ML20300A585

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Wb 2020301 File 2A-3 Exam Administrative Items - Delayed Release
ML20300A585
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 10/26/2020
From:
Division of Nuclear Materials Safety II
To:
Tennessee Valley Authority
References
ES-301-1
Download: ML20300A585 (34)
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Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: August 2020 Examination Level: RO SRO Operating Test Number: 2020-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

Calculate Shutdown Margin Conduct of Operations Calculate SDM and determine if any actions are 2016 NRC Exam RO R, M required based on results.

2.1.7 (4.7)

Determine Shift Staffing Requirements Determine shift staffing requirements based on Conduct of Operations R, N plant conditions.

2.1.5, (3.9)

Equipment Control Determine TS Completion Time Extension 2015 Audit Exam R, D Given plant/equipment conditions, determine allowable extension to complete actions.

2.2.37 (4.6)

Calculate Maximum Permissible Stay Time Radiation Control R, D 2015 NRC Exam Given applicable dose rates, calculate allowable stay time to perform a task.

2.3.14 (3.8)

REP Classification and State Notification R, D Emergency Plan (NOUE based on River Level Low) 2018 Audit Exam 2.4.29 (4.4)

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. Unit 1 is in Mode 2. The examinee will be directed to determine SDM in accordance with 1-SI-0-10, Shutdown Margin which will be provided. The examinee should determine that SDM is NOT adequate and recommend actions in accordance with TS 3.1.1., Shutdown Margin (SDM) - Tavg > 200 oF which will direct initiating boration to restore SDM within 15 minutes.

Conduct of Operations 2. With Unit 1 at 100% and Unit 2 cooling down for refueling and currently at 230 oF, the examinee will be directed to determine the shift staffing requirements in accordance with plant procedures. The examinee should reference OPDP-1, Conduct of Operations and determine the minimum required staffing for plant conditions.

Equipment Control. Given that one SI pump was inoperable in the initial conditions, a second SI pump is declared inoperable. The examinee will determine when one SI pump must be declared operable in order to avoid a TS required shutdown and if not able to, when the unit must be in mode 4.

Radiation Control. Given current radiation levels and times to complete several tasks, the examinee will determine which tasks can be completed without exceeding the allowed emergency radiation exposure limit (all) and then how much exposure they will have remaining prior to exceeding that limit.. SRO component will be evaluating emergency dose limits in accordance with the REP.

Emergency Plan. Given that river level is low, the examinee will classify the condition and make the appropriate REP call.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: August 2020 Exam Level: RO SRO-I SRO-U Operating Test No.: 2020-301 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Dropped Control Rod 001 A2.03 (4.2) D, A, S 1 Retrieve a Dropped Control Rod IAW 1-AOI-2 2016 Audit Exam
b. Transfer ECCS suction 013 A2.01 (4.8)

M, A, EN, L, 2 Transfer ECCS Pump Suction to Containment Sump S

IAW 1-ES-1.3 2016 NRC Exam

c. Shutdown STBY MFP 059 A4.03 (2.9)

N, S 4S Shutdown 1A MFP IAW 1-SOI-2&3.01, Condensate and Feedwater System, Section 7.3.4, Standby MFP Shutdown and Standby Alignment

d. Loss of Shutdown Cooling 025 AA1.03 (3.3)

N, A, EN, L, 4P Perform 1-AOI-14, Appendix A (RHR Pump 1A-A S

Alignment)

e. Raise PRT level 007 A4.01 (2.7) N, S 5 Raise PRT level IAW 1-SOI-68.01
f. Unload and Shutdown 1A-A DG 064 A4.06 (3.9)

N, A, S 6 Perform 0-SOI-82.01, Diesel Generator (DG) 1A-A, Section 7.1 Shutdown of DG from Main Control Room

g. Start CCW Pump 075 A2.02 (2.7)

N, A, S 8 Perform 1-SOI-27.01, Condenser Circulating Water, Section 5.4 to place a 4th CCW pump in service

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 Appendix A of 1-ES-1 .1, Thermal Overload D, E 3 Reset Operation, E02, EA1.1 (3.9) WB Bank (3-OT-J1E-2CB-E11)
j. Vent MD AFW Pumps E05 EA1.3 (4.2)

N, E, EN, L 4S Vents both MD AFW pump IAW 2-SOI-3.02

k. Loss of Component Cooling Water flow 008 A2.01 (3.6)

N, R, E, L 8 RCP Seals and Thermal Barrier Isolation IAW 1-AOI-15, Att 3

  • 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1 / 1 / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

a. The plant experienced a dropped control rod. The crew performed steps IAW 1-AOI-2, Malfunction of Reactor Control System, to stabilize the plant. The cause has been determined and corrected. The examinee will be directed to recover the dropped control rod by continuing in 1-AOI-2. When the control rod is within 12 steps of its respective bank, multiple control rods will drop (A) requiring the examinee to trip the reactor. This JPM is an updated JPM from the 2016 Audit Exam.
b. The plant has experienced a LOCA and RWST level has lowered to less than 34%. The examinee will be directed to perform 1-ES-1.3, Transfer to Containment Sump. The examinee will transfer suction of ECCS pumps to the containment sump IAW 1-ES-1.3. One Containment Sump suction valve will fail to open (A) which will require the examinee to place the associated RHR pump in PULL TO LOCK. This JPM is modified from the 2016 NRC Exam.
c. The plant is operating at full power. The examinee will be directed to remove the STBY MFW Pump from service in accordance with 1-SOI-2&3, Condensate and Feedwater System, Section 7.3.4, Standby MFP Shutdown and Standby Alignment. The examinee performs steps in the appropriate section. This is a NEW JPM.
d. While in Shutdown Cooling mode of operation, system Outleakage occurs. The crew enters 1-AOI-14, Section 3.7, RHR System Outleakage or LOCA While On Shutdown Cooling. The source of leakage has been determined and Shutdown Cooling is to be restored. The examinee is directed to perform Appendix A (RHR Pump 1A-A Alignment). While performing Appendix A, RCS HL to RHR Suction valves will not open(A). The examinee will perform the RNO step which directs the operator to open RHR system bypass valves. This is a NEW JPM.
e. Annunciator 88-B (PRT LEVEL HI/LO) is alarming due to a low level. The examinee is directed to raise level in the PRT in accordance with 1-SOI-68.01, Reactor Coolant System Pressurizer Relief Tank Operations, Section 8.2, Return PRT Level to Normal from Low Level. This is a NEW JPM.
f. The examinee will unload and shut down the 1A-A Diesel Generator IAW 0-SOI-82.01, Diesel Generator (DG) 1A-A, Section 7.1 Shutdown of DG from Main Control Room. After paralleling the Shutdown bus with the normal power supply, the DG will experience a high crankcase pressure(A). The applicant will be required to recognize this failure and trip the Diesel Generator. This is a NEW JPM.
g. Examinee will start a 4th CCW pump IAW 1-SOI-27.01. When the pump is started, it will subsequently trip and the pump discharge valve will fail to automatically close (A). The examinee will respond to the Annunciator for the pump trip and be required to manually close the pump discharge valve. This is a NEW JPM.
i. While in 2-ES-1.1, the examinee is directed to reset the thermal overloads on the MOV boards per 2-ES-1.1, Appendix A.. This is a BANK JPM.
j. During a loss of main feedwater, both MD AFW pumps experienced cavitation. The examinee is directed to vent both MD AFW pumps IAW 2-SOI-3.02. This is a NEW JPM.
k. A loss of CCS flow and RCP seal injection occurred. While performing 1-AOI-15 (Loss of Component Cooling Water), RCP Lower Bearing temperatures rose to greater than 225 oF.

The reactor was tripped and the examinee has been directed to perform 1-AOI-15, Attachment 3 (RCP Seals and Thermal Barrier Isolation, Section 2.0, Local Actions-Performed By Assistant Unit Operator. This is a NEW JPM.

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Exam Date:

1 2 3 4 5 6 ADMIN Attributes Job Content LOD Admin JPMs Topic U/E/S Explanation (1-5) I/C Critical Scope Perf.

and K/A Job Cues Overlap Key Minutia Focus Steps (N/B) Std. Link 1S 3.5 S Originally had incorrect answers on key and standard 2S 3 S 3S 2 S 4S 2 S 5S 2 S 1

Simulator/In-Plant Safety Function JPMs and K/A a S b S c S d S e S f S g 3 S h na N/A I S j S k S

ES-301 Operating Test Review Worksheet Form ES-301-7 ES-301 3 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 4 Form ES-301-7 Facility: Scenario: Exam Date:

1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.

Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap 1-1 3 S SRO decisions and bypassing in DCS as actions (4) 2 X S 1-2 TS for verifying interlocks 1-3 3 X S Dropped rod, had to correct TS call in D-2.

1-4 3 S 1-5 3 X S 1-6 3 X S 2-1 3 X S EVT 1 One of two TS calls incorrect on completion time 2-2 2 S 2-3 2 X X S 2-4 3 S 2-5 3 S 2-6 3 S 2-7 3 X S 3-1 3 X S 2nd TS in EVT 1 referenced wrong TS SR 3-2 2 X S Verifiable action is DCS bypassing only 3-3 2 S 3-4 4 X S 3-5 3 X S 3-6 3 X S CT2 needed editorial to avoid subset appeal possibility but acceptable 3-7 2 S

ES-301 5 Form ES-301-7 1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.

Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap 4-1 3.5 X X S 1 of 2 TS entries on D-2 was incorrect. Fixed.

4-2 2 S 4-3 3 X S 4-4 3 X S 4-5 2 S 4-6 2 S Had to change LT failure to fail high vs low. Caused problems not X X 5-1 anticipated by D Fixed 5-2 5-3 5-4 X 5-5 X 5-6 Make this the spare. Evaluated possible overlap with JPM as x

5-7 acceptable because action taken to correct problem was different.

ES-301 6 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 7 Form ES-301-7 Facility: Exam Date:

1 2 3 4 5 6 7 8 11 Scenario  % Unsat. Explanation Event Events TS TS CT CT Scenario U/E/S Totals Unsat. Total Unsat. Total Unsat.

Elements 1 6 0 2 1 2 0 10 S/E Validation required correcting expected TS call in event 3 2 7 0 3 1 2 0 8 S/E Validation required correcting expected TS call in event 1 3 7 0 4 1 2 0 8 S/E Validation required correcting expected TS call in event 1 4 6 0 4 1 2 0 8 S/E Validation required correcting expected TS call in event 1 There were 2 CTs specified but only one would meet safety critieria to be 5 7 1 3 0 2 1 16 E/S a CT. This will be the Spare scenario 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.

2+4+6 7 In column 7, calculate the percentage of unsatisfactory scenario elements: 100%

1+3+5 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.

ES-301 8 Form ES-301-7 Site name: Exam Date:

OPERATING TEST TOTALS Total Total Total  %

Total Explanation Unsat. Edits Sat. Unsat.

Admin.

5 1 3 JPMs Sim./In-Plant 10 0 10 JPMs Scenarios 5 0 5 5 Op. Test Admin 1S (A.1.a) had incorrect key items.

20 1 19 5 Totals: Corrected by examiner during OV week 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.

Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 and 2.

simulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.

Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous 3.

tables. This task is for tracking only.

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

Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. Test 5.

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%

Update this table and the tables above with post-exam changes if the as-administered operating test 6.

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: Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency and Abnormal Plant 2 1 1 2 N/A 2 2 N/A 1 9 2 2 4 Evolutions Tier Totals 4 4 5 5 4 27 5 5 10 1 3 2 2 2 3 2 3 3 2 3 3 28 3 2 5 2.

Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 2 1 3 Systems Tier Totals 4 2 3 3 4 3 4 4 3 4 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 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) X 007EA2.06; Occurrence of a reactor trip 4.3 1 Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space X 008AK2.02; Sensors and Detectors 2.5 2 Accident / 3 009EA2.39; Adequate core cooling.

000009 (EPE 9) Small Break LOCA / 3 X 4.7 76 000011 (EPE 11) Large Break LOCA / 3 X 011EG2.4.6; Knowledge of EOP mitigation 4.7 77 strategies 000015 (APE 15) Reactor Coolant Pump X 015AK3.04; Reduction of power to below the steady 3.1 3 Malfunctions / 4 state power- to flow limit 000022 (APE 22) Loss of Reactor Coolant X 022AA1.03; PZR level trend 3.2 4 Makeup / 2 025AG2.4.20; Knowledge of operational 000025 (APE 25) Loss of Residual Heat X implications of EOP warnings, cautions and notes 4.3 78 Removal System / 4 026 AA2.01; Ability to determine and interpret the 000026 (APE 26) Loss of Component x following as they apply to the Loss of Component 2.9 5 Cooling Water / 8 Cooling Water: Location of a leak in the CCS 000027 (APE 27) Pressurizer Pressure X 027AK2.03; Controllers and positioners 2.6 6 Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient X 029EK1.03; Effects of boron on reactivity 3.6 7 Without Scram / 1 000038 (EPE 38) Steam Generator Tube X 038EK3.08; Criteria for securing RCP 4.1 8 Rupture / 3 040EG2.2.22; Knowledge of limiting conditions for 000040 (APE 40; BW E05; CE E05; W E12) X operations and safety limits. 4.7 79 Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main X 054AA2.02; Differentiation between loss of all MFW 4.4 80 Feedwater /4 and trip of one MFW pump 055EA2.02; RCS core cooling through natural 000055 (EPE 55) Station Blackout / 6 X circulation cooling to S/G cooling 4.4 9 000056 (APE 56) Loss of Offsite Power / 6 X 056AA1.30; AFW flow control valve operating 3.5 10 switches 057 AA1.06; Ability to operate and / or monitor the 000057 (APE 57) Loss of Vital AC x following as they apply to the Loss of Vital AC 3.5 11 Instrument Bus / 6 Instrument Bus: Manual control of components for which automatic control is lost 058AG2.4.45; Ability to prioritize and interpret the 000058 (APE 58) Loss of DC Power / 6 X significance of each 4.1 12 annunciator or alarm.

062AK3.04; Effect on the nuclear service water 000062 (APE 62) Loss of Nuclear Service X discharge flow header on a loss of CCW 3.5 13 Water / 4 065AG2.4.2; Knowledge of system set points, 000065 (APE 65) Loss of Instrument Air / 8 X interlocks and automatic actions associated with 4.5 14 EOP entry conditions.

000077 (APE 77) Generator Voltage and X 077AK2.07; Turbine / Generator control 3.6 15 Electric Grid Disturbances / 6 WE04EK1.3; Annunciators and conditions indicating (W E04) LOCA Outside Containment / 3 X signals, and remedial actions associated with the 3.5 16 (LOCA Outside Containment).

WE04EA2.1; Facility conditions and selection of 4.3 81 appropriate procedures X during abnormal and emergency operations

ES-401 3 Form ES-401-2 we11EG2.2.3; (multi-unit license) Knowledge of the (W E11) Loss of Emergency Coolant X design, procedural and operational differences 3.8 17 Recirculation / 4 between units.

WE05EK1.3; Annunciators and conditions indicating (BW E04; W E05) Inadequate Heat X signals, and remedial actions associated with the 3.9 18 TransferLoss of Secondary Heat Sink / 4 (Loss of Secondary Heat Sink).

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 4 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 001AK2.08; Individual rod display 3.1 19 lights and indications 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 X 024AG2.4.8; Knowledge of how 4.5 82 abnormal operating procedures are used in conjunction with EOPs 000028 (APE 28) Pressurizer (PZR) Level Control X 028 AA2.01 Ability to determine 3.4 20 Malfunction / 2 and interpret the following as they apply to the Pressurizer Level Control Malfunctions: PZR level indicators and alarms 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 X 037AA2.06; Ability to determine 4.5 83 and interpret a S/G tube failure 000051 (APE 51) Loss of Condenser Vacuum / 4 X 051AA2.02; Conditions requiring 3.9 21 reactor and/or turbine trip 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 X 060AK3.02; Isolation of the 3.3 22 auxiliary building ventilation 000061 (APE 61) Area Radiation Monitoring System Alarms

/7 000067 (APE 67) Plant Fire On Site / 8 X 067 AA1.05; Ability to operate 3.0 23 and / or monitor the following as they apply to the Plant Fire on Site: Plant and control room ventilation systems 000068 (APE 68; BW A06) Control Room Evacuation / 8 X 068AK3.10; Maintenance of PZR 3.9 24 level, using pumps and heaters 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 000076 (APE 76) High Reactor Coolant Activity / 9 X 076AG2.1.23; Ability to perform 4.3 25 specific system and integrated plant procedures during all modes of plant operation 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 X WE13EA2.2; Adherence to 3.4 84 appropriate procedures and operation within the limitations in the facility's license and amendments (W E15) Containment Flooding / 5 X We15EG2.4.18; Knowledge of the 4.0 85 specific bases for EOPs (W E16) High Containment Radiation /9 (BW E08; W E03) LOCA CooldownDepressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 X WE09EK1.2; Normal, abnormal 3.3 26 and emergency operating procedures associated with (Natural Circulation Operations).

ES-401 5 Form ES-401-2 (CE A11**; W E08) RCS OvercoolingPressurized Thermal X WE08EA1.1; Components and 3.8 27 Shock / 4 functions of control and safety systems, including Instrumentation, signals, interlocks, failure modes and automatic and manual features.

K/A Category Point Totals: 1 1 2 2 2/2 1/2 Group Point Total: 9/4

ES-401 6 Form ES-401-2 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 X 003A4.01; Seal injection 3.3 28 Pump X 003K6.14; Starting requirements 2.6 29 004 A3.02; Ability to monitor automatic 004 (SF1; SF2 CVCS) Chemical and X 3.6 30 operation of the CVCS, Volume Control Including Letdown isolation X 004K1.23 Knowledge of the physical 3.4 31 connections and/or cause-effect relationships between the CVCS and the following systems:

RWST 005A1.05; Detection of and response to 005 (SF4P RHR) Residual Heat X presence of water in RHR emergency sump 3.3 32 Removal 2.6 33 X 005K5.01; Nil ductility transition temperature (brittle fracture) 006 K1.05; Knowledge of the physical 006 (SF2; SF3 ECCS) Emergency X 2.8 34 connections and/or cause-effect Core Cooling relationships between the ECCS and the following systems: RCP seal injection and X return 4.6 86 025G2.2.37; Ability to determine operability and/or availability of safety related equipment 007 (SF5 PRTS) Pressurizer X 007K5.02; Method of forming a steam bubble 3.1 35 Relief/Quench Tank in the PZR 008A2.05; Effect of loss of instrument and 008 (SF8 CCW) Component Cooling X control air on the position of the CCW valves 3.3 36 Water that are air operated X 008A2.07; Consequences of high or low CCW 2.5 37 flow rate and temperature; the flow rate at which the CCW standby pump will start 010 (SF3 PZR PCS) Pressurizer X 010K6.02; PZR 3.2 38 Pressure Control 012 (SF7 RPS) Reactor Protection X 012A3.06; Trip logic 3.7 39 013 (SF2 ESFAS) Engineered X 013A4.01; ESFAS-initiated equipment which 4.5 40 Safety Features Actuation fails to actuate X 013G2.2.25; Knowledge of the bases in 4.2 87 Technical Specifications for limiting conditions for operations and safety limits.

022 (SF5 CCS) Containment Cooling X 022K4.03, Automatic containment isolation 3.6 41 025 (SF5 ICE) Ice Condenser X 025K4.02; System control 2.8 42 026 (SF5 CSS) Containment Spray X 026A1.02; Containment temperature 3.6 43 039 (SF4S MSS) Main and Reheat X 039K3.06; SDS 2.8 44 Steam X 039K5.08; Effect of steam removal on 3.6 45 reactivity 059 (SF4S MFW) Main Feedwater X 059K1.02; AFW system 3.4 46

ES-401 7 Form ES-401-2 061G2.4.34; Knowledge of RO tasks 061 (SF4S AFW) X performed outside the main control 4.2 47 Auxiliary/Emergency Feedwater room during an emergency and the resultant operational effects 062G2.1.27; Knowledge of system purpose 062 (SF6 ED AC) AC Electrical X and/or function 3.9 48 Distribution 063 (SF6 ED DC) DC Electrical X 063K2.01; Major DC loads 2.9 49 Distribution 064 (SF6 EDG) Emergency Diesel X 064A4.06; Manual start, loading and stopping 3.9 50 Generator of the ED/G X 064A2.13; Ability to (a) predict the impacts of 2.8 88 opening auxiliary feeder bus (ED/G sub supply) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

073 (SF7 PRM) Process Radiation X 073A2.02; Detector failure 2.7 51 Monitoring 076 (SF4S SW) Service Water X 076K3.01; Closed cooling water 3.4 52 X 076A2.01; Loss of SWS 3.7 89 078 (SF8 IAS) Instrument Air X 078K2.01; Instrument air compressor 2.7 53 X 078G2.4.31; Knowledge of annunciator 4.2 54 alarms, indications, or response procedures 103 (SF5 CNT) Containment X 103A1.01; Containment pressure, temperature 3.7 55 and humidity X

103A2.03; Phase A and B isolation 3.8 90 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals: 3 2 2 2 3 2 3 3/ 2 3 3/ Group Point Total: 28/5 3 2 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 X 001A2.12; Erroneous ECP calculation. 4.2 91 002 (SF2; SF4P RCS) Reactor X 002K6.04; RCS vent valves 2.5 56 Coolant

ES-401 8 Form ES-401-2 011 (SF2 PZR LCS) Pressurizer X 011G2.1.7; Ability to evaluate plant 4.7 92 Level Control performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation 014 (SF1 RPI) Rod Position X 014A2.02; Ability to (a) predict the impacts of 3.6 93 Indication the following malfunctions or operations on the RPIS; and (b) use procedures to correct, control, or mitigate the consequences: Loss of power to the RPIS 015 (SF7 NI) Nuclear X 015A2.04; Effects on axial flux density of 3.3 57 Instrumentation control rod alignment and sequencing, xenon production and decay, and boron vs. control rod reactivity changes 016 (SF7 NNI) Nonnuclear X 016K5.01; Separation of control and protection 2.7 58 Instrumentation circuits 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool X 033K3.02; Area and ventilation radiation 2.8 59 Cooling monitoring systems 034 (SF8 FHS) Fuel-Handling X 034A1.02; Water level in the refueling canal 2.9 60 Equipment 035 (SF 4P SG) Steam Generator X 035K4.01; Knowledge of S/GS design 3.6 61 feature(s) and/or interlock(s) which provide for the following: S/G level control 041 (SF4S SDS) Steam X 041A3.02: Ability to monitor automatic 3.3 62 Dump/Turbine Bypass Control operation of the SDS, including: RCS pressure, RCS temperature, and reactor power 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation X 072A4.02; Major components 2.5 63 Monitoring 075 (SF8 CW) Circulating Water X 075G2.4.4; Ability to recognize abnormal 4.5 64 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures 079 (SF8 SAS**) Station Air 086 Fire Protection X 086K1.03; AFW system 3.4 65 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals: 1 1 1 1 1 1 1/ 1 1 1/ Group Point Total: 10/3 2 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-only IR # IR #

Knowledge of operator responsibilities during all modes of plant 2.1.2 operation 4.1 66 Knowledge of procedures and limitations involved in core 2.1.36 alterations 3.0 67 Ability to locate and operate components, including local 2.1.30 controls 4.4 68

1. Conduct of Operations Ability to perform specific system and integrated plant 2.1.23 procedures during all modes of plant operation 4.4 94 Ability to use procedures to determine the effects on reactivity 2.1.43 of plant changes 4.3 95 Subtotal 3 2 Ability to perform pre-startup procedures for the facility, 2.2.1 including operating those controls associated with plant 4.5 69 equipment that could affect reactivity 2.2.12 Knowledge of surveillance procedures 3.7 70 Ability to obtain and interpret station electrical and mechanical 2.2.41 drawings 3.5 71
2. Equipment Control Ability to determine the expected plant configuration using 2.2.15 design and configuration control documentaion 4.3 96 Knowledge of the process for managing maintenance activities 2.2.18 during shutdown operations. 3.8 97 Subtotal 3 2 2.3.15 Knowledge of radiation monitoring systems 2.9 72 Ability to comply with radiation work permit requirements during 2.3.7 normal or abnormal conditions 3.5 73 Knowledge of radiological safety principles pertaining to
3. Radiation 2.3.12 licensed operator duties, such as containment entry 3.7 98 Control requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc Subtotal 2 1 2.4.14 Knowledge of general guidelines for EOP usage 3.8 74 2.4.3 Ability to identify post-accident instrumentation 3.7 75
4. Emergency 2.4.19 Knowledge of EOP layout, symbols and icons 4.1 99 Procedures/Plan Knowledge of EOP implementation hierarchy and coordination 2.4.16 with other l support procedures or guidelines such as, 4.4 100 operating procedures, abnormal l operating procedures, and severe accident management guidelines Subtotal 2 2 Tier 3 Point Total 10 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A T1G1 026AA1.04 CRDM hi temperature alarms . Not applicable because CCS does not cool CRDMS at Watts Bar. Cooled by SW (ERCW)

T1G1 057AA2.11 Loss of Vital AC / instrument Bus does not affect MFPs at all at WB.

T1G2 028AA2.14 Reflux boiling would cause loss of PZR level, not sure about given change in ambient pressure either.

T1G2 067AA1.04 Watts Bar does not have this as a responsibility for Ros. They have separate Fire Ops group that handles these tasks. Low K/A value T2G1 004A3.16 Emergency boration lights not affected by power at WB T2G1006K 006K1.14 No cause effect relationship with ECCS and IAS at WB 1.14 T3 2.3.7 RWP question LOD issue RO question but KA really an SRO question, Also was a duplicate on this T2, Grp 1 2.2.25 KA so had to change 062G2.2.25; Knowledge of the bases in Technical Specifications for limiting conditions for operations and / or safety limits

Digitally signed by David E. Dumbacher David E. Dumbacher Date: 2020.08.14 11:26:24 -04'00'

ES-401 Written Examination Review Worksheet Form ES-401-9 1.

L 3. Psychometric Flaws 4. Job Content Flaws 5. Other O 2.

Q K LOD 6.

(F (1-5) Stem Cred. Job- Q- SRO 7. Status Cues T/F Partial Minutia #/Units Backward Source

/H Focus Dist Link K/A Only (U/E/S)

(B/M/N)

)

8. Explanation Numbers highlighted in Yellow were part of the pre-submittal Insufficient number of D answers (12) on the RO exam and insufficient number of Cs (3) existed on the SRO portion.

Please keep the answers but rearrange letter answer (unless modifying Unsat questions) to have at least 4 additional Ds on the RO and at least 3 additional C s on the SRO exam

  • Generically, plausibility could be a bit more credible with less margin to
  • The SRO questions need to be solidly SRO-only and not questions that can be answered with just systems knowledge.
  • Also the procedure selection aspect for SRO needs to be associated with AOIs or Emergency related procedures.
  • Higher Cog or Lower - sometimes the question could not support Higher.;
  • KA match. Be careful with the Generics in Tier 3.

They also have to match the category like conduct of ops or Equipment Control (see # 70) .

  • Careful with interplay between Part 1 and Part 2 of answers. Cannot have part one answer CUE part 2 of the answer. See 76 Note: All the below blue font, post submittal, items were corrected, changed, or added supporting material by 8-13-20.

Exam considered a good exam at this point 1 H 2 x N S 2 H 3 x N S It is clear the AOI provided states that four RCPs needed 3 H 3 N S for DNB criteria of Safety analysis. Could applicant argue that is not really true due to power level in stem?

ES-401 Written Examination Review Worksheet Form ES-401-9 1.

L 3. Psychometric Flaws 4. Job Content Flaws 5. Other O 2.

Q K LOD 6.

(F (1-5) Stem Cred. Job- Q- SRO 7. Status Cues T/F Partial Minutia #/Units Backward Source

/H Focus Dist Link K/A Only (U/E/S)

(B/M/N)

)

4 H 3 N S Does it make sense to close a vent valve on lowering 5 H 3 N S/? level (vacuum concern) Could question part 2 rather ask IF there is an auto closure feature available?

6 H 3 N S 7 H 3 B S 8 H 2 B S Ref1er 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.

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.)

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.

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?

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

ES-401 3 Form ES-401-9 2.

1. LO 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q LOK D Source Status 8. Explanation (F/H) (1- Stem Cred. Job- Q- SRO (B/M/N) (U/E/S)

Cues T/F Partial Minutia #/Units Backward

5) Focus Dist Link K/A Only 9 F/L 2 N S Editorial only request: Please make (1) and (2) 10 H 3 x N S/E consistent in stem 11 H 3 N S 12 H 3 x N S 13 H 4 N S 14 H 2 N S 15 H 2 N S 16 F/L 2 N S 17 F/L 3 N S 18 H 2 N S 19 F/L 2 N S 20 H 2 N S Please add curve that is referenced in answer into 21 H 3 N S/ E supporting material 22 H 2 B S 23 H 2 x N S 24 H 2 N S 25 F/L 2 B S

ES-401 4 Form ES-401-9 2.

1. LO 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q LOK D Source Status 8. Explanation (F/H) (1- Stem Cred. Job- Q- SRO (B/M/N) (U/E/S)

Cues T/F Partial Minutia #/Units Backward

5) Focus Dist Link K/A Only 26 H 2 N S 27 H 2 B S 28 H 2 N S 29 F/L 3 N S 30 F/L 2 N S 31 H 2 N S 32 F/L 2 N S 33 H 2 N S 34 H 2 N S 35 F/L 2 M S 36 H 2 N S 37 H 3 N S 38 H 2 N S 39 F/L 2 N S 40 F/L 2 x N S 41 F/L 2 N S 42 H 2 B S

ES-401 5 Form ES-401-9 2.

1. LO 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q LOK D Source Status 8. Explanation (F/H) (1- Stem Cred. Job- Q- SRO (B/M/N) (U/E/S)

Cues T/F Partial Minutia #/Units Backward

5) Focus Dist Link K/A Only 43 F/L 2 B S 44 H 1/2 N S 45 H 3 N S/? Verify this is ok as Tavg vs Tcold. Believe it is ok 46 F/L 2 N S 47 F/L 2 N S 48 F/L 2 N S 49 F/L 2 N S 50 F/L 2 N S

ES-401 6 Form ES-401-9 P

Stem T/ Cred ar B/M/ Status Q# LOK LOD Cues Job Minutia Units Backward K/A SRO Comments Focus F Distractor ti N U/E/S al 51 F/L 2 N S 52 F/L 2 N S 53 F/L 2 N S 54 H 3 N S 55 F/L 2 N S 56 F/L 2 N S 57 H 2 N S 58 H 2 N S 59 H 3 N S 60 F/L 2 N S 61 F/L 3 N S P

Stem T/ Cred ar B/M/ Status Q# LOK LOD Cues Job Minutia Units Backward K/A SRO Comments Focus F Distractor ti N U/E/S al 62 H 2 N S 63 F/L 2 MB S 64 H 2 N S 65 F/L 2 N S 66 H 2 B S

ES-401 7 Form ES-401-9 67 F/L 2 N S 68 F/L 2 S N

69 F/L 2 N S 70 L/F 2 N S 71 F/L 2 N S 72 F/L 2 X MB S/E .

73 F/L 2 N S 74 F/L 2 N S __

75 H 2 N S 76 H 2 x N S P

Stem T/ Cred ar B/M/ Status Q# LOK LOD Cues Job Minutia Units Backward K/A SRO Comments Focus F Distractor ti N U/E/S al 77 H 2 N S 78 H 2 x N S/E 79 F/L 3 N S 80 L/F 2 x N S 81 H 3 N S 82 H 2 N S

ES-401 8 Form ES-401-9 P

Stem T/ Cred ar SR Status Q# LOK LOD Cues Job Minutia Units Backward K/A B/M/N Comments Focus F Distractor ti O U/E/S al 83 H 2 N S 84 H 3 B S .

85 H 2 X X MB S 86 H 2 N S P

Stem T/ Cred ar SR Status Q# LOK LOD Cues Job Minutia Units Backward K/A B/M/N Comments Focus F Distractor ti O U/E/S al 87 F/L MB S 88 H 3 N S/E 89 H 3 N S 90 H 2 N S

ES-401 9 Form ES-401-9 P

Stem T/ Cred ar SR Status Q# LOK LOD Cues Job Minutia Units Backward K/A B/M/N Comments Focus F Distractor ti O U/E/S al 91 F/L 2 N S 92 H 2 N S S

93 3 N 94 F/L 2 N S 95 H 2 N S P

Stem T/ Cred ar SR Status Q# LOK LOD Cues Job Minutia Units Backward K/A B/M/N Comments Focus F Distractor ti O U/E/S al 96 F/L 2 N S 97 F;L 3 N S 98 F/L 2 N S 99 F/L 2 N S /E 100 F/L 2 N S

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