ML20302A432
| ML20302A432 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/28/2020 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| 50-269/20-301, 50-270/20-301, 50-287/20-301 50-269/OL-20, 50-270/OL-20, 50-287/OL-20 | |
| Download: ML20302A432 (113) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 ILT 20-1 NRC Exam Facility:
Oconee Nuclear Station Date of Examination:
6/04/2020 Examination Level: RO SRO Operating Test Number:
1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations
[KA: G2.1.43 (4.1/4.3)]
(25 min)
D, R ADM-114, Manually Calculate Shutdown Margin Conduct of Operations
[KA: G2.1.25 (3.9/4.2)]
(15 min)
M, R ADM-116, Determine Time for SFP to Reach 200°F Equipment Control
[KA: G2.2.12 (3.7/4.1)]
(15 min)
D, R ADM-204, Perform SG Downcomer Temperature Surveillance Radiological Control
[KA: G2.3.15 (2.9/3.1)]
(20 min)
N, R ADM-307, 1RIA-40 Setpoint Calculation Emergency Plan N/A 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 and Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and 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 ILT 20-1 NRC Exam Facility:
Oconee Nuclear Station Date of Examination:
6/04/2020 Examination Level: RO SRO Operating Test Number:
1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations
[KA: G2.1.43 (4.1/4.3)]
(30 min)
M, R ADM-S111, Manually Calculate Shutdown Margin and Determine any Required Actions Conduct of Operations
[KA: G2.1.25 (3.9/4.2)]
(35 min)
D, R ADM-S112, Manually Calculate Core Tilt Due to Loss of the OAC and Determine Any Required Actions and Completion Times Equipment Control
[KA: G2.2.18 (2.6/3.9)]
(20 min)
D, R ADM-S203, Complete Plant Configuration Sheet (Time to Core Boil) and Determine Any Required Actions Radiological Control
[KA: G2.3.6 (2.0/3.8)]
(25 min)
D, R ADM-S301, Determine RIA Setpoints and Approval Level Required for GWD Tank Release Emergency Plan
[KA G2.4.38 (2.4/4.4)]
(15 min)
N, R ADM-S408, Determine the Appropriate Emergency Action Level 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 and Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 06/04/2020 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function
[KA: EPE011 EA1.11 (4.2/4.2)] (15 min)
A, EN, D, L, S
3
- b. RO-607, Alignment of CT-5 per AP/48 AP/0/A/1700/048 (Loss of a Startup Transformer)
[KA: SYS062 A2.05 (2.9/3.3*)] (10 min)
N, S 6
- c. RO-306a, Perform Rule 5 (Main Steam Line Break)
EOP Rule 5 (Main Steam Line Break)
[KA: BW/E05 EA1.1 (4.2/4.2)] (10 min)
A, EN, M, L, S
4P
- d. RO-105, Perform Control Rod Movement PT for Grp 1 PT/1/A/0600/015 Encl. 13.2 (Control Rod Movement at Power)
[KA: SYS001 A4.08 (3.7/3.4)] (10 min)
D, S 1
[KA: SYS061 A2.04 (3.4/3.8)] (6 min)
D, L, S 4S
- f. RO-803a, Align Intake Canal for Recirc on Dam Failure AP/1/A/1700/013 Dam Failure
[KA: SYS075 A2.02 (2.5/2.7)] (20 min)
A, D, S 8
[KA: APE069 AA1.01 (3.5/3.7)] (15 min)
A, L, M, S 5
- h. RO-203, Pressure Makeup to CFT OP/1/A/1104/001 Encl. 4.7 (Pressure Makeup to CFTs Using Nitrogen)
[KA: SYS006 A1.13 (3.5/3.7)] (10 min)
D, S 2
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
AO-501, Place Reactor Building Hydrogen Analyzers in Service EOP Encl. 5,2 (Placing RB Hydrogen Analyzers in Service)
[KA: SYS028 A4.03 (3.1/3.3)] (12 min)
D, E, R 5
- j.
AO-S404a, MS-87, MS-126 & MS-129 Isolation AP/0/A/1700/025 Encl. 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
[KA: SYS039 A4.01 (2.9/2.8)] (15 min)
A, E, D, L 4S
- k. AO-802, Isolate HPSW and LPSW During an Auxiliary Building Flood AP/3/A/1700/030 (Auxiliary Building Flood) Enclosures 5.1 (HPSW AB Flood) and 5.2 (LPSW TB Isolations)
[KA: BW/A07 AA2.2 (3.3/3.7)] (15 min)
E, M 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (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
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 06/04/2020 Exam Level: RO SRO-I X SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function
[KA: EPE011 EA1.11 (4.2/4.2)] (15 min)
A, EN, D, L, S
3
- b. RO-607, Alignment of CT-5 per AP/48 AP/0/A/1700/048 (Loss of a Startup Transformer)
[KA: SYS062 A2.05 (2.9/3.3*)] (10 min)
N, S 6
- c. RO-306a, Perform Rule 5 (Main Steam Line Break)
EOP Rule 5 (Main Steam Line Break)
[KA: BW/E05 EA1.1 (4.2/4.2)] (10 min)
A, EN, M, L, S
4P
- d. RO-105, Perform Control Rod Movement PT for Grp 1 PT/1/A/0600/015 Encl. 13.2 (Control Rod Movement at Power)
[KA: SYS001 A4.08 (3.7/3.4)] (10 min)
D, S 1
[KA: SYS061 A2.04 (3.4/3.8)] (6 min)
D, L, S 4S
- f. RO-803a, Align Intake Canal for Recirc on Dam Failure AP/1/A/1700/013 Dam Failure
[KA: SYS075 A2.02 (2.5/2.7)] (20 min)
A, D, S 8
[KA: APE069 AA1.01 (3.5/3.7)] (15 min)
A, L, M, S 5
- h. N/A
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
AO-501, Place Reactor Building Hydrogen Analyzers in Service EOP Encl. 5,2 (Placing RB Hydrogen Analyzers in Service)
[KA: SYS028 A4.03 (3.1/3.3)] (12 min)
D, E, R 5
- j.
AO-S404a, MS-87, MS-126 & MS-129 Isolation AP/0/A/1700/025 Encl. 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
[KA: SYS039 A4.01 (2.9/2.8)] (15 min)
A, E, D, L 4S
- k. AO-802, Isolate HPSW and LPSW During an Auxiliary Building Flood AP/3/A/1700/030 (Auxiliary Building Flood) Enclosures 5.1 (HPSW AB Flood) and 5.2 (LPSW TB Isolations)
[KA: BW/A07 AA2.2 (3.3/3.7)] (15 min)
E, M 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (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
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 06/04/2020 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function
[KA: EPE011 EA1.11 (4.2/4.2)] (15 min)
A, EN, D, L, S
3
- b. RO-607, Alignment of CT-5 per AP/48 AP/0/A/1700/048 (Loss of a Startup Transformer)
[KA: SYS062 A2.05 (2.9/3.3*)] (10 min)
N, S 6
- c. RO-306a, Perform Rule 5 (Main Steam Line Break)
EOP Rule 5 (Main Steam Line Break)
[KA: BW/E05 EA1.1 (4.2/4.2)] (10 min)
A, EN, M, L, S
4P
- d. N/A
- e. N/A
- f. N/A
- g. N/A
- h. N/A
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
AO-501, Place Reactor Building Hydrogen Analyzers in Service EOP Encl. 5,2 (Placing RB Hydrogen Analyzers in Service)
[KA: SYS028 A4.03 (3.1/3.3)] (12 min)
D, E, R 5
- j.
AO-S404a, MS-87, MS-126 & MS-129 Isolation AP/0/A/1700/025 Encl. 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
[KA: SYS039 A4.01 (2.9/2.8)] (15 min)
A, E, D, L 4S
- k. N/A All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (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
ES-301 Operating Test Review Worksheet Form ES-301-7 m
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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, 0.3 and 0.4)
- 2.
Determine the level of difficulty (LOO) 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)
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oO 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, 0.1)
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, O.1.a, and ES-301, O.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).
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 reviewer's 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.
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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, 8.3).)
Check this box if the level of difficulty is not appropriate.
Check this box if the event has a TS.
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.
Check this box if the event overlaps with another event on any of the last two NRC examinations.
(Appendix D, C.1.f)
Based on the reviewer's 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.
Record any explanations of the events here.
In the shaded boxes, sum the number of check marks in each column.
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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 LOO 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 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.
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G 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-O-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-O-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-O-2 with measurable performance standards (see Appendix D).
Enter the total number of unsatisfactory CTs in column 6.
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In column 7, calculate the percentage of unsatisfactory scenario elements:
1 + 3 + 5 100%
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 Operating Test Review Worksheet Form ES-301-7 Sitename: 0Co/lJ£E,I[) u CLE,4/( S TA7oN Exam Date: Jove Ro2O OPERATING TEST TOTALS Total Total Total Total Unsat.
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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.
- 4.
- 5.
- 6.
Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous tables.
This task is for tracking only.
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 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 s 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 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-301, Page 33 of 33
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 1 of 30 JPM Comments Generic Comments:
A recent expectation is that all JPM task standards must exactly parallel the JPM Critical Steps as linked in the JPM document. Some JPM feedback comments provide examples of what we need to add for the task standard statements. All JPM task standards basically need to repeat/re-state all critical steps in detail.
As discussed in further detail below, there are some JPMs that may need replacement, or are unsatisfactory to administer as submitted:
o Too much overlap between Sim JPM B and Scenario 1 Event 7. One of these items will likely need to be replaced.
o Too much overlap between Sim JPM F (RB Purge) and written exam Q61.
One of these items will likely need to be replaced.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 2 of 30 ADMIN JPM Comments RO CONDUCT OF OPS (A1-a): Manually Calculate Shutdown Margin PT/1/A/1103/015, REACTIVITY BALANCE PROCEDURE Task Standard = Critical Steps.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 3 of 30 ADMIN JPM Comments RO CONDUCT OF OPS (A1-b): Determine Time for SFP to Reach 200 °F AP/035 Encl. 5.4 Based on the layout of Table 11, an applicant could lookup the wrong value and still obtain the correct answer (9.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). Recommend that we change the answer sheet to have the applicants list something like the following: (1) Table used, (2) Time used, (3) Temperature used, and then (4) Final value of time to reach 200 degrees. This way it will be obvious if a mistake is made (or not) by inspection. Otherwise, the only way to evaluate critical steps JPM 5/6 would be via post-exam questions.
Task standard needs to exactly match critical steps. For this one, recommend something like the following: AP/035 Encl. 5.4 is correctly performed and the following parameters determined:
Time (Days) = 55 days Actual SFP Temperature = 106 degrees F Table 11, 110 degrees F column selected Table 11, 54 days row selected 9.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> determined as time-to-reach 200 degrees F
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 4 of 30 ADMIN JPM Comments RO EQUIPMENT CONTROL (A2): Perform SG Downcomer Temperature Surveillance.
OP/014 CONTROL ROOM INSTRUMENTATION OPERATION AND INFORMATION What is the operational validity for only doing the surveillance on the 1A S/G? Better if the initiating cue state the following: The CRS directs you to perform OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) component check for the SG Downcomer Temperatures. Document your results below and list all deficiencies found, if any. Stating the exact page number is cueing and not operationally valid.
We can delete the second initial condition statement, it repeats information in the initiating cue and is therefore unnecessary.
Change the 1B SG Pressures to 890.0 psig.
Task Standard=Critical Steps
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 5 of 30 ADMIN JPM Comments RO RAD CONTROL (A3): 1RIA-40 Setpoint Calculation and Adjustment.
PT/0/A/0230/001, RADIATION MONITOR CHECK Task Standard=Critical Steps Initial Conditions: 1A CSAE flow to 12.0 for parallelism with other values High bounds on the JPM step 11 calculation: how would an applicant correctly round up to 682 for the high setpoint?
JPM step 12: if an applicant were to incorrectly start to perform section 4, examiner will not step in to give a cue - already given on the initial conditions sheet. It would be incorrect performance but not a critical step.
JPM step 13 and 14: just direct examiner to write SRO in the procedure blocks and placekeep, then return the procedure to applicant.
For JPM steps 15 and 17, we need to know what the RIA-40 setpoint are; they have to be far enough away from the calculated that adjustment is required.
For JPM step 19, how does the applicant and examiner know that the source check is performed correctly? Please include this information in the JPM text.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 6 of 30 ADMIN JPM Comments SRO CONDUCT OF OPS (A1-a): Manually Calculate Shutdown Margin and Determine any Required Actions.
PT/1/A/1103/015, REACTIVITY BALANCE PROCEDURE Task Standard=Critical Steps.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 7 of 30 ADMIN JPM Comments SRO CONDUCT OF OPS (A1-b): Manually Calculate Core Tilt Due to Loss of the OAC and Determine any Required Actions.
PT/0/A/1103/019 BACKUP INCORE DETECTOR SYSTEM Task Standard=Critical Steps Include two more blocks for TS/SLC, ACTIONs, and TIMEs on the cue sheet as head fakes
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 8 of 30 ADMIN JPM Comments SRO EQUIPMENT CONTROL (A2): Complete Plant Configuration Sheet (Time to Core Boil) and Determine Any Required Actions OP/0/A/1108/001 A, REACTOR CORE AND SFP LOSS OF COOLING HEATUP TABLES SD 1.3.5, SHUTDOWN PROTECTION PLAN, ATT. 9.2, PLANT CONFIGURATION SHEET Task Standard = Critical Steps
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 9 of 30 ADMIN JPM Comments SRO RADIATION CONTROL (A3): Determine RIA Setpoints and Approval Level Required for GWD Tank Release.
OP/1-2-/1104/018, GWD SYSTEM PT/0/A/0230/001, RADIATION MONITOR CHECK Task Standard=Critical steps.
Second part initiating cue needs to state minimum approval level somehow.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 10 of 30 ADMIN JPM Comments SRO EMERGENCY PLAN: Determine the Appropriate Emergency Action Level CSD-EP-ONS-0101-02 (WALLCHART) Rev 000 AD-EP-ALL-0101 Emergency Classification Rev 1 CSD-EP-ONS-0101-01 Bases Rev 000 Need to evaluate how the candidates will use EAL charts. If they use the large boards, they will have to be arranged in the room so they cannot see each others work as they look from the back to the front of the room.
Task Standard=Critical Steps Technically this could be argued as a simple one-step JPM and therefore unacceptable. The initial cues do not drive an applicant to make any evaluation of fission product barriers, and therefore someone could go straight to hostile action section and get the JPM correct without even evaluating the other stuff on the cue sheet. Recommend adding something else to the determination to fix this; for example, after the declaration is made, evaluate site assembly or evacuation?
Based on previous discussions, may need to change out this JPM due to overlap concerns with SRO written exam (2 draft SRO Qs that involve EAL declarations). NOTE: After this comment was made, Oconee modified one of the SRO written exam Qs so it did not involve an EAL call.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 11 of 30 Simulator JPMs JPM A: Align ECCS Suction to Emergency Sump. (ALT PATH)
EOP Encl 5.12, ECCS SUCTION SWAP TO RBES; K/A 011EA1.11 Apparent typo on JPM p. 3: Showdig likely means showing?
The examiner cues in the proposed JPM text are way too informative and are cueing.
In any event, it is always a good principle to minimize the amount of pre-scripted communications between the examiner and the applicant. For all steps where time compression may be used, prefer to have the booth operators call the applicant on the simulator floor and tell him/her: For the purpose of the JPM, we are exercising time compression, standby you may now resume performance of the JPM in real time. This way the booth operators know whether or not the timers are working and the BWST levels go to where we want them to go to, also with the phone in hand the applicant will hopefully not be adjusting the simulator during the time warps.
For JPM step 4/procedure step 52, we need to specify in the step exactly which HPI pump(s) will be secured.
The Task Standards for all JPMs need to exactly parallel the critical steps, as for example: Enclosure 5.12 ECCS Suction Swap to RBES is properly completed to align ECCS to the Emergency Sump by performing the following in sequence:
-securing (xyz) HPI pump(s)
-simultaneously opening 1LP-19 and 1LP-20
-closing 1LP-22
-stopping the 1A LPI pump, 1A RBS pump, and closing 1LP-19
-dispatching an operator to close 1LP-28 Lets run the JPM through procedure step 78, it will give some time-realism to the operator closing 1LP-28. Terminate the JPM when booth calls in that -28 is closed at step 78 (WHEN/THEN waiting for this call).
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 12 of 30 Simulator JPMs JPM B: Alignment of CT-5 Per AP/48. RO-SRO AP/48, LOSS OF A STARTUP TRANSFORMER Recommend adding You are the Unit 2 RO to the Initial Conditions (per NOTE before step
- 1)
The Task Standards for all JPMs need to exactly parallel the critical steps, as for example:
AP/48, Loss of a Startup Transformer, is properly completed to align CT-5 by performing the following in sequence:
-closing SL1 and SL2 breakers
-placing both CT-5 transfer switches in AUTO There is too much overlap between this Sim JPM and Scenario 1 Event 7 - its the same initiating event in both cases. Why would we assume that the CRS would not enter AP/048 during the scenario and thus complete the steps twice? One of these items will likely need to be replaced.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 13 of 30 Simulator JPMs JPM C: Perform Rule 5 (Main Steam Line Break) (ALT PATH)
EOP RULE 5, MAIN STEAM LINE BREAK The Task Standard for this JPM writeup (RO-306a) appears to be in error (same critical steps as JPM B). Please re-write Task Standard w/parallelism on all critical steps as indicated in the comments for JPMs A and B above.
JPM and Rule 5 step 12: what specifically is critical for the applicant to perform here? The specific items must be clearly defined for the examiner. The Rule 5 procedure step just says Throttle HPI. How does the applicant know what to do here? Is there other procedural guidance that should be referenced (Rule 6?)? (if so, we need to include it in the JPM steps)
Is there any other way for an applicant to Throttle HPI correctly besides what we have listed in the JPM step? Lets discuss this during prep week to ensure we are adequately covered.
Concern is that we do not have a specific procedurally-driven success path unless Oconee has clearly defined what Throttle HPI means here.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 14 of 30 Simulator JPMs JPM D: Perform Control Rod Movement PT for Group 1 PT/1/A/0600/015 Encl. 13.2, CONTROL ROD MOVEMENT AT POWER Task Standard and Critical Steps need to match, please use recommended format provided for JPMs A and B.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 15 of 30 Simulator JPMs JPM E: Feed Both SGs With One MDEFDW Pump EOP ENCL. 5.9, EXTENDED EFDW OPERATIONS As with all JPMs, ensure Task Standard exactly parallels the critical steps.
Recommend that we break out the initial conditions into separate bullets for readability.
Delete the last sentence in initial conditions, it is repeating the initiating cue information.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 16 of 30 Simulator JPMs JPM F: Place RB Purge in Operation (ALT PATH)
OP/014 ENCL. 4.1, RB PURGE RELEASE The Task Standard needs to exactly match critical steps, similar to feedback provided for JPMs A and B above.
There is too much overlap between this JPM and written exam Q61both items indicate that RIA-45 is interlocked to close all RB purge valves. Either Q61 or JPM F will need to be modified/changed.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 17 of 30 Simulator JPMs JPM G: Perform EOP Encl 5.35 (Containment Isolation) (ALTERNATE PATH)
EOP ENCL. 5.35, CONTAINMENT ISOLATION Task Standard = Critical Steps.
Unlike most of the other sim JPMs, there is nothing provided under the Directions without an IC section. Do we need them?
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 18 of 30 Simulator JPMs JPM H: Pressure Makeup to CFT.
OP/001 ENCL. 4.7, PRESSURE MAKEUP TO CFTS USING NITROGEN Task Standard = Critical Steps JPM step 5: are there indications available for an applicant to determine the status of 1N-128? Prefer to just not give a flat-out cue by stating valve position to the applicant if they can figure it out themselves.
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 19 of 30 IN-PLANT JPMS JPM i: Place Reactor Building Hydrogen Analyzers in Service EOP ENCL. 5.2, PLACING RB HYDROGEN ANALYZERS IN SERVICE Task Standard = Critical Steps Is this a time critical JPM? The task standard says: Reactor Building Hydrogen Analyzers are placed in service by procedure within 90 minutes.
But there is nothing in the JPM steps to reference 90 minutes, or to say why 90 minutes is required. Discuss.
The Task Title says Place the 1A H2 Analyzer in service, but the cue given to the applicant is to place both trains in service. Which is correct?
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 20 of 30 IN-PLANT JPMS JPM J: MS-87, MS-126, & MS-129 Isolation (ALT PATH)
AP/025 ENCL. 5.13 ms-87, ms-126 & MS-129 ISOLATION Task Standard = Critical Steps
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 21 of 30 IN-PLANT JPMS JPM K: Isolate HPSW and LPSW During an Auxiliary Building Flood AP/030 ENCL. 5.1 AND 5.2 Task Standard = Critical Steps The procedure says that enclosure 5.2 is time critical, but the JPM does not. Is this a time critical JPM? What times are the procedure referring to?
Unsure of the relationship/critical nature of valves LPSW-500 and -501. The JPM says that only closing LPSW-500 is critical. However, the procedure directs opening LPSW-501, and then says if LPSW-501 is open, then close LPSW-500? What if an applicant misses the step to open LPSW-501 and then completes the JPM, is LPSW isolated? Need to ensure whether or not opening LPSW-501 is (also) a critical step, or if closing LPSW-500 is not critical?
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 22 of 30 Scenario Comments Generic Comments:
Every scenario needs to include critical task statement that if the team causes or initiates an unexpected/unscripted Reactor trip, it is possibly unsatisfactory performance of a critical task.
Examiners need full TS information in the ES-D-2 to correctly evaluate the SROs on this competency (LCO statement, CONDITIONS, REQUIRED ACTIONS, and COMPLETION TIMES)
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 23 of 30 NRC Scenario 1: Station Blackout (SBO) (100% power)
Turnover:
Does CT-5 OOS for maintenance have any impact on the CT-1 lockout event or TS?
Event 1 - Restore 1B FWPT Pump from Handjack (SRO-Normal + BOP-Normal)
Event 2 - 1HP-120 Fails Closed (SRO-Component + OATC-Component)
Unsure why there is a booth cue on top of p. 5/52 where the booth calls in asking for 1CA battery voltages? How is this related to scenario?
On bottom of p. 7/52, it is assumed that the applicant crew has called to request repair of 1HP-120. Contingency/what is the path if the crew does not ask for maintenance support?
Event 3 - Controlling NR Tave Fails High (SRO-Instrument + OATC-Instrument)
If the operators do not take timely action to stop rod insertion, will rod insertion limits be reached? If so, how long would that take (data needs to be in an evaluator note)?
Potential that this is a critical task for event 3, lets discuss during prep week.
Event 4 - 1B FWPT Low Oil Level (SRO-Component + BOP-Component)
Event 5 - Manual Power Reduction for 1B FWPT (SRO-Reactivity, TS + OATC-Reactivity)
For all TS events, please include the full TS text for the evaluators (cut and paste full LCO, conditions, actions, completion times) p. 18 of 52. What reference says that SSF in inoperable below 85% RTP? Need to include as well.
Unsure about p. 19 of 52, why is it included at this point? It seems to be a duplicate of procedure steps already included on p. 15 of 52.
Event 6 - High Vibrations of 1A RBCU (SRO-Component, TS + BOP-Component)
Include full TS details for the RBCU event (p. 22 of 52)
Event 7 - CT-1 Lockout (SRO-TS)
Train-the-Chief-Examiner-time: are there really no actions required for this event? How would the station restore CT-1 if this really happened in the plant?
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 24 of 30 Event 8 - MAJOR EVENT: Switchyard Isolation/Station Blackout (SBO)
Event 8 - Malf after EOP entry - KHU-2 Emergency Lockout Event 8 - Malf after EOP entry - TDEFWP fails to start in Automatic Critical Tasks: (please update the critical task language with the below recommendations)
- 1. Any Event: Causing an unnecessary plant trip or ESF actuation may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021. (CT-1)
- 2. Event 3, potential: Stop automatic inward rod motion before control rod alignment limits are violated, placing the plant in a potentially unanalyzed condition. (CT-2)
- 3. Event 8: Establish adequate emergency feedwater flow from the TDEFWP such that entry into HPI Forced Cooling is not required. (CT-3)
- 4. Event 8: Need better criteriawhat is the adverse impact to the plant of not restoring electrical power from the KHU iaw the procedural direction? It would be better to determine a plant parameter to use instead of a somewhat arbitrary procedural bounding criterion. Agree this is critical but want to come up with a better bounding if possible. (CT-4)
Prior to Major Event:
RO: Event 2 (I/C) + Event 3 (I/C) + Event 5 (R) = three BOP: Event 1 (N) + Event 4 (I/C) + Event 6 (I/C) = three SRO Tech Specs: Event 5 + Event 6 + Event 7 = three Abnormal Events: Event 2 + Event 3 + Event 4 + Event 6 = four Critical Tasks = one + maybe rod insertion limits (Event 3)
After Major Event:
Instrument/component malfunctions after EOP entry = two EOPs entered =
EOP contingencies =
Critical Tasks = two
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 25 of 30 NRC Scenario #2: ATWS/Loss of 1TA Switchgear/Turbine Fails to Trip (97% power)
Turnover Event 1 - Turbine Control Valve Movement PT (CV3 & CV4) (BOP-Normal + SRO-Normal)
Event 2 - 1A CC Pump Trips & Standby CC Pump Fails to Auto-Start (BOP-Component +
SRO-Component)
Page 8, full listing of TS, ACTIONS, Times, etc.
Event 3 - Inadvertent ES Channel 3 Actuation (RO-Component + BOP-Component + SRO-Component, TS)
On paper, it is difficult to determine which actions are OATC and which are BOP actions for this event. Based on the pumps that inadvertently start (LPI), what are the OATC verifiable actions? We need to ensure this is a solid OATC I/C event so we could use it for SRO-Instants in the OATC position (ES-301 requires SRO-Is to get 2 I/C failures as ATC).
Examiner Note on page 12 has minor typo: ES Channel 3 actuation does not isolated the, should read does not isolate Page 13, full TS stuff.
Event 4 - Tc Controller Failure (RO-Instrument + SRO-Instrument)
On Page 16, please include examiner note on how the operators are required to re-ratio feedwater flow for the given power level. It would help to provide estimated values for examiners to compare against
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 26 of 30 Event 5 - Oil Leak on Main Turbine Dont think we can give Component-level credit for the Turbine Oil Leak. The only verifiable action(s) seem to be the downpower, there is no diagnosis or specific action that is required for the oil leak. In other words, how is this event different from the SVP directing a rapid shutdown due to weather or some other cause?
Event 6 - Manual Power Reduction (RO-Reactivity + BOP-Reactivity + SRO-Reactivity, TS)
I think we can give R/Reactivity credit here additionally to the BOP due to relative complexity of the downpower, as long as the event goes close to 18% power During prep week, lets run the downpower all the way down to 18%, or close to it, and put in the ATWS at the point where the operators were going to trip the turbine. This will give us some sense of how long a full downpower would take Page 21: full TS stuff please + justification for SSF inop at 85%.
Event 7 - MAJOR EVENT: ATWS (Loss of 1TA Switchgear)
Event 7 - Malf after EOP entry - Turbine Fails to Trip Event 7 - Malf after EOP entry - 1HP-26 Fails Closed Critical Tasks: (please update the critical task language with the below recommendations)
- 1. Any Event: Causing an unnecessary plant trip or ESF actuation may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021. (CT-1)
- 2. Event 2: Restore CC cooling before two CRD temperatures exceed 180 °F (manual Rx Trip required). (CT-2)
- 3. Event 7: Take action to Trip the Main Turbine before PTS conditions are met (400 °F with >100 °F/hr ). (CT-3) [note] Please establish during validation how long it would take, if the Turbine is not tripped, to reach this condition and add it as an examiner note in the ES-D-2. Is PTS established with Tave or Tc temperature indications?
- 4. Event 7: Take action to initiate negative reactivity addition by either rod insertion or emergency boration flow before Reactor Trip breakers are opened by local operator action. (CT-
- 4)
Prior to Major Event:
RO: Event 3 (I/C) + Event 4 (I/C) + Event 6 (R) = three BOP: Event 1 (N) + Event 2 (I/C) + Event 3 (I/C) + Event 6 (R) = four SRO Tech Specs: Event 3 + Event 6 = two Abnormal Events: Event 2 + Event 3 + Event 4 + Event 5 = four Critical Tasks: two After Major Event:
Instrument/component malfunctions after EOP entry = three EOPs entered =
EOP contingencies =
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 27 of 30 Critical Tasks = two
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 28 of 30 NRC Scenario #3: Small Break LOCA that Evolves into Large Break LOCA (Critial below POAH)
Turnover Event 1 - Pump the RBNS (BOP-Normal + SRO-Normal, TS)
This event needs to be a Normal credit because, even though there is a failure at the end of the event, the operators do not take verifiable action(s) to address the failure.
Please cut-and-paste full TS information for all TS events (page 3)
Event 2 - Raise Power to ~3% and Place ICS in AUTO (RO-Reactivity + SRO-Reactivity)
Event 3 - 1B FWPT Auxiliary Oil Pump Trip (BOP-Component + SRO-Component)
Event 4 - A LPSW Pump OB Bearing Temperature High (BOP-Component + SRO-Component)
Full TS info on p. 9 Event 5 - TDEFWP Oil Sump Dry (SRO-TS)
Full TS info on p. 10 Event 6 - PRZR Spray Valve (1RC-1) Fails Open (RO-Component + SRO-Component, possible TS)
Please add full TS info for DNB spec (TS 3.4.1) including pressure setpoint for this event.
Event 7 - Two Dropped Control Rods Requiring a Rx Trip (RO-Component + SRO-Component)
Event 8 - MAJOR EVENT: SBLOCA that becomes LBLOCA Event 8 - Malf after EOP entry - 1A LPI Pump Fails Event 8 - Malf after EOP entry - 1B LPI Pump Fails (requires 1C LPI alignment)
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 29 of 30 Critical Tasks: (please update the critical task language with the below recommendations)
- 1. Any Event: Causing an unnecessary plant trip or ESF actuation may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021. (CT-1)
- 2. Event 6: Control Pressurizer Pressure such that manual or automatic Rx Trip is not required due to lowering Pressurizer Pressure. (CT-2) [note] we need to know how long it will take to get an automatic Rx trip if no action taken
- 3. Event 8: Stop RCPs within 2 minutes of a Loss of SCM. (CT-3)
- 4. Event 8: Establish adequate core cooling with 1C LPIP to prevent reaching 700°F CETCs. (CT-4) [note] need to know how many minutes post-trip will we reach 700 degrees if this critical task is not performed.
- 5. Event 8: Implementation of Control Room Habitability Guidance: Start the Outside Air Booster Fans within 30 minutes of a LOCA. (CT-5) [note] is the critical requirement to start one, or all, outside air booster fans?
Prior to Major Event:
RO: Event 2 (R) + Event 6 (I/C) + Event 7 (I/C) = three BOP: Event 1 (N) + Event 3 (I/C) + Event 4 (I/C) = three SRO Tech Specs: Event 1 + Event 4 + Event 5 = three Abnormal Events: Event 3 + Event 4 + Event 5 + Event 6 = four Critical Tasks = two After Major Event:
Instrument/component malfunctions after EOP entry = two EOPs entered =
EOP contingencies =
Critical Tasks = three
OCONEE 2020 Draft Exam Comments (Attachment to ES-301-7)
EXAMINATION SECURITY MATERIAL Page 30 of 30
=£wt SA?LE ES-401, Rev. 11 PWR Examination Outline Form ES-401-2 Lao<<OoNE E Date of Exam: JUE 02O RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
A2 G
Total 1
2 3
4 5
6 1
2 3
4 Total
- 1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
2 2
1 2
2 1
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions Tier Totals 5
4 5
5 4
4 27 5
5 10 1
3 2
3 3
2 2
3 2
3 3
2 28 3
2 5
- 2.
1 1
0 1
1 1
1 1
1 1
1 10 O\\
2 1
3 Plant 2
Systems Tier Totals 4
3 3
4 3
3 4
3 4
4 3
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 3
3 1
3 2
2 1
2 Note:
- 1. Ensure that at least two topics from every applicable KIA 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 KIA category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it is replaced by a KIA 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 KIA 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 Kl 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 KIA categories.
- 7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 Kl As.
- 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' I Rs 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 KIA catalog and enter the KIA numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to Kl As that are linked to 1 O 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 KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the KIA catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan.
Fut En SAmt ho
ES-401, REV 11 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC:
008AK3.05 Pressurizer Vapor Space Accident/3 4
4.5 [][] z [))L]LL]L][][]
ECCS termination or throttling criteria 011EA1.02 Large Break LOCA / 3 3.8 4.1 DD@DD Reflux boiling sump level indicators 015AK2.07 RCP Malfunctions / 4 2.9 2.9 VDlDDIDIDT DD RCP seals 022AA2.01 Loss of Rx Coolant Makeup / 2 3.2 3.8 JDIDT @DDT Whether charging line leak exists 026AK3.02 Loss of Component Cooling Water I 8 3.6 3.9 DJVDDDDDDODD The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 IIDDDDDDDDD Controllers and positioners Malfunction/ 3 029EK2.06 ATWS / 1 2.9 3.1 WITLDJDIDDDID Breakers, relays, and disconnects.
038EG2.4.6 Steam Gen. Tube Rupture/ 3 3.7 4.7 JJDDDTDTD DID V Knowledge symptom based EOP mitigation strategies.
054AK1.02 Loss of Main Feedwater / 4 3.6 4.2 VDJIDDA Effects of feedwater introduction on dry SIG 055EG2.4.47 Station Blackout / 6 4.2 4.2 JDDD DD Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
056AK1.01 Loss of Off-site Power I 6 3.7 4.2 JDDDIDDLED Principle of cooling by natural convection Page 1 of 2 9/30/2020 9:50 AM
ES-401, REV 11 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR RO SRO K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:
057AG2.4.50 Loss of Vital AC Inst. Bus/ 6
<<2 Ao DDJDIDIDJDDD JET Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
058AK1.01 Loss of DC Power / 6 2s 3n WI]II]LJDTDTITDTLD Battery charger equipment and instrumentation 062AK3.01 Loss of Nuclear Svc Water I 4 32 as pDJV[JIDDA]JD The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers 065AA2.06 Loss of Instrument Air/ 8 as <<2 DJDJDJDJDDWI When to trip reactor if instrument air pressure is de-creasing 077AA1.02 Generator Voltage and Electric Grid 3.8 3.7 DDVD Disturbances / 6 BE05EA1.1 Steam Line Rupture - Excessive Heat 4.2 4.2 DDDDVIIDDD Transfer I 4 BE10EA2.2 Reactor Trip - Stabilization - Recovery 3.5 4 DDT zI
/ 1 Turbine/ generator controls Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
Page 2 of 2 9/30/2020 9:50 AM
ES-401, REV 11 T1 G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
1R K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC:
028AG2.2.44 Pressurizer Level Malfunction / 2
- 2 4A DIDI 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 037 AA 1.10 Steam Generator Tube Leak/ 3 2s 3 DDJTTDTDVD eves makeup tank level indicator 067AK3.02 Plant Fire On-site I B 2.5 3.3 0 0 ~ 0 0 Steps called out in the site fire protection plan, FPS manual and fire zone manual BA01AK3.3 Plant Runback / T as 32 [DJWDJDTDIDJDLT Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
BA04AK2.2 Turbine Trip/ 4 33 3s DJ@DJDJDJJDD Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
BA06AK1.1 Shutdown Outside Control Room / 8 4
4 JDS@sD Components, capacity, and function of emergency systems.
BE08EK1.3 LOCA Cooldown - Depress. / 4 33 3s A[JDJIDDA DD Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Cooldown).
BE09EA 1.2 Natural Circ. / 4 a2 3s JDJJDTDJSA DIDI DJ LD Operating behavior characteristics of the facility.
BE13EA2.2 EOP Rules 3a lDDDDBa Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
Page 1 of 1 9/30/2020 9:50 AM
ES-401, REV 11 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 003A4.08 Reactor Coolant Pump 3.2 2.9 TIDD DD v RCP cooling water supplies 004K5.19 Chemical and Volume Control 3.5 3.9 DDVD[IDDD Concept of SOM 005K5.02 Residual Heat Removal 3.4 3.5 JJWDDDDDTLT Need for adequate subcooling 005K6.03 Residual Heat Removal 2.5 2.6 DJDJDDDDD RHR heat exchanger 006K2.02 Emergency Core Cooling 2.5 2.9 VDDDLTD Valve operators for accumulators 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 DD]TIDD v D Relationships between PZR level and changing levels of the PRT and bleed holdup tank 008A3.03 Component Cooling Water 3.0 3.1 DDUD All flow rate indications and the ability to evaluate the performance of this closed-cycle cooling system..
010A1 04 Pressurizer Pressure Control 3.6 3.8 DD[TDD Effects of temperature change during solid operation 010A4.01 Pressurizer Pressure Control 3.7 3.5 DODD D PZR spray valve 012A2.06 Reactor Protection 4.4 4.7 DDlDzDDD Failure of RPS signal to trip the reactor 013K6.01 Engineered Safety Features Actuation 2.7 3.1 DDDVI]ITDDT Sensors and detectors Page 1 of 3 9/30/2020 9:50 AM
ES-401, REV 11 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 022A1.02 Containment Cooling 3.6 3.8 DD0IT Dr Containment pressure 026A2.09 Containment Spray 2.5 2.9 DDDD Radiation hazard potential of BWST 039A3.02 Main and Reheat Steam 3.1 3.5 DD Isolation of the MRSS 059G2.1.7 Main Feedwater 4.4 4.7 DJDJDDUDE Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
061K1.02 Auxiliary/Emergency Feedwater 3.4 3.7 zJDIJDTDTD DID)D MFW System 061K3.02 Auxiliary/Emergency Feedwater 4.2 4.4 DTWIDDLED DD SIG 062K3.01 AC Electrical Distribution 3.5 3.9 DD]ITITITD DDT D Major system loads 062K4.01 AC Electrical Distribution 2.6 3.2 DJDzDDDass Bus lockouts 063K1.02 DC Electrical Distribution 2.7 3.2 zJJDDDDTLTD AC electrical system 064K4.01 Emergency Diesel Generator 3.8 4.1 DVD Trips while loading the ED/G (frequency, voltage, speed) 073K3.01 Process Radiation Monitoring 3.6 4.2 TV IITITITDDJDTD Radioactive effluent releases Page 2 of 3 9/30/2020 9:50 AM
ES-401, REV 11 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC:
076K1.08 Service Water 3.5 3.5
~ 0 0 0 0 0 0 0 0 0 0 RHR system 076K2.01 Service Water 27 27 DVDTIIDDLIDTDTT Service water 078G2.4.35 Instrument Air 3 << DIDDLED Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 078K4.01 Instrument Air z7 2s [DDT[IDTD7JD]DTD Manual/automatic transfers of control 103A1.01 Containment a7 <<T DJI]DDJV]DID DD Containment pressure, temperature and humidity 103A3.01 Containment 3s 42 DJIDDDDI DD Containment isolation Page 3 of 3 9/30/2020 9:50 AM
ES-401, REV 11 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 001G2.1.23 Control Rod Drive 4.3 4.4 DODD Ability to perform specific system and integrated plant procedures during all modes of plant operation.
002A1.07 Reactor Coolant 3.3 3.5 lDMIT Reactor differential temperature 011K5.10 Pressurizer Level Control 3.7 4.0 ITDDVDT[TDD D Indications of reactor vessel bubble 014A2.03 Rod Position Indication 3.6 4.1 JTDTDDD©DD Dropped rod 015K2.01 Nuclear Instrumentation 3.3 3.7 VDDTDTITDD IDT D NIS channels, components and interconnections 029A3.01 Containment Purge 3.8 4.0 Dz DD CPS isolation 033K1.02 Spent Fuel Pool Cooling 2.5 2.7 zlITDDDDDDD RHRS 035A4.05 Steam Generator 3.8 4.0 JDDI D
Level Control to enhance natural circulation 041K6.03 Steam Dump/Turbine Bypass Control 2.7 2.9 DDVDDDLTDD Controller and positioners, including ICS, SIG, CRDS 045K4.37 Main Turbine Generator 3.4 3.6 DVD DIET Automatic functions associated with turbine trip: reactor trip, station power switched to offsite source, air to extraction steam non-return valves removed Page 1 of 1 9/30/2020 9:50 AM
ES-401, REV 11 T3 PWR EXAMINATION OUTLINE FORM ES-401-3 KA NAME / SAFETY FUNCTION:
1R K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC:
G2.1.3 Conduct of operations G2.1.42 Conduct of operations G2.1.8 Conduct of operations G2.2.4 Equipment Control G2.2.43 Equipment Control G2.2.7 Equipment Control G2.3.7 Radiation Control G2.4.2 Emergency Procedures/Plans G2.4.26 Emergency Procedures/Plans G2.4.34 Emergency Procedures/Plans 37 as DJ[TITTED7DJ DJ 2s 34 [DIDDLED]DJ]DIDI 3.4 4.1 lac 36 as TITTED DTDTLTDT A a0 33 DULL]JDJ 2s as pJITTDTDTDTLTL] LJ as s DD v 4.5 4.6 0 0 0 0 0 0 0 0 0 0 ~
31 3s DIDDLED 4.2 4.1 DJDDDIDOD Knowledge of shift or short term relief turnover practices.
Knowledge of new and spent fuel movement procedures Ability to coordinate personnel activities outside the control room.
(multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
Knowledge of the process used to track inoperable alarms Knowledge of the process for conducting special or infrequent tests Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Page 1 of 1 9/30/2020 9:50 AM
ES-401, REV 11 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC:
009EA2.34 Small Break LOCA / 3 as <<z pJIDLTDJD]LILT Conditions for throttling or stopping HPI 025AG2.1.32 Loss of RHR System/ 4 3a 4 [JDTDJDIDDDIDI LT so Ability to explain and apply all system limits and precautions.
040AG2.4.21 Steam Line Rupture - Excessive Heat 4.0 4.6 DIDDLED v Knowledge of the parameters and logic used to assess the Transfer I 4 status of safety functions 054AG2.1.25 Loss of Main Feedwater I 4 3.9 4.2 JDDDU v Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
056AA2.33 Loss of Off-site Power/ 6 3.6 3.7 DDDVD DD ESF channels A and B breaker-trip alarms, indicators and bus voltage indicators BE04EA2.2 Inadequate Heat Transfer - Loss of 3.6 4.4 DDDJDVDDD Adherence to appropriate procedures and operation within Secondary Heat Sink/ 4 the limitations in the facility s license and amendments.
Page 1 of 1 9/30/2020 9: 50 AM
ES-401, REV 11 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR K 1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO TOPIC:
069AA2.02 Loss of CTMT Integrity I 5 3s 4A JJDDDIVIED Verification of automatic and manual means of restoring integrity BA02AG2.1.20 Loss of NNI-X / 7
<<s 4s IDE]LTDJIDJDJD V Ability to execute procedure steps.
BE03EA2.1 Inadequate Subcooling Margin/ 4 3
4 JTDDD@DID Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
BE14EG2.4.30 EOP Enclosures 27
<1 DDJJIJDIDLDJDEI Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
Page 1 of 1 9/30/2020 9:50 AM
ES-401, REV 11 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC:
003A2.02 ReactorcootantPump a.7 a.9 [JD))())L))v[IL]L Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 00442.12 cemicalana volume Control 4.1 4.1
[] ]L))L] L] [] ? L)) L]
CIAS, SIAS 01262.2.26 Reactor Protection 3.2 4.2 [][][][][))LI][][]
Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
013G2.2.44 Engineered Safety Features Actuation 4.2 4.4 D D D D D D D D D D ~
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 022A204 contammentcooling 29 3.2 [))))L]LIL]II]
Loss of service water Page 1 of 1 9/30/2020 9:50 AM
ES-401, REV 11 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:
IR RO SRO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
034G2.1.30 Fuel Handling Equipment
<<A <<o (JIITDDIDDLE Ability to locate and operate components, including local controls.
056A2.04 Condensate 26 2s pJJJDJMJD Loss of condensate pumps 068A2.04 Liquid Radwaste a3 33 JJIJDJI[TWDTDT ID Failure of automatic isolation Page 1 of 1 9/30/2020 9:50 AM
ES-401, REV 11 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-3 KA NAME/ SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 AT A2 A3 A4 G RO SRO TOPIC:
G2.1.15 Conduct of operations 27 34 DIDI]DTDJDTJ DJ Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
G2.1.40 Conduct of operations 28 3s pJTDIJITITDDJ Knowledge of refueling administrative requirements G2.2.17 Equipment Control 26 3s pDIJDJD]DJ]LTD DJ i Knowledge of the process for managing maintenance activities during power operations.
G2.2.20 Equipment Control 26 3a DIDILIDTDTDTLDT DJ Knowledge of the process for managing troubleshooting activities.
G2.3.15 Radiation Control 29 3n pIDJDDTDDJ Knowledge of radiation monitoring systems G2.4.11 Emergency Procedures/Plans
<o 42 DDJIIDILDD Knowledge of abnormal condition procedures.
G2.4.44 Emergency Procedures/Plans 24 A DIDI]DIDI Knowledge of emergency plan protective action recommendations.
Page 1 of 1 9/30/2020 9:50 AM
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1 / 2 APE037 AA1.10 Q(19) K/A APE001 AA1.01 rejected due to Bank Select switch not being a part of the ONS control rod drive system.
NRC agreed and issued replacement KA APE037 AA1.10.
2 / 1 SYS059 2.1.7 Q(42) K/A SYS059 2.2.3 rejected due to no unit differences between MFW at ONS. NRC agreed and issued KA 059G 2.1.7 as a replacement.
2 / 2 SYS045 K4.37 Q(65) K/A SYS072 K3.01 rejected. The Area Radiation Monitoring System at Oconee has no affect on containment ventilation isolation. NRC Chief agreed and supplied replacement K/A SYS045 K4.37 on 1/08/2020.
1 / 1 APE040 2.4.21 Q(78) K/A EPE029 2.4.20 rejected. Oconee does not have any EOP warnings, cautions, or notes associated with ATWS in the UNPP tab or Rule 1. NRC Chief agreed and supplied new K/A APE040 G2.4.21 on 1/08/2020.
2 / 1 SYS013 2.2.44 Q(90) K/A SYS073 2.2.3 rejected. Oconee does not have Process Radiation Monitoring System differences between units that a question could address. NRC Chief agreed and supplied new K/A SYS013 G2.2.44 on 1/08/2020.
EA SvBmurn ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Oconee Nuclear Station Date of Exam: 06/01/2020 Exam Level:
Initial Item Description a
b c#
- 1.
Questions and answers are technically accurate and applicable to the facility.
-g__
Ck
- 40)
- 2.
- a.
NRC K/As are referenced for all questions.
- b.
Facility learning objectives are referenced as available.
a 61, 111 C.
Correct answer explanation and distractor analysis provided (ES-401, D.2.g)
- 3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401 a C
/117 4
The sampling process was random and systematic. (If more than four RO or two SRO questions a C
- 1 were repeated from the last two NRC licensing exams, consult the NRR/NRO OL program office).
- 5.
Question duplication from the licensee screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate.
_ The audit exam was systematically and randomly developed, or a C>>
_ the audit exam was completed before the license exam was started, or
_ the examinations were developed independently, or the licensee certifies that there is no duplication, or 4J1
_other (explain).
Bank Modified New
-=
Ml4
- 6.
Bank use meets limits (no more than 75% from the bank, at least 10% new, and the rest new or modified);
enter the actual RO/SRO-only question distribution(s) at 38 I 10 21/ 8 16 / 7 1!L-C>>
right.
51%/40%
28%/32%
21%/28%
/fr!
- 7.
Between 38 and 45 questions of the questions on the Memory CIA
-=
"lA RO exam and at least 13 questions of the questions on the SRO-only portion of the exam are written at the 35 / 8 40 / 17 a Cl comprehension/analysis level (see ES-401, D.2.c); enter
/fJ1 the actual RO/SRO-only question distribution(s) at right.
47%/32%
53%/68%
- 8.
References/handouts provided do not give away answers or aid in the elimination of distractors.
at Co 1/J'Y/
- 9.
Question content conforms to specific KIA statements in the previously approv<>d <>xamination outline 6-- Ch ]
and is appropriate for the tier to which they are assigned; deviations are justified.
- 10.
Question psychometric quality and format meet the guidelines in Appendix B.
a @>>
1?(
- 11.
The exam contains the required number of one-point, multiple-choice items; the total is correct and a C>>
/JI(
agrees with the value on the cover sheet.
Printed Name/Signature Date
- a.
Author i ta /3l..
3-1C- &Zo
- b.
Facility Reviewer () a a8tt'roe.. #
n, C.
NRC Chief Examiner(#)
- d.
NRC Regional Supervisor
'j\\ ~-a.~ ~ 1/4_~
Digitally signed by Gerald J. McCoy
\\...)
Date: 2020.09.28 13:46:38 -04'00' Note:
The facility reviewer's initials or signature are not applicable for NRC-developed examinations.
Independent NRC reviewer initials items in Column "c"; chief examiner concurrence is required, DRAFT Exmn
- Fu W1<17TEIII Aff !foJI/JL -
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Oconee Nuclear Station Date of Examination: 6/04/2020 Initials Item Task Descriplion a
b" e
1,
A A I@
w
- b. Assess whether the outline was systematically and randomly prepared in accordance with A
A <</]
R I
Section 0.1 of ES-401 or ES-401N and whether all KIA categories are appropriately sampled.
T Assess whether the outline overemphasizes any systems, evolutions, or generic topics.
{EL /IA h T
C.
E
- d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.
1L k h N
- 2.
- a.
Using Form ES-301-5, verify that the proposed scenario sets cover the required number of ti-normal evolutions, instrument and component failures, technical specifications, and major k h s
I M
- b. Assess whether there are enough scenario sets (and spares) to test the projected number and u
mix of applicants in accordance with the expected crew composition and rotation schedule 6 L
without compromising exam integrity, and ensure that each applicant can be tested using at Ck A
least one new or significantly modified scenario, that no scenarios are duplicated from the t#
T applicants' audit test(s), and that scenarios will not be repeated on subsequent days.
0 C. To the extent possible, assess whether the outline(s) confonns with the qualitative and R
quantitative criteria specified on Form ES-301-4 and described in Appendix D and in d Ck Section 0.5, "Specific Instructions for the 'Simulator Operating Test,'" of ES-301 (including Wt overlap).
3.,
- a. Verify that the systems walk through outline meets the criteria specified on Form ES-301-2:
(1) The outline(s) contains the required number of control room and in-plant tasks distributed w
among the safety functions as specified on the form.
ff-A (2) Task repetition from the last two NRC examinations is within the limits specified on the form.
CJ L
(3) No tasks are duplicated from the applicant's audit test(s).
K (4) The number of new or modified tasks meets or exceeds the minimums specified on the fonn.
T (5) The number of alternate-path, low-power, emergency, and radiologically controlled area lrHf H
tasks meets the criteria on the form.
R 0
- b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:
u (1) The tasks are distributed among the topics as specified on the form.
¢ ct.
G (2) At least one task is new or significantly modified.
- 1 H
(3) No more than one task is repeated from the last two NRC licensing examinations.
C. Determine whether there are enough different outlines to test the projected number and mix of 6. u V) applicants and ensure that no items are duplicated on subsequent days.
4,
- a. Assess whether plant-specific priorities (including probabilistic risk assessment and individual A Ck hr plant examination insights) are covered In the appropriate exam sections.
G A Ck h, E
- b. Assess whether the 10 CFR 55.41, 55.43, and 55.45 sampling is appropriate.
N C. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5.
111-C [hr E
R
- d. Check for duplication and overlap among exam sections and the last two NRC exams.
st \\, 4h A
a
-11//
L
- e. Check the entire exam for balance of coverage.
/!I,..
- f.
Assess whether the exam fits the appropriate job level (RO or SRO).
A C>> f/1
--rqjr111;ameJSignature Date
- a.
Author Sam Lark /{
5/21/20
- b.
Facility Reviewer (")
Christopher Harts 5ck //7L. X.a.X, I,
A 5/21/20 C.
NRC Chief Examiner(#)
/le ung EE //lf; K%/
4L,LA es7lso
- d.
NFRC Supervisor "Not applicable for NRC-prepared examination outlines.
- The independent NRC reviewer initials items in column "c"; the chief examiner's concurrence is required.
a The written outline was provided by the NRC.
-ftNfll WR1rtEIII HPPRoL SIGN
-- (1Nfll /[RITE
[xA!YJ 1/tf/<ov/-ll -
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Oconee Nuclear Station Date of exam: 06/04/2020 Exam Level:
RO [i]
SRO [iJ Initial Item Description a
b c
- 1.
Questions and answers are technically accurate and applicable to the facility.
a l!J,..
hM
- 2.
- a.
NRC KIAs are referenced for all questions.
- b.
Facility leamlng objectives are referenced as available.
a t/4 hM
- c.
Correct answer explanation and dislractor analysis provided (ES-401, D.2 g)
- 3.
SRO questions are appropriate in accordance with Section 0.2.d of ES-401
-z1_
Cu n 4
The sampling process was random and systemalic. {If more than four RO or two SRO questions d k
,#(
were repeated from the last two NRC licensing exams, consult the NRRINRO OL program office).
- 5.
Question duplication from lhe licensee screening/audit exam was controled as Indicated below (check the Item lhat applies) and appears appropriate.
_ The audit exam was systematically and randomly developed, or 6 Ck
_the audit exam was completed before the license exam was started, or
_ the examinations were developed Independently, or a--'the licensee certifies that there Is no duplication, or I#/
_ other (explain).
- 6.
Bank use meets limits (no more than 75% fror the Bank Modified New ~ ~ ~
bank, at least 10% new, and the rest new or modified);
enter the actual RO/SRO-only question distributlon(s) at 35/ 8 24 /9 16 / 8 A> Ck>>
right.
47%/32%
32%/36%
21%/32%
\\ml
- 7.
Between 38 and 45 questions of the questions on the Memory CIA
-~ ~./
RO exam and at least 13 questions of the questions on the SRO-only portion of the exam are written at the 35 /9 40 / 16 6 comprehension/analysis level (see ES-401, D.2.c); enter Ck
- I the actual RO/SRO-only question disltlbutlon(s) at right.
47%/36%
53%/64%
- 8.
References/handouts provided do not give away answers or aid In the elimination of distradors.
5
{!/4.
\\Z
- 9.
Question content confonns to specific KIA statements In the previously approved examination ouUine
't5L k h and is appropriate for the tier to which they are assigned; deviations are Justified.
ff[__
s
- 10.
Question psychometric quality and format meet the guidelines in Appendix B.
Ck hf
- 11.
The exam contains the required number of one-point, multiple-choice items; the total Is correct and 1X-CA
-fl(
agrees with the value on the cover sheet.
Printed Name/Signature Date
- a.
Author Sam Lark/ ~
5/21/20
- b.
Facility Reviewer ()
+gr=t+/-la r, C.
NRC Chief Examiner(#)
!!l.Jc.M_EL. li'/6£.K.
tJS-lz9 ;?c,~o
- d.
NRC Regional supervisor Note; The facility reviewer's initials or signature are not applicable for NRC-developed examinations.
independent NRC reviewer initials items in Column "c"; chief examiner concurrence Is required.
Fiuc WRtTtcN fX/JIYI SIGN
OCONEE Nuclear Station June 2020 ILO Exam 1 1 ES-401 Written Examination Review Worksheet 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
- /
units Back-ward Q=
K/A SRO Only All 1
H 2
X X
Y N
B E
K/A 008K3.05
- 1. Q=K/A, Q=RO level.
- 2. Recommend increased parallelism with A(2)/B(2) distractors and the C(2)/D(2) distractors. Unsure over plausibility of A(2) distractor when compared to B(2) distractorat 5% power, why would you be able/directed to slow down the negative reactivity rate, the Rx is still very much at power? Also the definitive statement of the C(2)/D(2) distractors makes it seem too strong:
can remove the heat.
Recommend the following for A(2)/B(2) distractors: maximum Boron addition continues until power level is low enough to throttle HPI Recommend the following for C(2)/D(2) distractors: sufficient core cooling exists until power level is low enough that HPI forced cooling would become effective Q as submitted evaluated as E due to one non-plausible distractor (A(2) as compared to the other choices).
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 2
H 2
Y N
N S
K/A 011EA1.02
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 2 2 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
- /
units Back-ward Q=
K/A SRO Only 3
H 2
X Y
N M
E K/A 015AK2.07
- 1. Q=K/A, Q=RO level.
- 2. Cue in the Q statementwe are asking actions which might serve to eliminate distractors A and B. Recommend asking describes the next required action(s) in accordance with Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 4
H 3
Y N
B S
K/A 022AA2.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
5 F
3 Y
N B
S K/A 026AK3.02
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
6 H
2 Y
N B
S K/A 027AK2.03
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 3 3 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
- /
units Back-ward Q=
K/A SRO Only 7
F 2
X X
Y N
B E
K/A 029EK2.06
- 1. Q=K/A, Q=RO level.
- 2. Second part Q statement and distractors are subset errors: it is factually correct that DSS will de-energize the rod groups at 2500 psig. Giving benefit of the doubt here due to ease of correction. Do we need to define the acronym DSS for the applicants?
Recommend the following for 2nd part Q statement: DSS is interlocked to automatically de-energize Control Rod Groups 1-7 at a high RCS Pressure setpoint of ___(2)___ psig.
Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 8
H 2
X Y
N M
E K/A 038EG2.4.6
- 1. Q=K/A, Q=RO level.
- 2. Fourth bullet down: recommend stating only 1A HPI pump operating for clarity
- 3. First part Q using will construct in somewhat imprecise manner.
Recommend The procedure ___(1)___ [will/will NOT] direct operators to use 1RIA-59 and 1RIA-60 to determine the SG tube leak rate.
Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 4 4 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
- /
units Back-ward Q=
K/A SRO Only 9
H 3
X X
Y N
B U
K/A 054AK1.02
- 1. Q=K/A, Q=RO level.
- 2. What technical reference defines dry SG and whether or not heat transfer is occurring (needed to use the table in Rule 7)?
- 3. 50 gpm max initial flowrate is not plausible because that value does not appear anywhere in Rule 7. RCS overcooling event is not plausible because you would not be overcooling the RCS at an initial 101 gpm flowrate coming out of a LOHT situation, where RCS Temperatures are likely high in any event.
Q as submitted evaluated as U due to multiple non-plausible distractors.
Potential fix with similar material:
Given info the same In accordance with Rule 7 (Steam Generator Feed Control), the MAXIMUM initial feed rate for the above conditions is ___(1)___, in order to prevent
___(2)___.
A. (1) 100 gpm to EACH SG (2) water hammer damage to voided feedwater lines B. (1) 100 gpm to EACH SG (2) damage to SG tubes C. (1) 1000 gpm per header (2) an RCS overcooling event D. (1) 1000 gpm per header (2) damage to TDEFWP (runout)
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 5 5 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
- /
units Back-ward Q=
K/A SRO Only 10 H
2 X
X Y
N N
E K/A 055EG2.4.47
- 1. Q=K/A, Q=RO level.
- 2. In order to ensure technical accuracy, we need to add a condition that the SBO occurred in MODE 1 or 2 (from 100% power recommended), and that the SFF has been activated with SSF RC Makeup Required.
- 3. Distractor D is non plausible. There are other places in the exam where TDEFWP flow greater than 600 gpm is allowed or used for distractor purposes.
Recommend another parameter that is in Rule 7 that is incorrect.
Q as submitted evaluated as E due to one non plausible distractor.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 11 H
2 X
Y N
M E
K/A 056AK1.01
- 1. Q=K/A, Q=RO level.
- 2. Stating that the given temperature indications do or do not prove natural circ has been established seems a little strong to medont you also need to know that T-colds are at Tsat for the SG Pressure? Recommend adding SG Pressure indications/pictures that are Psat for ~555 degrees F.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 12 F
2 Y
N M
S K/A 057AG2.4.50
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 6 6 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
- /
units Back-ward Q=
K/A SRO Only 13 H
3 Y
N B
S K/A 058AK1.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
14 F
2 Y
N B
S K/A 062AK3.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
15 F
2 Y
N B
S K/A 065AA2.06
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
16 H
1 X
Y N
B U
K/A 077AA1.02
- 1. Q=K/A, Q=RO level.
- 2. It is common knowledge/LOD=1 that main steam flow relates to turbine power/MW, and MVARs are controlled with generator voltage regulation.
- 3. Partial: second part Q is confusing. If a underfrequency condition exists and operators know they are approaching an automatic trip setpoint, is it wrong to say there is a manual trip required? Maybe better for the 2nd part Q to ask if the MTG will or will not automatically trip.
Q as submitted U due to LOD=1 (first part Q), basic generic knowledge only required to elicit the appropriate response.
Facility licensee essentially submitted new Q. Facility discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 17 F
3 Y
N B
S K/A BW05EA1.1
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 7 7 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
- /
units Back-ward Q=
K/A SRO Only 18 F
2 Y
N B
S K/A BW10EA2.2
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
19 H
2 X
Y N
N E
K/A 037AA1.10
- 1. Q=K/A, Q=RO level.
- 2. Worried that someone may read first part Q of whether or not 1HP-26 can be opened as a system interlock Q; something like what we just asked in Q17.
Recommend focusing on procedure, also putting procedure title before question blank as follows: The procedural guidance of AD-OP-ONS-0002 ___(1)___
[does/does NOT] allow operators to open 1HP-26 for the given conditions at Time=0800.
Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 8 8 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
- /
units Back-ward Q=
K/A SRO Only 20 H
2 X
Y N
M E
K/A 028AG2.2.44
- 1. Q=K/A, Q=RO level.
- 2. Concerned that the phrase without a procedure in hand may be mis-interpreted to mean that the RO needs to be physically holding a procedure, which does not seem to meet the intent of the AD-OP-ALL case (no procedure step required). Recommend slightly different situation that I think more closely meets the intent of the AD-OP-ALL provision:
Under Current conditions:
-Pzr level Channel 3 fails to 100 inches
-The CRS has not yet entered any abnormal procedure
-The RO has not yet referenced any alarm response procedure
-The RO requests CRS concurrence to select a valid Pzr level indication (1)
(2) Based on the current conditions, AD-OP-ALL-1000 [does/does NOT]
allow the RO to select a valid Pzr level indication with ONLY CRS verbal concurrence.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 21 F
2 Y
N B
S K/A 067AK3.02
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 9 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
- /
units Back-ward Q=
K/A SRO Only 22 F
2 X
Y N
N E
K/A BW01AK3.3
- 1. Q=K/A, Q=RO level.
- 2. Recommend slight tweak to 2nd part Q statement for more precise parallelism with lesson plan reference: (2) is because its high discharge pressure trip setpoint is set ___(2)___ than that.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 23 H
2 X
Y N
M E
K/A BW04AK2.2
- 1. Q=K/A, Q=RO level.
- 2. Modified or Bank? Submitted Q has different given conditions and could be argued different answer set than the Bank question. Why were given conditions changed from ILT47 Q25? Are they needed?
- 2. Concerned with the plausibility of SGs being fed from MFDW post-turbine trip. What conditions would need to exist for MFW pumps to continue to operate for this event? Lets discuss, maybe ok Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 10 10 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
- /
units Back-ward Q=
K/A SRO Only 24 F
2 X
X Y
N N
E K/A BW06AK1.1
- 1. Q=K/A, Q=RO level.
- 2. For parallelism, lets write out automatically start for first part Q.
- 3. Second part Q we have to enter with fear and trepidation anything asking vacuum or vacuum pressure trends lowering or raising in a technically correct and clear fashion. Recommend the following to fix this concern: (2)
The Unit 3 TBVs ___(2)___ automatically close on a loss of condenser vacuum condition Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 25 H
2 X
Y N
B E
K/A BW08EK1.3
- 1. Q=K/A, Q=RO level.
- 2. Will/Will NOT construct minorly squishy in the 2nd part Q statement; recommend In accordance with LOCA CD tab, conditions are met such that operators ___(2)___ [will/will NOT] be directed to manually bypass LPI.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 11 11 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
- /
units Back-ward Q=
K/A SRO Only 26 F
3 X
X Y
N N
E K/A BW09EA1.2
- 1. Q=K/A, Q=RO level.
- 2. I think the Q works if we can get even more parallelism with the procedures language. Based on IAAT step 1, we need to state what Tcold is at Time=1300 so the applicant is given enough information to elicit the correct answer.
Ensure the units are the same as what the procedure has for the first part Q.
Note that the Given information is listed in timeline form, but the timeline is not referenced in the Q statements. Recommended changes to Q statements as follows:
(1) At Time=1300, the EOP FCD tab will direct the crew to control the cooldown rate within the limit of ___(1)___ [ 50 °F / 1/2 hr OR 25 °F / 1/2 hr ].
(2) A NOTE in the EOP FCD tab states that RCS Pressure will NOT be reduced until the RCS is cooled to establish ___(2)___ [ 150 °F SCM OR 200 °F SCM].
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 12 12 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
- /
units Back-ward Q=
K/A SRO Only 27 H
2 X
X X
Y N
B E
BW13EA2.2
- 1. Q=K/A, Q=RO level.
- 2. There is cueing in the second part Q statement that affects the plausibility of the distractor. If the applicant understands that the LOHT tab has already shifted RCPs to one RCP/loop, then there is a big cue in that Rule 4 direct[s]
securing which is the correct answer. Benefit of the doubt given due to ease of correction:
(2) IF Rule 4 is initiated, it [will/will NOT] direct the crew to secure all but one RCP.
- 3. IF you accept the above change, I would also recommend stating which RCPs are running as a bulleted condition under Time=0430.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 28 F
2 X
Y N
N E
003A4.08
- 1. Q=K/A, Q=RO level.
- 2. Plausibility of waiting 3 hrs to stop cooling an RCP motor with seal failures vs. immediately stopping cooling the RCP motor is weak; also I could not find a case in AP/016 where the LPSW valves were closed immediately after RCP S/D for any condition. For best plausibility we need to use a parameter in the procedure as the alternate value for C(1)/D(1). Maybe 30 minutes per the NOTE at the end of the procedure discussing procedure changes?
Q evaluated as E due to distractor plausibility.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 13 13 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
- /
units Back-ward Q=
K/A SRO Only 29 H
2 X
N N
N U
004K5.19
- 1. Q does not meet K/A. Proposed K/A requires applicants to demonstrate knowledge of the operational implications of the following concepts SDM [as related to the CVCS system]. However, the submitted Q, although it had some bearing on boration to restore SDM, is not testing either the concept of SDM or operational implications of the concept beyond the time limit established by TS to begin a boration. In order to answer the Q, an applicant needs to correctly use a provided reference graph, and then apply knowledge of less than one hour or less TS action statements. The concept of SDM, or an applicants understanding of how boration affects SDM, or adverse consequences of not having adequate SDM on plant operation, is not specifically being tested with this Q.
- 2. Cues: if an applicant were to use the incorrect reference graph, the given conditions result in the plant being in a region of the graph that is not mentioned in the distractors.
Q as submitted evaluated as U due to not meeting K/A. K/A change may be needed here to get an operationally valid Q at the site-specific exam level.
Facility licensee submitted an essentially new Q as a substitute to the original Q29, no K/A change needed. New Q evaluated as S at this time following conference phonecall with facility licensee. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 05/14/2020 30 H
2 X
Y N
N E
005K5.02
- 1. Q=K/A, Q=RO level.
- 2. First part Q statement, please change will construct to is/is NOT required to be aligned Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 14 14 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
- /
units Back-ward Q=
K/A SRO Only 31 H
2 Y
N M
S 005K6.03
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
32 F
3 Y
N M
S 006K2.02
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
33 H
2 Y
N B
S 007A4.09
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 15 15 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
- /
units Back-ward Q=
K/A SRO Only 34 H
3 X
Y N
B E
008A3.03
- 1. Q=K/A, Q=RO level.
- 2. For complete technical accuracy, think we need to include the trend(s) that precede the given conditions.
- 3. Distractor D: could we be more specific and state which bus de-energizes, and that it says de-energized or locked-out on fault?
Recommend the following per the above comments:
A. CRD Outlet HDR Flow lowers to 136 gpm B. Component Cooling Total Flow lowers to 568 gpm C. Component Cooling Pump (Discharge?) Pressure lowers to 95 psig D. Bus ABC-123 (Nomenclature for ABC-123) becomes de-energized and locks out on overcurrent fault. [or equivalent description using Oconee terminology].
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 16 16 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
- /
units Back-ward Q=
K/A SRO Only 35 H
2 X
Y N
N U
K/A 010A1.04
- 1. Q=K/A, Q=RO level.
- 2. Distractor value of 180 psig raise for 1 degree T raise in solid plant operations non-plausible. 180 is a specific number that is not linked to operator thumb-rules. Claiming 180 as adverse Pzr level setpoint would not be a credible mental link to the amount of pressure rise due to 1 degree T rise. Also most thumbrules are round numbers or multiples of 25/50. Recommend another distractor here that is used at Oconee for operator aids and linked to RCS pressures (50? 125? 150?).
- 3. Distractor of Pzr heaters energized non plausible for solid plant operations.
The fact that solid plant operations is the plant condition is evident from the first part Q; with a relatively large number for SCM provided in the stem, Pzr heaters will have no initial effect on RCS pressure at all. It is common knowledge that switching Pzr heaters on/off is a relatively long time effect on pressure. Also the Enclosure for Recovery from HPI Forced Cooling procedure does not mention Pzr heater operation.
For second part Q, prefer to ask something like the following:
(2) The crew will be directed to initially control HPI by ___(2)___. [maintaining HPI flow approximately constant to maintain stable RCS temperature / lowering HPI flow to provide only for RCS leakage and seal injection]
Q as submitted evaluated as U due to multiple non-plausible distractors.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 17 17 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
- /
units Back-ward Q=
K/A SRO Only 36 H
2 X
X Y
N N
E K/A 010A4.01
- 1. Q=K/A, Q=RO level
- 2. Based on the relationships between the given distractors and the Q statement, believe we need to give all RCS pressure instrument indications.
We state that RCS pressure peaked at 2210 psig, but what if there is instrument error? Also, we are cueing against the correct answer, in that if 2RC-1 was opened by maximum value instead of median select, only one pressure value would be needed. We could use a picture here or just list the values of the particular instruments.
- 3. Is there a technical reason for 2.MAX instead of MAX or just a typo?
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 37 F
2 Y
N B
S K/A 012A2.06
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
NOTE: although submitted Q is S based on psychometric analysis, this is the second Q on the exam to deal specifically with local operation of CRD breakers for ATWS. We also have an ATWS scenario on the operating test that would involve Rule 1. We are at the maximum limit for this topic on the exam.
OCONEE Nuclear Station June 2020 ILO Exam 18 18 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
- /
units Back-ward Q=
K/A SRO Only 38 F
2 X
X X
Y N
B E
K/A 013K6.01
- 1. Q=K/A, Q=RO level.
- 2. Subset errors on the first part Q distractors 1-4. Need to state 1 - 4 ONLY or equivalent.
- 3. Further partial correct answer concern: logic for what? Also believe we need to state all channels for technical accuracy. Please review the following re-statement for technical correctness:
ES Channels ___(1)___ [1-4 ONLY/1-6] are all now in a ___(2)___ [1 out of 2 /
2 out of 2] logic for automatic actuation.
Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 39 H
3 X
X Y
N M
E K/A 022A1.02
- 1. Q=K/A, Q=RO level.
- 2. Unsure why we are asking conditions at Time=0930 when we do not give specific conditions at that time. Believe it would be better to ask first part Q statement as With no operator action, RB pressure after Time=0830 would be
___(1)___ RB pressure at Time=08000.
- 3. Technically a subset issue again with the 2.45 distractor. Recommend specifically asking the LCO language and including the + for exact parallelism with the specification:
(2) LCO 3.6.4 (Containment Pressure) states that Containment pressure shall be ___(2)___. [ +2.45 psig / +1.2 psig ]
Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 19 19 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
- /
units Back-ward Q=
K/A SRO Only 40 F
2 X
Y N
M E
K/A 026A2.09
- 1. Q=K/A, Q=RO level.
- 2. Concerned that lesson plan material states that a purpose of caustic addition is to minimize H2 production via Zirc-Water chemical reaction. Is the second part distractor technically incorrect? If so we will need a new distractor. Lets discuss Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 41 F
3 X
Y N
B E
K/A 039A3.02
- 1. Q=K/A, Q=RO level.
- 2. Please add some kind of with no operator actions statement for extra clarity.
Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 20 20 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
- /
units Back-ward Q=
K/A SRO Only 42 H
3 X
Y N
B E
K/A 059G2.1.7
- 1. Q=K/A, Q=RO level.
- 2. Recommend With no operator actions, at Time = 04:01:25 Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 43 H
2 Y
N N
E K/A 061K1.02
- 1. Q=K/A, Q=RO level.
OVERLAP: We already have two Qs on Rule 7 (Q9 and Q10). Three questions on any one topic such as Rule 7 is too much overlap. We will need to re-attack the second part Q with a different topic.
Q evaluated as E at this time.
Facility licensee proposed new 2nd part Q with essentially the same Q stem as before, and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 21 21 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
- /
units Back-ward Q=
K/A SRO Only 44 H
2 X
X X
Y N
B E
K/A 061K3.02
- 1. Q=K/A, Q=RO level.
- 2. Timing concern: what timeframe are we asking the applicant to determine plant response? Immediately after power is lost? Ten minutes later? We have to be exactly precise with these types of what is the trend Qs.
- 3. Units: please specify which S/G level range we intend for distractors A and B.
- 4. Technical accuracy: recently there have been a spate of Qs asking parameter trends that have been appealed and overturned due to the simulators not behaving the way the question authors and examiner reviewers thought they would. Please run this event in the simulator and provide graphical trends of S/G level(s) to ensure we have a technically correct answer.
Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Waiting for the facility licensee to provide simulator data for Q44 as indicated above.
MKM 04/30/2020 Facility licensee provided simulator data run with the conditions in the Q stem to verify technical accuracy of correct answer and distractors. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 05/14/2020 45 F
2 Y
N M
S K/A 062K3.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
46 H
3 Y
N B
S K/A 062K4.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 22 22 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
- /
units Back-ward Q=
K/A SRO Only 47 F
2 X
Y N
M E
K/A 063K1.02
- 1. Q=K/A, Q=RO level.
- 2. Distractor B is not plausible due to overlap with Q12. The correct answer to Q12 is the Manual Bypass Switch, it is not credible that the correct answer to two different questions on the NRC exam would be the same switch.
Q evaluated as E due to one non-plausible distractor.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. New distractor B provided.
Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 48 H
2 X
X Y
N N
E K/A 064K4.01
- 1. Q=K/A, Q=RO level.
- 2. Why is KHU 1 running at Time=0800? For example, was it started in emergency or normal mode for maintenance run or something like thatwe should specify what mode it was operating in.
- 3. We need to ensure it is clear to the applicants what time reference we intend for each of the 2-part Q statements.
- 4. Believe KHU shutdown on a signal RESET is very low probability/plausibility.
What systems at Oconee automatically shutdown when an actuation signal is reset? Lets discuss if none, well likely need to approach second part Q statement from a different angle.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Slight adjustments made to the Q statements. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 23 23 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
- /
units Back-ward Q=
K/A SRO Only 49 H
2 Y
N B
S K/A 073K3.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
50 F
2 X
X Y
N N
E K/A 076K1.08
- 1. Q=K/A, Q=RO level.
- 2. Requiring an applicant to differentiate between 5900 and 6000 gpm as setpoint for high flow LPSW runback is borderline minutia as both values relate to LPSW flow limits. Would be overturned on appeal. Consider: 100 gpm difference on a 6000 gpm setpoint is only 1.67% scale. Could applicants determine that small of a difference on installed plant instrumentation?
Recommend alternate approach below based on K/A language.
- 3. Train the Chief Examiner: Does it matter how LPI/LPSW were actuated?
(are there different setpoints, for example, between normal run vs. emergency start?)
Recommend the following for first part Q statement:
(1) The automatic runback of LPSW flow to the LPI system is based upon an interlock using ___(1)___. [LPSW flow to a single LPI cooler / total LPSW flow to both LPI coolers]
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 51 F
2 Y
N M
S K/A 076K2.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
52 H
3 Y
N M
S K/A 078G2.4.35
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 24 24 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
- /
units Back-ward Q=
K/A SRO Only 53 H
2 X
Y N
B E
K/A 078K4.01
- 1. Q=K/A, Q=RO level.
- 2. What is the status of the Auxiliary IA Compressors/control systems? Do we also need to specify their switch positions?
Q appears E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 54 H
2 Y
N M
S K/A 103A1.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
55 H
3 Y
N B
S K/A 103A3.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
56 F
2 X
Y N
B E
K/A 001G2.1.23
- 1. Q=K/A, Q=RO level.
- 2. Distractors B(2)/D(2) using indeterminate will construct for future-tense human action. Replace with will be required to or similar.
Q appears E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 25 25 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
- /
units Back-ward Q=
K/A SRO Only 57 H
3 X
Y N
M E
K/A 002A1.07
- 1. Q=K/A, Q=RO level.
- 2. Second part Q statement using indeterminate will construct. Replace with is required to or similar.
Q appears E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 58 H
2 X
Y N
M E
K/A 011K5.10
- 1. Q=K/A, Q=RO level.
- 2. Tweak to second part Q statement: change RC-160 are opened to are required to be opened Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 26 26 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
- /
units Back-ward Q=
K/A SRO Only 59 H
3 X
Y N
M E
K/A 014A2.03
- 1. Q=K/A, Q=RO level.
- 2. Think we need to add during the runback to the second part Q statement.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 60 F
2 Y
N M
S K/A 015K2.01
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
61 F
2 X
Y N
B E
K/A 029A3.01
- 1. Q=K/A, Q=RO level.
- 2. The use of the terminology will ALL automatically close in the Q statement implies that the valves were all OPEN (i.e. change state), although this condition is not specified in the Q statement. Recommend slight modification to Q statement that I think meets the intent: will ALL receive automatic close signals as a result of _____.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 27 27 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
- /
units Back-ward Q=
K/A SRO Only 62 H
3 X
Y N
B E
K/A 033K1.02
- 1. Q=K/A, Q=RO level.
- 2. Why not exact parallelism with second part Q statement? (2) discharge will be to the ___(2)___.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 63 F
2 X
Y N
M E
K/A 035A4.05
- 1. Q=K/A, Q=RO level.
- 2. For additional clarity, recommend adding With no operator actions, SG levels will be to Q statement.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 64 H
2 Y
N B
S K/A 041K6.03
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
65 H
3 Y
N M
S K/A 045K4.37
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 28 28 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
- /
units Back-ward Q=
K/A SRO Only 66 F
1 X
Y N
N U
K/A G2.1.3 (Tier 3)
- 1. Q=K/A, Q=RO level.
- 2. 60 minutes is doubleplus too long a time for someone relieved on a short-term basis who needs constant radio comms to respond back to the Control Room.
- 3. LOD=1 that someone standing watch for two hours would need to log in.
Q as submitted U due to multiple non-plausible distractors/LOD=1.
Potential fix w/similar info:
Concerning short term watch relief, procedure AD-OP-ALL-1000 (Conduct of Operations) states the following requirements:
(1) During all cases the operator requiring short term relief shall have adequate communication with the Control Room and be capable of responding to the Control Room within ___(1)___. [10 minutes / 20 minutes]
(2) Whenever a watch station is relieved for greater than ___(2)___ [30 minutes
/ one hour], this information shall be entered in a Narrative Log Program, a formal turnover and shift turnover sheet will be completed, including the logs signed over.
Facility licensee proposed a new Q (not the above suggestion), made additional changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 05/14/2020
OCONEE Nuclear Station June 2020 ILO Exam 29 29 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
- /
units Back-ward Q=
K/A SRO Only 67 F
2 X
X Y
N B
E K/A G 2.1.42 (Tier 3)
- 1. Q=K/A, Q=RO level.
- 2. Distractor D is not plausible. How does continuous RP coverage, independent of also having a portal survey monitor, compensate for a loss of radiation monitor? Maybe better: (unsure?) NOT continue until SFP boron concentration re-sampled and SFP level re-verified and both parameters are within requirements
- 3. Recommend slight tweak to correct answer to ensure technical accuracy per the OP/007: NOT continue until a replacement portable area radiation monitor with alarm capability is in use Q as submitted evaluated as E due to one non-plausible distractor.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 68 F
2 Y
N B
E K/A G2.1.8 (Tier 3)
- 1. Q=K/A but weak. Prefer the way the initial Bank Q (ILT 43 Q66) phrases the second part Q statement and distractors, better K/A match. Q=RO level.
- 2. Recommend re-writing second part Q statement as written in ILT 43 Q66.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 30 30 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
- /
units Back-ward Q=
K/A SRO Only 69 F
3 X
N N
B U
K/A G2.2.4 (Tier 3)
- 1. Q does not meet K/A, because an applicant could correctly answer the Q with only knowledge of Unit 1 configuration or procedural info; therefore the variations between Unit 1 and any other Unit is not directly being tested. (Chief Examiner agrees that unit differences are implied in the plausibility statements for the distractors). Is it possible to use the same info from the plausibility analysis in a way that meets the K/A statement? See recommendation below.
Q evaluated as U due to not meeting K/A statement.
When establishing the Alternate Post-LOCA Boron Dilution flow alignment, the appropriate LOCA CD tab would direct opening valve LP-105 on the appropriate unit(s) ___(1)___ [for Unit 1 ONLY / for Units 2 and 3 ONLY],
and would direct opening valve LP-19 on the appropriate unit(s) ___(2)___.[for Unit 1 ONLY / for Units 2 and 3 ONLY]
-OCONEE if using this recommendation ensure technical accuracy.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 70 F
2 Y
N B
S K/A G2.2.43 (Tier 3)
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 31 31 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
- /
units Back-ward Q=
K/A SRO Only 71 F
2 X
Y Y
N U
K/A G 2.2.7 (Tier 3)
- 1. Q=K/A. First part Q is on the SRO only level, identification of IPTE Manager roles and responsibilities/authority is more of an SRO level function and is the responsibility of the Plant Manager in any case.
- 2. Partial correct: It could be argued that a senior operations manager who was also qualified as Shift Manager could be assigned as IPTE Manager and therefore A Shift Manager potentially correct based on whether or not that was the case.
Q as submitted evaluated as U due to license-level mismatch on first part Q statement.
Are there other requirements specific to RO job function related to IPTEs at Oconee? For example, are IPTEs required to be entered/exited in the unit narrative log, is control room access restricted during IPTEs, etc. are examples of RO level knowledge items in the CEs opinion.
Based on the comments above, facility licensee re-submitted a completely new Q with same K/A. Facility licensee made additional changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall.
Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 05/14/2020 72 F
2 X
Y N
M E
K/A G2.3.7 (Tier 3)
- 1. Q=K/A. Q=RO level.
- 2. Distractors C(2), D(2) non plausible. In first part Q we have just determined what is supposed to be the correct designation of the area per the appropriate RWP, why would it then be posted and signed with flashing lights that signify the area is a higher level? Benefit of the doubt given here, recommend just asking whether or not the flashing blue light indicates a radiography barrier.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 32 32 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
- /
units Back-ward Q=
K/A SRO Only 73 F
2 X
Y N
B E
K/A G2.4.2 (Tier 3)
- 1. Q=K/A, Q=RO level.
- 2. Distractor C is non-plausible due to simulator scenario involving multiple dropped rods Rx trip. Recommend a different parameter from the AD-OP-ONS-002.
Q as submitted evaluated as E due to one non-plausible distractor.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 74 F
2 Y
N B
S K/A G2.4.26 (Tier 3)
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
75 H
2 Y
N B
S K/A G 2.4.34 (Tier 3)
- 1. Q=K/A, Q=RO level.
Q appears S at this time.
- SRO-ONLY EXAM QUESTIONS BELOW***
OCONEE Nuclear Station June 2020 ILO Exam 33 33 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
- /
units Back-ward Q=
K/A SRO Only 76 H
2 X
X X
X Y
Y M
E K/A 009EA2.34
- 1. Q=K/A, Q=SRO-only.
- 2. There is training-in-the-distractors in that, with the current format, it is true that the 1B HPI header is exceeding the limit. In other words, logically the only differentiation in the first part Q is whether or not the 1A HPI header is or is not (also) exceeding the flow limit. Better if we write the Q statement to reflect this.
- 3. Second part Q statement implies that the TS 3.5.2 BASES specifically states that one HPI train is adequate for the given accident (SBLOCA on the 1A hot leg). However, the BASES actually states that most SBLOCAs can be mitigated with one HPI train, and then gives one specific case where two are required. It could be argued that technically we do not have a correct answer for the second part Q statement, unless we can point to a specific accident analysis for a 1A hot leg break. It is better to test the specific case listed in the BASES.
- 4. I normally do not prefer to state where a specific LOCA is located for job-link concerns/operational validityhow would control room operators know where the LOCA is located 10 minutes after the event?
Q evaluated as E at this time.
Recommend the following modifications to the Q:
Given Information the same, except delete the first bullet under Time=0410 (1) The 1A HPI header [is/is NOT] exceeding the HPI pump flow limits in accordance with Rule 6 (HPI Pump Throttling Limits)
(2) TS 3.5.2 BASES states that a MINIMUM of ___[one/two]___ HPI train(s) is/are required to mitigate cold leg breaks located on the discharge of the Reactor Coolant Pumps.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 34 34 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
- /
units Back-ward Q=
K/A SRO Only 77 H
2 X
Y Y
B E
K/A 025AG2.1.32
- 1. Q=K/A, Q=SRO-only
- 2. Second part Q statement: need to change CRS will initiate to CRS is required to initiate Q evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 78 H
3 X
X X
Y Y
M E
K/A 040AG2.4.21
- 1. Q=K/A, Q=SRO only.
- 2. 300 psig and lowering seems low to be plausible for AFIS actuation operability. Recommend better N2 bottle pressure of 550 psig and stable.
- 3. 2nd part of the 2nd part Q statement is training in the Q statement and needs to be deleted. First part of 2nd part Q statement needs to more closely parallel the TS BASES language. Recommend the following: TS 3.3.13 BASES states that the AFIS circuitry provides protection against [an inadvertent return to criticality/exceeding containment design pressure] for MSLBs inside containment.
- 4. Recommend adding inside containment to the bullet about SLB on 2A SG.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 35 35 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
- /
units Back-ward Q=
K/A SRO Only 79 H
2 X
X Y
Y M
U K/A 054AG2.1.25
- 1. Q=K/A but weak - SRO applicant is not really interpreting a table, more of an understanding of how to correctly use the notification form. CE is willing to accept the topic for K/A match purposes. Q=SRO only.
- 2. First part Q -we need to be very careful here, I think it could be argued that there is no technically correct answer because we do not exactly match the language in the DBD. For example, are we asking total EFW flow (to both SGs) or how much EFW flow must be provided to each SG? See recommendation below. Ensure distractor flow rate is within the limits allowed for one MDEFWP.
- 3. Multiple correct answers to second part Q - both 4-and 8-hour reports are required.
Q as submitted evaluated as U due to multiple correct answers.
Recommendation as to how we could use similar info for modified Q:
Given the following Unit 1 conditions:
Initial Conditions:
-Reactor power=100%
-Both Main Feedwater Pumps tripped
-All plant systems functioned as designed Current Conditions:
-Approximately 30 minutes after the above event, the STA informs the SM that the only required Non-Emergency 10 CFR 50.72 notification to the NRC is a 4-hour report.
(1) In accordance with the Emergency Feedwater (EFW) Design Basis Document (DBD), in order to mitigate the given event each motor driven emergency feedwater pump shall be capable of delivering at least [375 GPM/650 GPM] at or below 130°F to any single steam generator that is at a pressure of 1064 psia or below.
(2) In addition to a 4-hour report, an 8-hour Non-Emergency 10 CFR 50.72 notification to the NRC [is/is NOT] required for this event.
REFERENCE PROVIDED Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 36 36 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
- /
units Back-ward Q=
K/A SRO Only 80 F
3 X
N Y
N E
K/A 056AA2.33
- 1. Q does not meet K/A. The two parts of the Q are not related, and neither part directly related to a loss of offsite power condition on ESG channels, breaker-trip alarms, indicators and bus voltages. Another way to look at this:
we could delete all of the Given conditions and just list the Q statements, and the Q would not be affected. To 100% meet the K/A we need to address a straight-up loss of offsite power abnormal condition, not a LOCA or MSLB with coincident LOSP. K/A change may be warranted here if there is not a better way to attack the K/A match.
This Q was submitted as one of the preview Qs. During the initial review the Chief Examiner failed to identify the K/A mismatch/no link between parts concern listed above. Due to the Chiefs mistake, Q as submitted evaluated as E to not excessively count U questions against the quality standards of NUREG-1021. Reference ES-201.
Based on above discussion, facility licensee re-submitted entirely different Q from the draft submittal. Facility licensee made additional changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 05/14/2020 81 F
2 X
Y Y
B E
K/A BW04EA2.2
- 1. Q=K/A, Q=SRO only.
- 2. First part question need to change will/will not to is/is not required to format.
- 3. Same thing for second part Q, swap method that will be used to method that is required to be used Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 37 37 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
- /
units Back-ward Q=
K/A SRO Only 82 H
3 Y
Y B
S K/A 069AA2.02
- 1. Q=K/A, Q=SRO only.
Q as submitted evaluated as S at this time.
83 H
2 Y
Y B
S K/A BW02AG2.1.20
- 1. Q=K/A, Q=SRO only.
Q as submitted evaluated as S at this time.
84 H
2 Y
Y N
S K/A BW03EA2.1
- 1. Q=K/A, Q=SR only Q as submitted evaluated as S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 38 38 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
- /
units Back-ward Q=
K/A SRO Only 85 H
3 X
X Y
Y M
E K/A BW14EG2.4.30
- 1. Q=K/A, Q=SRO only
- 2. Need to be careful with this Q that we have a technically correct answer. Q provides given information in a timeline format, but then does not ask the correct answer in terms of the timeline. If this timeline would occur in the plant, the SM would have to declare an EAL before the last times information, so what is the time reference for the first part Q statement?
Q as submitted evaluated as E at this time.
Recommend the following:
Given information the same except modify the timestamps:
Time=0800 Time=0802 Time=0812 Time=0814
-The SM declares an Emergency (1) Based on the given conditions, the correct Emergency Plan Classification at time 0814 is a/an ___(1)___.
[ALERT/SITE AREA EMERGENCY]
(2) The LATEST time allowed to notify the NRC per AD-EP-ALL-0111 is
___(2)___. [0829/0914]
DO NOT USE EMERGENCY COORDINATOR JUDGEMENT AS THE BASIS FOR EAL DETERMINATION REFERENCE PROVIDED Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 39 39 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
- /
units Back-ward Q=
K/A SRO Only 86 H
2 X
Y Y
B E
K/A 003A2.02
- 1. Q=K/A, Q=SRO only
- 2. Second part Q statement: change the SRO should direct to the SRO is required to direct Q is evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 87 H
2 X
X Y
Y M
E K/A 004A2.12
- 1. Q=K/A, Q=SRO only.
- 2. The Q was one of the initial/preview Qs, and was later discussed between the Chief Examiner and the facility. There is cueing in the second part Q in that valves LP-15 and LP-16 are either covered under LCO 3.5.2 (HPI) or 3.5.3 (LPI) and it would be too easy (LOD=1) if LP valves were simply covered under the LPI TS. Recommend asking the second part Q as follows: (2) In accordance with TS Bases, 1LP-15 and 1LP-16 ___(2)___ [are/are NOT]
subject to TS 3.5.2 High Pressure Injection (HPI).
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 40 40 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
- /
units Back-ward Q=
K/A SRO Only 88 H
3 X
X Y
Y M
E K/A 012G2.2.25
- 1. Q=K/A, Q=SRO only.
- 2. It could be argued that first part Q does not have a technically correct answerwhat reference states that 1810 is the actual RPS setpoint? Were focusing on the TS here, and the allowable value is listed in the Table as >1800 psig, which is supposedly the incorrect distractor? Also, what is the basis in the distractor analysis that 10 psig is the band for the allowable value?
- 3. Minutiato get the Q correct, the applicant would need to know the allowable values of the TS RPS table from memory. Do not believe this is an operationally valid setpoint to require SRO applicants to commit to memory. In the plant, IE surveillances will have acceptance criteria written into the test procedure paperwork, and the SRO will be able to refer to the TS 3.3.1 Table in any case. If we were to provide a reference for this Q it would likely devolve into a direct-look-up.
Recommend trying to approach this K/A from a different point-of-view. CE believes there is a lot of valid test material on the SRO level in the 3.3.1 TS BASES, K/A change should not be needed.
Q as submitted evaluated as E at this time due to minutia and operational validity concerns.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Facility licensee convinced Chief Examiner that first part Q was operationally valid and not minutia level-of-knowledge. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 89 H
2 Y
Y M
S K/A 022A2.04
- 1. Q=K/A, Q=SRO only.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 41 41 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
- /
units Back-ward Q=
K/A SRO Only 90 F
3 X
X Y
Y M
E K/A 013G2.2.44
- 1. Q=K/A, Q=SRO only.
- 2. Recommend adding Based on the given conditions, to the first part Q statement to ensure technically correct answer.
- 3. Additional parallelism with 3.5.3 B language recommended with second part Q: In accordance with TS 3.5.3, Low Pressure Injection (LPI) Bases, the safety grade flow indicator of an LPI train [is/is NOT] required to support OPERABILITY of an RBS train.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 91 F
2 X
Y Y
N E
K/A 034G2.1.30
- 1. Q=K/A, Q=SRO only.
- 2. Minor change first part Q will be utilized to is required to be utilized Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 42 42 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
- /
units Back-ward Q=
K/A SRO Only 92 H
2 X
Y Y
B E
K/A 056A2.04
- 1. Q=K/A, Q=SRO only.
- 2. First part Q distractors modify from will/will NOT be established to is/is NOT required to be established Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 43 43 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
- /
units Back-ward Q=
K/A SRO Only 93 H
1 X
Y Y
N U
K/A 068A2.04
- 1. Q=K/A, Q=SRO only.
- 2. First part Q distractors are non plausible due to the specificity of the question: if the TBS pumps continued to operate following the HIGH RIA-54 alarm, why would someone think it would not be required to open and white tag the TBS pump breakers?
- 3. Second part Q distractors are direct look-up and therefore LOD=1: it is a logical TRUE that CONDITION F will be entered, and the language of CONDITION F specifically states that CONDITION F is entered based on entry into CONDITION B.
Q as submitted evaluated as U due to LOD=1/Direct L/U and non plausible distractors.
K/A change may be warranted, this is a hard K/A to match on the SRO level.
Potential fix recommendation below using similar information:
Given the following sequence of events on Unit 3:
Initial Conditions:
-Unit 3 Reactor power=90% stable for fuel conditioning
-Routine liquid radwaste release in progress from Turbine Building Sump (TBS)
-Spurious electrical transient causes 3RIA-54 (TBS) HIGH alarm and damage to 3RIA-54
-SRO declares 3RIA-54 NON-FUNCTIONAL
-3RIA-54 is removed from service and tagged out
-Instrument vendor notifies site that it will take 60-90 days to send repair parts due to instrument obsolescence Current Conditions:
-It has been 45 days since 3RIA-54 was declared NON-FUNCTIONAL (1) 3RIA-54 in HIGH alarm ___(1)___ [does/does NOT] cause automatic actions.
(2) Based on the current conditions, if SLC 16.11.3 REQUIRED ACTION F.2 is satisfied, liquid radwaste releases from the Unit 3 TBS ___(2)___ [are/are NOT]
allowed.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 44 44 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
- /
units Back-ward Q=
K/A SRO Only 94 F
2 Y
Y N
S K/A G2.1.15
- 1. Q=K/A, Q=SRO only.
Q appears S at this time.
95 F
2 X
Y Y
B E
K/A G 2.1.40
- 1. Q=K/A, Q=SRO only.
- 2. None of the given information is required to answer the Q. Can delete all given conditions bulleted information above the Q statements.
- 3. For parallelism and technical accuracy, ensure the first part Q statement contains the full text of the NOTE modifying LCO 3.9.4in other words, add the clause provided no operations are permitted to the end of the Q statement.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 96 F
2 Y
Y N
S K/A G 2.2.17
- 1. Q=K/A, Q=SRO only.
Q appears S at this time.
OCONEE Nuclear Station June 2020 ILO Exam 45 45 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
- /
units Back-ward Q=
K/A SRO Only 97 F
2 X
Y Y
N E
K/A G 2.2.20
- 1. Q=K/A, Q=SRO only.
- 2. Plausibility of OPS Manager lowest level of approval for Troubleshooting is low. OPS Manager does not appear in the entire procedure IP001. Giving some benefit-of-doubt here, think we should just replace OPS Manager distractor with Unit SRO.
Q as submitted evaluated as E at this time.
Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020 98 H
2 X
Y Y
B E
K/A G 2.3.15
- 1. Q=K/A, Q=SRO only.
- 2. Minor tweak to second part Q statement: prefer The correct Emergency classification for this is event is vice The HIGHEST classification
- 3. Recommend the following for the dont-use-judgement statement: DO NOT USE EMERGENCY COORDINATOR JUDGEMENT AS THE BASIS FOR EAL DETERMINATION Q as submitted evaluated as E at this time.
OVERLAP CONCERN: There is excessive amount of EAL declaration on the exam when you include SRO Admin JPM A4 (EAL call based on hostile action) along with this Q and Q85. One of these test items will need to be changed.
Chief Examiner is o.k. with two diverse instances of EAL call on exam, three is too many items on one topic.
Q85 was modified to remove excessive overlap with EAL declarations, this Q (Q98) left relatively intact as submitted on draft exam. Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 46 46 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
- /
units Back-ward Q=
K/A SRO Only 99 H
3 N
N B
U K/A G 2.4.11
- 1. Q does not match K/A on the SRO level. Tier 3/Generic K/As need to be more generic than the submitted Q, which elicits detailed information from one AP procedure in a specific sense that does not meet Tier 3 requirements.
Things that would work for this K/A would be more generic implementation stuff from e.g. AP users guide that relate to the SRO job function. For example:
when is it allowed to perform AP procedures in parallel with EOPs? Are IAAT steps from one procedure still valid after entry into another AP or AP attachment (did step say GO TO or IMPLEMENT)? Are there any procedures (for example RCP abnormal trip in Westinghouse space) where the operator is directed to trip the RX, implement IMAs, then return to perform steps in the AP? We should be able to meet this K/A on a more generic topic.
Q as submitted evaluated as U due to not meeting K/A (Tier 3) on the SRO level.
Based on the above discussion, the facility licensee proposed an entirely new Q that more exactly meets Tier 3/generic administrative requirements. Facility licensee made changes/adjustments to Q and discussed the rationale with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 04/30/2020
OCONEE Nuclear Station June 2020 ILO Exam 47 47 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
- /
units Back-ward Q=
K/A SRO Only 100 F
2 X
X Y
Y B
E K/A G 2.4.44
- 1. Q=K/A, Q=SRO only.
- 2. Plausibility of EOF not assuming responsibility, once activated, is low. Some teaching-in-the Q statement that EOF also does notifications-K/A is only concerned with PARS. Giving some benefit of the doubt here. Believe the better way to ask the Q is TSC vs. EOF.
Recommend the following for the second part Q statement: (2) Once activated, the ___(2)___ [TSC/EOF] is required to assume responsibility for PARS.
Q as submitted evaluated as E at this time.
Facility licensee initially argued that draft submitted Q was plausible and operationally valid as submitted. Chief Examiner demurred. Facility licensee proposed another variant on the original Q which still contained some of the issues stated above. Facility licensee intends to re-write another different Q that takes another approach to meeting this K/A.
MKM 04/30/2020 Facility licensee proposed new Q after additional validations. New Q was discussed with Chief Examiner during conference phonecall. Q as now submitted appears Sat at this time and ready for administration on the final written exam.
MKM 05/14/2020
OCONEE Nuclear Station June 2020 ILO Exam 48 48 Instructions
[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 using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4.
Check the appropriate box if a job content error is identified:
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).
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).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
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 that are designated SRO-only (K/A and license level mismatches are unacceptable).
- 6.
Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of 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 ratings (e.g., how the Appendix B psychometric attributes are not being met).