Text

301 Exam Administrative Items (2 Year Delayed release)(ADAMS-2A-3)
	ML22350A469
Person / Time
Site:	Hope Creek
Issue date:	12/16/2022
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	Download: ML22350A469 (1)
	v • d • e

Form 3.2-1 Administrative Topics Outline A1a This is a Modified Bank JPM. The operator will be told the plant tripped from 100% RTP when a loss of offsite power occurred, the crew is in EOP-ES-0.2, Natural Circulation Cooldown, GARDEL is NOT available, Boric Acid Storage Tank B is aligned to blend with level at 90% and the TSC is NOT staffed. The operator will be provided with the Unit Status Board, a copy of EOP-ES-0.2, the Station Curve Book and the Reactor Operating Data (ROD) Manual. The operator will be directed to calculate the boron addition necessary to achieve CSD boron concentration and complete the applicable sections of EOP-ES-0.2, Attachment 1, Boration Using MOV-350. The operator will be expected to use the ROD Manual to determine that 1884.3 gallons of Boric Acid is required to achieve the required 768 ppm change in Boron Concentration.

A1b This is a Bank JPM. This JPM is to be performed in the Simulator. The operator will be told that they are the On-Shift BOP with no equipment out of service and the plant at 100%

RTP. The operator will be directed to perform OST-010, Power Range Calorimetric During Power Operations, and to adjust any NIs found to be +/-0.5% out of tolerance. The operator will be expected to correctly perform the OST-010 and determine that the gain on NI-42 is required to be adjusted to 100% power. The operator is expected to adjust the gain on NI-42 to 100% power and complete the necessary paperwork to support that adjustment.

A2 This is a Bank JPM. The operator will be told that the plant is at 100% power, that they are the Reactor Operator, that OST-051, Reactor Coolant System Leakage Evaluation, is in progress, and that the plant has remained at steady state, with no automatic makeups for one hour. The operator will be provided with a final set of monitored parameters and directed to complete OST-051, and to identify any administrative limits, if any, that are Facility: H.B. Robinson Date of Examination: October 3, 2022 Examination Level: RO Operating Test Number: 2022-301 Administrative Topic Activity and Associated K/A Type Code Conduct of Operations G2.1.25, Ability to interpret reference materials, such as graphs, curves, and tables (RO 3.9)

Calculate the boron addition required prior to initiating a natural circulation cooldown to CSD M, R Conduct of Operations G2.1.19, Ability to use available indications to evaluate system or component status (RO 3.9)

Power range calorimetric during power operation D, S Equipment Control G2.2.12, Knowledge of surveillance procedures (RO 3.7)

Determine leak rate IAW OST-051 D, P, R

Radiation Control G2.3.12, Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters (RO 3.2)

Calculate the maximum permissible stay time with emergency dose limits D, R ML22350A469

exceeded. The operator will be expected to complete Attachment 1 and 2 of OST-051 IAW the attached KEY and identify that the Unidentified RCS Leakage exceeds that allowed by Technical Specification LCO 3.4.13.

A3 This is a Bank JPM. The operator will be told that an event is in progress that has resulted in an ALERT being declared and a Containment Entry would enhance the pressure control of the plant but is NOT required to protect valuable plant equipment. The operator will be presented with a series of tasks to be performed and the time that it took to complete the first two tasks. The operator will be expected to determine the dose received by the operator preforming the first 2 tasks and then calculate the amount of time that they would have to complete task #3 without exceeding the applicable Emergency Dose Limit.

Form 3.2-1 Administrative Topics Outline A1a This is a Bank JPM. The operator will be told that the plant is operating at 100% power and that ERFIS is OOS. The operator will be provided with Power Range Excore Nuclear Instrumentation indicated and normalized detector currents, and directed to calculate Quadrant Power Tilt Ratio, and based on the QPTR calculation, write down all Technical Specification CONDITIONs, REQUIRED ACTIONs, and COMPLETION TIMEs, if any, that would be required. The operator will be expected to calculate QPTR in accordance with FMP-007, Quadrant Power Tilt, identify that Technical Specification LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR), is NOT met, and identify that all six ACTIONs (A.1-A.6) must be taken for Condition A of LCO 3.2.4, including the maximum permitted power level of 97-98.2%.

A1b This is a Modified Bank JPM. The operator will be provided a set of Hot Ops Logs to review following the 0800 readings. The operator will be directed to review the logs in accordance with AD-OP-ALL-0112, Operations Log Keeping and Chart Recorders, and AD-OP-ALL-1000, Conduct of Operations. The operator is expected to identify that C SI Accumulators recorded pressure is high out of specification on both the 0400 and 0800 reading. The operator will identify that at 0800 SR 3.5.1.3 is not met and ITS 3.5.1 Condition C is required to restore the accumulator to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The operator will also identify that Refueling Water Storage Tank level is low out of Facility: H.B. Robinson Date of Examination: October 3, 2022 Examination Level: SRO Operating Test Number: 2022-301 Administrative Topic Activity and Associated K/A Type Code Conduct of Operations G2.1.7, Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation (SRO 4.7)

Calculate QPTR D, R Conduct of Operations G2.1.18, Ability to make accurate, clear, and concise logs, records, status boards, and reports (SRO 3.8)

Review a set of Hot Ops Logs / ERFIS Out of Service M, R Equipment Control G2.2.38, Knowledge of conditions and limitations in the facility license (SRO 4.5)

Determine if mode change is permissible D, R Radiation Control G2.3.6, Ability to approve liquid or gaseous release permits (SRO 3.8)

Approve a Waste Gas Release Permit D, P, R Emergency Plan G.2.4.41, Knowledge of the emergency action level thresholds and classifications (SRO Only) (SRO 4.6)

Perform an Emergency Action Level Classification M, R

specification and determine that ITS 3.5.4 Condition B is applicable to restore the RWST to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Lastly the candidate will identify that the Isolation Seal Water Storage Tank pressure is low out of specification per the logs. The operator will identify that ITS 3.6.8 Condition A is applicable to restore the tank to 46.2 psig IAW SR 3.6.8.1 within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

A2 This is a Bank JPM. The operator will be told that the plant is in Mode 5, returning from a refueling outage, that the RCS temperature is 165°F and there is a bubble in the PZR, and that RHR Loop A is maintaining RCS temperature. The operator will be provided with an Inoperable Equipment List and directed to complete Attachment 1 of GP-002, Cold Shutdown to Hot Subcritical at No Load Tavg, 200°F to 350°F (MODE 4) MEL, that was started on the previous shift and to determine if any Mode 4 restrictions exists. The operator will be expected to complete Attachment 1 and determine that the Mode change cannot occur with current plant conditions, per the attached KEY.

A3 This is a Bank JPM. The operator will be told that the plant is in Mode 1 at 100% power, and that a Waste Gas Release Permit for the B WGDT has been presented to the Shift Manager for review and approval. The operator will be provided with a WGDT Release Permit and directed to review and approve the Waste Gas Release Permit, or to identify all issues found which would prevent approval. The operator will be expected to review the WGDT Release Permit and identify that it cannot be approved because (1) it has been written for the wrong WGDT and (2) the R14C setpoint is less conservative than required.

This was used on the ILC-21 exam and was randomly reselected for reuse on this exam.

A4 This is a Modified Bank JPM. The operator will be given the necessary plant conditions to classify that an emergency event has occurred. This classification is time critical and is required to be determined within 15 minutes of the onset of the event. The operator will be expected to classify the event as a General Emergency, due to a Loss of the Fuel Cladding Barrier, Loss of the RCS Barrier, and a Potential Loss of the Containment Barrier.

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: H.B. Robinson Date of Examination: October 3, 2022 Exam Level: RO (only) / SRO-I / SRO-U Operating Test Number: 2022-301 System/JPM Title Type Code Safety Function Control Room Systems

a. 001 Control Rod Drive System [001 A1.06 (4.0)]

Reactor Startup with Ejected Control Rod A, D, L, S 1

b. 004 PZR Level Control Malfunction [APE 028 AA1.05 (3.1)]

Place Excess Letdown in Service D, P, S 2

c. 010 Pressurizer Pressure Control System ((010 A2.02 (4.5/3.8)]

Pressurizer Pressure Control Malfunction D, S 3

d. 076 Service Water [076 A1.03 (3.3)]

Restore SW Flow/Pressure in AOP-022 A, N, S 4S

e. 026 Containment Spray System [026 A4.05 (4.0)]

Secure Containment Spray after Actuation D, EN, L, S 5

f. 062 AC Electrical Distribution System [062 A4.07 (3.7)]

Transfer of Auxiliary Electrical Load from UAT to SUTs D, P, S 6

g. 015 Nuclear Instrumentation System [015 A4.03 (3.7)]

Remove Source Range Instrument from Service D, L, S 7

h. 086 Fire Protection System [086 A2.05 (4.0/3.8)]

Control Room response to fire IAW AOP-041 M, S 8

In-Plant Systems

i. 068 Control Room Evacuation [APE 068 AA1.06 (3.7)]

Respond to Control Room Inaccessibility D, E, L, R 2

j. 061 AFW [061 A2.04 (4.1/4.0)]

Rapid Alignment of AFW Pump C as directed by EOP network A, D, E, L, P 4S

k. 064 Emergency Diesel Generators [064 A2.26 (3.8/4.2)]

Restore AC Power to an EDG Control Panel A, D, E, R 6

JPM A This is a Bank JPM. The operator will be told that the plant is stabilized at 2% power, that the RCS is at normal operating temperature and pressure, and that a plant startup is in progress IAW GP-003, Normal Plant Startup From Hot Shutdown to Critical, and complete through Step 6.4.6. They will also be told that they are the OATC, and that the BOP is temporarily outside the Control Room. The operator will be directed to pull control rods to stabilize reactor power between 3-5% by continuing with Step 6.4.7 of GP-003. The operator will be expected to raise reactor power to 3-5% by withdrawing control rods.

Control Bank Rod H-8 will fail, ejecting from the core (Alternate Path) at which time the operator is expected to manually trip the reactor, manually actuate Safety Injection and manually start SI Pumps in response to the degrading plant conditions, and equipment failures.

JPM B This is a Bank JPM. The operator will be told to respond to plant conditions as the OATC with the plant at 100% RTP. The operator will be expected to diagnose that a loss of letdown has occurred when CVC-460A & B inadvertently close, and is expected to respond IAW AOP-003-1, LOSS OF CHARGING OR LETDOWN. The operator is expected to minimize charging pump speed, maintain RCP seal injection flow, control RCS pressure and place Excess Letdown in service IAW Attachment 1 of the AOP-003-1. This JPM was previously used on the ILC-19 NRC exam and was randomly reselected for re-use on this exam.

JPM C This is a Bank JPM. The operator will be told to respond to plant conditions as the OATC with the plant at 100% RTP. The operator will be expected to diagnose and respond to CVC-311, Auxiliary Spray valve failing open, IAW AOP-019, Malfunction of RCS Pressure Control. The operator will be expected to determine that CVC-311 cannot be closed and will have to isolate letdown, secure one charging pump, minimize charging pump speed and close HIC-121 to isolate CVC-311.

JPM D This is a NEW JPM. The operator will be told to respond to plant events as the BOP with the plant at 100% RTP. The operator will be expected to diagnose a service water leak in the Turbine building has occurred based on North and South Service Water Header low pressure alarms, and a report from the field. The operator will respond IAW AOP-022, Loss of Service Water. The operator is expected to shut V6-16C, which will fail to shut (Alternate Path) and then shut V6-16A and V6-16B in order to isolate the service water break. The operator is then expected to recognize that a reactor trip is required, and manually trips the reactor.

JPM E This is a Bank JPM. The operator will be told that a LOCA occurred 32 minutes ago, and that the crew is implementing EOP-E-1, Response to Loss of Primary or Secondary Coolant. The operator will be directed to perform Step 12 of EOP-E-1. The operator will be expected to determine that Containment Spray needs to be terminated, but cannot be terminated until 41 minutes has elapsed since the start of the event; and then after sufficient time has elapsed, secure the Containment Spray System per Step 12 of EOP-E-1.

JPM F This is a Bank JPM. The operator will be told that a plant shutdown is being performed in accordance with GP-006-1, Normal Plant Shutdown from Power Operation to Hot Shutdown, generator gross loading is 100 MWe, and they are the BOP operator. The operator will be directed to transfer Auxiliary Electrical load from the Unit Auxiliary Transformer (UAT) to the Startup Transformers (SUT) with the Unit synchronized to the grid, IAW OP-603, Electrical Distribution, Section 6.2.1. The operator will be expected to

transfer the electrical loading, paralleling across breakers 52/12 and 52/19 and ensuring breakers 52/7 and 52/20 open. This JPM was previously used on the ILC-21 NRC exam and was randomly reselected for re-use on this exam.

JPM G This is a Bank JPM. The operator will be told that the plant is shutdown 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months after a trip from 100% power, and that SR Channel NI-31 has just failed low. The operator will be directed to remove SR Channel NI-31 from service IAW OWP-011, Nuclear Instrumentation.

The operator will be expected to remove SR Channel NI-31 from service IAW NI-1 of OWP-011.

JPM H This is a Modified Bank JPM. The operator will be told to respond to plant conditions as the OATC with the plant at 100% RTP. The operator will be expected to diagnose that a fire in the Containment has occurred and respond IAW AOP-041. The operator will be expected to sound plant alarms, make the plant announcements and isolate the PZR PORVs by closing the Block Valves, RC-535 and RC-536 and isolating power to the PCV-456 and PCV-455C within 10 minutes of the confirmed fire.

JPM I This is a Bank JPM. The operator will be told that a control room evacuation in accordance with AOP-004, Control Room Inaccessibility has been conducted due to a fire in the kitchen, and that the required actions IAW AOP-004 were taken prior to evacuation. The operator will be told that B and C Charging pumps are running. The operator will be directed to perform Attachment 1, Auxiliary Building Operator of AOP-004. The operator will be expected to open breakers on MCCs in the Aux Building, transfer the charging pump suction flowpath to the RWST, place the charging pumps in local control and secure all but one. The operator will be expected to control Pressurizer Level with one charging pump in manual speed control and secure that pump with Pressurizer Level above 73%.

JPM J This is a Bank JPM. The operator will be told that the plant has tripped from 100% power and the EOP Network has been entered. The operator will be directed to perform OP-402, Section 6.2.13, Rapid Alignment of AFW Pump C as Directed by EOP Network.

When aligning the CST as the water source, the operator will determine that DW-285, the Condensate Storage Tank Drain valve is stuck CLOSED (Alternate Path) and cannot be opened. The operator will determine that the CST is not available and proceed to Step 10 to align Deepwell Water. The operator is expected to align the Deepwell water source, start the AFW Diesel Generator and start AFW pump C. This JPM was previously used on the ILC-19 NRC exam and was randomly selected for use.

JPM K This is a Bank JPM. The operator will be told that the plant has experienced a total loss of AC power, and that the crew is implementing EOP-ECA-0.0, Loss of All AC Power. The operator will be directed to locally start the A Emergency Diesel Generator and energize Bus E-1 in accordance with Attachment 5, Restoring AC Power From The EDG(s), of EOP-ECA-0.0. The operator will be expected to attempt a normal local start (Alternate Path), and then locally start the A Emergency Diesel Generator by manually operating the Hand Start Valves; and then after determining that the Control Room cannot close the A Emergency Diesel Generator Output Breaker (Alternate Path), locally close this breaker (52/17B).

License Level Control Room In-Plant Total RO 8

3 11 SRO-I 7

3 10 SRO-U 2 or 3 3 or 2 5

RO SRO-I SRO-U (A)lternate path 4-6 (4) 4-6 (4) 2-3 (2)

(C)ontrol Room (D)irect from bank 9 (9) 8 (8) 4 (3)

(E)mergency or abnormal in-plant 1 (3) 1 (3) 1 (2)

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

(L)ow power/shutdown 1 (5) 1 (4) 1 (2)

(N)ew or (M)odified (must apply to at least one alternate path JPM) 2 (2) 2 (2) 1 (2)

(P)revious two exams (randomly selected) 3 (3) 3 (3) 2 (0)

(R)CA 1 (2) 1 (2) 1 (2)

(S)imulator

1. 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.

2. 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.

Form 3.4-1 Events and Evolutions Checklist Facility: H. B. Robinson Date of Exam: October 3, 2022 Operating Test No.: 2022-301 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios T

O T

A L

M I

1 2

3 4

N (Spare Scenario)

(N/A)

I M

POSITION POSITION POSITION POSITION U

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

M*

RO I

U RO1 SRO-I SRO-U RX 1

1 1

1 0

NOR 4

1 1

I/C 4,6,10 1,2,3,7,9 8

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 4,10 2

1 1

0 TS 0

0 2

2 RO2 SRO-I SRO-U RX 4

1 1

1 0

NOR 1

1 1

I/C 3,5,8,9 5,8 6

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 8,9 5

3 1

1 0

TS 0

0 2

2 RO3 SRO-I SRO-U RX 1

1 1

1 0

NOR 4

1 1

I/C 4,6,10 1,2,3,7,9 8

4 4

2 MAJ 7

6 2

2 2

1 Man. Ctrl 4,10 2

1 1

0 TS 0

0 2

2 RO RX 4

1 1

1 0

SRO-I NOR 1

1 1

1 I/C 3,4,5,6, 8 9 10 5,8 9

4 4

2 MAJ 7

6 2

2 2

1 SRO-U Man. Ctrl 5

1 1

1 0

TS 2,4,5,6 4

0 2

2 RO RX 4

1 1

1 0

SRO-I NOR 1

1 1

2 I/C 3,4,5,6, 8,9,10 5,8 9

4 4

2 MAJ 7

6 2

2 2

1 SRO-U Man. Ctrl 5

1 1

1 0

TS 2,4,5,6 4

0 2

2

Form 3.4-1 Events and Evolutions Checklist Facility: H. B. Robinson Date of Exam: October 3, 2022 Operating Test No.: 2022-301 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios T

O T

A L

M I

1 2

3 4

N (Spare Scenario)

(N/A)

I M

POSITION POSITION POSITION POSITION U

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

M*

RO I

U RO RX 0

1 1

0 SRO-I NOR 4

1 1

I/C 1,2,3,5, 7 8 9 7

4 4

2 MAJ 6

1 2

2 1

SRO-U 1 Man. Ctrl 0

1 1

0 TS 2,5 2

0 2

2 RO RX 0

1 1

0 SRO-I NOR 4

1 1

I/C 1,2,3,5, 7 8 9 7

4 4

2 SRO-U MAJ 6

1 2

2 1

2 Man. Ctrl 0

1 1

0 TS 2,5 2

0 2

2 RO RX 0

1 1

0 SRO-I NOR 1

4 2

1 1

1 I/C 3,5,8,9 1,2,3,5, 7 8 9 11 4

4 2

SRO-U MAJ 7

6 2

2 2

1 3 Man. Ctrl 8,9 2

1 1

0 TS 2,5 2

0 2

2 RO SRO-I SRO-U RX 1

1 0

NOR 1

1 1

I/C 4

4 2

MAJ 2

2 1

Man. Ctrl 1

1 0

TS 0

2 2

RO SRO-I SRO-U RX 1

1 0

NOR 1

1 1

I/C 4

4 2

MAJ 2

2 1

Man. Ctrl 1

1 0

TS 0

2 2

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

Form 2.3-3 Operating Test Review Worksheet (JPMs)

Facility: H. B. Robinson Exam Date: October 3, 2022 1

JPM # or title 2

Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6

U/E/S 7

Explanation LOD REF IC TSK CUE CS TL Calculate the boron addition required prior to initiating a natural circulation cooldown to CSD A

(RO)

N 3

S Power range calorimetric during power operation A

(RO)

N 2

S Determine leak rate IAW OST-051 A

(RO)

N 2

S Calculate the maximum permissible stay time with emergency dose limits A

(RO)

N 2

S Calculate QPTR A

(SRO)

N 2

S Review a set of Hot Ops Logs /

ERFIS Out of Service A

(SRO)

N 2

S Determine if mode change is permissible A

(SRO)

N 2

S Approve a Waste Gas Release Permit A

(SRO)

N 2

S

Facility: H. B. Robinson Exam Date: October 3, 2022 1

JPM # or title 2

Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6

U/E/S 7

Explanation LOD REF IC TSK CUE CS TL Perform an Emergency Action Level Classification and recommend Protective Actions A

(SRO)

N 2

S Reactor Startup with Ejected Control Rod S

Y 2

S Place Excess Letdown in Service S

N 2

S Pressurizer Pressure Control Malfunction S

N 2

S Restore SW Flow/Pressure in AOP-022 S

Y 2

S Secure Containment Spray after Actuation S

N 2

S Transfer of Auxiliary Electrical Load from UAT to SUTs S

N 2

S Remove Source Range Instrument from Service S

N 2

S Step 7/10 standard states NI-5 vice NI-1 valve/breaker/switch line-up. (Verified corrected during onsite validation)

Control Room response to fire IAW AOP-041 S

N 2

S

Facility: H. B. Robinson Exam Date: October 3, 2022 1

JPM # or title 2

Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6

U/E/S 7

Explanation LOD REF IC TSK CUE CS TL Respond to Control Room Inaccessibility P

N 3

S Rapid Alignment of AFW Pump C as directed by EOP network P

Y 3

S Restore AC Power to an EDG Control Panel P

Y 2

S

Form 2.3-3 Instructions for Completing the JPM Table

1. Enter the JPM number and/or title.

2. Enter the type of JPM(S)imulator, (P)lant, or (A)dministrative.

3. Enter (Y)es or (N)o for an Alternate Path JPM.

4. Rate the level of difficulty (LOD) of each JPM using a scale of 1-5 (easy-difficult). A JPM containing less than two critical steps, a JPM that tests solely for recall or memorization, or a JPM that involves directly looking up a single correct answer is likely LOD = 1 (too easy). Conversely, a JPM with over 30 steps or a JPM that takes more than 45 minutes to complete is likely LOD = 5 (too difficult).

5. Check the appropriate block for each JPM error type, using the following criteria:

LOD = 1 or 5 is unsatisfactory (U).

REF: The JPM lacks required references, tools, or procedures (U).

IC: The JPM initial conditions are missing or the JPM lacks an adequate initial cue (U).

CUE: The JPM lacks adequate evaluator cues to allow the applicant to complete the task, or the evaluator cues are subjective or leading (U).

TSK: The JPM lacks a task standard or lacks completion criteria for a task standard (U).

CS: The JPM contains errors in designating critical steps, or the JPM lacks an adequate performance standard for a critical step (U).

TL: The JPM validation times are unreasonable, or a time-critical JPM lacks a completion time (U).

6. Mark the JPM as unsatisfactory (U), satisfactory (S), or needs enhancements (E). A JPM is (U) if it has one or more (U) errors as determined in step 5. Examples of enhancements include formatting, spelling, or other minor changes.

7. Briefly describe any JPM determined to be unsatisfactory (U) or needing enhancement (E). Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a satisfactory (S) resolution on this form.

Form 2.3-3 Operating Test Review Worksheet (Scenarios)

Facility: H. B. Robinson Scenario: 1 Exam Date: October 3, 2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS Raise Power to 5-8% IAW GP-005, Power Operation Start up the Main Turbine S

SDAFW Oil Leak S

High Turbine Eccentricity S

Pzr Pressure Control PC-444J Control Band Shift S

C Service Water Pump Trips S

RCS Leakage in Containment S

Steam Space LOCA S

Turbine fails to AUTO trip S

Failure of CV Ventilation S

Isolation to Auto Actuate Failure of CV Spray to Auto Actuate S

S

Facility: H. B. Robinson Scenario: 2 Exam Date: October 3, 2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS Loop 1 Thot fails LOW S

CCW system leakage isolable to the A CCW HX S

A Steam Flow Transmitter FT-474 Fails HIGH S

VCT Level Transmitter, LT-112 fails HIGH S

High Turbine Vibrations /

Load Reduction S

Loss of Both Condensate Pumps/ATWS S

Turbine Trip Failure -

MSIV Isolation Required S

MOV-350 fails to OPEN S

Loss of 230KV SUT S

Event removed during onsite validation.

Facility: H. B. Robinson Scenario: 3 Exam Date: October 3, 2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS HVE-6A trips on overload, HVE-6B starts in Manual ONLY S

Power Range NI-41 Detector fails HIGH S

Main Feedwater Pump B trips S

Load reduction to

<60% RTP S

Pressurizer Spray Valve PCV-455B fails OPEN while in AUTO S

Loss of Offsite Power S

B EDG fails to AUTO start S

A CCW AUTO start

failure, Restore RCP Seal Cooling S

V1-8A/B/C fail to AUTO open, Restore AFW Flow during SBO S

Form 2.3-3 Instructions for Completing the Scenario Table

1. For each scenario, enter the scenario event names and descriptions.

2. Review the individual events contained in each scenario, and identify and mark event errors:

The scenario guide event description is not realistic/credibleunsatisfactory (U).

The scenario guide event description lacks adequate crew/operator performance standardsneeds enhancement (E).

The scenario guide event description lacks verifiable actions for a credited normal event, reactivity event instrument/component malfunction, or technical specification (TS) event (or a combination of these) (U).

The scenario guide event description incorrectly designates an event as a critical task (i.e., a noncritical task labeled as critical or a critical task labeled as noncritical). This includes critical tasks that do not meet the critical task criteria (i.e., the critical task does not have a measurable performance standard) (U).

The scenario guide event description incorrectly designates entry into TS actions when not required or does not designate entry into TS actions when required (U).

3. Based on the outcome in step 2, mark the scenario event as unsatisfactory (U), satisfactory (S), or needs enhancements (E). An event is (U) if it has one or more (U) errors as determined in step 2. Examples of enhancements include formatting, spelling, or other minor changes.

4. Briefly describe any scenario event determined to be unsatisfactory (U) or needing enhancement (E). Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario event is marked by a satisfactory (S) resolution on this form.

Form 4.1-PWR Pressurized-Water Reactor Examination Outline Facility:

Robinson K/A Catalog Rev. 3 Rev.

1 Date of Exam: 10/03/2022 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

Emergency and Abnormal Plant Evolutions 1

3 3

18 3

3 6

2 1

1 2

1 8

2 2

4 Tier Totals 4

5 4

4 5

4 26 5

5 10

2.

Plant Systems 1

2 2

2 3

3 3

3 2

2 3

3 28 3

2 5

2 1

1 1

1 0

1 1

0 1

9 0

1 2

3 Tier Totals 3

3 3

3 4

4 3

3 3

3 4

37 4

4 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM 6

CO EC RC EM 7

2 2

1 1

2 2

1 2

4. Theory Reactor Theory Thermodynamics 6

3 3

Notes: CO = Conduct of Operations; EC = Equipment Control; RC = Radiation Control; EM = Emergency Procedures/Plan These systems/evolutions may be eliminated from the sample when Revision 2 of the K/A catalog is used to develop the sample plan These systems/evolutions are only included as part of the sample (as applicable to the facility) when Revision 2 of the K/A catalog is used to develop the sample plan

ES-4.1-PWR Robinson 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 (EPE 7) Reactor Trip, Stabilization, Recovery X

EK2.12 - Knowledge of the relationship between Reactor Trip, Stabilization, Recovery and: RCS (CFR 41.7, 45.7) 3.5 30 2

(APE 8) Pressurizer Vapor Space Accident X

AK3.04 Knowledge of the reasons for the following responses and/or actions as it applies to (APE 8)

PRESSURIZER VAPOR Space Accident:

(CFR 41.5, 41.10, 45.6, 45.13)

AK3.04 - RCP tripping requirements 4.1 11 3

(APE 40)

Steamline Rupture X

AA2.04 - Ability to determine and/or interpret the following as they apply to a Steamline Rupture:

AA2.04 Conditions requiring ESFAS initiation 4.4 89 4

(EPE 9) Small Break LOCA X

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 79 5

(EPE 11) Large Break LOCA X

EA2.05 - Ability to determine and/or interpret the following as it applies to Large-Break LOCA:

Significance of ECCS pump operation (CFR 43.5, 45.13) 4.1 95 6

(APE 15) Reactor Coolant Pump Malfunctions X

AK2.07 - Knowledge of the relationship between RCP Malfunctions and: RCP seals (CFR 41.7, 45.7) 3.8 13 7

(APE 22) Loss of Reactor Coolant Makeup X

AK1.03 -Knowledge of the operational implications and/or cause and effect relationships of the following as it applies to Loss of RCS Makeup: (CFR 41.8, 41.10, 45.3, 45.5)

AK1.03 - Relationship between charging flow and PZR level 3.6 66 8

(APE 25) Loss of Residual Heat Removal System X

AA2.09 - Ability to determine and/or interpret the following as it applies to Loss of RHR:

Lights and alarms (CFR 43.5, 45.13) 3.5 82 9

(APE 26) Loss of Component Cooling Water X

G2.4.52 - Knowledge of the lines of authority during implementation of the emergency plan, emergency plan implementing procedures, emergency operating procedures, or severe accident guidelines (CFR: 41.10 / 45.13) 4.0 88 10 (APE 27) Pressurizer Pressure Control System Malfunction X

AK3.06 - Knowledge of the reasons for the following responses and/or actions as they apply to PZR PCS malfunction: Actions to be taken if PZR pressure instrument fails low (CFR 41.5, 41.10, 45.6, 45.13) 3.9 20 11 (EPE 29) Anticipated Transient Without Scram X

G2.2.22 - Knowledge of limiting conditions for operation and safety limits (CFR 41.5, 43.2, 45.2) 4.7 9

12 (EPE 38) Steam Generator Tube Rupture X

EA1.45 - Ability to operate and/or monitor the following as it applies to Steam Generator Tube Rupture: SPDS (CFR 41.7, 45.5, 45.6) 3.5 26 13 (APE 40; WE 12)

Steam Line Rupture -

Excess. Heat Transfer X

AK2.11 - Knowledge of the relationship between a Steamline Rupture and: RCS (CFR 41.7, 45.7) 3.7 27 14 (APE 54) Loss of Main FW X

AA2.03 - Ability to determine and/or interpret the following as it applies to Loss of MFW: Conditions and reasons for AFW pump startup (CFR 41.10, 43.5, 45.13) 4.3 57 15 (EPE 55) Station Blackout X

EK3.01 - Knowledge of the reasons for the following responses and/or actions as it applies to Station Blackout: Length of time for which battery capacity is designed (CFR 41.5, 41.10, 45.6, 45.13) 4.1 49 16 (APE 56) Loss of Offsite Power X

G2.1.43 - Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion (CFR 41.10, 43.6, 45.6) 4.1 56

17 (APE 57) Loss of Vital AC Instrument Bus X

AA1.01 - Ability to operate and/or monitor as it applies to Loss of Instrument Bus: Inverter transfer to backup power supply (CFR 41.7, 45.5, 45.6) 3.7 58 18 (APE 58) Loss of DC Power X

AA2.02 - Ability to determine and/or interpret the following as it applies to Loss of DC Power: 125V DC bus voltage (CFR 43.5, 45.13) 3.6 25 19 (APE 62) Loss of Nuclear Service Water X

AK1.02 - Knowledge of the operational implications and/or cause and effect relationships of the following concept as it applies to Loss of SW: Knowledge of backup cooling water systems (CFR 41.8, 41.10, 45.3) 3.5 6

20 (APE 65) Loss of Instrument Air X

AA2.07 - Ability to determine and/or interpret the following as it applies to Loss of IA: Determination of whether backup nitrogen supply is controlling the valve position (CFR 41.10, 43.5, 45.13) 3.3 53 21 (APE 77) Generator Voltage and Electric Grid Disturbances X

AK1.02 - Knowledge of the operational implications and/or cause and effect relationships of the following as it applies to Generator Voltage and Grid Disturbances:

Overexcitation (CFR 41.4, 41.5, 41.7, 41.10, 45.8) 3.3 71 22 (WE 04) LOCA Outside Containment X

EA1.05 - Ability to operate and/or monitor the following as it applies to LOCA Outside Containment: RHRS (CFR 41.5 to 41.8, 45.5 to 45.8) 3.8 21 23 (WE 11) Loss of Emergency Coolant Recirculation X

G2.1.29 - Knowledge of how to conduct system lineups, such as valves, breakers, or switches (CFR 41.10, 45.1, 45.12) 4.1 59 24 (WE 05) Loss of Secondary Heat Sink X

G2.2.37 - Ability to determine operability or availability of safety-related equipment (CFR 43.2, 43.5, 45.12) 4.6 92 K/A Category Totals:

3 3

3/3 3/3 Group Point Total:

18/6

ES-4.1-PWR Robinson 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 (APE 1)

Continuous Rod Withdrawal X

AA2.05 - Ability to determine and/or interpret the following as it applies to Continuous Rod Withdrawal:

RPI (CFR 43.5, 45.13)

AA2.05 Uncontrolled rod withdrawal 4.1 99 26 (APE 3)

Dropped Control Rod X

G2.4.23 - Knowledge of the bases for prioritizing emergency operating procedures implementation (CFR 41.10, 43.5, 45.13) 4.4 78 27 (APE 24)

Emergency boration X

G2.1.20 - Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5 / 45.12) 4.6 94 28 (APE 28)

PZR Level Control Malfunction X

AK3.03 - Knowledge of the reasons for the following as it applies to PZR Level Control Malfunction: False indication of PZR level when PORV or spray valve is open and RCS is saturated (CFR 41.5,41.10,45.6,45.13) 3.8 33 29 (APE 37)

Steam Generator Tube Leak X

AA2.02 - Ability to determine and/or interpret the following as it applies to SGTL:

Agreement/disagreement among diverse radiation monitors (CFR 41.7, 41.10, 43.5, 45.13) 3.7 35 30 (WE 06) Degraded Core Cooling X

AK2.09: Knowledge of the relationship between Degraded Core Cooling and ECCS.

(CFR 41.7, 41.8, 45.2, 45.4) 4.1 64 31 (APE 67)

Plant Fire on Site X

AA2.16 - Ability to determine and/or interpret the following as it applies to Plant Fire on Site: Vital equipment and control systems to be maintained and operated during a fire (CFR 41.10, 43.5, 45.13) 3.7 65 32 (APE 78)

RCS Leak X

AA2.08 - Ability to determine and/or interpret as it applies to RCS Leak: Containment temperature, pressure, humidity, or sump level limits (CFR 43.5, 45.13) 3.8 90 33 (WE 01 & 02)

Rediagnosis & SI Termination X

EA1.15 Ability to operate and/or monitor the following as they apply to SI Termination:

(CFR: 41.5 to 41.8 / 45.5 to 45.8)

EA1.15 ECCS 3.9 19 34 (WE 15)

Containment Flooding X

G2.4.5 - Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions. (CFR 41.10, 43.5, 45.13) 3.7 39 35 (WE 03)

LOCA Cooldown -

Depressurization X

EK2.03 - Knowledge of the relationship between LOCA Cooldown and Depressurization and: AC electrical distribution system (CFR 41.7, 41.8, 45.2, 45.4) 3.3 12 36 (WE 09 & 10)

Natural Circulation X

EK1.06 - Knowledge of the operational implications and/or cause and effect relationships of the following as it applies to Natural Circulation Operations: Controlling reactor vessel head voids (CFR 41.5, 41.7, 45.7, 45.8) 3.7 61 K/A Category Totals:

1 2

1 1

2/2 1/2 Group Point Total:

8/4

ES-4.1-PWR Robinson Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)

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

K/A Topic(s)

IR Q#

37 (003) (SF4P)

RCP SYSTEM X

K4.07 - Knowledge of RCP design features and/or interlocks that provide for: Minimizing RCS leakage (mechanical seals)

(CFR 41.7) 3.8 10 38 (004) (SF1; SF2)

CHEMICAL AND VOLUME CONTROL SYSTEM X

K6.27 - Knowledge of the effect of the following on CVCS:

RHR relief and isolation valves (CFR 41.7, 45.7) 2.9 68 39 (004) (SF1; SF2)

CHEMICAL AND VOLUME CONTROL SYSTEM X

G2.3.14 - Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only)

(CFR 43.4, 45.10) 3.8 84 40 (005) (SF4P)

RESIDUAL HEAT REMOVAL SYSTEM X

A4.06 - Ability to manually operate and/or monitor RHR in the control room: RCS and containment isolation valves (CFR 41.7, 45.5 to 45.8) 3.8 74 41 (006) (SF2; SF3)

EMERGENCY CORE COOLING SYSTEM X

A2.06 - Ability to (a) predict the impacts of the following on ECCS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences: Water hammer (CFR 41.5, 45.3 to 45.5) 3.1 18 42 (007) (SF5)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM X

K3.01 - Knowledge of the effect that a loss or malfunction of the PRT will have on: Containment (CFR 41.7, 41.9) 3.4 43 43 (008) (SF8)

COMPONENT COOLING WATER SYSTEM X

A2.05 - Ability to (a) predict the impacts of the following on CCW, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences: Effect of loss of instrument and control air on the position of air-operated CCW valves (CFR 41.5,43.5,45.3,45.13) 3.2 32 44 (008) (SF8)

COMPONENT COOLING WATER SYSTEM X

A2.11 - Ability to (a) predict the impacts of the following on CCW, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences: RCP thermal barrier heat exchanger leak (CFR 41.5, 43.5, 45.3, 45.13) 4.0 97 45 (010) (SF3)

PZR PRESSURE CONTROL SYSTEM X

K4.03 - Knowledge of PZR PCS design features and/or interlocks that provide for:

Overpressure control (CFR 41.7) 3.9 54

46 (010) (SF3)

PZR PRESSURE CONTROL SYSTEM X

A2.02 - Ability to (a) predict the impacts of the following on PZR PCS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences:

Spray valve failures (CFR 41.5, 43.5, 45.3, 45.13) 3.8 77 47 (012) (SF7)

RPS X

A1.03 - Ability to predict and/or monitor changes in parameters associated with operation of RPS, including: Individual channels (CFR 41.5, 46.5) 3.6 47 48 (012) (SF7)

RPS X

K4.08 - Knowledge of RPS design features and/or interlocks that provide for:

Logic matrix testing (CFR 41.7) 3.3 14 49 (013) (SF2)

ESFAS X

K1.15 - Knowledge of the physical connections and/or cause and effect relationships between ESFAS and: MFW system (CFR 41.2 to 41.9, 45.7, 45.8) 3.4 55 50 (013) (SF2)

ESFAS X

G2.4.35 - Knowledge of non-licensed operator responsibilities during an emergency (CFR 41.10, 43.1, 43.5, 45.13) 4.0 85 51 (022) (SF5)

CONTAINMENT COOLING SYSTEM X

A4.02 - Ability to manually operate and/or monitor in the control room:

CCS pumps (CFR 41.7, 45.5 to 45.8) 3.6 46 52 (022) (SF5)

CONTAINMENT COOLING SYSTEM X

G2.4.6 - Knowledge of emergency and abnormal operating procedure major action categories (CFR 41.10, 43.5, 45.13) 3.7 8

53 (026) (SF5)

CONTAINMENT SPRAY SYSTEM X

A4.05 - Ability to manually operate and/or monitor in the control room:

Containment spray actuation and/or reset switches (CFR 41.7, 45.5 to 45.8) 4.0 2

54 (026) (SF5)

CONTAINMENT SPRAY SYSTEM X

K5.03 - Knowledge of the operational implications or cause and effect relationships of the following concept as it applies to the CSS Stratification of liquids:

Concentrated sodium hydroxide solution has a higher specific gravity than weak boric acid solution; therefore, the two solutions must be vigorously mixed to make an effective spray (CFR 41.5, 45.7) 2.5 31 55 (039) (SF4S)

MAIN AND REHEAT STEAM SYSTEM X

K1.11 - Knowledge of the physical connections and/or cause and effect relationships between MSS and: Condensate System (CFR 41.2 to 41.9, 45.7, 45.8) 3.1 50 56 (039) (SF4S)

MAIN AND REHEAT STEAM SYSTEM X

K6.10 - Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the MSS: Main Turbine Generator (CFR 41.7, 45.7) 3.4 60 57 (059) (SF4S)

MAIN FEEDWATER SYSTEM X

K2.01 - Knowledge of electrical power supplies to:

MFW system pumps (CFR 41.7) 3.2 15 58 (061) (SF4S)

AUXILIARY, EMERGENCY FEEDWATER X

K3.01 - Knowledge of the effect that a loss or malfunction of AFW will have on: RCS (CFR 41.7, 41.7, 45.6) 4.3 1

59 (062) (SF6)

AC ELECTRICAL DISTRIBUTION SYSTEM X

K5.08 - Knowledge of the operational implications or cause and effect relationships of the following as it applies to AC Distribution: Energizing a faulted or grounded bus or motor control center (CFR 41.5, 45.7) 3.8 28 60 (063) (SF6)

DC ELECTRICAL DISTRIBUTION SYSTEM X

A3.02 - Ability to monitor automatic features, including:

Battery charger undervoltage stripping (CFR 41.7, 45.5) 3.1 44 61 (063) (SF6)

DC ELECTRICAL DISTRIBUTION SYSTEM X

A2.05 - Ability to (a) predict the impacts of the following on DC DISTRIBUTION, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences: Loss of all AC (CFR 41.5, 43.5, 45.3, 45.13) 4.3 98 62 (064) (SF6)

EMERGENCY DIESEL GENERATOR SYSTEM X

A1.10 - Ability to predict and/or monitor changes in parameters associated with operation of the EDGs, including: Generator operating parameters (CFR 41.5, 45.5) 3.6 67 63 (064) (SF6)

EMERGENCY DIESEL GENERATOR SYSTEM X

K5.05 - Knowledge of the operational implications or cause and effect relationship of the following concept as it applies to the EDGs: I (CFR 41.5, 45.7)

K5.05 - Parallel operation of EDGs 3.9 40 64 (073) (SF7)

PROCESS RADIATION MONITORING SYSTEM X

K6.01 - Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the PRM: PRM component failures (CFR 41.7) 3.2 37 65 (076) (SF4S)

SERVICE WATER X

A3.06 - Ability to monitor automatic features of SW, including: (CFR 41.7, 45.5)

A3.06 - ESFAS 3.9 4

66 (076) (SF4S)

SERVICE WATER X

A1.06 - Ability to predict and/or monitor changes in parameters associated with operation of SW, including: (CFR 41.5, 45.5)

A1.06: Lights and alarms 2.9 23 67 (078) (SF8)

INSTRUMENT AIR SYSTEM X

G2.1.43 - Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion (CFR 41.10, 43.6, 45.6) 4.1 72 68 (078) (SF8)

INSTRUMENT AIR SYSTEM X

K2.01 - Knowledge of electrical power supplies to: IA compressor (CFR 41.7) 3.3 48 69 (103) (SF5)

CONTAINMENT SYSTEM X

G2.2.42 - Ability to recognize system parameters that are entry-level conditions for TS (CFR 41.7, 41.10, 43.2, 43.3, 45.3) 3.9 36 K/A Category Totals:

2 2

2 3

3 3

3 2/3 2

3 3/2 Group Point Total:

28/5

ES-4.1-PWR Robinson Emergency and Abnormal Plant EvolutionsTier 2/Group 2 (RO/SRO)

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

K/A Topic(s)

IR Q#

70 (001) (SF1)

CONTROL ROD DRIVE SYSTEM X

K3.02 - Knowledge of the effect that a loss or malfunction of the CRDS will have on: RCS (CFR 41.6) 3.4 5

71 (002) (SF2; SF4P)

REACTOR COOLANT SYSTEM X

K1.19 - Knowledge of the physical connections and/or cause and effect relationships between the RCS and: SFPCS (CFR 41.2 to 41.8, 45.7, 45.8) 2.6 62 72 (011) (SF2)

PRESSURIZER LEVEL CONTROL SYSTEM X

A2.04 - Ability to (a) predict the impacts of the following on the PZR LCS, and (b) based on those predictions, use procedures to correct, control, or mitigate:

Loss of one, two, or three charging pumps (CFR 41.5, 43.5, 45.3, 45.13) 3.9 81 73 (015) (SF7)

NUCLEAR INSTRUMENTATION SYSTEM X

K4.06 - Knowledge of NI System design features and/or interlocks that provide for: Reactor trip bypasses (CFR 41.7) 4.0 22 74 (016) (SF7)

NONNUCLEAR INSTRUMENTATION SYSTEM X

G2.4.12 - Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR 41.10, 45.12) 4.3 87 75 (017) (SF7)

IN-CORE TEMPERATURE MONITOR SYSTEM X

K5.01 - Knowledge of the operational implications or cause and effect relationships as it applies to ITM: Temperature at which cladding and fuel melt (CFR 41.5, 45.7) 3.8 7

76 (027) (SF5)

CONTAINMENT IODINE REMOVAL SYSTEM X

K6.01 - Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on CIRS:

CSS (CFR 41.7, 45.7) 2.9 24 77 (034) (SF8)

FUEL HANDLING EQUIPMENT SYSTEM X

A2.01 - Ability to (a) predict the impacts of the following on the FHS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences: Dropped and/or damaged fuel element (CFR41.5, 43.5, 43.7, 45.3, 45.8, 45.13) 4.0 38 78 045 (SF4S) MAIN TURBINE GENERATOR X

G2.2.17 - 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) 3.8 96 79 (050) (SF9)

CONTROL ROOM VENTILATION X

G2.1.27 - Knowledge of system purpose and/or function (CFR 41.7) 3.9 63 80 (056) (SF4S)

CONDENSATE SYSTEM X

K2.01 - Knowledge of electrical power supplies to: Condensate pumps and/or booster pumps (CFR 41.7) 3.1 52 81 (072) (SF7)

AREA RADIATION MONITORING SYSTEM X

A3.01 - Ability to monitor automatic features of the ARM, including: Changes in system alignment (CFR 41.7, 45.8, 45.9) 3.3 45 K/A Category Totals:

1 1

0 1/1 1

0 1/2 Group Point Total:

9/3

Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Robinson)

Facility:

Robinson Date of Exam: 10/12/2022 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)

Category K/A #

Topic RO SRO-Only Item IR Q#

IR Q#

1.

Conduct of Operations G2.1.1 Knowledge of conduct of operations requirements (CFR 41.10, 43.10, 45.13) 82 4.2 10 0

G2.1.23 Ability to perform general and/or normal operating procedures during any plant condition (CFR 41.10, 43.5, 45.2, 45.6) 84 4.3 16 G2.1.41 Knowledge of the refueling process (CFR 41.2, 41.10, 43.6, 45.13) 83 3.7 93 G2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communicating with fuel-handling personnel, operating systems from the control room to support fueling operations, or supporting instrumentation (CFR 41.10, 43.7, 45.12) 85 3.9 42 Subtotal N/A 2

N/A 2

2.

Equipment Control G2.2.6 Knowledge of the process for making changes to procedures (CFR 41.10, 43.3, 45.13) 88 3.6 86 G2.2.40 Ability to apply TS with action statements of less than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (CFR 41.10, 43.2, 43.5, 45.3) 86 3.4 17 G2.2.42 Ability to recognize system parameters that are entry-level conditions for TS (CFR 41.7, 41.10, 43.2, 43.3, 45.3) 87 3.9 75 G2.2.45 Ability to determine and/or interpret TS with action statements of greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (SRO Only) (CFR 43.2, 43.5, 45.3) 89 4.7 83 Subtotal N/A 2

N/A 2

3.

Radiation Control G2.3.11 Ability to control radiation releases (CFR 41.11, 43.4, 45.10) 91 4.3 91 G2.3.12 Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters (CFR 41.12, 43.4, 45.9, 45.10) 90 3.2 51 Subtotal N/A 1

N/A 1

4.

Emergency Procedures, Plan G2.4.14 Knowledge of general guidelines for emergency and abnormal operating procedures usage (CFR 41.10, 43.1, 45.13) 92 3.8 29 G2.4.42 Knowledge of emergency response facilities (CFR 41.10, 45.11) 93 3.8 76 G2.4.44 Knowledge of emergency plan implementing procedures protective action recommendations (SRO Only)

(CFR 41.10, 41.12, 43.5, 45.11) 94 4.4 80 Subtotal N/A 1

N/A 2

Tier 3 Point Total N/A 6

N/A 7

Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Robinson)

Facility:

Robinson Date of Exam: 10/12/2022 Theory (Tier 4) (RO)

Category K/A #

Topic RO Item IR Q#

Reactor Theory 192006 192006K1.08 - FISSION PRODUCT POISONS:

Describe the effects of xenon concentration on flux shape and control rod patterns (CFR 41.1) 95 3.4 73 192007 192007K1.04 - FUEL DEPLETION AND BURNABLE POISONS:

Describe how and why boron concentration changes over core life (CFR 41.1) 96 3.4 3

192008 192008K1.14 - REACTOR OPERATIONAL PHYSICS:

(INTERMEDIATE RANGE OPERATION) Describe reactor power and startup rate response prior to reaching the POAH (CFR 41.1) 97 3.1 34 Subtotal N/A 3

Thermodynamics 193003 193003K1.02 - STEAM: Describe effects of pressure and temperature on density or specific volume of a liquid (CFR 41.1) 98 2.5 69 193004 193004K1.11 - THERMODYNAMIC PROCESS:

(CONDENSERS) Describe the process of condensate depression (subcooling) and its effect on plant operation (CFR 41.1) 99 2.5 70 193009 193009K1.05 - CORE THERMAL LIMITS:

State why thermal limits are necessary. (CFR 41.1) 100 3.5 41 Subtotal N/A 3

Tier 4 Point Total N/A 6

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

Tier/Group Randomly Selected K/A Reason for Rejection T2 / G1 12/13/21 076 A3.03 At RNP theres no functional tie between SW and CCW auxiliary building header supply and return valves. Randomly sampled A3.06 - ESFAS T1 / G2 12/14/21 WE01 EA1.05 Ability to operate and/or monitor MFW system as it applies to Rediagnosis.

Neither the Chief Examiner assigned this Q, another CE, nor I could come up with a practical idea for this K/A.

This is a rare line item in the Exam Outline that lists two EPEs, and the Generator chose from WE01, which had only 4 other A.1s to choose from. But WE02 - SI Termination A.1 had 21 choices, so I randomly selected: WE02, SI Termination, EA1.15: ECCS.

T1 / G1 12/16/21 APE008 AA2.32 No good link to SRO knowledge (PZR vapor space accident and PRT conditions), and this K/A overlaps with RO APE008 AK3.03.

To remove the overlap, randomly sampled another T1G1 topic that didn't have an SRO question already selected, and got APE 40.

Had to stay in A2 for this SRO Q, so randomly sampled those 7 options and got AA2.04. New K/A: APE040, Steam Line Rupture, AA2.04: Conditions requiring ESFAS initiation.

T1 / G2 12/23/21 APE061 G2.4.39 Couldnt create an operationally-valid RO question.

T1G2 has many un-sampled EPEs/APEs that are more safety-significant than Area Radiation Monitoring, so I randomly chose one of those: "000074 -

Inadequate Core Cooling". But thats actually "(EPE74, W E06 & E07)," 3 different casualties in the catalog; randomly chose: "WE06 - Degraded Core Cooling" The skyscraper shows that G was sampled twice for RO in T1G2 (along with A2),

and G is over-sampled across T1 & T2 at 9, while the other topics have only 8 or 7 samples; so I could sample from K1-3 or A1.

Randomly chose K2. Within that, chose the highest IR. New K/A:

WE06 EK2.09: Relationship between Degraded Core Cooling and ECCS.

T1 / G1 2/2/22 APE008 AK3.03 Couldnt create a valid RO question for the reasons for actions contained in EOPs/AOPs for a vapor space accident without getting into basis knowledge.

Stayed in APE008 AK3, new K/A:

AK3.04 - RCP tripping requirements T2 / G1 2/3/22 076 A1.07 Couldnt create an operationally valid question about how intake screen blockage would affect SW operation at Robinson. Some stations, such as Indian Point 3, have dedicated essential SW intake structures, with features like bypass gates to bypass clogged screens. Robinsons SW pumps share the main intake structure with the CW pumps, with no provisions for clogged-screen bypass. Furthermore, Robinson is on a smallish freshwater lake with no history of major impingement by plant life, aquatic life, or frazzle ice, which are common at other stations in different environments.

Stayed in 076A1 and randomly sampled:

A1.06 - Ability to predict and/or monitor changes in parameters associated with operation of SW including Lights and alarms

T2 / G1 2/22/22 064 K5.14 Couldnt create an operationally valid RO question that tested a pretty specific concept in a once-every-refueling-outage surveillance test.

Staying in 064 K5, two statements are tied for highest IR at 3.9, with this one more amenable to a written question:

K5.05 - Parallel operation of EDGs T1 / G2 2/24/22 APE001 AA2.09 Couldnt create an SRO question based on RPIs during Continuous Rod Withdrawal. Stayed in APE001 and randomly selected:

AA2.05 - Uncontrolled rod withdrawal T1 / G2 2/24/22 APE024 G2.2.35 Unable to write an SRO question for Tech Specs related to Emergency Boration, because by the time you need EB youre in the EOPs and TS dont apply. About the only 2.2 that would cross well with EB is:

2.1.20 - Ability to interpret and execute procedure steps T1 / G2 2/25/22 WE15 G2.4.6 NUREG-1021 Rev. 12 has a new requirement that Generics cant be duplicated across Tier 1 and Tier 2. G2.4.6 was sampled twice by the Sample Plan Generator and not caught by staff. The other 2.4.6 was tied to System 022, and that question had already been written and approved, so this one was resampled to:

2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

T1 / G1 3/11/22 APE026 G2.4.49 This K/A was for an SRO question, and ROs are required to know immediate operator actions. Randomly selected:

G2.4.52 - Knowledge of the lines of authority during implementation of the emergency plan, emergency plan implementing procedures, emergency operating procedures, or severe accident guidelines T2 / G2 3/25/22 050 G2.4.16 Couldnt come up with a valid question after 2 attempts that related Control Room Ventilation with AOPs and EOPs. Stayed in SYS050 and resampled the Generic. This was a G2.4 category, which was sampled 9 times even after removing this one, while G2.2 was sampled 8 times, and G2.1 only 6 times, so to help even out the coverage I sampled from G2.1:

G2.1.27 - Knowledge of system purpose and/or function T1 / G1 5/20/22 APE 022 AK1.04 Changing from manual to automatic control of charging flow valve controller.

HCV-121 is the Charging Flow Valve at RNP, controlled by HIC-121, which is just a potentiometer to open or close the valve, with no Auto function.

There are 4 other AK1s in APE022, so randomly selected:

APE022 AK1.03 - Relationship between charging flow and PZR level

Form 2.3-5 Written Examination Review Worksheet Q#

NRC (RB)

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 1

(44)

F 2

M S

K/A 061 K3.01 T2 G1 2

(39)

H 2

M S

K/A 026 SF5 A4.05 T2 G1 3

(71)

H 2

M S

K/A 192007 K1.04 T4 4

(51)

H 3

B S

K/A 076 A3.06 T2 G1 (2015 RB NRC Exam Q13)

1. Changed K/A number to A3.06 on Examination Outline Cross-Reference sheet. The description was correct.

5 (55)

F 2

M S

K/A 001 K3.02 T2 G2 6

(14)

F 2

N S

K/A APE 062 AK1.02 T1 G1

1. Reference titles moved out of answer choices to improve readability.

7 (58)

H 2

N S

K/A 017 K5.01 T2 G2

1. First part answer choices changed due to the potential for two correct answers.

8 (38)

F 3

N S

K/A 022 SF5 G2.4.6 T2 G1

1. Updated question due to new procedure in effect.

9 (6)

F 2

N S

K/A EPE 029 G2.2.22 T1 G1

1. Second part question and answer choices reworded slightly to improve readability.

10 (27)

H 3

B S

K/A 003 K4.07 T2 G1 (2015 RB NRC Exam Q29)

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 11 (2)

H 3

N S

K/A APE 8 AK3.04 T1 G1

1. Label for bistable status panel a was removed from picture to remove any potential power supply cues for other questions on the exam.

12 (25)

H 3

M S

K/A WE03 EK2.03 T1 G2

1. Moved second part question to the first part.

2. Developed new second part question that is operationally valid. Based on validation comments.

13 (3)

H 2

B S

K/A APE 15 AK2.07 T1 G1 (2015 RB Audit Exam Q6) 14 (32)

H 2

N S

K/A 012 K4.08 T2 G1

1. Changed second part question to improve operational validity.

15 (43)

F 2

N S

K/A 059 K2.01 T2 G1

1. Question stem split into two different sentences based on validator input.

16 (64)

F 2

N S

K/A G2.1.23 T3

1. Based on validation comments, the order of the questions asked was switched.

17 (66)

F 2

N S

K/A G2.2.40 T3 18 (30)

F 2

N S

K/A 006 A2.06 T2 G1 19 (23)

H 3

N S

K/A WE02 EA1.15 T1 G2 20 (5)

H 2

M S

K/A APE027 AK3.06 T1 G1

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 21 (17)

F 2

B S

K/A WE04 EA1.05 T1 G1 (2017 RB NRC Exam Q17) 22 (57)

F 3

N S

K/A 015 K4.06 T2 G2

1. New question submitted due to valid problems with references listed in initial conditions. New question is satisfactory.

23 (49)

H 3

B S

K/A 076 A1.06 T2 G1 (2015 RB NRC Exam Q41) 24 (59)

H 2

N S

K/A 027 K6.01 T2 G2 25 (13)

H 3

N S

K/A 058 AA2.02 T1 G1

1. Additional information added to initial conditions based on validation comments.

26 (7)

H 3

N S

K/A EPE 038 EA1.45 T1 G1 27 (8)

F 2

N S

K/A APE 40 AK2.11 T1 G1 28 (45)

F 2

N S

K/A 062 K5.08 T2 G1 29 (69)

F 2

N S

K/A G2.4.14 T3 30 (1)

H 3

N S

K/A 007 EK2.12 T1 G1

1. Correct answer changed to C because a reduction in in the reactor power for the initial conditions on the original version of the question resulted in the low power trip being blocked.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 31 (40)

F 2

N S

K/A 026 K5.03 T2 G1 32 (33)

H 3

N S

K/A 008 A2.05 T2 G1 33 (19)

F 2

B S

K/A APE 28 AK3.03 T1 G2 (2019 TP NRC Exam Q19) 34 (72)

H 2

N S

K/A 192008 K1.14 T4 35 (20)

H 2

N S

K/A APE037 AA2.02 T1 G2

1. Based on validation comments, a different operationally relevant second part question was developed. A reference was added.

36 (54)

F 2

N S

K/A 103 G2.2.42 T2 G1 37 (50)

F 2

B S

K/A 073 K6.01 T2 G1 (2017 RB NRC Exam Q50) 38 (60)

H 2

N S

K/A 034 A2.01 T2 G2

1. Last bullet on current conditions removed due to that radiation monitor not being in service for refueling lineup.

2. First part question change to a more operationally relevant question for reactor operators.

39 (24)

H 3

N S

K/A WE15 G2.4.5 T1 G2

1. Answer choices, procedure titles, and valve nomenclature reformatted to improve readability.

40 (48)

F 2

N S

K/A 064 K5.14 T2 G1

1. Added position of Appendix R isolation switch to subsequent conditions based on validation comments.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 41 (75)

F 2

N S

K/A 193009 K1.05 T4

1. Question statement to improve understanding of the question being asked. Based on validation comments.

42 (65)

F 2

N S

K/A G2.1.44 T3

1. GP-010 title was added to the first part question.

2. IAW statement added to second part question.

43 (31)

F 2

B S

K/A 007 K3.01 T2 G1 (2014 RB NRC Exam Q34) 44 (46)

H 2

M S

K/A 063 A3.02 T2 G1

1. Additional information added to initial conditions based on validator input.

45 (63)

F 2

N S

K/A 072 A3.01 T2 G2 46 (37)

F 2

N S

K/A 022 A4.02 T2 G1

1. Changed to an operationally relevant two-part question. Still tests motor start limitations.

47 (35)

H 2

B S

K/A 012 A1.03 T2 G1 (2021 RB NRC Exam Q38) 48 (53)

F 3

B S

K/A 078 K2.01 T2 G1 (2017 RB NRC Exam Q54) 49 (10)

F 2

N S

K/A 055 EK3.01 T1 G1

1. Question stem reworded to improve focus and readability. Based on audit recommendations.

50 (41)

F 2

N S

K/A 039 K1.11 T2 G1

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 51 (68)

H 2

N S

K/A G2.3.12 T3 52 (62)

F 2

N S

K/A 056 K2.01 T2 G2 53 (15)

F 2

N S

K/A APE 065 AA2.07 T1 G1

1. Minor changes made to wording in the stem to improve readability and focus. Based on validation comments.

54 (34)

H 2

B B

K/A 010 K4.03 T2 G1 (2019 RB NRC Exam Q36) 55 (36)

F 2

M S

K/A 013 K1.15 T2 G1

1. Added reason for FWIS based on validation feedback.

56 (11)

H 3

M S

K/A 056 G2.1.43 T1 G1 57 (9)

H 2

B S

K/A 054 AA2.03 T1 G1 (2014 RB NRC Exam Q12) 58 (12)

H 3

N S

K/A 057 AA1.01 T1 G1 59 (18)

H 2

N S

K/A WE11 G2.1.29 T1 G1 60 (42)

H 2

N S

K/A 039 K6.10 T2 G1

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 61 (26)

F 2

B S

K/A WE10 EK1.06 T1 G2 (2021 RB NRC Exam Q26)

1. Answer choices shortened by placing part of choices in question stem.

62 (56)

F 2

N S

K/A 002 K1.19 T2 G2 63 (61)

F 2

N S

K/A 050 G2.1.27 T2 G2 64 (21)

H 2

M S

K/A WE06 EK2.09 T1 G2 65 (22)

H 3

N S

K/A APE067 AA2.16 T1 G2 66 (4)

H 3

B S

K/A APE022 AK1.03 T1 G1 (2021 RB Audit Exam) 67 (47)

F 2

N S

K/A 064 A1.10 T2 G1

1. Changed second part question to test reactive loading vice power factor based on validator recommendations.

68 (28)

F 2

N S

K/A 004 K6.27 T2 G1 69 (73)

H 2

M S

K/A 193003 K1.02 T4 70 (74)

H 2

M S

K/A 193004 K1.11 T4

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 71 (16)

H 3

N S

K/A 077AK1.02 T1 G1

1. Based on RNP operators not being required to no APP actions closed book, a new two part question was developed.

72 (52)

F 2

N S

K/A 078 G2.1.43 T2 G1 73 (70)

H 2

N S

K/A 192006 K1.08 T4 74 (29)

H 3

B S

K/A 005 A4.06 T2 G1 (2014 RB NRC Exam Q32) 75 (67)

H 2

N S

K/A G2.2.42 T3 76 (99)

H 2

N S

K/A G2.4.42 T3 77 (88)

H 3

N S

K/A 010 A2.02 T2 G1

1. Question stem reworded to improve clarity. Based on validation comments.

78 (83)

H 2

N S

K/A 003A G2.4.23 T1 G2 79 (77)

H 3

B S

K/A 009 EG2.2.44 T1 G1 (2017 RB NRC Exam Q85) 80 (100)

F 2

N S

K/A G2.4.44 T3

1. Changed second part of original questions due to operational validity concerns without a reference.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 81 (91)

H 3

N S

K/A 011 A2.04 82 (79)

F 2

M S

K/A APE025 AA2.09 T1 G1 83 (97)

H 2

B S

K/A G2.2.45 T3 (2021 RB NRC Exam Q97) 84 (86)

F 2

N S

K/A 004 G2.3.14 T2 G1

1. Changed first part of original question to improve operational relevance. Operators are not expected to know setpoints of radiation monitors from memory.

85 (89)

F 2

M S

K/A 013 G2.4.35 86 (96)

F 2

N S

K/A G2.2.6 T3 87 (92)

F 2

N S

K/A 016 G2.4.12 T2 G2

1. Changed first part question to prevent asking specific details from an AOP attachment.

88 (80)

F 2

N S

K/A APE 26 G2.4.52 T1 G1 89 (76)

H 2

N S

K/A APE 40 AA2.04 T1 G1 90 (85)

H 2

N S

K/A APE078 AA2.08 T1 G2

1. Answer choice distractors reworded for clarity.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

/Units Logic Q-K/A License Level 91 (98)

H 3

B S

K/A G2.3.11 T3 (2014 RB NRC Exam Q98) 92 (81)

H 3

B S

K/A WE05G2.2.37 T1 G1 (2021 RB NRC Exam Q76) 93 (95)

H 3

M S

K/A G2.1.41 T3 94 (84)

F 2

N S

K/A APE 24 G2.1.20 T1 G2 95 (78)

F 3

N S

K/A EPE11 EA2.05 T1 G1 96 (93)

H 2

B S

K/A 045 G2.2.17 T2 G2 (2017 RB Audit Exam) 97 (87)

H 3

N S

K/A 008 A2.11 T2 G1

1. Units for second part answer choices changed to gallons vice gpm.

2. Some initial condition seal flow values changed to be more realistic.

98 (90)

F 2

N S

K/A 063 A2.05 T2 G1

1. Second part of question changed based on valid comments following validation.

99 (82)

H 2

B S

K/A APE1 AA2.05 T1 G2 (2019 BV NRC Exam Q82) 100 (94)

F 2

N S

K/A G2.1.1 T3

1. Added name for SSC acronym.

Form 2.3-5 Instructions for Written Examination Review Worksheet Refer to ES-4.2 for the definitions of terms used in this worksheet for the written examination.

Review each question (Q) as submitted and as subsequently revised and document the following in the associated worksheet columns:

1. Enter the level of knowledge (LOK) as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) from 1 (easy) to 5 (difficult); mark direct lookup questions (applicant can directly determine the answer from the provided reference) as LOD 1. A question is (U)nsatisfactory if it is LOD 1 or LOD 5.

3. Check the appropriate box if a psychometric flaw is identified:

Stem Focus: The stem lacks enough focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). This is an (U)nsatisfactory question.

Cues: The stem or one or more answer choices contains cues (e.g., clues, specific determiners, phrasing, length). This is an (U)nsatisfactory question.

T/F: All of the answer choices are a collection of unrelated true/false statements. This is an (U)nsatisfactory question.

Cred. Dist.: The distractors are not credible; single implausible distractors require (E)nhancement, and more than one noncredible distractor in the same question results in an (U)satisfactory question.

Partial: One or more distractors are partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by the stem). This is an (U)nsatisfactory question.

4. Check the appropriate box if a job content flaw is identified:

Job Link: The question is not linked to the job requirements (i.e., the question has a valid knowledge or ability (K/A) but, as written, is not operational in content). This is an (U)nsatisfactory question.

Minutia: The question requires the recall of knowledge that is too specific for the closed-reference test mode (i.e., it is not required to be known from memory). This is an (U)nsatisfactory question.

/Units: The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). This is an (U)nsatisfactory question.

Logic: The question requires backward or reverse logic or application compared to the job requirements. This is an (U)nsatisfactory question.

5. Check the first box if a K/A mismatch flaw exists. Check the second box if the question is flawed because it is written at the wrong license level. Either condition results in an (U)nsatisfactory question.

6. Enter the questions source: (B)ank, (M)odified, or (N)ew. Verify that (M)odified questions meet the criteria of ES-4.2.

7. Based on the review performed in steps 2-5, mark the question as (U)nsatisfactory, in need of (E)nhancement, or (S)atisfactory.

8. Fully explain the reason for any (U) in column 7 (e.g., how the psychometric attributes are not being met).

9. Save the initial review comments and detail subsequent comment resolution so that each exam-bound question is marked by an (S) on this form.

ML22350A469

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