2.05 Loss of dc control power 4.2 88 022 (SF5 CCS) Containment Cooling 026 (SF5 CSS) Containment Spray 039 (SF4S MSS) Main and Reheat Steam 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)

Auxiliary/Emergency Feedwater X

Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.06 Back leakage of MFW 3.0 89 062 (SF6 ED AC) AC Electrical Distribution 063 (SF6 ED DC) DC Electrical Distribution X 2.2.40 Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 / 45.3) 4.7 90

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 7 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 064 (SF6 EDG) Emergency Diesel Generator 073 (SF7 PRM) Process Radiation Monitoring 076 (SF4S SW) Service Water 078 (SF8 IAS) Instrument Air 103 (SF5 CNT) Containment K/A Category Point Totals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

5

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 8 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS)

Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) InCore Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS)

FuelHandling Equipment X

Knowledge of design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7)

K4.03 Overload protection 3.3 91 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 9 of 11 Rev 2 Form 4.1-PWR PWR Examination Outline Plant SystemsTier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring X

2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (CFR: 41.10 / 43.5 / 45.11) 4.4 92 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection X

Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR:

41.5 / 43.5 / 45.3 / 45.13)

A2.02 Low FPS header pressure 3.3 93 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:

0 0 0 1 0 0 0 1 0 0 1 Group Point Total:

3

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 10 of 11 Rev 2 Facility: South Texas Project Date of Exam: 9/8/2022 Form 4.1-COMMON Generic Knowledge and Abilities - Tier 3 Category K/A #

Topic RO SRO-Only IR IR

1.

Conduct of Operations 2.1.15 Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc. (CFR:

41.10 / 45.12) 3.4 94 2.1.35 Knowledge of the fuel-handling responsibilities of SROs. (CFR: 41.10 / 43.7) 3.9 95 Subtotal N/A N/A 2

2.

Equipment Control 2.2.6 Knowledge of the process for making changes to procedures. (CFR: 41.10 / 43.3 / 45.13) 3.6 96 2.2.12 Knowledge of surveillance procedures. (CFR: 41.10 /

45.13) 4.1 97 Subtotal N/A N/A 2

3.

Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 3.7 98 Subtotal N/A N/A 1

4.

Emergency Procedures/

Plan 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

(CFR: 41.7 / 41.10 / 43.5 / 45.12) 4.4 99 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. (CFR: 41.10 / 43.5 / 45.11) 4.5 100 Subtotal N/A N/A 2

Tier 3 Point Total 7

STPNOC LOT 26 NRC Written Exam Outline - SRO Page 11 of 11 Rev 2 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 2/1 003 A2.05 Could not write a psychometrically sound question at the SRO level for this K/A. Replaced with 003 A2.01 3/2 2.2.4 Could not write a psychometrically sound question at the SRO level for this K/A. Replaced with 2.2.6