ML18057A814

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301 Exam Administrative Items (Delayed Release-2 Year)
ML18057A814
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 02/26/2018
From:
NRC/RGN-II
To:
References
Download: ML18057A814 (54)


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: V.C. Summer Date of Examination:

9/18/2017 Examination Level: RO SRO Operating Test Number: NRC-ILO-15-01 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations (A1-a)

D,R JPA-030B-(R)N17:

Calculate Shutdown Margin with a Stuck Rod. (STP-134.001)

Conduct of Operations (A1-b)

M JPA-1010-(R)N17 Calculate work hour limitations.

Equipment Control (A2)

D,R P

JPA-1006-(R)N17 Given a loss of a DC power panel affecting annunciators use AOP-100.5 to determine applicable Surveillance requirements.

Radiation Control (A3)

M,R JPA-814E-(S)N17 Perform a worker radiation exposure calculation.

Emergency Plan (A4)

Not selected for RO.

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 JPM

SUMMARY

STATEMENTS CONDUCT OF OPERATIONS (A1-a): CONDUCT OF OPERATIONS (A1-a): This is a bank JPM. The candidate will be directed to verify shutdown margin for Mode 3 with a single control rod not inserted is met using data provided and STP-134.001, Shutdown Margin Verification.

K/A 2.1.25: Ability to interpret reference materials such as graphs, curves, tables, etc.

(RO: 3.9, SRO: 4.2)

K/A 2.1.37: Knowledge of procedures, guidelines, or limitations associated with reactivity management. (RO: 4.3, SRO: 4.6)

VCS Task:

O-002-021-01-01, Perform Shutdown Margin Verification Per STP-134.001.

CONDUCT OF OPERATIONS (A1-b): This is a modified JPM. The candidate will be given conditions for the past work week schedule. They will determine the latest time they can work for a given day in the upcoming work week in accordance with SAP-152.

K/A 2.1.5:

Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

VCS Task:

O-119-003-03-01, Conduct shift and Relief Turnover.

EQUIPMENT CONTROL (A2): This is a bank JPM that was used in 2015 on the NRC exam.

The candidate will be given information regarding a loss of a DC power panel while in Mode 1 and a copy of AOP-100.5, Loss of Main Control Board Annunciators. The candidate will determine applicable Surveillance requirements for the lost Annunciators using AOP-100.5.

K/A: 2.2.14 Knowledge of the process for controlling equipment configuration or status.

(RO: 3.9, SRO: 4.3)

VCS Task:

O-000-170-05-01: Respond to loss of Main Control Board annunciators per AOP-100.5.

RADIATION CONTROL (A3): This is a modified bank JPM. The candidate will be directed to work with Health Physics to perform a field task in the RCA. A survey will be provided and the candidate will determine the stay time for this task.

K/A 2.3.4:

Knowledge of radiation exposure limits under normal or emergency conditions.

(RO: 3.2, SRO: 3.7)

VCS Task:

O-119-010-03-01, Apply Radiation and Contamination Safety Procedures EMERGENCY PLAN (A4): Not selected for RO.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: V.C. Summer Date of Examination: 9/18/2017 Examination Level: RO SRO Operating Test Number: NRC-ILO-15-01 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations (A1-a)

D,R JPA-030-(S)N17:

Review shutdown margin calc with stuck rod.

(STP-134.001)

Conduct of Operations (A1-b)

M,R Modified version of JPA-100B-(S)N17 Evaluate Shift Manning requirements for turnover.

Equipment Control (A2)

D,R JPA-011-(S)N17:

Evaluation of RHR Surveillance Test results.

Radiation Control (A3)

N,R JPA-190-(S)N17 Review a release permit prior to approval/ release Emergency Plan (A4)

D,R P

JPA-1003-(S)N17 Classify Emergency (SAE - Inadequate Core Cooling (ENF)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 JPM

SUMMARY

STATEMENTS CONDUCT OF OPERATIONS (A1-a): This is a bank JPM. The candidate will be required to review a completed shutdown margin for Mode 3 with a single control rod not inserted using data and forms provided and STP-134.001, Shutdown Margin Verification.

K/A 2.1.25: Ability to interpret reference materials such as graphs, curves, tables, etc.

(RO: 3.9, SRO: 4.2)

K/A 2.1.37: Knowledge of procedures, guidelines, or limitations associated with reactivity management. (RO: 4.3, SRO: 4.6)

VCS Task:

O-345-061-01-02, Recover from a stuck or misaligned rod situation per AOP-403.5.

CONDUCT OF OPERATIONS (A1-b): This is a modified JPM. The candidate will be required to review completed paperwork and determine if on-coming shift personnel meet qualifications to conduct all required shift activities.

K/A: 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (RO: 2.9, SRO: 3.9)

VCS Tasks: O-341-001-03-02, Conduct shift and relief turnover.

EQUIPMENT CONTROL (A2): This is a bank JPM. The candidate will review an RHR pump surveillance in accordance with STP-205.004, RHR Pump and Valve Operability Test. The candidate will find errors in the conduct of the STP and its documentation, determine that the RHR pump is inoperable, and apply technical specifications.

K/A: 2.2.12: Knowledge of surveillance procedures. (RO: 3.7, SRO: 4.1)

VCS Task:

O-342-026-03-02: Review Results of Surveillance Tests. (SAP-134, GTP-301, AND GTP-302)

RADIATION CONTROL (A3): This is a new JPM. The candidate will be required to review a release permit to determine if the any details of the permit, or any plant condition, will prohibit starting the release.

K/A: 2.3.6 Ability to approve release permits. (RO: 2.0, SRO: 3.8)

VCS Task:

O-341-012-03-02 Approve radioactive waste discharge/release permits. (HPP-709 AND HPP-710)

ES-301 Administrative Topics Outline Form ES-301-1 EMERGENCY PLAN (A4): This is a bank JPM that was used on the 2015 exam. The candidate will declare a Site Area Emergency in accordance with EPP-001, Activation and Implementation of Emergency Plan. The candidate will declare the Site Area Emergency due to an inadequate core cooling event that results in a potential loss of the Fuel Clad Barrier and a loss or potential of the Reactor Coolant System Barrier. The candidate will also be required to complete the EPP-002, Communication and Notification, Attachment I, Nuclear Power Plant Notification Form. This is a time critical JPM.

K/A: 2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation.

(RO: 2.7, SRO: 4.5)

K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications. (RO:

2.9, SRO: 4.6)

VCS Task:

O-343-063-03-02: Given several events, determine the Emergency Action level for each event, IAW EPP-01.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: V.C. Summer Date of Examination: 9/18/2017 Exam Level: RO SRO-I SRO-U Operating Test No.: NRC-ILO-15-01

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U

System / JPM Title Type Code*

Safety Function System 004: Chemical and Volume Control System (CVCS)

(JPS-012F-N17)

a.

Emergency borate, MVT-8104 and the blender will not work. They will have to borate using gravity drains.

D,A,S

1 System 006: Emergency Core Cooling System (ECCS)

(JPS-002F-N17)

b.

Terminate Safety Injection. Once Safety Injection is terminated, a RCS leak will go in that will meet the requirements to re-initiate Safety Injection.

D,A,EN,L,S

2 System 010: Pressurizer Pressure Control System (JPS-003F-N17)

c.

Depressurize Pressurizer with Aux Spray following a Steam Generator Tube Rupture.

D,A,L,S

3 EPE 011: Large Break LOCA (JPS-004-N17)

d.

Initiate Hot Leg Recirculation following a LOCA.

D,EN,L,P,S

4P EPE 038: Steam Generator Tube Rupture (JPS-005F-N17)

e.

Alternate isolation of ruptured Steam Generator (SG) due to "A" SG Main Steam Isolation Valve failing to close. (EOP-4.0, E-3)

D,A,L,S

4S APE 009: Small Break LOCA (JPS-006F-N17)

f.

Ensure Containment Isolation.

A,EN,M,L,S

5

System 064: Emergency Diesel Generators JPS-007-N17

g.

Start and load "B" Emergency Diesel Generator. (SOP-306)

D,P,S

6 System 029: Containment Purge System (JPS-008-N17)

h.

Respond to high reactor building pressure.

D,S

8

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

APE 054: Loss of Main Feedwater (MFW) (JPP-009-N17)

Using Service Water for Emergency Feedwater-Bypass Flow Blockage.

M,E,R,L

4S

j.

APE 015/017: Reactor Coolant Pump (RCP) Malfunctions (RCPS)

(JPP-010-N17)

Locally isolate Reactor Coolant Pump seals during a total loss of ESF power.

D,E,L,R

4P

k. System 012: Reactor Protection System (JPP-011-N17)

Place key switches in bypass per EOP-15.0.

D,E,L

7

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO / SRO-I / SRO-U RO (A)lternate path 4-6 / 4-6 / 2-3 5

(C)ontrol room (D)irect from bank 9 / 8 / 4 9

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

(EN)gineered safety feature 1 / 1 / 1 (control room system) 3 (L)ow-Power / Shutdown 1 / 1 / 1 8

(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 2

(P)revious 2 exams 3 / 3 / 2 (randomly selected) 2 (R)CA 1 / 1 / 1 2

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

VC SUMMER NRC RO JPM

SUMMARY

a. This is a bank JPM. The candidate will be tasked with responding to an alarm associated with the control rods being below their LO-LO insertion limit. They will emergency borate IAW AOP-106.1, EMERGENCY BORATION. They will attempt to borate through MVT-8104, however, this boration path will not work. They will then try to borate through the blender, which will not work. Then the candidate will align the system for gravity drain to get boric acid into the RCS, which will work. Borating using the gravity drain is the alternate path of this JPM.

K/A000004A4.12: Ability to manually operate and/or monitor in the control room:

Boration/dilution batch control. (RO 3.8 SRO 3.3)

NUREG 1122 System: 004, Chemical and Volume Control System

VCS Task: O-000-024-05-01, PERFORM EMERGENCY BORATION

b. This is a bank JPM. The candidate will be tasked with terminating Safety Injection. Once the candidate has closed the last valve to terminate Safety Injection, a RCS leak will go in. The candidate will meet the conditions to re-initiate Safety Injection and have to manually re-align Safety Injection pumps and valves.

K/A000006A4.01: Ability to manually operate and/or monitor in the control room: Pumps (RO 4.1 SRO 3.9)

NUREG 1122: 006, Emergency Core Cooling System (ECCS)

VCS Task: O-006-013-01-01, MANUALLY INITIATE SAFETY INJECTION.

c. This is a bank JPM. EOP-4.0, E3, Steam Generator Tube Rupture, is in progress due to a rupture in the C Steam Generator (SG). The candidate is directed to control Reactor Coolant System (RCS) pressure to minimize Primary to Secondary leak IAW EOP-4.0 step
40. The candidate will attempt to lower RCS pressure using normal pressurizer spray, however, the spray valves will not work. As an alternate path the candidate will then align Aux Spray to lower RCS pressure. The JPM is complete when Aux Spray is being used to control Pressurizer Pressure and SG level.

K/A 0000038EA1.04: Ability to operate and monitor the following as they apply to a SGTR: PZR spray, to reduce coolant system pressure. (RO 4.3 SRO 4.1)

NUREG 1122 038, Steam Generator Tube Rupture (SGTR)

VCS Task: O-004-066-01-01, Operate Pressurizer Auxiliary Spray per SOP-102.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

d. This is a bank JPM. EOP-2.3, Transfer to Hot Leg Recirculation, has been implemented eight hours after a LOCA. The candidate will be directed to align charging for Hot Leg Recirculation.

K/A 000011EA1.11: Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term cooling of core. (RO 4.2 SRO 4.2)

NUREG 1122 EPE: 011, Large Break LOCA VCS Task: O-000-137-05-01, Transfer RHR from Cold Leg to Hot Leg Recirculation per EOP-2.3/EOP-2.0.

e. This is a bank JPM. A Steam Generator Tube Rupture has occurred. The candidate will be tasked with isolating the A SG in accordance with EOP-4.0, STEAM GENERATOR TUBE RUPTURE. A SG Main Steam Isolation Valve (MSIV) will fail to close when the candidate tries to close this valve. As the alternate path, the candidate will take alternative actions to isolate the ruptured SG in accordance with EOP-4.0 (E-3), Steam Generator Tube Rupture.

K/A: 038 EA1.32: Ability to operate and monitor the following as they apply to a SGTR:

Isolation of a ruptured S/G. (RO: 4.6, SRO: 4.7)

NUREG 1122 EPE: 038, Steam Generator Tube Rupture

VCS Task: O-000-504-05-01, PERFORM RUPTURED STEAM GENERATOR ISOLATION PER EOP-4.0.

f.

This is a modified JPM. A LOCA and safety injection has occurred. The candidate is to verify Phase A and Containment Ventilation Isolation IAW EOP-1.0, Attachment 3, step 13. While performing this step, the candidate will find that Phase A has not actuated. The candidate will manually actuate Phase A and then determine that several valves did not close. As an alternate path, the candidate will then use a procedure attachment to perform backup isolations of the affected penetrations.

K/A: 0000103A3.01, Ability to monitor automatic operation of the containment system, including: Containment isolation. (RO 3.9 SRO 4.2)

NUREG 1122: 103, Containment System.

VCS Task: O-000-102-05-01, RESPOND TO CONTAINMENT ISOLATION PER EOP-17.0/EOP-1.0.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

g. This a bank JPM. The initial conditions for this JPM have the plant operating at 100% power with normal AC power available to all buses with all systems in automatic. Candidate will be instructed to start the B Diesel Generator (DG) in the test start mode for purposes of monitoring cylinder temperatures while the machine is at full load. All pre-start check steps for the B DG will have been completed. The candidate will be directed to start and load "B" DG per SOP-306, Emergency Diesel Generator,Section IV.B, Steps 2.3 and 2.4.

K/A 064000A4.01 Ability to manually operate and/or monitor in the control room: Local and remote operation of the ED/G. (RO: 4.0, SRO: 4.3)

NUREG 1122 System: 064, Emergency Diesel Generators

VCS Task: O-064-003-01-01, Load the Diesel Generator.

h. This is a bank JPM. The initial condition for this JPM is the plant is at 100% power and preparations are underway to conduct maintenance on the personnel access inner door.

The candidate is to lower Reactor Building (RB) pressure IAW SOP-114, REACTOR BUILDING VENTILATION SYSTEM, III.P. LOWERING REACTOR BUILDING PRESSURE USING NORMAL PRESSURE CONTROL starting at step 2.5. The candidate should stop the purge once RB pressure is less than +0.05 and greater than -0.05 psig.

K/A 000029A4.01: Ability to manually operate and/or monitor in the control room:

Containment purge flow rate. (RO: 4.0, SRO: 4.3)

NUREG 1122 System: 029, Containment Purge System (CPS)

VCS Task: O-029-004-01-01, LOWER REACTOR BUILDING PRESSURE USING PRESSURE CONTROL IAW SOP-114.

i.

This is a modified JPM. The Candidate will be directed to locally configure the EFW system for using Service Water for Emergency Feedwater using SOP-211, EMERGENCY FEEDWATER SYSTEM.

000054AA1.01: Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW): AFW controls, including the use of alternate AFW sources. (RO 4.5 SRO 4.4)

NUREG 1122 APE: 054, Loss of Main Feedwater (MFW)

VCS Task: O-061-007-01-01, SHIFT EMERGENCY FEEDWATER (EFW) PUMP SUCTION TO SW PER SOP-211.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

j.

This is a bank JPM. The candidate will be directed to isolate Reactor Coolant Pump seals by closing 3 different valves IAW EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER,, LOCALLY OPERATED ISOLATION VALVES.

015/017AA1.22: Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCP seal failure/malfunction (RO 4.0 SR 4.2)

NUREG 1122 APE: 015/017 Reactor Coolant Pump (RCP) Malfunctions

VCS Task: O-000-055-05-01, RESPOND TO LOSS OF OFF SITE AND ON SITE ESF POWER PER EOP-6.0/EOP-1.0.

k. This is a bank JPM. The candidate will be directed to bypass trains A and B of each main feed regulating valve and feedwater header isolation valves by using the appropriate key switches to enable restoring feed in EOP-15.0, FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK.

000012K1.08: Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems: MFW. (RO 2.9 SRO 3.1)

NUREG 1122 System: 012 Reactor Protection System

VCS Task: O-059-001-04-04, PLACE KEY SWITCHES IN BYPASS PER EOP-15.0.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility:

V.C. Summer Date of Examination: 9/18/2017 Exam Level:

RO SRO-I SRO-U Operating Test No.:NRC-ILO-15-01 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function System 004: Chemical and Volume Control System (CVCS)

a.

(JPS-012F-N17)

Emergency borate, MVT-8104 and the blender will not work. They will have to borate using gravity drains.

D,A,S

1 System 006: Emergency Core Cooling System (ECCS)

b.

(JPS-002F-N17)

Terminate Safety Injection. Once Safety Injection is terminated, a RCS leak will go in that will meet the requirements to re-initiate Safety Injection.

D,A,EN,L,S

2 System 010: Pressurizer Pressure Control System (JPS-003F-N17)

c.

Depressurize Pressurizer with Aux Spray following a Steam Generator Tube Rupture.

D,A,L,S

3

d.

EPE 011: Large Break LOCA (JPS-004-N17)

Initiate Hot Leg Recirculation following a LOCA.

D,EN,L,P,S

4P EPE 038: Steam Generator Tube Rupture (JPS-005F-N17)

e.

Alternate isolation of ruptured Steam Generator (SG) due to "A" SG Main Steam Isolation Valve failing to close. (EOP-4.0, E-3)

D,A,L,S

4S

f.

APE 009: Small Break LOCA (JPS-006F-N17)

Ensure Containment Isolation.

A,EN,M,L,S

5

g.

System 064: Emergency Diesel Generators JPS-007-N17 Start and load "B" Emergency Diesel Generator. (SOP-306)

D,P,S

6

h.

Not for SRO-I use.

N/A N/A

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

APE 054: Loss of Main Feedwater (MFW) (JPP-009-N17)

Using Service Water for Emergency Feedwater-Bypass Flow Blockage.

M,E,R,L

4S

j.

APE 015/017: Reactor Coolant Pump (RCP) Malfunctions (RCPS)

(JPP-010-N17)

Locally isolate Reactor Coolant Pump seals during a total loss of ESF power.

D,E,L,R

4P

k. System 012: Reactor Protection System (JPP-011-N17)

Place key switches in bypass per EOP-15.0.

D,E,L

7

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO / SRO-I / SRO-U SRO-I (A)lternate path 4-6 / 4-6 / 2-3 5

(C)ontrol room (D)irect from bank 9 / 8 / 4 8

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

(EN)gineered safety feature 1 / 1 / 1 (control room system) 3 (L)ow-Power / Shutdown 1 / 1 / 1 8

(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 2

(P)revious 2 exams 3 / 3 / 2 (randomly selected) 2 (R)CA 1 / 1 / 1 2

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

VC SUMMER NRC SRO-I JPM

SUMMARY

a. This is a bank JPM. The candidate will be tasked with responding to an alarm associated with the control rods being below their LO-LO insertion limit. They will emergency borate IAW AOP-106.1, EMERGENCY BORATION. They will attempt to borate through MVT-8104, however, this boration path will not work. They will then try to borate through the blender, which will not work. Then the candidate will align the system for gravity drain to get boric acid into the RCS, which will work. Borating using the gravity drain is the alternate path of this JPM.

K/A000004A4.12: Ability to manually operate and/or monitor in the control room:

Boration/dilution batch control. (RO 3.8 SRO 3.3)

NUREG 1122 System: 004, Chemical and Volume Control System

VCS Task: O-000-024-05-01, PERFORM EMERGENCY BORATION.

b. This is a bank JPM. The candidate will be tasked with terminating Safety Injection. Once the candidate has closed the last valve to terminate Safety Injection, a RCS leak will go in. The candidate will meet the conditions to re-initiate Safety Injection and have to manually re-align Safety Injection pumps and valves.

K/A000006A4.01: Ability to manually operate and/or monitor in the control room: Pumps (RO 4.1 SRO 3.9)

NUREG 1122: 006, Emergency Core Cooling System (ECCS)

VCS Task: O-006-013-01-01, MANUALLY INITIATE SAFETY INJECTION.

c. This is a bank JPM. EOP-4.0, E3, Steam Generator Tube Rupture, is in progress due to a rupture in the C Steam Generator (SG). The candidate is directed to control Reactor Coolant System (RCS) pressure to minimize Primary to Secondary leak IAW EOP-4.0 step
40. The candidate will attempt to lower RCS pressure using normal pressurizer spray, however, the spray valves will not work. As an alternate path the candidate will then align Aux Spray to lower RCS pressure. The JPM is complete when Aux Spray is being used to control Pressurizer Pressure and SG level.

K/A 0000038EA1.04: Ability to operate and monitor the following as they apply to a SGTR: PZR spray, to reduce coolant system pressure. (RO 4.3 SRO 4.1)

NUREG 1122 038, Steam Generator Tube Rupture (SGTR)

VCS Task: O-004-066-01-01, Operate Pressurizer Auxiliary Spray per SOP-102.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

d. This is a bank JPM. EOP-2.3, Transfer to Hot Leg Recirculation, has been implemented eight hours after a LOCA. The candidate will be directed to align charging for Hot Leg Recirculation.

K/A 000011EA1.11: Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term cooling of core. (RO 4.2 SRO 4.2)

NUREG 1122 EPE: 011, Large Break LOCA VCS Task: O-000-137-05-01, Transfer RHR from Cold Leg to Hot Leg Recirculation per EOP-2.3/EOP-2.0.

e. This is a bank JPM. A Steam Generator Tube Rupture has occurred. The candidate will be tasked with isolating the A SG in accordance with EOP-4.0, STEAM GENERATOR TUBE RUPTURE. A SG Main Steam Isolation Valve (MSIV) will fail to close when the candidate tries to close this valve. As the alternate path, the candidate will take alternative actions to isolate the ruptured SG in accordance with EOP-4.0 (E-3), Steam Generator Tube Rupture.

K/A: 038 EA1.32: Ability to operate and monitor the following as they apply to a SGTR:

Isolation of a ruptured S/G. (RO: 4.6, SRO: 4.7)

NUREG 1122 EPE: 038, Steam Generator Tube Rupture

VCS Task: O-000-504-05-01, PERFORM RUPTURED STEAM GENERATOR ISOLATION PER EOP-4.0.

f.

This is a modified JPM. A LOCA and safety injection has occurred. The candidate is to verify Phase A and Containment Ventilation Isolation IAW EOP-1.0, Attachment 3, step 13. While performing this step, the candidate will find that Phase A has not actuated. The candidate will manually actuate Phase A and then determine that several valves did not close. As an alternate path, the candidate will then use a procedure attachment to perform backup isolations of the affected penetrations.

K/A: 0000103A3.01, Ability to monitor automatic operation of the containment system, including: Containment isolation. (RO 3.9 SRO 4.2)

NUREG 1122: 103, Containment System.

VCS Task: O-000-102-05-01, RESPOND TO CONTAINMENT ISOLATION PER EOP-17.0/EOP-1.0.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

g. This a bank JPM. The initial conditions for this JPM have the plant operating at 100% power with normal AC power available to all buses with all systems in automatic. Candidate will be instructed to start the B Diesel Generator (DG) in the test start mode for purposes of monitoring cylinder temperatures while the machine is at full load. All pre-start check steps for the B DG will have been completed. The candidate will be directed to start and load "B" DG per SOP-306, Emergency Diesel Generator,Section IV.B, Steps 2.3 and 2.4.

K/A 064000A4.01 Ability to manually operate and/or monitor in the control room: Local and remote operation of the ED/G. (RO: 4.0, SRO: 4.3)

NUREG 1122 System: 064, Emergency Diesel Generators

VCS Task: O-064-003-01-01, Load the Diesel Generator.

h. Not for SRO-I use.
i.

This is a modified JPM. The Candidate will be directed to locally configure the EFW system for using Service Water for Emergency Feedwater using SOP-211, EMERGENCY FEEDWATER SYSTEM.

000054AA1.01: Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW): AFW controls, including the use of alternate AFW sources. (RO 4.5 SRO 4.4)

NUREG 1122 APE: 054, Loss of Main Feedwater (MFW)

VCS Task: O-061-007-01-01, SHIFT EMERGENCY FEEDWATER (EFW) PUMP SUCTION TO SW PER SOP-211.

j.

This is a bank JPM. The candidate will be directed to isolate Reactor Coolant Pump seals by closing 3 different valves IAW EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER,, LOCALLY OPERATED ISOLATION VALVES.

015/017AA1.22: Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCP seal failure/malfunction (RO 4.0 SR 4.2)

NUREG 1122 APE: 015/017 Reactor Coolant Pump (RCP) Malfunctions

VCS Task: O-000-055-05-01, RESPOND TO LOSS OF OFF SITE AND ON SITE ESF POWER PER EOP-6.0/EOP-1.0.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

k. This is a bank JPM. The candidate will be directed to bypass trains A and B of each main feed regulating valve and feedwater header isolation valves by using the appropriate key switches to enable restoring feed in EOP-15.0, FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK.

000012K1.08: Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems: MFW. (RO 2.9 SRO 3.1)

NUREG 1122 System: 012 Reactor Protection System

VCS Task: O-059-001-04-04, PLACE KEY SWITCHES IN BYPASS PER EOP-15.0.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility:

V.C. Summer Date of Examination: 9/18/2017 Exam Level:

RO SRO-I SRO-U Operating Test No:NRC-ILO-15-01 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function System 004: Chemical and Volume Control System (CVCS)

(JPS-012F-N17)

a.

Emergency borate, MVT-8104 and the blender will not work. They will have to borate using gravity drains.

D,A,S

1 System 006: Emergency Core Cooling System (ECCS)

(JPS-002F-N17)

b.

Terminate Safety Injection. Once Safety Injection is terminated, a RCS leak will go in that will meet the requirements to re-initiate Safety Injection.

D,A,EN,L,S

2

c.

Not for SRO-U use.

N/A

N/A

d.

Not for SRO-U use.

N/A

N/A

e.

Not for SRO-U use.

N/A

N/A APE 009: Small Break LOCA (JPS-006F-N17)

f.

Ensure Containment Isolation.

A,EN,M,L,S

5

g.

Not for SRO-U use.

N/A

N/A

h.

Not for SRO-U use.

N/A

N/A In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Not for SRO-U use.

N/A

N/A

j.

APE 015/017: Reactor Coolant Pump (RCP) Malfunctions (RCPS)

(JPP-010-N17)

Locally isolate Reactor Coolant Pump seals during a total loss of ESF power.

D,E,L,R

4P

k. System 012: Reactor Protection System (JPP-011-N17)

Place key switches in bypass per EOP-15.0.

D,E,L

7

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

  • Type Codes Criteria for RO / SRO-I / SRO-U SRO-U (A)lternate path 4-6 / 4-6 / 2-3 3

(C)ontrol room (D)irect from bank 9 / 8 / 4 4

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

(EN)gineered safety feature 1 / 1 / 1 (control room system) 2 (L)ow-Power / Shutdown 1 / 1 / 1 4

(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 1

(P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1 / 1 / 1 1

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

VC SUMMER NRC SRO-U JPM

SUMMARY

a. This is a bank JPM. The candidate will be tasked with responding to an alarm associated with the control rods being below their LO-LO insertion limit. They will emergency borate IAW AOP-106.1, EMERGENCY BORATION. They will attempt to borate through MVT-8104, however, this boration path will not work. They will then try to borate through the blender, which will not work. Then the candidate will align the system for gravity drain to get boric acid into the RCS, which will work. Borating using the gravity drain is the alternate path of this JPM.

K/A000004A4.12: Ability to manually operate and/or monitor in the control room:

Boration/dilution batch control. (RO 3.8 SRO 3.3)

NUREG 1122 System: 004, Chemical and Volume Control System

VCS Task: O-000-024-05-01, PERFORM EMERGENCY BORATION.

b. This is a bank JPM. The candidate will be tasked with terminating Safety Injection. Once the candidate has closed the last valve to terminate Safety Injection, a RCS leak will go in. The candidate will meet the conditions to re-initiate Safety Injection and have to manually re-align Safety Injection pumps and valves.

K/A000006A4.01: Ability to manually operate and/or monitor in the control room: Pumps (RO 4.1 SRO 3.9)

NUREG 1122: 006, Emergency Core Cooling System (ECCS)

VCS Task: O-006-013-01-01, MANUALLY INITIATE SAFETY INJECTION.

c. Not for SRO-U use.
d. Not for SRO-U use.
e. Not for SRO-U use.
f.

This is a modified JPM. A LOCA and safety injection has occurred. The candidate is to verify Phase A and Containment Ventilation Isolation IAW EOP-1.0, Attachment 3, step 13. While performing this step, the candidate will find that Phase A has not actuated. The candidate will manually actuate Phase A and then determine that several valves did not close. As an alternate path, the candidate will then use a procedure attachment to perform backup isolations of the affected penetrations.

K/A: 0000103A3.01, Ability to monitor automatic operation of the containment system, including: Containment isolation. (RO 3.9 SRO 4.2)

NUREG 1122: 103, Containment System.

VCS Task: O-000-102-05-01, RESPOND TO CONTAINMENT ISOLATION PER EOP-17.0/EOP-1.0.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

g. Not for SRO-U use.
h. Not for SRO-U use.
i. Not for SRO-U use.
j.

This is a bank JPM. The candidate will be directed to isolate Reactor Coolant Pump seals by closing 3 different valves IAW EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER,, LOCALLY OPERATED ISOLATION VALVES.

015/017AA1.22: Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCP seal failure/malfunction (RO 4.0 SR 4.2)

NUREG 1122 APE: 015/017 Reactor Coolant Pump (RCP) Malfunctions

VCS Task: O-000-055-05-01, RESPOND TO LOSS OF OFF SITE AND ON SITE ESF POWER PER EOP-6.0/EOP-1.0.

k. This is a bank JPM. The candidate will be directed to bypass trains A and B of each main feed regulating valve and feedwater header isolation valves by using the appropriate key switches to enable restoring feed in EOP-15.0, FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK.

000012K1.08: Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems: MFW. (RO 2.9 SRO 3.1)

NUREG 1122 System: 012 Reactor Protection System

VCS Task: O-059-001-04-04, PLACE KEY SWITCHES IN BYPASS PER EOP-15.0.

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: V.C. Summer (Unit 1) Exam Date: 09/18/2017 1

2 3

Attributes 4

Job Content 5

6 Admin JPMs ADMIN Topic and K/A LOD (1-5)

U/E/S Explanation I/C Cues Critical Scope Overlap Perf.

Key Minutia Job Link Focus Steps (N/B)

Std.

Calculate Shutdown Margin with a Stuck Rod (RO)

Conduct of Operations G2.1.25 2

E

1.

The title of the JPM on the ES-301-1 and the JPM coversheet do not match (stuck or dropped rod).

2.

The same problem exists on page 9 of 10.

3.

Will further evaluate all JPMs (admin, control room, and in-plant) by observing their performance during on-site prep week.

Review Shutdown Margin calculation with Dropped Rod (SRO)

Conduct of Operations G2.1.25 2

X X

E

1.

The task standard does not address correctly identifying all of the errors.

2.

The JPM step standards with errors do not include lining out the incorrect entry and entering the correct information as is directed on the cue sheet.

3.

JPM step 9 should be critical.

4.

There should be an examiner cue of when to provide the questions about the technical specifications and surveillances to the applicant because it is not listed in the cue sheet and we would not want to provide it to the applicant too early because that could be a cue that the calculation was in error.

Calculate work hour limits IAW SAP-152 (RO)

Conduct of Operations G2.1.5 2

X E

1.

The initiating cues provide a cue that the operator cannot work the full amount of time.

Reword the cue, answer sheet, and key to ask if they can or cannot cover the whole time and if not, why.

Evaluate shift manning requirements for turnover (SRO)

Conduct of Operations G2.1.5 3

E

1.

The title on the coversheet and JPM setup sheet does not match the ES-301-1 Given a loss of a DC Power Panel affecting annunciators use AOP-100.5 to determine applicable surveillance requirements (RO)

Equipment Control G2.2.14 2

E

1.

The title on the coversheet and JPM setup sheet does not match the ES-301-1

ES-301 Operating Test Review Worksheet Form ES-301-7

\\

Review RHR Surveillance Test Results (SRO)

Equipment Control G2.2.12 2

X E

1.

The task standard should address identifying each of the critical errors. The task still would not meet acceptance criteria if only one of multiple errors were identified.

2.

The second question on the answer sheet is a cue.

Perform a radiation worker exposure calculation (RO)

Radiation Control G2.3.4 2

E

1.

The title on the coversheet and JPM setup sheet does not match the ES-301-1.

2.

The task standard is not complete. Correct exposure must also be calculated for worker B.

The operations manager must also sign the form.

3.

Why is there an allowable range for the worker B calculation? If there is an acceptable reason for an allowable range, then why is there one for worker B and not one for worker A.

Review a release permit prior to approval/release (SRO)

Radiation Control G2.3.6 2

E

1.

The task standard does not match the task.

Declare a Site Area Emergency IAW EPP-001 and complete the EPP-002 notification form (SRO)

Emergency Plan G2.4.41 2

S

1.

No comments during initial review. Will further evaluate during on-site prep week.

1 Simulator/In-Plant Safety Function and K/A JPMs Emergency Borate, MVT-8104 and blender will not work 1

006 A4.01 2

E

1.

The K/A listed on the ES-301-2 and on the JPM do not match.

Terminate and then re-initiate 2

009 EK3.28 2

X E

1.

Based NUREG-1021 on Rev. 11 requirements, steps that must be performed to complete the task standard should be designated as critical

ES-301 Operating Test Review Worksheet Form ES-301-7 SI following RCS Leak steps. Therefore, the steps for establishing normal charging should be critical steps.

Depressurize pressurizer w/

aux spray following SGTR 3

038 A1.04 2

E

1.

The K/A listed on the ES-301-2 and on the JPM do not match.

Initiate Hot Leg recirculation following a LOCA 4P 011 EA1.11 2

X E

1.

Verify should be placed at the beginning of the step 9 step standard if the condition already exists.

2.

I believe that steps 10-13 should be critical steps. If not, please explain why.

Alternate isolation of ruptured steam generator due to A MSIV failing to close 4S 039 A4.01 2

X E

1.

All steps required to complete the task standard are not listed as critical steps.

Ensure containment isolation 5

103 A3.01 2

E

1.

The task standard is not complete with all of the valves that are required to be closed and does not give the option for either the A or B train valves when either/or is acceptable.

Start and Load B EDG 6

064 A4.01 3

S

1.

No comments during initial review. Will further evaluate during on-site prep week.

Respond to high reactor building pressure 8

029 A4.01 2

S

1.

No comments during initial review. Will further evaluate during on-site prep week.

Using Service Water for Emergency Feedwater bypass flow blockage 4S 054 AA1.01 2

X X

U

1.

I believe that steps 3-7 should be critical steps.

If not, please explain why.

2.

The task standard can never be accomplished because bypass flow around the TDEFWP is never established per step 2.5.b.

Locally isolate RCP seals during a total loss of ESF power 4P 015/017 AA1.22 2

X E

1.

JPM step 3 should be listed as EOP step 1.c) instead of 1.b).

Place key switches in bypass per EOP-15.0 7

012 K1.08 2

S

1.

No comments during initial review. Will further evaluate during on-site prep week.

ES-301 4

Form ES-301-7 Instructions for Completing This Table:

Check or mark any item(s) requiring a comment and explain the issue in the space provided using the guide below.

1.

Check each JPM for appropriate administrative topic requirements (COO, EC, Rad, and EP) or safety function requirements and corresponding K/A. Mark in column 1.

(ES-301, D.3 and D.4)

2.

Determine the level of difficulty (LOD) using an established 1-5 rating scale. Levels 1 and 5 represent an inappropriate (low or high) discriminatory level for the license that is being tested. Mark in column 2 (Appendix D, C.1.f)

3.

In column 3, Attributes, check the appropriate box when an attribute is not met:

The initial conditions and/or initiating cue is clear to ensure the operator understands the task and how to begin. (Appendix C, B.4)

The JPM contains appropriate cues that clearly indicate when they should be provided to the examinee. Cues are objective and not leading. (Appendix C, D.1)

All critical steps (elements) are properly identified.

The scope of the task is not too narrow (N) or too broad (B).

Excessive overlap does not occur with other parts of the operating test or written examination. (ES-301, D.1.a, and ES-301, D.2.a)

The task performance standard clearly describes the expected outcome (i.e., end state). Each performance step identifies a standard for successful completion of the step.

A valid marked up key was provided (e.g., graph interpretation, initialed steps for handouts).

4.

For column 4, Job Content, check the appropriate box if the job content flaw does not meet the following elements:

Topics are linked to the job content (e.g., not a disguised task, task required in real job).

The JPM has meaningful performance requirements that will provide a legitimate basis for evaluating the applicant's understanding and ability to safely operate the plant. (ES-301, D.2.c)

5.

Based on the reviewers judgment, is the JPM as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 5.

6.

In column 6, provide a brief description of any (U)nacceptable or (E)nhancement rating from column 5.

Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a (S)atisfactory resolution on this form.

ES-301 5

Form ES-301-7 Facility: Scenario: Exam Date:

1 2

3 4

5 6

7 8

9 10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation Facility: V.C. Summer (Unit 1) Scenario: 1 Exam Date: 09/18/2017 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S 2

S 3

S 4

S 5

X X

S 6

X U

LCO 3.4.5 should be entered for the S/G tube leak per the TS basis.

7 X(2)

S 7

0 0

0 2

2 6

E Further evaluation will be performed during on-site prep week.

ES-301 6

Form ES-301-7 Facility: Scenario: Exam Date:

1 2

3 4

5 6

7 8

9 10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation Facility: V.C. Summer (Unit 1) Scenario: 2 Exam Date: 09/18/2017 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S 2

X X

S 3

X S

4 X

S 5

X S

6 X(2)

E Need actual FR.C.1 criteria vice transition for RHR pump critical task.

See Appendix D Section B.2 : Need some equipment out of service at Turnover.

6 0

0 0

2 4

5 E

Further evaluation will be performed during on-site prep week.

ES-301 7

Form ES-301-7 Facility: Scenario: Exam Date:

1 2

3 4

5 6

7 8

9 10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation Facility: V.C. Summer (Unit 1) Scenario: 3 Exam Date: 09/18/2017 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S 2

S 3

X S

4 X

X S

5 X

X X

S 6

X(2)

S 6

0 0

0 2

4 4

S Further evaluation will be performed during on-site prep week.

ES-301 8

Form ES-301-7 Facility: V.C. Summer (Unit 1) Scenario: 4 Exam Date: 09/18/2017 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S 2

X X

S 3

X S

4 S

5 X

S 6

X(3)

E Need actual criteria for red and orange paths relating to critical tasks.

See Appendix D Section B.2 : Need some equipment out of service at turnover.

6 0

0 0

2 5

6 E

ES-301 9

Form ES-301-7 Instructions for Completing This Table:

Use this table for each scenario for evaluation.

2 Check this box if the events are not related (e.g., seismic event followed by a pipe rupture) OR if the events do not obey the laws of physics and thermodynamics.

3, 4 In columns 3 and 4, check the box if there is no verifiable or required action, as applicable. Examples of required actions are as follows: (ES-301, D.5f) opening, closing, and throttling valves starting and stopping equipment raising and lowering level, flow, and pressure making decisions and giving directions acknowledging or verifying key alarms and automatic actions (Uncomplicated events that require no operator action beyond this should not be included on the operating test unless they are necessary to set the stage for subsequent events. (Appendix D, B.3).)

5 Check this box if the level of difficulty is not appropriate.

6 Check this box if the event has a TS.

7 Check this box if the event has a critical task (CT). If the same CT covers more than one event, check the event where the CT started only.

8 Check this box if the event overlaps with another event on any of the last two NRC examinations. (Appendix D, C.1.f) 9 Based on the reviewers judgment, is the event as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 9.

10 Record any explanations of the events here.

In the shaded boxes, sum the number of check marks in each column.

In column 1, sum the number of events.

In columns 2-4, record the total number of check marks for each column.

In column 5, based on the reviewer's judgement, place a checkmark only if the scenario's LOD is not appropriate.

In column 6, TS are required to be 2 for each scenario. (ES-301, D.5.d)

In column 7, preidentified CTs should be 2 for each scenario. (Appendix D; ES-301, D.5.d; ES-301-4)

In column 8, record the number of events not used on the two previous NRC initial licensing exams. A scenario is considered unsatisfactory if there is < 2 new events. (ES-301, D.5.b; Appendix D, C.1.f)

In column 9, record whether the scenario as written (U)nacceptable, in need of (E)nhancement, or (S)atisfactory from column 11 of the simulator scenario table.

ES-301 10 Form ES-301-7 Facility: V.C. Summer (Unit 1) Exam Date: 09/18/2017 Scenario 1

2 3

4 5

6 7

8 11 Event Totals Events Unsat.

TS Total TS Unsat.

CT Total CT Unsat.

% Unsat.

Scenario Elements U/E/S Explanation 1

7 0

2 1

2 0

14 E

2 6

0 2

0 4

0 0

E 3

7 0

2 0

4 0

0 S

4 6

0 2

0 5

0 0

E Instructions for Completing This Table:

Check or mark any item(s) requiring comment and explain the issue in the space provided.

1, 3, 5 For each simulator scenario, enter the total number of events (column 1), TS entries/actions (column 3), and CTs (column 5).

This number should match the respective scenario from the event-based scenario tables (the sum from columns 1, 6, and 7, respectively).

2, 4, 6 For each simulator scenario, evaluate each event, TS, and CT as (S)atisfactory, (E)nhance, or (U)nsatisfactory based on the following criteria:

a.

Events. Each event is described on a Form ES-D-2, including all switch manipulations, pertinent alarms, and verifiable actions. Event actions are balanced between at-the-controls and balance-of-plant applicants during the scenario. All event-related attributes on Form ES-301-4 are met. Enter the total number of unsatisfactory events in column 2.

b.

TS. A scenario includes at least two TS entries/actions across at least two different events. TS entries and actions are detailed on Form ES-D-2. Enter the total number of unsatisfactory TS entries/actions in column 4. (ES-301, D.5d)

c.

CT. Check that a scenario includes at least two preidentified CTs. This criterion is a target quantitative attribute, not an absolute minimum requirement. Check that each CT is explicitly bounded on Form ES-D-2 with measurable performance standards (see Appendix D). Enter the total number of unsatisfactory CTs in column 6.

7 In column 7, calculate the percentage of unsatisfactory scenario elements:

8 If the value in column 7 is > 20%, mark the scenario as (U)nsatisfactory in column 8. If column 7 is 20%, annotate with (E)nhancement or (S)atisfactory.

9 In column 9, explain each unsatisfactory event, TS, and CT. Editorial comments can also be added here.

Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario is marked by a (S)atisfactory resolution on this form.

2 + 4 + 6 1 + 3 + 5100%

ES-301 11 Form ES-301-7 Site name: V.C. Summer (Unit 1) Exam Date:

OPERATING TEST TOTALS Total Total Unsat.

Total Total Unsat.

Explanation Edits Sat.

Admin.

JPMs 9

0 8

1 Sim./In-Plant JPMs 11 1

7 3

Scenarios 4

0 3

1 Op. Test Totals:

24 1

18 5

4 Instructions for Completing This Table:

Update data for this table from quality reviews and totals in the previous tables and then calculate the percentage of total items that are unsatisfactory and give an explanation in the space provided.

1.

Enter the total number of items submitted for the operating test in the Total column. For example, if nine administrative JPMs were submitted, enter 9 in the Total items column for administrative JPMs.

For scenarios, enter the total number of simulator scenarios.

2.

Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 and simulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.

3.

Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous tables. This task is for tracking only.

4.

Total each column and enter the amounts in the Op. Test Totals row.

5.

Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. Test Total) and place this value in the bolded % Unsat. cell.

Refer to ES-501, E.3.a, to rate the overall operating test as follows:

  • satisfactory, if the Op. Test Total % Unsat. is 20%
  • unsatisfactory, if Op. Test Total % Unsat. is > 20%
6.

Update this table and the tables above with post-exam changes if the as-administered operating test required content changes, including the following:

  • The JPM performance standards were incorrect.
  • The administrative JPM tasks/keys were incorrect.
  • CTs were incorrect in the scenarios (not including postscenario critical tasks defined in Appendix D).
  • The EOP strategy was incorrect in a scenario(s).
  • TS entries/actions were determined to be incorrect in a scenario(s).

ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Randomly Reason for Rejection Group Selected K/A RD KAs Changes approved in thi&ii6t by email from Chief Examiner on 10/19/16.

2/2 055A3.03 055A3,03 Condenser Air Removal: Ability to monitor automatic operation of the system including: Automatic diversion of CARS exhaust.

Utility comment: VC Stirnmner does miot have an auto divert of CARS exh oust. It is nwnually aligned.

Replaced with 055K3.O1, Condenser Air Removal: Ability to monitor automatic operation of the system including: Main Condenser, (RO 2.5 SRO2.7) 3 G2.2.3 02.2.3 Knowledge ofthe design, procedural and operational differences between units.

Utility comment: V. C. Summer Unit 2amtd 3 are not operating and are of different designs. No multiunit licensing is anticipated.

Reilaced with G2.2.14, 02.2.14 Equipment Control Knowledge of the process for controlling equipment configuration or status. (RO 3.9 SRO 4.3)

SROKAs Changes approved in this section by email from Chief Examiner on 1 0/19/16.

3 02.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Utility comment: This is vemy similar to another K4, G2.3.14, on the sample plan.

Replaced with G2.3.6, Ability to approve release permits. (RO 2.0 SRO 3.8)

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: J, C.

- (

) Date of Exam: 5-Exam Level:

RO SRO El 1.

QuestIons and answers are technically accurate and applicable to the facility.

7 2.

a.

NRC KJAs are referenced for all questions.

A) b.

Facility teaming objectives are referenced as available.

a.

Correct answer explanation and distractor analysis provided (ES-401 D.2.g)

V 3.

SRO questions are appropriate in accordance with Section D.2.d of ES-401 t

4 The sampting process was random and systematic.

(If more than four RO or two SRO questions were repeated from the last two NRC licensing exams, consult the NRR)NRO oc program_office).

5.

Question duplication from the licensee screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate.

The audit exam was systematically and randomly developed, or the audit exam was completed before the license exam was started, or the examinations were developed independently, or ihe licensee certifies Ihat there is no duplication, or other (explain).

6.

Bank use meets limits (no more than 75% from the bank, Bank Modified New at least 10% new, and the rest new or modified); enter the SR actual R0/SRO-only question distribution(s) at right.

2 23 7) 7.

Between 38 and 45 questions of the questions on Ihe RO Memo C/A exam and at least 13 questions of the questions on the SRO-only portion of the exam are written at the RO SRO RO SRO comprehension/analysis level (see ES-401, D,2.c); enter 32 I

6 43 I

19 the actual_ROISRO-only_question_distribution(s)_at_right 8.

References/handouts provided do not give away answers or aid in the elimination of distractors.

9.

Question content conforms to specific K/A statements In the previously approved examination outline and_is_appropriate_for_the tier to_which_they_are_assigned;_deviations_are justified.

10.

Question psychometric quality and format meet the guidelines in Appendix B.

o1 11.

The exam contains the required number of one-point, multiple-choice items; the total Is correct and agrees with the value on the cover sheet.

Printed Name/Signature Date a.

Author Ja\\s b.

FacilIty Reviewer ()

74A)AI

,V41/?

W2?,47 a.

NRCChiefExaminerf#)

))(v)t.)

fv\\

d.

NRC RegionalSupervisor CTIAlh.rs_( /

,lvv.

ct13 J17 Note:

The facility reviewers Initials or signature are not applicable for NRC-developed examinations.

Independent NRC reviewer initials items in Column *0*; chief examiner concurrence Is required.

Item Description initial a

b c#

ES-401, Page 48 of 52

ES-401 Written Examination Review Worksheet Form ES-401-9 V.C. Summer Unit 1 2017-301 Q

1. LOK (F/H)
2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

Source (B/M/N)

7.

Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. /Units Backward Q - K/A SRO Only 1

H 2

N S

K/A 008AK2.02 Question is satisfactory.

2 H

2 X

X X

N E

K/A 009EK2.03 The first part question should not start with If. I do not believe that choices C.2 and D.2 are plausible with RCS pressure greater than S/G pressure, and TH greater than TC (Delta T across steam generators),

and both lowering. The first part question cues the applicants to use the steam tables. The title of the procedure also provides a cue. The support you highlighted concerning the SBLOCA discusses when the safety valves go closed and not when you are bleeding steam for a cooldown. Is it plausible for all of the hot and cold leg temperatures to be the same if there is safety injection and break flow at some location?

This is not a discriminating question the way that it is written.

8/15/17-Discussed validation results with licensee and additional reasons for plausibility. Licensee is updating the distractor analysis and rewording the first part question.

8/15/17 - Question is satisfactory.

3 H

2 N

S K/A 011EG2.2.36 Question is satisfactory.

4 H

2 X

M E

K/A 015AA1.06 Choice A is not plausible.

8/15/17-Licensee is replacing choice A with A CCW pump amps increase.

8/15/17 - Question is satisfactory.

ES-401 Written Examination Review Worksheet Form ES-401-9 V.C. Summer Unit 1 2017-301 5

H 2

X X

N U

K/A 022AK1.04 Choices A and B are essentially the same answer when compared with each other. Both choices imply that pressurizer level is currently not at program level. It is obvious that the automatic control system will return level to program as designed.

Question is unsatisfactory due to two non-plausible distractors.

8/15/17-Licensee is changing choice A wording.

8/15/17 - Question is satisfactory.

6 H

2 X

?

M E

K/A 025AA2.06 With both temperatures being in mode 4, only 10 degrees apart, and below the temperature required for LTOP, this question may not test if an applicant actually knows the value of the required temperature for LTOP.

Change the temperatures to 295 F and 305 F (and the answer to Choice D). Is the PORV information necessary in the initial conditions?

Should the information for the B RHR loop be included in the initial conditions? We need to discuss this.

8/15/17 - Licensee is changing the temperature in the current conditions to 310 degrees F and the answer will change to Choice D.

8/15/17 - Question is satisfactory.

7 H

2 X

M E

K/A 027AA1.01 Question stem needs to state at 5 seconds after the failure or something to that effect.

8/15/17-Licensee made changes as described.

8/15/17 - Question is satisfactory.

8 H

2 S

K/A 029EA1.08 Question is satisfactory.

ES-401 Written Examination Review Worksheet Form ES-401-9 V.C. Summer Unit 1 2017-301 Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts:

1.

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

2.

Enter the level of difficulty (LOD) of each question a 1 (easy) to 5 (difficult); questions with a difficulty between 2 and 4 are acceptable.

3.

Check the appropriate box if a psychometric flaw is identified:

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

Cues: The stem or distractors contain cues (e.g., clues, specific determiners, phrasing, length).

T/F: The answer choices are a collection of unrelated true/false statements.

Cred. Dist.: The distractors are not credible; single implausible distractors should be repaired, and more than one is unacceptable.

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

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 K/A but, as written, is not operational in content).

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).

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

Backward: The question requires reverse logic or application compared to the job requirements.

5.

Check questions that are sampled for conformance with the approved K/A and those K/As that are designated SRO-only. (K/A and license-level mismatches are unacceptable.)

6.

Enter questions source: (B)ank, (M)odified, or (N)ew. Verify that (M)odified questions meet the criteria of Form ES-401, Section D.2.f.

7.

Based on the reviewers judgment, is the question, as written, (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8.

At a minimum, explain any U status ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 4

Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 9

H 2

X N

E K/A 038EK1.01 The last word in the first bullet of the plant conditions should have an s at the end.

8/15/17-Licensee made change as described.

8/15/17 - Question is satisfactory.

10 H

3 M

S K/A 054AA2.03 Question is satisfactory.

11 H

2 X

X B

E K/A 055EG2.4.6 OAP-103.4 step 6.13.b states that EOP immediate operator actions shall be committed to memory. Are ROs required to know the first step if it is not an immediate action. AOP immediate operator actions are not required to be committed to memory. The immediately in choices C and D is different from choices A and B. This could potentially lead to choice A also being correct.

8/15/17-Licensee stated that this tests major mitigation strategy vice SRO knowledge of procedure direction and content.

Removed immediately from choices C and D.

8/15/17 - Question is satisfactory.

12 H

2 X

N E

K/A 057AK3.01 The interplay between APN-5903 being de-energized and choice B stating the reason as B train ESFLS being de-energized could provide a cue. Change the

ES-401 5

Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only reason in choice B to because APN-5903 is de-energized.

8/15/17-Licensee added that a LOOP at time 0715 and reworded choice C.

8/15/17 - Question is satisfactory.

13 H

2 N

E K/A 058AA2.01 Question was submitted for preliminary review.

Change the answer choices from was to is.

Is the second part question with the appropriate answer choice really fully correct? Isnt there more that you need to do to clear the alarm. Do you not need to start up the battery charger?

8/15/17-Licensee updated question for present tense.

Discussed other concerns and no other changes are required.

8/15/17 - Question is satisfactory.

14 H

2 X

X N

U K/A 062AG2.4.46 The noun name listed for the annunciator in choice B is not complete. It is actually FLO LO/TEMP HI. Should the active train be listed in the initial conditions? If choice A was correct, then choice B would also be correct. Same thing for choices C and D. Question is unsatisfactory due to more than one non-plausible distractor.

8/15/17-Licensee changed distractor answer choices.

ES-401 6

Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 8/16/17 - Choice A in the revised question does not appear to be plausible. The ARP for XCP-601 1-3 states that the probable cause for that alarm is an overcurrent trip in conjunction with an overload alarm.

8/16/17 - Verified with license that XCP-601 1-3 would alarm if the associated bus was de-energized.

8/16/17 - Question is satisfactory.

15 F

2 M

S K/A 077AK1.01 Question is satisfactory.

16 H

2 X

X N

E K/A WE04EK2.2 Question was submitted for preliminary review.

The second bullet in the initial conditions needs to be present tense.

8/15/17-Licensee updated question for present tense.

8/16/17 - Question is satisfactory.

17 F

2 X

N E

K/A WE11EK3.4 Change sub-cooling value in the initial conditions so that it is not superheated, but still does not meet the criteria for terminating SI.

8/15/17-Licensee made change as described.

8/16/17 - Question is satisfactory.

ES-401 7

Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 18 F

2 B

S K/A WE12EK3.2 Question was used on 2015-301 NRC exam.

Question is satisfactory.

19 H

2 X

B U

K/A 001AA2.05 Question is about rod insertion, not rod withdrawal.

Question is unsatisfactory due to not meeting the K/A.

8/15/17-Licensee wrote a new question.

8/16/17 - Question is satisfactory.

20 H

2 X

X N

E K/A 028AK3.03 Question was submitted for preliminary review.

Question stem should state conditions.

Choice A is not plausible with RVLIS at 50% and decreasing.

8/15/17-Licensee re-wrote question.

8/16/17 - Question is satisfactory.

21 F

2 X

N E

K/A 060AK1.01 The second part question stem needs to have curie added before content.

The distractor analysis is not correct. It discusses reducing hydrogen to <4% within one hour. The LCO action statement discusses reducing oxygen.

8/15/17-Licensee updated question and distractor analysis as required.

ES-401 8

Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 8/16/17 - Question is satisfactory.

22 F

2 X

N E

K/A 067AA2.15 Choices A.2 and C.2 are not plausible. For the second part question, ask if the re-flash watch is required to be stationed for a minimum of 20 or 30 minutes.

8/15/17-Licensee made changes as described.

8/16/17 - Question is satisfactory.

23 F

?/2 N

E K/A 068AG2.2.22 For the CREP, with steam generator level versus the other choices, believe that the level of difficulty is very low. Need to discuss.

8/13/17-Discussed validation results with licensee. Three of twelve validators did not pick the correct answer with choices A and D being chosen. Licensee updated distractor analysis with that information.

8/16/17 - Question is satisfactory.

24 H

2 N

S K/A 076AA1.04 Question is satisfactory.

25 H

2 N

S K/A WE08EK2.1 Question is satisfactory.

26 H

2 N

S K/A WE10EK2.2 Question is satisfactory.

27 F

2 N

S K/A WE15EK3.1 Question is satisfactory.

ES-401 9

Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 28 F

2 M

S K/A 003K6.14 Question is satisfactory.

29 H

2 X

M E

K/A 004K1.30 Choices A.2 and C.2 are not plausible. With more flow going in, how could letdown remain the same?

8/15/17-Licensee submitted a different bank question. Bank question submitted was on the 2013 NRC exam.

8/16/17 - Question is satisfactory.

30 H

2 M

S K/A 005A4.02 Question is satisfactory.

31 F

2 B

S K/A 005K4.12 Question is satisfactory.

32 H

2 M

S K/A 006K2.02 Question is satisfactory.

33 F

2 N

E K/A 006K5.04 The distractor analysis needs to be corrected. The analysis for the second part for choices B and D states that EOP-2.0 has a requirement to maintain pressurizer spray for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. It is actually Reactor Building spray.

8/15/17-Distractor analysis updated with correct information.

8/16/17 - Question is satisfactory.

34 F

2 B

S K/A 007K4.01 Question is satisfactory.

ES-401 10 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 35 F

2 N

S K/A 008K3.03 Question is satisfactory.

36 H

2 M

S K/A 010A4.02 Question is satisfactory.

37 H

3 X

N E

K/A 012A2.03 The distractor analysis does not make sense to me. It only talks about the input error inhibit switch for all choices. It does not mention the multiplexer test switch, which was operated in the conditions, for any choice.

Need clarification.

8/15/17-Distractor analysis updated with correct information.

8/16/17 - Question is satisfactory.

38 H

2 N

S K/A 013K2.01 Question is satisfactory.

39 F

2 B

S K/A 022A3.01 Question used on 2011 NRC exam.

Question is satisfactory.

40 H

2 M

S K/A 022A4.01 Question is satisfactory.

41 F

2 N

S K/A 026G2.2.38 Question was submitted for preliminary review.

Question is satisfactory.

42 H

2 M

S K/A 039K4.02 Question is satisfactory.

43 F

2 X

N E

K/A 059A1.07 Choice D is not plausible. 500 psig is too high. See Enclosure B of SOP-210.

ES-401 11 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 8/15/17-Licensee changed the pressure in choice D from 500 psig to 300 psig.

8/16/17 - Question is satisfactory.

44 H

2 M

E K/A 059K3.03 The word of needs to be inserted between failure and Steam in choices A.2 and C.2.

8/15/17-Licensee made changes as described.

8/16/17 - Question is satisfactory.

45 H

2 X

N E

K/A 061K5.01 The distractor analysis for choices B and D do not match the conditions given.

8/15/17-Distractor analysis updated with correct information.

8/16/17 - Question is satisfactory.

46 H

2 M

S K/A 061K6.01 Question is satisfactory.

47 F

2 B

S K/A 062K1.04 Question is satisfactory.

48 H

2 N

S K/A 063A1.01 Question is satisfactory.

49 H

2 X

?

X N

E K/A 064A1.05 Is the RO required to know the design basis temperatures for all rooms from memory?

Choices B.2 and D.2 are not plausible. Why would ventilation start for the diesel room be tied to safety injection and not diesel start? The diesel automatically starts for a LOOP without an SI.

ES-401 12 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 8/15/17-Licensee wrote a new question.

8/16/17 - Question is satisfactory.

50 H

2 N

S K/A 064A2.07 Question is satisfactory.

51 H

3 X

M U

K/A 073A2.02 Do your ROs have to know ODCM action statements from memory?

Question is unsatisfactory due to license level mismatch.

8/15/17-Licensee is modifying the question.

8/16/17 - Question is satisfactory.

52 H

2 B

S K/A 076G2.4.46 Used on 2015 NRC exam.

Question is satisfactory.

53 F

2 M

S K/A 076K2.01 Question is satisfactory.

54 F

2 N

S K/A 078G2.2.38 Question is satisfactory.

55 F

2 N

S K/A 103A3.01 Question is satisfactory.

56 F

2 N

S K/A 001K6.08 Question is satisfactory.

57 F

2 M

S K/A 002A2.04 Question is satisfactory.

58 H

2 X

N E

K/A 011K2.02 Group is capitalized in choice D, but not in any of the other choices.

The distractor analysis for choice A has an extra if in it.

ES-401 13 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 8/15/17-Licensee made changes as described.

8/16/17 - Question is satisfactory.

59 H

2 B

S K/A 014G2.2.44 Question is satisfactory.

60 H

3 B

S K/A 017A1.01 Question is satisfactory.

61 H

3 N

S K/A 029A4.01 Question is satisfactory.

62 H

2 M

S K/A 033K4.01 Question is satisfactory.

63 F

2 X

X

?

M E

K/A 055G2.4.21 Question has a justification statement that states that it is SRO-Only.

The given conditions do not address whether there is feed from the turbine driven EFW pump. This could make choice A not plausible.

8/15/17-Licensee removed erroneous SRO Only statement and added the TDEFWP running in the given conditions.

8/16/17 - Question is satisfactory.

64 H

2 M

S K/A 055K3.01 Question is satisfactory.

65 F

2 B

S K/A 068K1.07 Question is satisfactory.

66 F

2 M

S K/A G2.1.3 Question is satisfactory.

ES-401 14 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 67 F

2 X

M U

K/A G2.1.37 Choices A and B are not plausible.

Question is unsatisfactory due to more than one non-plausible distractor.

8/15/17 - Licensee modified the question.

8/16/17 - Question is satisfactory.

68 F

2 B

S K/A G2.2.14 Used on 2015 NRC exam.

Question is satisfactory.

69 F

2 X

M E

K/A G2.2.36 The title of the Technical Specification listed in the question stem is not correct.

8/15/17-Licensee corrected TS LCO title.

8/16/17 - Question is satisfactory.

70 F

2 X

?

M E

K/A G2.3.13 What is the actual criteria for placing RB Charcoal Filters in service? Are there potentially two correct answers. Who determines what sample analysis dictates?

8/15/17-Licensee changed the second part question.

8/16/17 - Question is satisfactory.

71 F

2 X

X M

U K/A G2.3.14 Question does not meet the K/A.

It tests EOP knowledge and systems knowledge. Choices

ES-401 15 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only C.1 and D.1 are not plausible.

Question is unsatisfactory due to more than one non-plausible distractor and not meeting the K/A.

8/15/17-Licensee is replacing the question.

8/16/17 - Question is satisfactory.

72 F

2 M

S K/A G2.3.4 Question is satisfactory.

73 H

2 X

X N

U K/A G2.4.2 The annunciator noun name provides clues to the correct answer. Choices A.1 and A.2 are not plausible distractors.

Question is unsatisfactory due to more than one non-plausible distractor.

8/15/17-Licensee re-wrote the question.

8/16/17 - Question is satisfactory.

74 H

2 N

S K/A G2.4.21 Question is satisfactory.

75 F

2 X

N S

K/A G2.4.43 Question was submitted for preliminary review.

Question is satisfactory.

76 H

2 X

?

N E

K/A 007EA2.04 Choice B is not plausible given the conditions. Request that the question stem be stated, The CRS (or SRO) will next direct.

(or something to that effect). Red path entry conditions are RO knowledge. Need to discuss.

ES-401 16 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 8/15/17-Licensee is changing current power level to less than 5% with a negative IR SUR.

8/16/17 - Question is satisfactory.

77 H

1 X

X X

X M

U K/A 009EA2.06 The fourth bullet in the initial conditions could be a cue.

Choice A is not plausible given the conditions and could be eliminated by RO level of knowledge. Choice D can be eliminated by RO level systems knowledge (location of components). Choice C is also potentially correct with the wording of the stem and choice.

Why would anyone enter EOP-2.0 and just wait for EOP-2.2?

Question is unsatisfactory due to LOD =1.

8/15/17-Licensee is submitting a new question.

8/16/17 - Question is satisfactory.

78 H

2 N

S K/A 007AA2.12 Question was submitted for preliminary review.

Question is Satisfactory.

79 F

2 M

S K/A 040AG2.2.38 Question is Satisfactory.

80 H

2 N

S K/A 057AG2.1.30 Question is Satisfactory.

81 H

2 N

S K/A 062AG2.4.35 Question is Satisfactory.

82 H

2 N

S K/A 059AG2.4.21 Question is Satisfactory.

ES-401 17 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 83 H

2 N

S K/A 067AA2.14 Question was submitted for preliminary review.

Question is Satisfactory.

84 H

2 N

S K/A WE06EG2.4.11 Question is Satisfactory.

85 H

2 X

N U

K/A WE15EA2.1 See EOP-12 and 17.1.

Question is unsatisfactory due to not meeting the K/A.

8/15/17-Licensee is submitting a new question.

8/16/17 - Question is satisfactory.

86 H

2 N

S K/A 004G2.1.23 Question is Satisfactory.

87 F

2 N

S K/A 006G2.2.44 Question is Satisfactory.

88 H

2 N

S K/A 013A2.04 Question is Satisfactory.

89 F

2 B

S K/A 059A2.03 Question is Satisfactory.

90 H

2 X

N E

K/A 064A2.08 The distractor analysis states that one of the reasons for being in the condition is the TDEFW pump being inoperable. Based on the given conditions, that does not appear to be the case.

8/15/17-Licensee corrected the distractor analysis.

8/16/17 - Question is satisfactory.

ES-401 18 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 91 F

2 N

S K/A 002A2.04 Question was submitted for preliminary review.

Question is Satisfactory.

92 H

1 X

B U

K/A 011G2.4.46 The second part of the question is a direct lookup. Is an LCO met if you are not even in a mode of applicability?

Question is unsatisfactory due to LOD = 1.

8/15/17-Licensee significantly modified the question.

8/16/17 - Question is satisfactory.

93 H

2 X

X

?

N U

K/A 041A2.02 Choice B is not plausible with the given conditions.

The last bullet in the current conditions is missing the /.

Need to discuss if this is a K/A match.

Choices C and D are not plausible given the current conditions. D is a subset of C.

Question is unsatisfactory due to more than one non-plausible distractor.

8/15/17-Licensee is modifying the question.

8/16/17 - Question is satisfactory.

94 H

2 N

S K/A G2.1.34 Question is satisfactory.

ES-401 19 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 95 H

2 X

N E

K/A G2.1.6 Question was submitted for preliminary review.

Some of the distractor analysis does not match the second part question. The question asks nothing about peer checks.

The K/A match statement does not match the question.

3/14/17 - Licensee corrected the K/A match statement and the distractor analysis.

8/16/17 - Question is satisfactory.

96 F

2 X

N S

K/A G2.2.6 Need to discuss wording of 6.7.2 and 6.7.3 of VCS-SAP-0139.

Question is satisfactory.

97 H

2 B

S K/A G2.3.12 Used on 2016 NRC exam.

Question is satisfactory.

98 H

1 N

U K/A G2.3.6 The first part question is a direct lookup. The second part question (surveillance extension) was tested on a previous question.

Question is unsatisfactory due to LOD = 1.

8/17/14-Licensee revised the question.

8/16/17 - Question is satisfactory.

ES-401 20 Form ES-401-9 Q

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. Source (B/M/N)
7. Status (U/E/S)
8. Explanation Stem Focus Cues T/F Cred.

Dist Partial Job-Link Minutia

  1. / Units Backward Q - K/A SRO Only 99 H

2 X

N E

K/A G2.4.19 Could ask if the event would be classified as an alert or unusual event.

8/15/17 - Licensee modified question.

8/16/17 - Question is satisfactory.

100 H

2 X

X X

N E

K/A G2.4.44 Question was submitted for preliminary review.

The distractor analysis does not match the question for all choices.

Choices C.1 and D.1 are not credible when compared to A.1 and B.1.

8/15/17-Licensee is submitting a new question.

8/16/17 - Question is satisfactory.