ML20043F025

301, 2A-3, Exam Administrative Items (Delayed Release)

ML20043F025
Person / Time
Site:	Watts Bar
Issue date:	02/12/2020
From:	Tennessee Valley Archaeological Research
To:	NRC/RGN-II
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ML20043F022	List: ML20043F024 ML20043F025
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Download: ML20043F025 (61)

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: August 2019 Examination Level:

RO SRO Operating Test Number: 2019-301 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations R, N Evaluate a pre-determined Main Turbine Roll strategy IAW 1-SOI-47.02. Evaluate LCOs and Operating Requirements for partial completion of 1-TRI-47-2, Main Turbine Overspeed Test, and determine any required ACTIONs.

K/A Conduct of Ops: 2.1.23 (4.3/4.4): Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Conduct of Operations R, M Evaluate a pre-determined calculation for amount of boric acid addition needed to raise RCS Cb to a specified value IAW 2-SOI-62.02 Appendix D and 2-TI-59. Determine OPERABILITY of BAT B following the specified boration with no make-up to BAT B. (Modified to Unit 2 and different RCS Cb values and LCO actions.)

K/A Conduct of Ops: 2.1.25 (3.9/4.2): Ability to interpret reference materials such as graphs, curves, tables, etc.

Equipment Control R, M Review quarterly performance test of Containment Spray Pump 2B-B. Determine LCOs NOT met and ACTIONs required.

(Modified to specified pump with associated LCO actions.)

K/A Equipment Control 2.2.12 (3.7/4.1)

Knowledge of surveillance procedures.

Radiation Control R, D, P Determine Requirements for Authorizing Emergency Exposure. SROs determine EPIP-15 Appendix B requirements.

K/A Radiation Control 2.3.4 (3.2/3.7):

Knowledge of radiation exposure limits under normal or emergency conditions.

ES-301 Administrative Topics Outline Form ES-301-1 Emergency Plan R, N REP Classification and State Notification (Site Area Emergency (SAE) based on HS6, Inability to control a key safety function from outside the Control Room)

K/A Emergency Procedures 2.4.29 (4.4):

Knowledge of the emergency plan.

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 Conduct of Operations 1. (3-OT-J1A-0-1AS-S4702) The following are provided to the SRO applicants as part of a Main Turbine Roll strategy:

1. Minimum time to bring Main Turbine to synchronous speed (from 1-SOI-47.02, Turbo-Generator Startup Operation, Figure 3, Turbine Startup Curve).

2. Selected Turbine Acceleration Rate IAW 1-SOI-47.02 Section 5.3, Rolling Turbine, and Section 8.17.4, Turbine Acceleration Rate.

3. Hold times and rpm settings at these times IAW 1-SOI-47.02 Attachment 2, Turbine Resonant Speed Ranges.

SRO applicants will determine if the provided Main Turbine Roll Strategy meets all requirements. Strategy will be flawed.

SRO applicants evaluate a failure of 1-FCV-1-64, HP Turbine Stop Valve #2, to CLOSE during performance of 1-TRI-47-2, Main Turbine Overspeed Test, against TR LCO 3.3.5, Turbine Overspeed Protection, for OPERABILITY; and OR 14.10, Fire Safe Shutdown Equipment, for functionality. SRO applicants will specify required actions.

Conduct of Operations 2. (3-OT-J1A-0-1AS-S6202) SRO applicants evaluate a completed calculation for amount of boric acid addition (gal) required to raise RCS Cb from EOL value (~50 ppm) to P-11 block value (~700 ppm) IAW 2-SOI-62.02 Appendix D and 2-TI-59 given initial RCS temperature and RCS boron concentration. Calculated amount of boric acid will be wrong.

SRO applicants interpret an indication for initial BAT B level, determine BAT B volume following a boration using the above calculated value (even though incorrect) and evaluate BAT B volume against TR 3.1.6, Borated Water Sources, Operating, for OPERABILITY. SRO applicants will specify required actions.

Equipment Control. (3-OT-J8A-0-2AS-SI7291) SRO applicants will review quarterly performance test of Containment Spray Pump 2B-B. Calculations for pump Differential Pressure will be incorrect and NOT meet acceptance criteria. Pump vibration will NOT meet acceptance criteria.

SRO applicants determine appropriate LCOs NOT MET based on any acceptance criteria NOT met. SRO applicants will specify required actions.

Radiation Control. (3-OT-J1A-0-1AS-R15) SRO applicants:

1. Determine the exposure expected to be received by the AB AUO during the completion of a series of tasks. Task durations and dose rates are provided in tabular format.

2. Determine if EPIP-15, Emergency Exposure Guidelines, Appendix B, Authorization to Exceed Occupational Dose Limits Form, is required.

Emergency Plan. (3-OT-J1A-0-1AS-R1) SRO applicants assume the role of Site Emergency Director and classify an abandonment of the MCR IAW EPIP-1, Emergency Plan Classification Logic, Emergency, Attachment 1, WBN Hot Condition EALs (wallboard). SRO applicants declare a SITE AREA EMERGENCY based on HS6, Inability to control a key safety function from outside the Control Room, within 15 minutes of being provided the data. (Time Critical)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar.

Date of Examination: August 2019 Exam Level:

RO SRO-I SRO-U Operating Test No.: 2019-301.

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function

a. Align Control Bank D to Misaligned M8 after runback 001 A2.17 (3.3/3.8)

N, A, S 1

b. Add water to Cold Leg Accumulator 2 006 A4.07 (4.4/4.4)

N, A, L, S 2

c. Align RHR for Hot Leg Recirculation 006 A4.04 (3.7/3.6)

A, D, EN, S 4P

d. Latch Main Turbine 045 A4.01 (3.1/2.9)

N, S 4S

e. Manually CLOSE Phase A Train B valves 103 A3.01 (3.9/4.2)

N, EN, S 5

f. Synchronizing DG 1B-B from the MCR 064 A4.01 (4.0/4.3)

A, D, P, S 1606 6

g. Respond to ERCW Flood alarm 076 A4.01 (3.5/3.7)

A, D, S 8

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

System / JPM Title Type Code*

Safety Function

i. Perform local Emergency Boration 004 A2.14 (3.8/3.9)

D, E, P, R 1606 2

j. Isolate CST from Hotwell 061 A1.04 (3.9/3.9)

D, E 4S

k. Transfer 250VDC Turbine Building Distribution Board 1 058 A1.01 (3.4/3.5)

D 6

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 (A)lternate path 5 (C)ontrol room (D)irect from bank 6 (E)mergency or abnormal in-plant 2 (EN)gineered safety feature 2 (L)ow-Power / Shutdown 1 (N)ew or (M)odified from bank including 1(A) 4 (P)revious 2 exams 2 (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

Align Control Bank D to Misaligned M8 after Runback. (3-OT-J8A-1-1SI-A2) Applicant withdraws CBD to M8 which is 15 steps above CBD IAW AOI-2 section 3.4. During CBD withdrawal, CBC Group 1 fully inserts requiring a Reactor Trip.

Add Water to Cold Leg Accumulator 2. (3-OT-J1A-1-1SI-S63E0) Unit is in MODE 3 with RCS temperature approx.

500 F and RCS pressure approx. 1500 psig. Applicant will add water to Cold Leg Accumulator 2 IAW 1-SOI-63.01 to clear alarm 132-A, CL ACCUM 2 LEVEL HI/LO. Applicant will manually initiate Safety Injection in response to a small break LOCA that cannot be isolated prior to Pressurizer level dropping below 15% (approx. 2 minutes from start of small break LOCA). AUTO SI on Containment Pressure HI is failed. AUTO SI on Pressurizer Pressure LO is blocked.

Align RHR for Hot Leg Recirculation. (3-OT-J2E-1-1SI-E1.4) Applicant attempts to align RHR Train A for Hot Leg Recirculation, but to due 1-FCV-74-33 failure, re-aligns RHR Train A to Cold Leg Recirculation then aligns RHR Train B to Hot Leg Recirculation.

Latch Main Turbine. (3-OT-J8A-1-1SI-S47) Applicant will latch Main Turbine IAW 1-SOI-47.02 Section 5.2. Applicant will perform lamp test, verify alarm status, latch the turbine, check valve status and open the governor valves by raising the Valve Position Limiter (VPL) to 100%.

Manually CLOSE Phase A Train B valves. (3-OT-J8A-0-1SI-E0) Applicant will manually CLOSE Phase A Train B valves IAW 1-E-0 Attachment 10. SI occurred due to LOCA. SSPS Train A master relay K502 failed to actuate resulting in the following (only 1-E-0 Attachment 10 MCR valves/dampers listed) to CLOSE automatically: 1-FCV 305, 1-FCV-31-309, 1-FCV-31-327, 1-FCV-31-329, 1-FCV-61-192, 1-FCV-61-194, 1-FCV-62-77, 1-FCV-77-9, 1-FCV-77-16, 1-FCV-77-18 and 1-FCV-77-127.

Synchronizing DG 1B-B from the MCR. (3-OT-J2A-1-1SI-S82.2) Applicant will synchronize and load DG 1B-B IAW 0-SOI-82.02 Section 8.1.4 and Emergency Stop DG 1B-B due to Low Lube Oil Pressure IAW ARI-205-B.

Respond to ERCW Flood Alarm. (3-OT-J1E-1-1SI-S67A13) Applicant starts E-B ERCW pump and responds to an ERCW supply header rupture in the Auxiliary Building by isolating the header IAW 0-AOI-13.

Perform local Emergency Boration. (3-OT-J1A-0-1AB-FRS1) Applicant will perform local emergency boration IAW 1-FR-S.1 due to 1-FCV-62-138 being unable to be opened from the MCR or locally.

Isolate CST from Hotwell. (3-OT-J2A-0-1TB-EC00) Applicant isolates CST A from the Unit 1 Hotwell IAW 1-ECA-0.0.

Transfer 250VDC Turbine Building Distribution Board 1. (3-OT-J1C-0-1TB-S239) Applicant simulates transferring 250VDC Turbine Building Distribution Board 1 to its Alternate supply IAW 0-SOI-239.01.

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Watts Bar Exam Date: August 12 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.

SRO 1S COO: Review Turbine Roll Limitations and Turbine Testing Results 2.1.23: Ability to perform specific system and integrated plant procedures during all modes of plant operation 3

S Rev 0 comment: The K/A identified for this task does not match the task in the as-written JPM (i.e. there is no execution of procedure steps present). The K/As most appropriate for use here are: 2.1.23 or 2.1.25 K/A 2.1.20 could be appropriate if the initiating cue was modified. Example: Perform a review of 1-TRI-47-2 IAW Step xx. However, 1-TRI-47-2 has no procedural performance steps for an SRO.

What is the purpose of adding JPM page 14: Questions 1, 2, 3, and conditions? Is this JPM trying to elicit answers to these questions or perform a review of a completed procedure? Maybe a bit of both?

The as-written JPM seems to meld two versions of a JPM into a single product but becomes confusing in implementation (i.e. address questions 1, 2, 3 &

perform partial procedure review?).

Can an SRO perform a procedural review although Steps [13], [16], and Section 7 of 1-TRI-47-2 are not completed?

How is a Turbine Rolling Plan normally provided to the on-shift SRO for approval?

Rev 1 comment: no changes in submitted version Post prep comment: Editorial revisions required, SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 SRO 2S COO: Review Boration Calculation 2.1.25: Ability to interpret reference materials such as graphs, curves, tables, etc.

3 S

Rev 1 comment: Remove to allow Low Steamline Pressure SI to be blocked as the RCS depressurizes below P-11 from the third bullet under Initial Conditions Revise the fourth bullet under Initial Conditions to read: Boric Acid Tank (BAT) B is currently available at 10900 gallons with a sampled boron concentration of 6820 ppm Revise the fifth bullet under Initial Conditions to read:

Boric Acid Tank (BAT) B will be used for this evolution.

Revise the second bullet under Initiating Cues to read:

Evaluate Technical Specifications (Requirements), as necessary.

Remove the second page from the Applicant Cue Sheet (page with questions 1 and 2)

Post prep comment: Editorial revisions required, SAT SRO 3S EC: Review CS Pump 2B-B Quarterly Performance Test 2.2.12:

Knowledge of surveillance procedures 3

S Rev 1 comment: As submitted, JPM is UNSAT.

Post prep comment: Editorial revisions required, SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 SRO 4S RC: Calculate the Expected Dose and Determine if SED is permitted to authorize Emergency Dose Limits in excess of TVA Administrative Dose Limits.

2.3.4: Knowledge of radiation exposure limits under normal or emergency conditions 3

S Rev 1 comment: Significant overlap with this JPM and SRO Question #99 of the written exam. Written exam modification is recommended as Q99 K/A is much broader in scope.

Revise first bullet under Initial Conditions to read: An ALERT has been declared due to a Loss of RHR Shutdown Cooling during Midloop Operations. The TSC is manned.

Revise second bullet to read: RHR Pump 1B-B is OOS and 1A RHR Pump is air bound and must be vented using 1-TV-74-543 AND 1-TV-74-504 in accordance with appropriate procedures.

Relocate table of information under Initiating Cue to reside under Initial Conditions. Split table up by valve number for each identified AUO. Revise times/Dose Rates for AUO 1 to result in a total expected dose of 17 Rem (manipulation of 1-TV-74-543). Revise times/Dose Rates for AUO 2 to result in a total expected dose of 9 Rem (manipulation of 1-TV 504).

Relocate NOTE to Initial Conditions.

Revise first bullet under Initiating Cue to read:

Calculate expected AUO doses and determine ability to perform this task. Include required actions, if appropriate.

Remove second bullet under Initiating Cues.

If JPM Step 4 is critical, then JPM Steps 1, 2, and 3 are not. Or vice versa. We shouldnt be double hitting the applicants during calculations with critical steps.

Ensure JPM contains CRITICAL STEPS for determination of dose for AUO 1 & 2 and that SED permission is required to perform task.

Can an applicant conclude that another source of DHR is available to mitigate plant heatup (i.e. CA3)?

Post prep comment: Editorial revisions required, SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 SRO 5S EP: REP Classification and State Notification 2.4.29:

Knowledge of the emergency plan 3

S Rev 1 comment: Add a new bullet under Unit 1 Conditions to read: The 1A and 2B 6.9kV Shutdown Boards have been lost with no expected time of recovery available Add a new bullet under Unit 1 Conditions to read:

National Weather Service provided wind direction is 270o with an average speed of 10 mph Add a new bullet under Unit 1 Conditions to read:

There are no impediments to evacuation Add chart under Unit 1 conditions with normal steady state values at 100% Rx Pwr for the following rad monitors (in cpm): Shield Building Exhaust, 1-RM 400; Aux Building Vent Gas monitor, 0-RM-90-101; and Condenser Vacuum Exhaust, 1-RM-90-255/256 Revise second bullet under Initial Conditions to read:

CCP 1B-B is tagged out for maintenance Revise fourth bullet under Initial Conditions to read:

The Operating crew has abandoned the Main Control Room Revise the sixth bullet under Initial Conditions to read:

When the Transfer Switch for CCP 1A-A is placed in AUX, CCP 1A-A breaker OPENs and cannot be reclosed Revise seventh bullet under Initial Conditions to read:

You are the Shift Manager Remove the first bullet under Initiating Cues.

Add a new bullet under Initiating Cues to read: The current time is, as indicated on the wall mounted clock (CURRENT time)

Add blank Appendix As of EPIP-2, 3, 4, and 5 (pages 1 and 2) to the Handout Package for Applicant section of this JPM.

Remove JPM steps 1-4 Post prep comment: Editorial revisions required, SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 1

Simulator/

In-Plant Safety Function and K/A JPMs 4-6x AP 1x (ESF & s/d LP)

LOD I/C Focus Cues Critical Steps Scope Overlap Perf.

Std.

Key Minutia Job Link U/E/S Explanation JPM A AP SF 1, 001A2.17: Rod mis-alignment alarm 3

S Rev 1 comment: Remove bullets 1, 4 and 5.

Revise bullet 2 to read: The following plant conditions exist after an unanticipated runback and lift coil fuse failure.

Add a new bullet under the Initiating Cues first bullet to read: Steps 1 through 8 have already been completed, you are directed to begin starting at Step 9 If appropriate at WBN ensure a pre-marked up copy of Section 3.4 is provided to each applicant with steps 1-8 circle/slashed.

Remove JPM Steps 1-8.

Im not understanding initiation of the alternate path (JPM Step 12). Is this incorporated to occur as a result of operator action at a specific CBD position? Actuation of the control switch at a specific time? It is desirable to standardize the rod drops to ensure consistent administration to all applicants.

Considering the incorporation of a time standard (2 min) associated with JPM Step 12. This JPM should be marked as TIME CRITICAL. Ensure the plant design basis consideration for incorporation of the 2 min management expectation is incorporated into this JPM.

(may require modification of the Task Standard and/or Time Critical areas of Pg 2)

Ensure Applicant Cue Sheet is revised.

Post prep comment: Editorial revisions required, validation time changed to 10 minutes, SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 JPM B s/d, LP AP SF 2, 006A4.07: ECCS Pumps and Valves 3

S Rev 1 comment: Plant indications that are readily observable during simulator JPMs are not provided in applicant cue sheets. Remove first and third bullets under Unit 1 conditions.

Why is SI Pump 1B unavailable for this JPM?

Inadvertent use of this pump appears to be an appropriate evaluation tool during performance of Step

[8] and should be retained.

Revise bullet two under Unit 1 conditions to read:

During a maintenance activity, Cold Leg Accumulator 2 was inadvertently drained.

Revise first bullet under Initiating Cues to read:

Complete 1-SOI-63.01, Section 8.3.2, starting at Step 2

Ensure a marked-up procedure is available for each applicant with Step 1 circle/slashed (as appropriate at WBN)

Remove JPM Step 1 Regardless of what the applicant asks or the report they make, JPM Step 11 is the completion point of this JPM. Revise the cue for JPM Step 11 to read, Another operator will continue from here to signify completion.

Post prep comment: Editorial revisions required, SAT JPM C ESF AP Bank SF 4P, 006A4.04: Ability to manually operate/

monitor RHR 3

S Rev 1 comment: Remove the second bullet under Unit 1 conditions.

Post prep comment: Editorial revisions required, validation time changed to 10 minutes, JPM Step 1 is not critical, SAT JPM D SF 4S, 045A4.01: Turbine vlv inds, alarms, and anns 3

S Rev 1 comment: Remove first bullet under Unit 1 Conditions (Rx Pwr is readily observable).

Revise first bullet under Initiating Cues to read:

Perform 1-SOI-47.02, Section 5.2 Revise the second bullet under Initiating Cues to read:

Notify the US when task complete Revise the Cue for JPM Step 20 to read: Another operator will continue from here Post prep comment: Editorial revisions required SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 JPM E ESF 5,

103A3.01:

Containment Isol 3

S Rev 1 comment: Potential overlap with Simulator Exam (performance of E-0, Att 10), may require revising JPM or scenario to remove overlap Remove the third bullet under Unit 1 Conditions.

What is the basis for specifying that the applicant is an extra operator (i.e. bullet 4 under Unit 1 conditions)?

Revise the first bullet under Initiating Cues to read:

Perform 1-E-0 Attachment 10 Revise the second bullet under Initiating Cues to read:

Notify the US when task complete Should the standard for JPM Step 5 read: No manipulations are required on 1-M-5?

Revise the Cue for JPM Step 9 to read: Another operator will continue from here Post prep comment: SAT JPM F AP Bank Previous 6,

064A4.01/.03: Ability to manually operate/

monitor EDG/Synchroscope 3

S Rev 1 comment: Remove the first bullet under Unit 1 and Unit 2 Conditions. Why not just state Plant Conditions as the title here?

Add a bullet under Unit 1 and Unit 2 Conditions that states: The load dispatcher has been notified of DG operations.

Revise bullet 1 under Initiating Cues to read: Perform 0-SOI-82.02, Section 8.1.4 using DG 1B-B Remove bullet 2 under Initiating Cues.

Incorporate acceptable observation bands for JPM Steps 7, 8, and 9.

What is the expected DG loading value (i.e. by applicant training) applicants will establish in JPM Step 11? 1.1-1.5 MW? Do we expect applicant to go all the way to 2 MW here?

It is desirable for 205-B to annunciate for every administration of this JPM (consistent administration).

Is there a possibility that JPM Step 13 would require manual sim booth action to accomplish? Why?

Add to the Cue for JPM Step 17 to read: Another operator will continue from here Post prep comment: Editorial revisions required, SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 JPM G AP Bank 8,

076A4.01: ERCW, correct/control mitigate 3

S Rev 1 comment: Add a bullet under Unit 1 and Unit 2 Conditions to read: Performance of 0-SOI-67.01, Appendix A & Appendix B are NOT required.

Revise the Cue in JPM Step 5 to read: If AUO is dispatched again, acknowledge request, and report:

The flooding is coming from the pipe tunnel above the Unit 1 TDAFW pump from the 1B ERCW Supply Header.

At what panel (indication) is the applicant expected to perform the JPM Step 7 verification?

At what panel (indication) is the applicant expected to perform the JPM Step 8 verification?

Is it expected that an applicant will secure any ERCW pumps in JPM Step 14?

Add a Cue in JPM Step 14 to read: Another operator will continue from here Post prep comment: Editorial revisions required, SAT JPM H N/A (no RO)

JPM I ESF Bank Previous RCA 2,

004A2.14: CVCS, correct/control mitigate 3

S Rev 1 comment: Remove bullets 2, 3 and 4 under Initial Conditions.

Add a bullet under Initial Conditions to read: 1-FR-S.1, Nuclear Power Generation / ATWS is currently in progress Revise bullet 1 under Initiating Cues to read: Perform 1-FR-S.1, Step 4.g RNO.

Remove the last Cue in JPM Step 1 (one that includes:

tell them to continue with )

Add a Cue in JPM Step 4 to state: Another operator will continue from here Post prep comment: SAT JPM J ESF Bank 4S, 061A1.04:

Predict/monitor changes in AFW source tank paras 3

S Rev 1 comment: SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 JPM K Bank 6,

058AA1.01:

Operate/monitor DC Bus alt supply x-tie wrt DC 3

S Rev 1 comment: Remove bullets 1 and 2 under Initial Conditions Revise the opening statement under Initiating Cues to read: The Unit Supervisor has directed you to: (to remove potential ambiguity with Step [1])

Revise bullet 1 under Initiating Cues to read: Perform 0-SOI-239.01, Section 8.7.1 Remove Verification statement cue in JPM Steps 5, 6, 7, 8, and 12. Examiners will not verify correct component or position.

Post prep comment: SAT

ES-301 Operating Test Review Worksheet 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 Operating Test Review Worksheet Form ES-301-7 Facility: Watts Bar Scenario: 2 Exam Date: August 12 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 1N (BOP)

S S/D TDAFW Pump and MDAFW 1B-B (SI-99-303-B)

It would be helpful to identify in the D-2 portion what the verifiable actions are (i.e. by highlighting the specific steps the operators will be performing)

Why is this event included? One normal evolution per scenario is all thats required for each applicant to obtain their NOR. Since this class is all Instants, it would be prudent to incorporate the NOR as an OATC task.

Post prep comment: SAT 2N (OAC)

S S/U CCP 1A-A and S/D CCP 1B-B (SOI-62.01)

It would be helpful to not have to wait for both time intervals during actual administration (i.e. 2 min and 30 sec - closing springs charged reports).

Post prep comment: SAT 3I/TS (BOP/SRO) x S

1-PT-1-72 fails low (ARI 66-E or 1-AOI-2), TS ARI 66-E usage is defined as a success path for the applicants yet is not included in the D-2?

Post prep comment: SAT 4I (OAC)

S 1-PT-62-81 fails low (letdown isolation) (ARI-110-C)

Post prep comment: SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 5C/TS (BOP/SRO) x S

CCS leak downstream of CCS C-S (1-AOI-15)

The roleplay on Page 23 requires modification. Applicants are not cued by the sim booth for actions during administration. The only role play performed should be reporting of MCR requests or reporting of field investigations as directed by the applicant crew. Remove I wont be able to isolate it with the pump running and Do you want me to CLOSE 0-ISV-70-505?

Same issue with roleplay on Page 26.

Which TS requires entry based on this scenario event? Is it the list of 4 on page 38?

Post prep comment: SAT 6C (OAC)

S RCP #3 seal leak Post prep comment: SAT 7R (OAC)

S RCP #3 seal failure, rapid downpower (1-AOI-39)

What is the expected target power level based on training?

Is there a specific load rate % that the applicants are expected to use here?

NOTE: Expect examiner to advance the scenario once a power change ~ 5% is observed.

Examiners may desire seeing more activities, but 5% is a good rule-of-thumb.

Post prep comment: SAT 8M S

RCP trip criteria met => Rx trip/RCP trip/E-0 -> ES-0.1 -> E-0 -> E-1 -> ES-1.3 Failure of SI train A Typically when you make the transition from RCP trip criteria exceedance to Loop 3 LOCA

- this would be identified as the transition point of a different scenario event (i.e event 8 to event 9) - Top Page 65, I dont think you have to change it here (will discuss during Prep week)

Is it guaranteed in the as-constructed scenario for RWST level to drop < 34%? So its possible that ES-1.3 will not be entered? (Page 88) Whats the timeframe here?

Scenario D-2 header changes to Scenario 1 on page 105. (for E-0 Appendices)

Post prep comment: SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 9C (BOP)

CT x

S ECCS Train A pumps FTS (SI train A) - (E-0 Appendix A)

Is this actually an Instrumentation failure (due to failure of SI train A logic)? There isnt anything actually wrong with these pumps?

CT: Manually s/u RHR pump 1A-A prior to meeting ORANGE path - at what point would the criteria for an ORANGE path be met in the as-constructed scenario?

Revise Scenario D-2 to include identification of Event 9 (top of page)

Post prep comment: SAT 10C (OAC)

CT x

S 1-FCV-63-72 fails to OPEN (SI train A)

Is this actually an Instrumentation failure (due to failure of SI train A logic)? There isnt anything actually wrong with this valve?

CT: 1-FCV-63-72 OPEN prior to RWST lvl reaching 8% - how long does it take for RWST lvl to drop to 8% as-constructed?

Revise Scenario D-2 to include identification of Event 10 (top of page)

Post prep comment: SAT 11C (BOP)

S Cont Air Return Fan (CARF) 1B-B o/c trip on s/u, CARF 1A-A trips 1 min later Revise Scenario D-2 to include identification of Event 11 (top of page)

Post prep comment: SAT 11 2

2 0

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Watts Bar Scenario: 3 Exam Date: August 12 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 1N (OAC)

S Lower VCT pressure (SOI-62.01)

Post prep comment: SAT 2N (BOP)

S Transfer 6.9kV Common Board A from NORM to ALT (SOI-200.03)

Why is this event included? One normal evolution per scenario is all thats required for each applicant to obtain their NOR. Since this class is all Instants, it would be prudent to incorporate the NOR as an OATC task.

Post prep comment: SAT 3C/TS (OAC/SRO) x S

CCP 1B-B broken coupling (AOI-20)

Isol charging/letdown, s/u 1A-A, restore charging/letdown TS 3.5.2, TR 3.1.4 Post prep comment: SAT 4C/TS (BOP/SRO) x S

1-R-3 loss of power (AOI-44, AOI-16)

MFW reg valve man control TS 3.3.2, 3.3.3, TR 3.3.7 Post prep comment: SAT 5C (OAC)

S SG 2 tube leak (AOI-33)

Post prep comment: SAT 6R (OAC)

S Rapid downpower to 50% (AOI-33, AOI-39)

Post prep comment: SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 7M x, x S

SG 2 tube rupture (E-0, E-3, ECA-3.1) and SG 2 safety OPEN Scenario D-2 header changes to Scenario 1 on page 100. (for E-0 Appendices)

The as-written bounding criteria for CT2 is insufficient for this scenario for two reasons.

1)

Bounding: Since AFW flow is being used to measure the success of CT2 (as specified on Page 66), CT 2 should be reworded to require AFW flow > 0gpm with SG 2 NR level 29%[39% ADV] as the failure criteria of CT2.

(incorporating this suggestion also addresses justification)

2)

Justification: Since ECA-3.1 requires entry later on per scenario design, there is no change in mitigative strategy associated with failing to isolate SG 2 (i.e.

either procedural path provides an eventual success path).

If the scenario was constructed such that ECA-3.1 entry was NOT required, then the as-written CT2 could be considered acceptable. (although this option does not appear to be appropriate for the as-designed scenario and would require failure of a FW isolation valve to accomplish)

The as-written bounding criteria for CT3 is insufficient for this scenario. What is the limit to max rate cooldown that defines failure to meet this CT? At what point would radiation release occur due to operator mis-operation? What is the scope of the radiation release based on scenario construction? Exceed off-site limits? Exceed radiation worker limits?

Post prep comment: SAT 8C (BOP)

S MDAFW 1A-A fails to AUTO start (Prudent start, E-0 Appendix A)

Revise Scenario D-2 to include identification of Event 8 (top of page)

How is applicant response for this event different than what is required for Scenario 4, Event 9?

Post prep comment: SAT 9C (OAC)

S Steam Dumps fail to operate in Press Mode (E-3)

Revise Scenario D-2 to include identification of Event 9 (top of page)

Post prep comment: SAT 10C (BOP)

S ABI Train B fails (E-0 Appendix A)

Revise Scenario D-2 to include identification of Event 10 (top of page)

Post prep comment: SAT 10 2

2 0

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Watts Bar Scenario: 4 Exam Date: August 12 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 1N (BOP)

S S/U HPFP 1B-B (SOI-26.01)

This event may not be required (refer to Event 4). Additionally, OAC focused events are desired due to class composition (all Instant SRO class).

Post prep comment: SAT 2R (OAC)

S Raise Rx Pwr from 3-15% (GO-3)

This can be revised to start scenario at ~8% RTP.

Post prep comment: SAT 3I/TS (BOP/SRO) x S

IRNI fails low (AOI-4)

TS 3.3.1, 3.3.3 Post prep comment: SAT 4N (OAC)

S Block of IR and PR Low Reactor Trips above P-10 This event doesnt appear to be necessary. Depending on the scope of power change performed in Event 2, examiners will not likely need to observe additional reactivity manipulations. If it is desired for the scenario to drive reactor power above 10% (to obtain this as a normal evolution), recommend revising the placement of Event 3 to occur after exceeding 10% power.

If it is ultimately desired to include this as a normal event, Event 1 is no longer necessary and can be removed.

Revise role play on Page 15 to read: Continue directed power ascension IAW turnover sheet.

Post prep comment: SAT 5C (OAC)

S FCV-62-70 fails CLOSED due to blown fuse (AOI-20)

Why is this event not classified as an (I)nstrumentation event?

Crew isolates charging/letdown, restores excess letdown.

Post prep comment: SAT

ES-301 Operating Test Review Worksheet Form ES-301-7 6C/TS (BOP/SRO) x S

ERCV E-B coupling break (AOI-13)

TS 3.7.8, 3.8.1 Post prep comment: SAT 7C (OAC)

S PZR Spray vlv fails OPEN (AOI-18), Attempt to Trip Rx Post prep comment: SAT 8M x, x S

ATWS (FR-S.1)

Exceeding what specific entry condition criteria of FR-H.1 results in failure to meet CT1?

Total feed flow 410 gpm? Parameter should be incorporated into CT.

Will field operator action to open the Rx Trip and Byp bkrs be delayed to provide examiner assessment of CT2? As written, the scenario D-2 implies that field operator action may very well occur before CT2 success/failure can be evaluated. If this is the case, then CT2 is an invalid CT (would require building in a time delay for field operator actions to permit assessment)

Post prep comment: SAT 9C (BOP)

S MDAFW pumps fail to START How is applicant response for this event different than what is required for Scenario 3, Event 8?

Post prep comment: SAT 2

2 0

ES-301 Operating Test Review Worksheet 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 Operating Test Review Worksheet Form ES-301-7 Facility: Watts Bar Exam Date: August 12 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

9 1

2 0

3 0

6.67 S

One unsat event revised and determined to be acceptable during Prep Week 2

11 0

2 0

2 0

0 S

3 10 0

2 0

3 1

6.67 S

Three submitted CTs, revised to two during Prep Week 4

9 0

2 0

2 0

0 S

13.24 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 Operating Test Review Worksheet Form ES-301-7 Site name: Watts Bar Exam Date: August 12 OPERATING TEST TOTALS Total Total Unsat.

Total Total Unsat.

Explanation Edits Sat.

Admin.

JPMs 5

1 4

Sim./In-Plant JPMs 10 0

10 Scenarios 4

0 4

Op. Test Totals:

19 1

18 5.26 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 PWR Examination Outline Form ES-401-2 Facility: Watts Bar Date of Exam: August 2019 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

3 N/A 3

3 N/A 3

18 3

3 6

2 1

1 2

2 2

1 9

2 2

4 Tier Totals 4

4 5

5 5

4 27 5

5 10

2.

Plant Systems 1

3 2

3 3

2 3

2 2

3 3

2 28 3

2 5

2 1

1 1

1 1

1 1

1 1

0 1

10 0

2 1

3 Tier Totals 4

3 4

4 3

4 3

3 4

3 3

38 5

3 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

2 3

2 3

2 2

1 2

Note: 1.

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

2.

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

3.

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

4.

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

5.

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

6.

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

7.

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

8.

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

9.

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

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

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

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000007 (EPE 7; BW E02&E10; CE E02)

Reactor Trip, Stabilization, Recovery / 1 X

007EK1.05, Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Decay power as a function of time 3.3 000008 (APE 8) Pressurizer Vapor Space Accident / 3 X

008AG2.1.7, Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.7 000009 (EPE 9) Small Break LOCA / 3 X

009EA1.10, Ability to operate and monitor the following as they apply to a small break LOCA: Safety parameter display system 3.8 000011 (EPE 11) Large Break LOCA / 3 X

011EK3.13, Knowledge of the reasons for the following responses as the apply to the Large Break LOCA: Hot-leg injection/recirculation 3.8 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X

015AA2.10, Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on loss of cooling or seal injection 3.7 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X

022AA2.01, Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup:

Whether charging line leak exists 3.8 000025 (APE 25) Loss of Residual Heat Removal System / 4 X

025AG2.2.42, Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

3.9 000026 (APE 26) Loss of Component Cooling Water / 8 X

026AG2.4.20, Knowledge of the operational implications of EOP warnings, cautions, and notes.

3.8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X

027AK2.03, Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners 2.6 000029 (EPE 29) Anticipated Transient Without Scram / 1 X

029EA2.08, Ability to determine or interpret the following as they apply to a ATWS: Rod bank step counters and RPI 3.4 000038 (EPE 38) Steam Generator Tube Rupture / 3 X

038EK1.02, Knowledge of the operational implications of the following concepts as they apply to the SGTR: Leak rate vs.

pressure drop 3.2 000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 X

WE12EG2.1.20, Ability to interpret and execute procedure steps.

4.6

ES-401 3

Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X

054AA2.03, Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

Conditions and reasons for AFW pump startup 4.2 000055 (EPE 55) Station Blackout / 6 X

055EK3.01, Knowledge of the reasons for the following responses as the apply to the Station Blackout: Length of time for which battery capacity is designed 2.7 000056 (APE 56) Loss of Offsite Power / 6 X

056AG2.2.44, 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.

4.4 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X

057AA2.04, Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: ESF system panel alarm annunciators and channel status indicators 3.7 000058 (APE 58) Loss of DC Power / 6 X

058AA1.02, Ability to operate and / or monitor the following as they apply to the Loss of DC Power: Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector 3.1 000062 (APE 62) Loss of Nuclear Service Water / 4 X

062AK3.04, Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water:

Effect on the nuclear service water discharge flow header of a loss of CCW 3.5 000065 (APE 65) Loss of Instrument Air / 8 X

065AA1.04, Ability to operate and / or monitor the following as they apply to the Loss of Instrument Air: Emergency air compressor 3.5 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X

077AK2.03, Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Sensors, detectors, indicators 3.0 (W E04) LOCA Outside Containment / 3 X

WE04EG2.1.31, Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

4.6

ES-401 4

Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR (W E11) Loss of Emergency Coolant Recirculation / 4 X

X WE11EK1.1, Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation):

Components, capacity, and function of emergency systems WE11EA2.2, Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

3.7 4.2 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X

WE05EK2.2, Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:

Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

3.9 K/A Category Totals:

3 3

3 3

3/3 3/3 Group Point Total:

18/6

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

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

001AA2.04, Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Reactor power and its trend 4.2 000003 (APE 3) Dropped Control Rod / 1 X

003AG2.2.22, Knowledge of limiting conditions for operations and safety limits.

4.7 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 X

028AK3.02, Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions: Relationships between PZR pressure increase and reactor makeup/letdown imbalance.

2.9 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X

036AA2.02, Ability to determine and interpret the following as they apply to the Fuel Handling Incidents: Magnitude of potential radioactive release 4.2 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 X

051AA1.04, Ability to operate and / or monitor the following as they apply to the Loss of Condenser Vacuum: Rod position 2.5 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 X

060AA1.01, Ability to operate and / or monitor the following as they apply to the Accidental Gaseous Radwaste: Area radiation monitors 2.8 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 X

068AK2.07, Knowledge of the interrelations between the Control Room Evacuation and the following: ED/G 3.3 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X

069AG2.1.23, Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.4 000074 (EPE 74; W E06 & E07)

Inadequate Core Cooling / 4

ES-401 6

Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000076 (APE 76) High Reactor Coolant Activity / 9 X

076AG2.1.19, Ability to use plant computers to evaluate system or component status.

3.9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure /

4 (W E15) Containment Flooding / 5 X

WE15EK3.3, Knowledge of the reasons for the following responses as they apply to the (Containment Flooding):

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

2.9 (W E16) High Containment Radiation /9 (BW E08; W E03) LOCA Cooldown Depressurization / 4 X

WE03EA2.1, Ability to determine and interpret the following as they apply to the (LOCA Cooldown and Depressurization): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

4.2 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 X

WE10EA2.2, Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS):

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

3.4 (CE A11**; W E08) RCS Overcooling Pressurized Thermal Shock / 4 X

WE08EK1.2, Knowledge of the operational implications of the following concepts as they apply to the (Pressurized Thermal Shock): Normal, abnormal and emergency operating procedures associated with (Pressurized Thermal Shock).

3.4 K/A Category Point Totals:

1 1

2 2

2/2 1/2 Group Point Total:

9/4

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 003 (SF4P RCP) Reactor Coolant Pump X

X 003K6.02, Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: RCP seals and seal water supply 003K6.14, Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: Starting requirements 2.7 2.6 004 (SF1; SF2 CVCS) Chemical and Volume Control X

X 004A4.15, Ability to manually operate and/or monitor in the control room:

Boron concentration 004K6.14, Knowledge of the effect of a loss or malfunction on the following CVCS components: Recirculation path for charging pumps 3.6 2.7 005 (SF4P RHR) Residual Heat Removal X

X K/A changed from 005K4.12 (3/6/19) 005K4.07, Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following:

System protection logics, including high-pressure interlock, reset controls, and valve interlocks 005K5.05, Knowledge of the operational implications of the following concepts as they apply the RHRS: Plant response during "solid plant": pressure change due to the relative incompressibility of water 3.2 2.7 006 (SF2; SF3 ECCS) Emergency Core Cooling X

006K1.04, Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems: Auxiliary spray system 2.7 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X

007G2.2.12, Knowledge of surveillance procedures.

3.7

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 008 (SF8 CCW) Component Cooling Water X

X 008A2.05, Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated 008A2.01, Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCW pump 3.3 3.6 010 (SF3 PZR PCS) Pressurizer Pressure Control X

010K5.02, Knowledge of the operational implications of the following concepts as the apply to the PZR PCS: Constant enthalpy expansion through a valve 2.6 012 (SF7 RPS) Reactor Protection X

X 012A3.02, Ability to monitor automatic operation of the RPS, including: Bistables 012G2.2.22, Knowledge of limiting conditions for operations and safety limits.

3.6 4.0 013 (SF2 ESFAS) Engineered Safety Features Actuation X

X 013K2.01, Knowledge of bus power supplies to the following:

ESFAS/safeguards equipment control 013A2.01, Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; LOCA 3.6 4.8 022 (SF5 CCS) Containment Cooling X

022K2.01, Knowledge of power supplies to the following:

Containment cooling fans 3.0 025 (SF5 ICE) Ice Condenser X

025K4.02, Knowledge of ice condenser system design feature(s) and/or interlock(s) which provide for the following: System control 2.8

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 026 (SF5 CSS) Containment Spray X

026A1.02, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment temperature 3.6 039 (SF4S MSS) Main and Reheat Steam X

X 039K1.06, Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: Condenser steam dump 039G2.4.34, Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.

3.1 4.1 059 (SF4S MFW) Main Feedwater X

059A3.06, Ability to monitor automatic operation of the MFW, including: Feedwater isolation 3.2 061 (SF4S AFW)

Auxiliary/Emergency Feedwater X

K/A changed from 061A2.02 (3/6/19) 061A2.04, Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation 3.4 062 (SF6 ED AC) AC Electrical Distribution X

X 062K1.02, Knowledge of the physical connections and/or cause-effect relationships between the ac distribution system and the following systems: ED/G 062K3.01, Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: Major system loads 4.1 3.5 063 (SF6 ED DC) DC Electrical Distribution X

X 063K3.02, Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: Components using DC control power 063G2.4.45, Ability to prioritize and interpret the significance of each annunciator or alarm.

3.5 4.3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 064 (SF6 EDG) Emergency Diesel Generator X

X 064A1.04, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: Crankcase temperature and pressure 064A3.09, Ability to monitor automatic operation of the ED/G system, including: Functions (modes) of automatic transfer switch (to a startup bank) 2.8 4.0 073 (SF7 PRM) Process Radiation Monitoring X

073A4.03, Ability to manually operate and/or monitor in the control room:

Check source for operability demonstration 3.1 076 (SF4S SW) Service Water X

076K4.03, Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: Automatic opening features associated with SWS isolation valves to CCW heat exchangers 2.9 078 (SF8 IAS) Instrument Air X

X 078K3.03, Knowledge of the effect that a loss or malfunction of the IAS will have on the following: Cross-tied units 078A2.01, Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions 3.0 2.9 103 (SF5 CNT) Containment X

103A4.04, Ability to manually operate and/or monitor in the control room:

Phase A and phase B resets 3.5 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:

3 2

3 3

2 3

2 2/3 3 3

2/2 Group Point Total:

28/5

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

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

002K1.12, Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: NIS 3.5 011 (SF2 PZR LCS) Pressurizer Level Control X

011K5.12, Knowledge of the operational implications of the following concepts as they apply to the PZR LCS: Criteria and purpose of PZR level program 2.7 014 (SF1 RPI) Rod Position Indication X

014K3.02, Knowledge of the effect that a loss or malfunction of the RPIS will have on the following: Plant computer 2.5 015 (SF7 NI) Nuclear Instrumentation X

015A2.05, Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core void formation 3.8 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor X

017K4.01, Knowledge of ITM system design feature(s) and/or interlock(s) which provide for the following: Input to subcooling monitors 3.4 027 (SF5 CIRS) Containment Iodine Removal X

027K2.01, Knowledge of bus power supplies to the following: Fans 3.1 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control X

028A2.03, Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment 3.8

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 029 (SF8 CPS) Containment Purge X

029A3.01, Ability to monitor automatic operation of the Containment Purge System including: CPS isolation 3.8 033 (SF8 SFPCS) Spent Fuel Pool Cooling X

033A1.02, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including: Radiation monitoring systems 2.8 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator X

035K6.01, Knowledge of the effect of a loss or malfunction on the following will have on the S/GS: MSIVs 3.2 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal X

055G2.2.4, (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

3.6 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste X

K/A changed from 068A2.02 (6/20/19) 068A2.04, Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation 3.3 071 (SF9 WGS) Waste Gas Disposal X

071G2.4.30, Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

4.1 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:

1 1

1 1

1 1

1 1/2 1 0

1/1 Group Point Total:

10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Watts Bar Date of Exam: August 2019 Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations G2.1.18 K/A changed from G2.1.27 (3/6/19)

Ability to make accurate, clear, and concise logs, records, status boards, and reports.

3.6 G2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

2.9 G2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

3.8 G2.1.41 Knowledge of the refueling process.

3.7 Subtotal 2

2

2. Equipment Control 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.

2.6 G2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

2.6 G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

3.5 G2.2.3 (multi-unit license) Knowledge of the design, procedural, and operational differences between units.

3.9 G2.2.7 Knowledge of the process for conducting special or infrequent tests.

3.6 Subtotal 3

2

3. Radiation Control G2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.4 G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.4 G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

3.7 Subtotal 2

1

4. Emergency Procedures/Plan G2.4.11 Knowledge of abnormal condition procedures.

4.0 G2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.

3.1 G2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

4.2 2.4.37 Knowledge of the lines of authority during implementation of the emergency plan.

4.1 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

4.3 Subtotal 3

2 Tier 3 Point Total 10 7

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

Group Randomly Selected K/A Reason for Rejection T2/G1 005K4.12 WBN does not have a CSS/RHR piggyback mode. CSS takes suction directly from the containment sump.

T2/G1 061A2.02 WBNs TD AFW steam supply valves are MOVs.

T2/G2 068A2.02 Unable to write a question to meet the K/A. Issue stems from subject matter of K/A, lack of tank recirculation prior to release which is not possible in accordance with site procedures.

T3 G2.1.27 Unable to write a question to meet the K/A at acceptable generic level.

ES-401 Written Examination Review Worksheet Form ES-401-9 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).

• #/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).

Revision History Revision 0 - 5/14/2019: Pre-Review test item NRC review Revision 1 - 5/24/2019: Draft Submittal NRC review Revision 2 - 6/24/2019: Revised Draft NRC review Revision 3 - 7/29/2019: Final Submittal NRC review Q#

1.

LOK (H%)

(50-60% H% RO)

(38-45)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N (Prev used)

7.

U/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 38 (50%)

14 (56%)

2 19 6

5 2

9 2

3 2

4/0/71 (2 RO) 5/1/19 (0 SRO) 14/61 4/22 RO - #9, 10, 23, 28, 33, 36, 46, 50, 56, 63, 67, 68, 71, 74 (19% Unsat)

SRO - #79, 80, 88, 89 (16% Unsat)

(if applicable) Post-Exam Comment xxx.

ES-401 2

Form ES-401-9 Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only Generic Comments:

1 H

3 N

S Rev 1 comment: Question is SAT 2

H 3

N S

Rev 0 comment: Question is SAT 3

F 3

N S

Rev 1 comment: Remove the reactor is tripped and Safety Injection is actuated portion of the 00:00 information.

Revise the 00:01 information from is in progress to was entered.

Change the word transitions to transitioned in the 00:08 information.

Remove the extra is complete from the 00:30 information.

Revise the second half question statement to read: 1-ES-1.4 is/is NOT performed to prevent boron precipitation in the core.

Rev 2 comment: Question is SAT 4

F 3

N S

Rev 1 comment: Question is SAT 5

H 3

N S

Rev 1 comment: Question is SAT 6

H 3

N S

Rev 1 comment: Remove the B Side Level indication (i.e. right side of the graphic) and revise this bullet to state The following indication is observed. (cueing of expected normal indication)

Rev 2 comment: Question is SAT 7

H 3

N S

Rev 1 comment: There are PZR setpoints and associated PZR interlocks included on the graphic provided for this question. Revise the graphic to only show the lower left hand side red box (to add A.1/B.1 plausibility) or restructure question to permit removal of the graphic entirely.

Rev 2 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 8

F 2

N S

Rev 1 comment: Im not understanding the justification statements for this question. You mention that the rx trip bkrs indicate closed yet you provide a green indication?

Remove first bullet (information provided by second bullet) and fourth bullet (information not needed to answer question).

Rev 2 comment: Question is SAT 9

H 3

N S

Rev 1 comment: The B.2/D.2 distractors are implausible. The second half question is worded such that the justification provided for these distractors cannot occur from a physics perspective.

Consider the following as a second half question statement to meet this K/A: RCS depressurization is performed to lower RCS leak rate/ prevent S/G over-pressurization.

Rev 2 comment: Question is SAT 10 F

3 N

S Rev 1 comment: Revise the first half question statement to read:

Each vital battery is required to have adequate storage capacity to carry required loads for AT LEAST __(1)__ in the event (simplification)

B.2/D.2 distractors are implausible. With a loss of onsite and offsite power, cold shutdown cant realistically be achieved. (cred distr)

It seems that this question could easily be converted to a 1x4 format using only the first half question Rev 2 comment: Question is SAT 11 H

3 N

S Rev 1 comment: Too much information provided as a reference here. This question requires revision to pare down graphic or ideally, remove it entirely. Question revision required.

Rev 2 comment: Question is SAT 12 H

3 N

S Rev 1 comment: Is there a situation where distractor C can occur?

(i.e. following a malfunction where 1-I output bkr OPENs while retaining a power supply?) (cred dist?)

Rev 2 comment: Question is SAT 13 H

3 N

S Rev 1 comment: Question is SAT 14 H

3 N

S Rev 1 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 15 H

3 B

WBN 2018 S

Rev 1 comment: Question is SAT 16 F

3 N

S Rev 1 comment: Question is SAT 17 H

3 N

S Rev 1 comment: Question is SAT 18 H

3 N

S Rev 1 comment: Revise first half question and answer choices to match tense of question:

The required feed path has/has NOT been established.

Rev 2 comment: Question is SAT 19 H

3 N

S Rev 1 comment: Question is SAT 20 F

3 N

S Rev 1 comment: Question is SAT 21 H

3 N

S Rev 0 comment: This question requires no knowledge of the relationship between the Loss of Condenser Vacuum abnormal procedure and Rod Position to answer. All reference to AOI-11 in this question can be removed with no effect on knowledge required to arrive at correct answer. Subject matter is focused on knowledge of AOI-39 and TS (with respect to Control Rods). (K/A mismatch)

This K/A may be difficult to hit without incorporating some aspect of Tave effects due to lowering vacuum with corresponding impact on rod position (rods initially in AUTO).

Rev 1 comment: Question is SAT 22 F

3 N

S Rev 1 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 23 H

3 N

S Rev 0 comment: The first half question has a LOD=1 with little discriminatory value (i.e. EDG operation not possible from the ACR). This question can be modified to ask something like: The operator position responsible for starting Emergency DGs IAW AOI-27 is AUO#3 (ACR)/ AUO#1 (DGB). This half question could also ask which type of EDG start is available in the ACR (i.e.

emergency start, non-prelube start, normal start, etc.). Provided there is plausibility for the other answer choice. (LOD)

Concerning the plausibility of the second half answer choices, are controls present in the ACR at WBN to restore power to other electrical boards? (Cred Dist.)

Rev 1 comment: Question revised The first half question has a LOD=1 with little discriminatory value (i.e. non-auto EDG start on LOOP). I dont understand the significance of SI AUTO start bypass when question is asking for EDG start criteria (justification writeup).

Second half question is plausible as-written.

Rev 2 comment: Question is SAT 24 F

3 N

S Rev 1 comment: Question is SAT 25 H

3 N

S Rev 1 comment: Revise second half question and answer choices to incorporate the stated justification reason: (cred distr)

The reason for transferring the Containment Sump water to the RWST is to minimize the potential for flooding of plant components/

dilution of containment sump boron concentration.

Rev 2 comment: Add the word is to the second half question statement (readability): The reason for transferring Containment Sump water to the RWST is to minimize potential for Rev 3 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 26 H

3 N

S Rev 1 comment: Second half answer choices A.2/C.2 are implausible based on the given information in the question stem (specifically the title of ES-0.3, Natural Circulation). (cred distr)

Insert a second bullet under Given to read: - Letdown is currently in service Modify second half question/distractors to read: RCS depressurization will be accomplished using a PZR PORV/ AUX SPRAY.

Rev 2 comment: Question is SAT 27 F

3 N

S Rev 1 comment: Question is SAT 28 H

3 N

S Rev 1 comment: This is a systems level K/A related to RCP cooling. The question is written as an amalgam of CCP subjects which doesnt hit the K/A as an overall question (2nd half does) and would be more suited to a Tier 2 CCP K/A.

Perhaps revising the first half question to ask about the 225F criteria of AOI-20 Section 3.3, Step 6 or even knowledge related to how long can a RCP be run without adequate thermal barrier cooling could be appropriate K/A topics for the first half question.

Rev 2 comment: Question is SAT 29 H

3 N

S Rev 1 comment: Question is SAT 30 H

3 N

S Rev 1 comment: Revise the second half question statement to read:

The crew __(2)__ able to DIRECTLY monitor RCS Boron Concentration from the MCR.

Rev 2 comment: Question is SAT 31 H

3 N

S Rev 1 comment: Replace the word incorrectly with inadvertently and remove the phrase ISOLATING CVCS flow through the Seal Water Heat Exchanger both from the bulleted statement under Subsequently (teaching in the stem).

Rev 2 comment: Revise second half question statement to read (readability): CLOSING 1-ISV-62-650 __(2)__ result in an AUTOMATIC CCP suction swap to the RWST.

Rev 3 comment: Question is SAT 32 F

3 N

S Rev 1 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 33 H

3 N

S Rev 1 comment: Similar to Q#28, this question combines concepts related to charging and use of RHR for a K/A solely focused on RHR.

A way forward to correct could be to revise the 3rd bullet under the Given conditions to read: PCV-62-81, LETDOWN PRESS CONTROL, is being used by operators to control RCS pressure And revise the second half question to read:

1-AOI-14 will/ will NOT direct placing Train A RHR Pumps in P-T-L.

Rev 2 comment: Question is SAT 34 H

3 N

S Rev 1 comment: Remove the title Align Aux Spray from the first half question statement (already included in the given conditions).

Rev 2 comment: Question is SAT 35 H

3 N

S Rev 1 comment: Revise the first bullet under Subsequently to read:

- An unidentified leak to the PRT has been calculated to be 2 gpm Revise the second bullet under Subsequently to read:

- There is no other RCS leakage Rev 2 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 36 H

3 N

S Rev 1 comment: Wording of first and second half question statements, in particular The closure of and direct the crew to RE-OPEN, provides cueing that FCV-70-66 is the root cause of the adverse surge tank alarm (cueing). Use of these phrases negates the plausibility of the C.1/D.1 and B.2/D.2 distractors.

This can be corrected by:

1)

Remove the third bullet under Subsequently

2)

Revise the first half question to read:

A closure of 1-FCV-70-66, U1 Surge Tank Vent,

3)

Revise the second half question to read:

The ARI for U1 SURGE TANK LEVEL HI/LO [249-A]

does/ does NOT direct the installation of bottled gas to restore 1-FCV-70-66, U1 Surge Tank Vent.

Rev 2 comment: Question is SAT 37 H

3 B

S Rev 1 comment: Question is SAT 38 F

3 B

S Rev 1 comment: Question is SAT 39 F

3 N

S Rev 1 comment: Question is SAT 40 F

3 N

S Rev 1 comment: Question is SAT 41 F

3 N

S Rev 1 comment: Revise distractors A and B to use 480V boards.

6.9kV boards arent realistic load centers for fans.

Rev 2 comment: Question is SAT 42 F

3 N

S Rev 1 comment: Question is SAT 43 H

3 N

S Rev 1 comment: Revise the second half question to read (clarity):

BOTH containment pressure AND containment temperature

__(2)__ REQUIRED to be verified below a specified value to STOP Containment Spray Rev 2 comment: Question is SAT 44 F

2 N

S Rev 0 comment: Question is SAT 45 F

3 N

S Rev 1 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 46 H

3 N

S Rev 1 comment: For the second half question, does E-0 contain any pump venting instructions? B.2/D.2 distractors are not plausible. (cred dist)

Rev 2 comment: Question is SAT 47 H

3 N

S Rev 1 comment: Remove the second bullet under 12:30 (6.9kV SD BD de-energized). Information already provided due to receipt of the 215-C alarm and wording of second half question (teaching in the stem).

Remove the third bullet (information not necessary to answer the question and teaching in the stem).

Revise both question statements to read: At 12:31 Rev 2 comment: Question is SAT 48 H

3 N

S Rev 1 comment: Question is SAT 49 H

3 N

S Rev 1 comment: Revise the second half question to read (clarity):

Use of the MDAFW Pump 1B-B MCR handswitch is/ is NOT affected by the 125Vdc board loss Rev 2 comment: Question is SAT 50 H

3 N

S Rev 1 comment: A.2/C.2 are implausible distractors for the second half question as there are no EDG engine monitoring parameters present in the MCR.

This can be corrected by:

1)

Removing the given conditions

2)

Revising the first half question to read:

An alarming CRANKCASE PRESS HI [203-D] will/ will NOT prevent an automatic DG START.

3)

And revising the second half question to read:

During performance of 0-SI-82-11-B, DG 1B-B Monthly Load Test, receipt of annunciator CRANKCASE PRESS HI [203-D] does/ does NOT require use of the 1-HS 47A, EMERGENCY STOP, pushbutton.

Rev 2 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 51 H

3 N

S Rev 1 comment: Crop the right hand graphic to remove the DG 1A-A symbol and focus in on the 1912 breaker light indications.

Overlap with SRO Q80 (EDG output bkr response during LOOP).

Modification to RO Q51 or SRO Q80 required.

Rev 2 comment: Question is SAT 52 H

3 N

S Rev 1 comment: The Included graphic is not required to answer this question and can be removed.

Rev 2 comment: Question is SAT 53 F

3 N

S Rev 1 comment: Question is SAT 54 F

3 N

S Rev 1 comment: Question is SAT 55 F

3 N

S Rev 1 comment: Question is SAT 56 H

3 N

S Rev 1 comment: This is a GFES question related to reactivity effects on NIs. Not understanding the tie between NIs and the RCS as required by the K/A statement. (Q=K/A)

Rev 2 comment: Question is SAT 57 F

3 N

S Rev 1 comment: First half question statement is confusing, revise it to read (also, how could C.1/D.1 be realistic):

A basis for the MINIMUM PZR program level is to ensure that the PZR will NOT empty following a Rx Trip/ that sufficient inventory is available to prevent uncovering PZR heaters following a MSLB Rev 2 comment: Question is SAT 58 F

3 N

S Rev 1 comment: Question is SAT 59 F

3 N

S Rev 1 comment: Question is SAT 60 F

3 N

S Rev 1 comment: Revise distractors A and B to use 480V boards.

6.9kV boards arent realistic load centers for fans.

Rev 2 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 61 H

3 N

S Rev 0 comment: Change the word Giving to Given What is the purpose of including switch graphic when the information Upper Containment Purge is in progress is already present in question stem? (Stem Focus)

Graphic can be removed as it provides no value in answering this question.

What is the purpose of containing the Subsequently bullet:

Containment Vent Isolation (CVI) is actuated on both Trains?

(Stem Focus)

The CVI can be determined by the conditions stated in the question. Teaching in the stem due to correlation with receipt of HI RAD alarm. Additionally, this is already revealed in the first half question when the applicant is informed that valves require being VERIFIED CLOSED. CVI bullet can be removed.

Concerning the first half question. Are there other MCR panels which contain valves associated with containment? (Cred. Dist.)

Second half question has no bounding and therefore requires an unstated assumption to answer (i.e. that this half question is being asked after receipt of the HI RAD alarm). This can be clarified by stating: Following receipt of Annunciator [174-A], 1-HS-30-1A indicating lights are xxx. A.2/C.2 answer choices can be misconstrued as being correct based on unstated assumption.

(Partial)

Revise the question statement to read: Based on the conditions above, which ONE of the following completes the statements below? (this may fix the bounding issue above)

Rev 1 comment: Question is SAT Remove third bullet under Given since no longer applicable.

Rev 3 comment: Question is SAT 62 F

3 N

S Rev 1 comment: Question is SAT 63 F

2 N

S Rev 1 comment: B.2/D.2 distractors are implausible based on the given condition (i.e. MSIV failing CLOSED).

The second half question could be revised to incorporate the level effect that inadvertent MSIV closure has on the other S/Gs.

Rev 2 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 64 F

3 N

S Rev 1 comment: Question is SAT 65 F

N S

Rev 1 comment: Are there any other release path radiation monitors that do not automatically terminate a release on a RAD HI alarm? (cred dist of C.1/D.1)

Why does this question pose a situation where the plant was operated incorrectly (i.e. by failing to recirc the tank prior to release as required by procedure)?

Unable to evaluate this question as it appears to be invalid based on given conditions (specifically the second half question).

Rev 2 comment: Question is SAT 66 F

2 N

S Rev 1 comment: Question is SAT Capitalize the word required in both half question statements:

REQUIRED Rev 3 comment: Question is SAT 67 F

3 N

S Rev 1 comment: B.2/D.2 distractors are implausible considering there are only two Units at WBN.

The second half question can be revised to read: The STA position can/can NOT be filled concurrently with the Unit Supervisor position.

Rev 2 comment: Second half question contains implausible distractors B.2/D.2 (SS can only be qualified as an SRO, how could they not accomplish a temporary relief, regardless of duty position).

(Cred Distr)

Revision required.

Rev 3 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 68 F

3 N

S Rev 1 comment: The first half question is worded in a way that disqualifies the C.1/D.1 distractors. (cred distr, LOD=1)

The first half question can be reworded to state: The department responsible for performing a FINAL Risk Characterization for a Mechanical Maintenance work activity is Mechanical Maintenance/

Operations.

The second half question also contains implausible distractors (use of MAXIMO for the performance of risk calculations).

The second half question can be reworded to state: The computer program Equipment Out of Service (EOOS) is used to CALCULATE risk for maintenance activities during power operations and/but NOT shutdown operations.

Rev 2 comment: Question is SAT Add the word The before the first half question statement (readability).

Rev 3 comment: Question is SAT 69 H

3 N

S Rev 1 comment: Question is SAT 70 F

3 N

S Rev 1 comment: The number 1 in the upper left-hand corner of the box provides a cue that the circled number is a Unit number (which reflects the numbering of all components at multiple unit sites). This provides an inappropriate cue for the first half question.

Revise the provided reference to change the 1 in the upper left-hand block to a 2 (there should be precedence for having Unit 1 components designated on Unit 2 drawings or vice versa). This change would negate the inappropriate cueing issue above.

Rev 2 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 71 F

3 x

N S

Rev 1 comment: C.1/D.1 distractors made implausible by the wording of first half question statement (i.e. required to be in an approved ). Subject matter is still valid though.

Revise the first half question to read: During containment entry on Unit 1/ 2, in-core detectors are REQUIRED to be DANGER tagged.

Remove third bullet under given conditions. Modify the Unit 2 Mode to indicate Mode 5.

Modify second half question to incorporate the stated justification reason: A containment Access Control Custodian is REQUIRED to be established on Unit 1/ 2.

Rev 2 comment: The distractor statements for this question imply that a Unit difference is being tested here. With the difference in MODE presented in the Given conditions this knowledge is not actually being tested. (referenced procedure also doesnt address M5)

Revise the Unit 2 MODE given condition to read: Unit 2 is in Mode 4

Rev 3 comment: Question is SAT 72 F

3 N

S Rev 1 comment: Question is SAT Modify the opening statement to this question to read: Which ONE of the following completes the statements below? (simplification)

Rev 3 comment: Question is SAT 73 F

2 N

S Rev 1 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 74 F

2 B

WBN 2018 S

Rev 1 comment: Based on the wording of the first half question statement (i.e. meet the requirements of a SRO or STA),

distractors A.1/B.1 are implausible. At WBN, Fire Brigade Leaders arent even in the Operations department?

Revise the first half question to read: During an incident, the Fire Brigade Leader/ Incident Commander is responsible for the supervision of firefighting activities.

Rev 2 comment: Inclusion of the example provides cueing. Use of the word DIRECTLY already provides the necessary differentiation between positions.

Remove the example statement from the first half question statement.

Another acceptable way of revising the first half question statement could be: The __(1)__ is responsible for the selection and employment of appropriate extinguishing agent during a site fire.

Rev 3 comment: Question is SAT 75 F

3 N

S Rev 1 comment: Wording of bullet PREVIOUSLY DISCUSSED is vague and ambiguous (i.e. discussed between the field and board operators only?). This vague-ness could prompt an applicant question during administration.

Add a third bullet under the given conditions to state: - Receipt of alarm is discussed by Reactor Operator and Unit Supervisor Revise the bullet under Subsequently to read: - This annunciator alarms in the MCR Rev 2 comment:

The Annunciator Response Instruction ___(2)___ required to be referenced upon receipt of the alarm.

Rev 3 comment: Question is SAT 76 H

3 N

S Rev 1 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 77 H

3 N

S Rev 1 comment: Remove the bullet at 00:07 related to AOI-6 entry (information not required to answer).

Inclusion of EAL chart designation to evaluate (i.e. SU4) as part of the second half question removes the SRO knowledge component to this question. Particularly since the first half question solicits the leakage source. Revise the second half question statement to read:

An EAL declaration __(2)__ required.

Rev 2 comment: Question is SAT 78 H

3 N

S Rev 1 comment: Question is SAT 79 H

2 N

S Rev 1 comment: First half question asks for AFW auto start criteria while second half asks for FR-H.1 procedure entry condition.

Neither item rises to the level of SRO LOK.

Additionally, this question has a very low LOD with little discriminatory value for the first half question based on the provided indication graphics coincident with a loss of all MFW.

Some ideas for revising this question:

1)

Remove the pump graphics and instead provide a bullet indicating that AFW has failed to auto start (also remove loss of all MFW)

2)

Revise the first half question to ask what signal would have started the AFW pumps based on plant parameters (i.e. loss of 1, 2 MFW pumps, SGWL of x%, etc)

3)

Revise the second half question to ask if the Unit Supervisor is required to remain in ES-0.1 or transition to FR-H.1 based on provided indications Rev 2 comment: Second half question statement is confusing, revise this statement to read: The US is REQUIRED to __(2)__.

Rev 3 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 80 H

3 x

x N

S Rev 1 comment: Overlap with RO Q51 (EDG output bkr response during LOOP). Modification to RO Q51 or SRO Q80 required.

Rev 2 comment: Referring to a procedure is never wrong, regardless of plant state (b/c a US can always continue in the procedure in effect). The way the second half question is worded, there is a potential for multiple choices to be correct (as well as eroding the credibility of A.2/C.2). In order to test the procedure selection aspect, there must be a definitive procedural path directed. (Cred Distr, Partial)

Second half question requires revision.

Rev 3 comment: Question is SAT 81 H

3 N

S Rev 1 comment: There doesnt appear to be a need for the 12:00, 12:01, or 12:25 information in the question stem. This information can be removed.

I dont understand the first half question. Are the CS pumps running due to operator action or as a result of an auto start. The justification seems to indicate that this half question is answered based on procedural knowledge, but this appears to ask if x number of pumps should already be running based on an auto start.

Perhaps if the first half was reworded to read:

At 12:35, Operators will be directed to start __(1)__ Containment Spray Pumps. Or At 12:35, Operators will be directed to ensure __(1)__

Containment Spray Pumps are RUNNING.

Rev 2 comment: Question is SAT 82 H

3 N

S Rev 0 comment: Question is SAT 83 F

3 N

S Rev 1 comment: Capitalize the word not in the third bullet of given conditions.

Rev 2 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 84 H

3 N

S Rev 1 comment: The indication graphics are not required to answer this question. Remove these graphics and instead substitute the nomenclature for FCV-72-2A.

Use of the word PRUDENTLY implies that the valve operation is permitted (i.e. are there any instances of imprudent operation of a plant component in any procedure at WBN?). This makes answer choices C.1/D.1 implausible. (cred distr)

Additionally, use of the word prudently implies that either provided answer can be correct based on plant conditions.

This can be corrected by modifying the first half question to read:

Based upon the given conditions and upon a failure to actuate, the OAC __(1)__ permitted to reposition 1-FCV-72-2A, CNTMT SPRAY HDR B TO CNTMT, without procedural direction.

Rev 2 comment: Question Is SAT Revise the valve designation in the first half question statement to read: 1-FCV-72-2 Rev 3 comment: Question is SAT 85 H

3 N

S Rev 0 comment: Question is SAT 86 H

3 N

S Rev 0 comment: Question is SAT 87 H

3 N

S Rev 0 comment: A LOCA requiring SI actuation and performance of E-0 Appendix A is already incorporated as part of the Simulator operating test (pre-review provided Scenario 2).

NUREG-1021, ES-301, D.1.h: The walkthrough and simulator portions should not be redundant, nor should they duplicate material that is covered on the written examination.

Rev 1 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 88 H

3 N

S Rev 1 comment: Remove the indication graphics and provide nomenclature designations and positions of the MSIVs.

I dont understand the justification statement for distractors C.1/D.1.

These distractors dont appear to be credible based on the given conditions of the question (i.e. how else will the errant MSIV be closed?). (cred distr)

This can be corrected by revising the first half question to read:

The US will direct SG 4 MSIV closure in accordance with 1-E-3,, Steamline Isolation (MCR)/ Attachment 4, Steamline Isolation (Local).

Rev 2 comment: Question is SAT 89 F

3 N

S Rev 1 comment: Unsure what the purpose of including the provided graphic adds to this question. Remove the graphic and state:

Operators receive the following annunciators: x, y, z The second half question is not asking about Unit 2 as implied in the justification statement (i.e. no procedure selection present in the as-written question). (SRO LOK)

To correct, revise the second half question to read:

The procedure directed to restore plant equipment configuration is 1-AOI-21.03, Appendix A, Transfer of 125V DC Buses/ 2-AOI-21.03, Appendix A, Major Equipment Availability Rev 2 comment: Question is SAT 90 H

3 B

Harris 2013 S

Rev 1 comment: Since the question provides the status of CAS D as originally being in service with no information provided to evaluate a change in state, the only plausible answer to the first half question is are (i.e. answer cued by given information).

This can be corrected by revising the first half question to read:

CAS Compressors A, B, and C __(1)__ RUNNING and LOADED.

Rev 2 comment: Question is SAT 91 F

3 B

TPN 2010 S

Rev 1 comment: Question is SAT 92 H

3 N

S Rev 0 comment: Question is SAT

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 93 F

2 N

S Rev 0 comment: Question is SAT 94 F

2 N

S Rev 1 comment: Question is SAT 95 F

3 B

WBN 2008 S

Rev 1 comment: Question is SAT 96 F

3 N

S Rev 0 comment: Simplify the question statement: Which ONE of the following completes the statements below in accordance with the TRM?

As written, this question doesnt rise to the license level required for an SRO question (i.e. this question is asking RO LOK subject matter). Specifically, the second half question since the subject matter is Tier 2 in nature (e.g. Plant Systems basis). (SRO Only)

To elevate this question to the level of SRO LOK the following could be incorporated as the second half question: reporting requirements when maximum licensed thermal power is exceeded Rev 1 comment: Question is SAT 97 F

3 B

WBN 2010 S

Rev 1 comment: Question is SAT 98 F

3 B

WBN?

S Rev 1 comment: Has this question been previously provided on a WB ILO examination?

Question is SAT 99 F

2 N

S Rev 1 comment: Remove the word FUTURE from the first half question. The given conditions already state TSC status. (Cues)

Rev 2 comment: Question is SAT 100 F

3 M

S Rev 1 comment: Question is SAT