ML23206A054
| ML23206A054 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/25/2023 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| Download: ML23206A054 (1) | |
Text
ES-301 Administrative Topics Outline RO FINAL Form ES-301-1 Facility:
E. I. HATCH Date of Examination:
3/01/2021 Examination Level: RO SRO Operating Test Number:
2021-301 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations RO Admin 1 D, R Diesel Fuel Oil Inventory. (G2.1.26) (3.4)
Conduct of Operations RO Admin 2 D, R Determine if plant conditions allow a Quick Restart of a Recirc Pump.
(G2.1.20) (4.6)
Equipment Control RO Admin 3 M, R Determine Bulk Average DW temperature per 34SV-SUV-019-1, and then determine if any additional DW cooling requirements.
(G2.2.12) (3.7)
Emergency Plan RO Admin 4 M, R Determine the Evacuation Route During an Emergency. (G2.4.39) (3.9)
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 (2) for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1) (2)
(P)revious 2 exams ( 1, randomly selected)
ES-301 Form ES-301-1 Facility:
E. I. HATCH Date of Examination:
3/01/2021 Examination Level: RO SRO Operating Test Number:
2021-301 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations SRO Admin 1 D, R Failed RWL Instruments - SRO determine required actions. G2.1.23 (4.4)
Conduct of Operations SRO Admin 2 M, R Verify Fuel Movements (G2.1.35) (3.9)
Equipment Control SRO Admin 3 M, R Determine Bulk Average DW temperature per 34SV-SUV-019-1, and then evaluates DW temperature & TS. (G2.2.12 &
G2.2.22) (4.1 & 4.7)
Radiation Control SRO Admin 4 N, R Assess Radiological Conditions in an Emergency and Approve Emergency Exposure Permits (G2.3.4) (3.7)
Emergency Plan SRO Admin 5 D, R Determine the Emergency Classification -
Complete NMP-EP-142 Form 1.
(G2.4.41) (4.6)
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 (2) for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1) (3)
(P)revious 2 exams ( 1, randomly selected)
Administrative Topics Outline SRO FINAL
ES-301 Control Room/In-Plant Systems Outline - RO FINAL Form ES-301-2 Facility:
Plant E.I. Hatch Date of Examination:
03/01/2021 Exam Level: RO SRO-I SRO-U Operating Test Number:
2021-301 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*
Safety Function CR/SIM 1 - Normal Start of Recirc ASD With Cooling Water Failure (Alt path)
A, L, D, S SF-1 Reactivity Control 202001K6.02 (3.1/3.2)
CR/SIM 2 - Perform a Manual RCIC Startup, Failed Controller High (Alt Path)
A, EN, L, D, S SF-2 Reactor Water Inventory Control 217000A4.01 (3.7/3.7)
CR/SIM 3 - Maintain Rx. Press within 700-800 psig using BPVs, then transition to SRVs with same band, after BPVs fail close.
A, D, L, S SF-3 Reactor Pressure Control 239002A4.01 (4.4/4.4)
CR/SIM 4 - Lower RPV Pressure in Shutdown Cooling -
Alternate Path for Manual Initiation of LPCI From Shutdown Cooling A, EN, L, N, S SF-4 Heat Removal From the Core 203000A4.05 (4.3/4.1)
CR/SIM 5 -Lower Torus Water Level D, S SF-5 Containment Integrity 223001A2.11 (3.6/3.8)
CR/SIM 6 - Hot Transfer 600VAC 2A to Alternate Supply - Alternate Path A, N, S SF-6 Electrical 262001A4.01 (3.4/3.7)
CR/SIM 7 - Loss of Air Actions for Rx Bldg Ventilation D, S SF-8 Plant Service System 295019AK2.08 (2.8/2.9)
CR/SIM 8 - Place Control Room HVAC Systems in the Purge Mode, C, L, D SF-9 Radioactivity Release 290003A4.01 (3.2/3.2)
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U PLANT 1 - JPM 10-18A - U1 From Outside the MCR, Insert a Manual Reactor Scram (Alt Path)
A, D, E, R SF-1 Reactivity 295006AA1.05 (4.2/4.2)
PLANT 2 - From The Remote Shutdown Panel, Start RCIC For Injection Into The Reactor D, L, R SF-2 Reactor Water Inventory Control 295016G2.1.30 (4.4/4.0)
PLANT 3 - Crosstie Unit 2 Instrument Bus B to Instrument Bus A D, E SF-6 Electrical 262001A2.07 (3.0/3.2)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
ES-301 Control Room/In-Plant Systems Outline - RO FINAL Form ES-301-2
- 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 (6) / 4-6 / 2-3 0 (1) / 0 / 0 9 (9) / 8 / 4 1 (2) / 1 / 1 1 (2) / 1 / 1 (control room system) 1 (6) / 1 / 1 2 (2) / 2 / 1 3 (0) / 3 / 2 (randomly selected) 1 (2) / 1 / 1
ES-301 Control Room/In-Plant Systems Outline - SRO-I FINAL Form ES-301-2 Facility:
Plant E.I. Hatch Date of Examination:
3/01/2021 Exam Level: RO SRO-I SRO-U Operating Test Number:
2021-301 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*
Safety Function CR/SIM 1 - Normal Start of Recirc ASD With Cooling Water Failure (Alt path)
A, L, D, S SF-1 Reactivity Control 202001K6.02 (3.1/3.2)
CR/SIM 2 - Perform a Manual RCIC Startup, Failed Controller High (Alt Path)
A, EN, L, D, S SF-2 Reactor Water Inventory Control 217000A4.01 (3.7/3.7)
CR/SIM 3 - Maintain Rx. Press within 700-800 psig using BPVs, then transition to SRVs with same band, after BPVs fail close.
A, D, L, S SF-3 Reactor Pressure Control 239002A4.01 (4.4/4.4)
CR/SIM 4 - Lower RPV Pressure in Shutdown Cooling -
Alternate Path for Manual Initiation of LPCI From Shutdown Cooling A, EN, L, N, S SF-4 Heat Removal From the Core 203000A4.05 (4.3/4.1)
CR/SIM 5 -Lower Torus Water Level D, S SF-5 Containment Integrity 223001A2.11 (3.6/3.8)
CR/SIM 6 - Hot Transfer 600VAC 2A to Alternate Supply - Alternate Path A, N, S SF-6 Electrical 262001A4.01 (3.4/3.7)
CR/SIM 7 - Loss of Air Actions for Rx Bldg Ventilation D, S SF-8 Plant Service System 295019AK2.08 (2.8/2.9)
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U PLANT 1 - JPM 10-18A - U1 From Outside the MCR, Insert a Manual Reactor Scram (Alt Path)
A, D, E, R SF-1 Reactivity 295006AA1.05 (4.2/4.2)
PLANT 2 - From The Remote Shutdown Panel, Start RCIC For Injection Into The Reactor D, L, R SF-2 Reactor Water Inventory Control 295016G2.1.30 (4.4/4.0)
PLANT 3 - Crosstie Unit 2 Instrument Bus B to Instrument Bus A D, E SF-6 Electrical 262001A2.07 (3.0/3.2)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
ES-301 Control Room/In-Plant Systems Outline - SRO-I FINAL Form ES-301-2
- 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 (6) / 2-3 0 / 0 (0) / 0 9 / 8 (8) / 4 1 / 1 (2) / 1 1 / 1 (2) / 1 (control room system) 1 / 1 (5) / 1 2 / 2 (2) / 1 3 / 3 (0) / 2 (randomly selected) 1 / 1 (2) / 1
ES-301 Transient and Event Checklist Form ES-301-5 Facility: E. I. HATCH Date of Exam: 3/01/2021 Operating Test No.: 2021-301 A
P P
L I
C A
N T
E V
E N
T T
Y P
E Scenarios 1
2 3
4 T
O T
A L
M I
N I
M U
M(*)
CREW POSITION CREW POSITION CREW POSITION CREW POSITION S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P R
I U
RO X
SRO-I SRO-U RX 6
2 2
5 4
1 1
0 NOR 1
1 1
1 4
1 1
1 I/C 2,4 3,5 4,6 3,5 3,5 4,6 3,6 2,4 16 4
4 2
MAJ 7
7 7
7 7
7 7
7 4
2 2
1 TS NA NA NA NA NA NA NA NA NA 0
2 2
RO SRO-I X
SRO-U RX 6
2 2
5 4
1 1
0 NOR 1
1 1
1 4
1 1
1 I/C 2,3, 4,5 3,4, 5,6 3,4, 5,6 2,3, 4,6 16 4
4 2
MAJ 7
7 7
7 4
2 2
1 TS 2,4,5 5,6 3,4, 5,6 2,4 11 0
2 2
RO SRO-I SRO-U RX 1
1 0
NOR 1
1 1
I/C 4
4 2
MAJ 2
2 1
TS 0
2 2
Instructions:
- 1.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional I/C malfunctions on a one-for-one basis.
- 3.
Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
- 4.
For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.
ES-301 Competencies Checklist Form ES-301-6 Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)
Facility: E. I. HATCH Date of Examination: 3/01/2021 Operating Test No.: 2021-301 APPLICANTS RO SRO-I SRO-U RO SRO-I SRO-U Competencies SCENARIO SCENARIO 1
2 3
4 6
7 Interpret/Diagnose Events and Conditions 2,3,4,5, 7,8,9 3,4,5, 6,7,8 3,4,5, 6,7,8 2,3,4, 6,7,8 3,4,5, 6,7,8 2,3,4,5, 6,7,8,9 Comply with and Use Procedures (1) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Operate Control Boards (2) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Communicate and Interact 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Demonstrate Supervisory Ability (3)
N/A N/A N/A N/A N/A N/A Comply with and Use TS (3)
N/A N/A N/A N/A N/A N/A Notes:
(1)
Includes TS compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
ES-301 Competencies Checklist Form ES-301-6 Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)
Facility: E. I. HATCH Date of Examination: 3/01/2021 Operating Test No.: 2021-301 APPLICANTS RO SRO-I SRO-U RO SRO-I SRO-U Competencies SCENARIO SCENARIO 1
2 3
4 6
7 Interpret/Diagnose Events and Conditions 2,3,4,5, 7,8,9 3,4,5, 6,7,8 3,4,5, 6,7,8 2,3,4, 5,6,7,8 3,4,5, 6,7,8 2,3,4,5, 6,7,8,9 Comply with and Use Procedures (1) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Operate Control Boards (2) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Communicate and Interact 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Demonstrate Supervisory Ability (3) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Comply with and Use TS (3) 2,4,5 5,6 3,4,5,6 2,4 3,6 3,4,6 Notes:
(1)
Includes TS compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
ES-301 Competencies Checklist Form ES-301-6 Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)
Facility: E. I. HATCH Date of Examination: 3/01/2021 Operating Test No.: 2021-301 APPLICANTS RO SRO-I SRO-U RO SRO-I SRO-U Competencies SCENARIO SCENARIO 1
2 3
4 6
7 Interpret/Diagnose Events and Conditions 2,3,4,5, 7,8,9 3,4,5, 6,7,8 3,4,5, 6,7,8 2,3,4, 5,6,7,8 3,4,5, 6,7,8 2,3,4,5, 6,7,8,9 Comply with and Use Procedures (1) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Operate Control Boards (2) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Communicate and Interact 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Demonstrate Supervisory Ability (3) 1,2,3,4,5, 6,7,8,9 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4, 5,6,7,8 1,2,3,4,5, 6,7,8,9 Comply with and Use TS (3) 2,4,5 5,6 3,4,5,6 2,4 3,6 3,4,6 Notes:
(1)
Includes TS compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Exam Date: March 1 1
2 3
Attributes 4
Job Content 5
6 Admin JPMs ADMIN Topic and K/A LOD (1-5)
U/E/S Explanation Rev 0 - Outline Submittal comments Rev 1 - Draft Submittal comments Rev 2 - Prep Week comments/ Final Submittal review I/C Cues Critical Scope Overlap Perf.
Key Minutia Job Link Focus Steps (N/B)
Std.
RO 1, COO (D) from bank Diesel Generator Fuel Oil Tank, K/A 2.1.26 3
x x
S Rev 0 comment:
Ensure JPM guide contains a separate examiner answer key with delineated (i.e. highlighted)
Critical Steps (one pager). Ensure calculated values contain error bands. Step 22 appears to require revision Notify SS requirements are not met due to 1A Tank Rev 1 comment:
Revise step numbers referenced in Performance Step boxes to match 34SO-R43-001-1, (i.e. JPM Steps 6 & 7 correlate to procedure step 1.2 or Section 1, Step 2). This error is carried forward throughout the JPM for performance steps and requires correction.
JPM Step 13 requires an evaluator prompt. How would this be controlled in a group setting?
Provide dipstick level indications for all tanks as part of the JPM initial conditions.
Prompt following JPM Step 19 is also not required, as part of the initiating cue provide information that the applicant is the RO performing this activity.
Rev 2: Revise given indicated level to 35k gal (JPM step 10), JPM is SAT RO 2, COO (D) from bank Quick Start of RR
- Pump, K/A 2.1.20 3
x S
Rev 0 comment:
Ensure JPM initiating cue has a space for applicant to identify if conditions allow or conditions do not allow RRP restart. Are calculations required for this JPM? Summary indicates applicant is expected to only evaluate given information and compare indications.
Rev 1 comment:
Include, in JPM Step 18, what the reason is for not meeting quick restart criteria Rev 2: Revise initial conditions, JPM is SAT
ES-301 Operating Test Review Worksheet Form ES-301-7 RO 3, EQ (M) from bank 34SV-SUV-019-1 Surveillance, K/A G2.2.12 3
S Rev 0 comment:
Ensure JPM guide contains a separate examiner answer key with delineated (i.e. highlighted)
Critical Steps (one pager). Ensure calculated values contain error bands.
Rev 1 comment:
JPM is identified as COO JPM (G2.1.7), yet is claimed as EQ JPM (G2.2.12) on Form 301-1 Rev 2: K/A revised, JPM is SAT RO 4, EPlan (M) from bank Determine Evacuation Route (Emerg)
K/A G2.4.39 3
S Rev 1 comment:
Based on the NOTE on the bottom of Page 5.
Shouldnt JPM Step 3 be identified as a CRITICAL step?
Rev 2: Revise initial condition (ED order), JPM is SAT
ES-301 Operating Test Review Worksheet Form ES-301-7 SRO 1, COO (D) from bank Failed RWL Instruments, K/A G2.1.25 3
S Rev 0 comment:
Bank (2015-301), Admin, Task Standard SAT, G2.1.25 met JPM steps 4, 5 and 6 specify using LFD. What is LFD?
Shouldnt task standards for JPM steps 7, 8, 9 and 10 be based on application of TS LCO 3.3.5.3?
Rev 1 comment: JPM is SAT SRO 2, COO (D) from bank Verify Fuel Movement Sheet, K/A G2.1.35 3
S Rev 1 comment: JPM is SAT SRO 3, EQ (M) from bank 34SV-SUV-019-1 Surveillance, K/A G2.2.12 3
S Rev 0 comment:
Ensure calculated values contain error bands.
Rev 1 comment:
JPM is identified as COO JPM (G2.1.7), yet is claimed as EQ JPM (G2.2.12) on Form 301-1 Rev 2: K/A revised, JPM is SAT SRO 4, RC New Assess Conditions &
Approve Emerg Exposure Permit K/A G2.3.4 3
S Rev 1 comment:
Include reasoning for JPM Steps 3 and 5.
Specifically why those permits can be approved.
Rev 2: Convert to Unit 2 and 2G31-F004 (pgs 4/12),
revise to 15 min validation time, JPM is SAT SRO 5, EPlan (D) from bank EALClassification
& ENF Form K/A G2.4.41 3
S Rev 1 comment: JPM is SAT Rev 2: Revise to only one 15 Time Critical aspect (i.e.
completion of EAL declaration form), remove JPM steps 14 through 27, JPM is SAT
ES-301 Operating Test Review Worksheet Form ES-301-7 1
Simulator/
In-Plant Safety Function and K/A JPMs LOD I/C Focus Cues Critical Steps Scope Overlap Perf.
Std.
Key Minutia Job Link U/E/S Explanation SIM 1 AP, L, D
- SF1, 202001K6.02 3
S Rev 0 comment:
This JPM may be appropriate as a pre-review JPM (need to see draft version)
Rev 1 comment: JPM is SAT Rev 2: Pre-brief JPM, Add visual checks initial condition (#9). JPM is SAT SIM 2 AP, L, EN, D SF2 217000A4.01 3
S Rev 0 comment:
Ensure demanded level band is above or below initiation point of JPM alternate path (allow evaluation of applicant control of RCIC flow/RWL)
Rev 1 comment: JPM is SAT Rev 2: JPM is SAT SIM 3 AP, L, D SF3 239002A4.01 3
S Rev 1 comment: JPM is SAT Rev 2: Revise completion time (10 min), JPM task standard revision, Add jpm step standard regarding pressure control band (700-800#), JPM is SAT SIM 4 AP, L, EN, New SF4 203000A4.05 3
S Rev 0 comment:
JPM Step 2 discussion states Closing F048A.
Should this say Opening?, This JPM may be appropriate as a pre-review JPM (need to see draft version)
Rev 1 comment:
Ensure cue sheet (page 14) is updated Rev 2: Pre-brief JPM, convert alternate path trigger to be automatic based on lowering RPV pressure, revise initial condition (100# and slowly rising), JPM is SAT
ES-301 Operating Test Review Worksheet Form ES-301-7 SIM 5 D
SF5 223001A2.11 3
S Rev 0 comment:
Can JPM Step 3 be incorporated as given information (i.e. RW has reported sufficient volume available)?, This JPM may be appropriate as a pre-review JPM (need to see draft version)
Rev 1 comment: JPM Is SAT Rev 2: Revise task standard (.5 vs.25), revise time standard, JPM is SAT SIM 6 AP, New SF6 262001A4.01 3
S Rev 0 comment:
How much time from alternate path start to Turbine trip on generator amps? What is magnitude of amperage lowering required to prevent Turbine trip?, This JPM may be appropriate as a pre-review JPM (need to see draft version)
Rev 1 comment: JPM is SAT Rev 2: Pre-brief JPM, revise Step 3 standard (20 min),
SF8 295019AK2.08 3
S Rev 1 comment:
Ensure JPM and 301-2 are updated to reflect this JPM as being Alternate Path Rev 2: Revise time standard, JPM is SAT SIM 8 (RO)
MCR, L, D
SF9 290003A4.01 3
S Rev 0 comment:
(RO only, CR administration): This JPM may be appropriate as a pre-review JPM (need to see draft version)
Rev 1 comment:
This JPM is identified as MCR performance.
Ensure JPM includes setup instructions to ensure appropriate on-shift approvals are obtained prior to administration.
Ensure cue-sheet Is updated with a notice concerning operation of actual plant equipment (like an in-plant JPM).
Is this JPM affected by unit differences?
Rev 2: Pre-brief JPM, include as-found locations in JPM step standards, revise initial conditions, JPM is SAT
ES-301 Operating Test Review Worksheet Form ES-301-7 Plant 1 AP, D, E, R
SF1 295006AA1.05 3
S Rev 0 comment:
This JPM designated as alternate path, yet summary states Normal Path? Are RPS supply breakers unable to be opened?
Rev 1 comment:
Ensure any required tools are identified in JPM concerning the removal of magnetrol switch covers (and locations where obtained).
Rev 2: Add page numbers (pictures) to JPM step standards, Add examiner cue (SDV/HCU noise), JPM is SAT Plant 2 D, L, R SF2 295016G2.1.30 3
S Rev 0 comment:
JPM Step 13 Close 2E51-F019 - Connects EDG to the bus? RCIC Min Flow Valve?; Ensure an examiner cue is incorporated to provide applicant RSDP indication of RWL change Rev 1 comment: JPM is SAT Rev 2: Add examiner cues (Turb supply/pump injection valves), JPM is SAT Plant 3 D, E SF6 262001A2.07 3
S Rev 0 comment:
Are Essential Cabinet 2B, Instrument Bus 2B and Instrument Bus 2A all co-located? How many different locations are required for this JPM?
Rev 1 comment: JPM is SAT Rev 2: JPM is SAT
ES-301 Operating Test Review Worksheet Form ES-301-7 Instructions for Completing This Table:
Check or mark any item(s) requiring a comment and explain the issue in the space provided using the guide below.
- 1.
Check each JPM for appropriate administrative topic requirements (COO, EC, Rad, and EP) or safety function requirements and corresponding K/A. Mark in column 1.
(ES-301, D.3 and D.4)
- 2.
Determine the level of difficulty (LOD) using an established 1-5 rating scale. Levels 1 and 5 represent an inappropriate (low or high) discriminatory level for the license that is being tested. Mark in column 2 (Appendix D, C.1.f)
- 3.
In column 3, Attributes, check the appropriate box when an attribute is not met:
The initial conditions and/or initiating cue is clear to ensure the operator understands the task and how to begin. (Appendix C, B.4)
The JPM contains appropriate cues that clearly indicate when they should be provided to the examinee. Cues are objective and not leading. (Appendix C, D.1)
All critical steps (elements) are properly identified.
The scope of the task is not too narrow (N) or too broad (B).
Excessive overlap does not occur with other parts of the operating test or written examination. (ES-301, D.1.a, and ES-301, D.2.a)
The task performance standard clearly describes the expected outcome (i.e., end state). Each performance step identifies a standard for successful completion of the step.
A valid marked up key was provided (e.g., graph interpretation, initialed steps for handouts).
- 4.
For column 4, Job Content, check the appropriate box if the job content flaw does not meet the following elements:
Topics are linked to the job content (e.g., not a disguised task, task required in real job).
The JPM has meaningful performance requirements that will provide a legitimate basis for evaluating the applicant's understanding and ability to safely operate the plant. (ES-301, D.2.c)
- 5.
Based on the reviewers judgment, is the JPM as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 5.
- 6.
In column 6, provide a brief description of any (U)nacceptable or (E)nhancement rating from column 5.
Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a (S)atisfactory resolution on this form.
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 13-1 (spare) Exam Date: March 1 1
2 3
4 5
6 7
8 9
10 Event (new)
Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation RCIC Stby (N)
S 1-BOP RCIC SLB (C,TS) x x
S 2-ATC FW Cont Failure (I)
S 3-BOP PSW FTS (C, TS) x S
4-ATC Inst Bus 2B loss (C, TS) x S
5-BOP (moved from scenario 2)
Earthquake w/
1D loss (SAT)
(R)
7 RPS Failure (C)
S 8
LOCA (M)
S 9
CS Inj Vlv failure (C) x S
9 Rev 0 comment:
Event 3: Ensure D-2 identifies verifiable action for cooling water controller failure. D-1 isnt clear why operator action will be required (i.e. manual control to raise/lower cooling water flow?).
Events 4 & 6: Consider that Events 4 and 6 accomplish the same goal, i.e. abnormal events where ATC downpower credited to mitigate. Event 6 makes sense considering the scenario path. Evaluate if Event 4 is necessary.
Event 6: potential overlap Scenario 12-1, Event 7 (2019-301) - different bus loss SAT 2C (difference in crew response?)
Event 9: Does manual opening of CS injection valve count for both verifiable action and CT criteria? Crediting CP-1 direction?
Rev 2: editorial, no changes to scenario composition (spare)
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 13-2 Exam Date: March 1 1
2 3
4 5
6 7
8 9
10 Event (new)
Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation RFPT cont RTS (N)
S 1-BOP Pwr Ascension (R - flow)
S 2-ATC IA d/p High (C)
S 3-BOP RRP 2A Hi Vib (C)
S 4-ATC (lower speed success path, moved from scenario 1)
HPCI inad init (I, TS) x S
5-BOP (re-ordered to before SRV)
Cycling SRV (I, TS) x x
S 6-ATC ATWS (M) x S
S 8
Rev 0 comment:
Event 1: potential overlap Scenario 11-3, Event 1 (2017-301) - different Major, 2A controller (vs 2B)
Event 4: What is mechanism behind SRV failure? Should this be categorized as a (C)omponent failure?
Event 5: potential overlap Scenario 11-4, Event 5 (2017-301) - different Major, 2A breaker (vs 2B)
Event 6: TS entry (HPCI) potential overlap with Scenario 13-7, Event 3 &/or Scenario 13-6, Event 4. To correct, can state on 13-2 turnover that a single SRV is already INOP. Would then require applicant identification of 3.5.1, Condn G (3.0.3 entry).
Event 7: Will crew transition to RC prior to anticipated end of scenario?
CT-2: Where does the six minute time limit come from? Also, is there a possibility CT-2 could become invalid if the ATC is quick to drive rods (i.e. transition out of RCA to RC)?
Rev 2: editorial, no changes to scenario composition
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 13-3 (Low Power) Exam Date: March 1 1
2 3
4 5
6 7
8 9
10 Event (new)
Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation H2 Seal Oil rest (N)
S 1-BOP Pwr Ascension (R - rods)
S 2-ATC CR double notch (C)
S 3-ATC HPCI clr to flow (C, TS) x S
4-BOP, (moved from scenario 6) D-2 states issue with RCIC - should this say HPCI? Is sim booth cue referring to wrong event referenced (inadvertent start)? Event appears to be (I)nstrumentation malfunction.
Rev 2: Component malfxn, corrected RWCU line brk (C, TS) x x
S 5-ATC DW Chiller Loss (C)
S 6-BOP LOOP (M)
S 7
2A DG Trip/Res (C) x S
8 Rev 0 comment:
Event 6: Evaluate potential PCC entry based on loss of DW chillers. Potentially after LOOP.
Event 8: potential overlap Scenario 12-3, Event 9 (2019-301) - same major but no loss of all EDGs Event 8: apart from addressing EDG 2A loss, what additional crew actions are required following loss of all EDGs?
Rev 2: editorial, no changes to scenario composition
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 13-4 Exam Date: March 1 1
2 3
4 5
6 7
8 9
10 Event (new)
Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation RF filter RFS (N)
S 1-BOP 2B CS Disch Lk (C, TS) x S
2-BOP CRD 2A OVLD (C)
S 3-ATC ADS Inad Init (I, TS) x x
S 4-BOP RR Inad RB (R - rods) x S
5-ATC CR sticks (C)
S 6-ATC (drive water d/p success path)
Unisol Stm Lk (M) x S
7 HPCI flow failure (C)
S 8
Pre-submittal comments:
Malfxn after EOP (1), Abn (4), Major (1), EOPs (2), Cont EOP (0, RHRSW after EOP entry), CT (3), TS (2)
Should events 4/5 and 6 be swapped? Potential for applicant SCRAM on event 4 (pg 8). Scenario guide is unclear after the runback, will the crew be in RPI or in the Immediate Exit region?
Guide not specific, do LPRM oscillations start < 5% peak-to-peak & gradually increase over time (reinforce validity of CT1, 5 minute criteria) or just remain < 5%
peak-to-peak?
Sim cue in Event 4, pg 9 IF it was NOT inserted previously. Should be revised to read IF it WAS inserted previously.
- 5) ADS timer at Plant Hatch is 105 seconds?
ES-301 Operating Test Review Worksheet Form ES-301-7 Rev 0 comment:
Event 6: potential overlap Scenario 11-2, Event 3 (2017-301) - same major, CR w/d vs (insertion). Rod motion is required?
Event 7: Are there any crew mitigation actions following crew discovery of MSIV failure to close? I.e. actions specific to address the MSIV failure CT-1: Remove the following: to prevent exceeding >100oF cooldown rate. CT is failed once the plant receives auto blowdown (i.e. valves open on timer) since upon opening, 100F/hr will be exceeded.
CT-2: Where does five minute time limit come from?
Rev 2: editorial, no changes to scenario composition
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 13-5 (not used) Exam Date: March 1 1
2 3
4 5
6 7
8 9
10 Event (new)
Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Vac Bkr Oper (N)
S 1-BOP Pwr Ascension (R - rods/flow)
S 2-ATC APRM failure (I)
S 3-ATC TB SF low flow (C)
S 4-BOP RHR 2A DC bkr (TS) x S
5 RFPT seal fail (C)
S 6-BOP RR A seal leak (C, TS) x x
S 7-ATC Flooding (M)
S 8
9 Rev 0 comment:
Event 3: ensure D-2 specifies that crew is expected to continue rod withdrawal (IAW turnover directed Event 2 evolution), prior to transitioning to Event 4 Event 3: Should this be categorized as an (I)nstrumentation failure?
Event 6: credited to ATC operator on D-1, however it is more likely that BOP operator is directed to perform bypass valve manipulation to mitigate RFPT seal failure Event 7: credited to BOP operator on D-1, however it is more likely that ATC operator is directed to secure/isolate RR pump Event 7: is it anticipated that PCC will require entry based on RR seal leakage (DW/T)? Is there an AOP specific to degrading containment conditions at Plant Hatch? Is there a possibility that crew could invoke RC based on rising DW pressure in advance of Flooding/Vacuum Loss (i.e. based on rate of rise)?
CT-2: D-1 specifies that MSL isolation is critical to prevent release to TB. There is no mention of fuel failure in the D-1. Ensure fuel failure (with cascading alarms) is incorporated into D-2.
Rev 2: editorial, not used
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 13-6 Exam Date: March 1 1
2 3
4 5
6 7
8 9
10 Event (new)
Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Lower Pwr (R - flow)
S 1-ATC Rmv 2A RFPT (N)
S 2-BOP RCIC inad init (C, TS) x S
3-ATC RCC leak (C)
S 4-BOP 2A SSAC s/u (C) x S
5-ATC (moved from scenario 1)
DW leak, vent (C, TS) x x
S 6-BOP (venting successful)
Loss of FW (M)
S 7
HPCI F001 FTO (C) x S
8 (use of RCIC success path)
Rev 0 comment:
Event 2/3: Considering anticipated location of BOP operator for Event 2. Does examiner guidance need to be incorporated into D-2 to ensure ATC operator obtains Event 3? Or is it expected that ATC will respond to RCIC regardless of Event 2 status?
Event 4: Ensure D-2 is clear on how BOP obtains Event 4.
Event 3/4 TS: Ensure timing of invoking 3.5.1, Condn E & 3.5.3, Condn B is clear in D-2.
Event 5: Ensure D-2 is clear how ATC will be responding to Event 5.
Event 6: Evaluate potential PCC entry based on loss of RCC.
Event 8: Ensure driver for inventory loss (DW leak) is sized to make -180 RWL realistic during the timeframe of administration (affects CT-2). Does leak grow over time?
Rev 2: editorial, no changes to scenario composition
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 13-7 Exam Date: March 1 1
2 3
4 5
6 7
8 9
10 Event (new)
Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation RB sump surv (N)
S 1-BOP CRD trip (I)
S 2-ATC HPCI SP sensor (I, TS) x S
3-BOP RR 2B trip (C, TS) x S
4-ATC Lower Pwr (R - rods)
S 5-ATC B/U SDVs (TS) x S
6 SC 2B Trip/FTS (C) x S
7-BOP LOCA (M)
S 8
RHR F016 FTO (C) x S
9 Rev 0 comment:
Event 3: Is CST realignment required following Event 3 (i.e. use of time compression)?
Event 3: potential overlap Scenario 12-5, Event 4 (2019-301) - different major, RCIC vs (HPCI)
Event 4: There doesnt appear to be a verifiable action available for Event 4. Event 5 would count yet is listed as (R)eactivity evolution. What other action is required by ATC operator to obtain credit for Event 4?
Rev 2: editorial, no changes to scenario composition
ES-301 Operating Test Review Worksheet Form ES-301-7 Instructions for Completing This Table:
Use this table for each scenario for evaluation.
2 Check this box if the events are not related (e.g., seismic event followed by a pipe rupture) OR if the events do not obey the laws of physics and thermodynamics.
3, 4 In columns 3 and 4, check the box if there is no verifiable or required action, as applicable. Examples of required actions are as follows: (ES-301, D.5f) opening, closing, and throttling valves starting and stopping equipment raising and lowering level, flow, and pressure making decisions and giving directions acknowledging or verifying key alarms and automatic actions (Uncomplicated events that require no operator action beyond this should not be included on the operating test unless they are necessary to set the stage for subsequent events. (Appendix D, B.3).)
5 Check this box if the level of difficulty is not appropriate.
6 Check this box if the event has a TS.
7 Check this box if the event has a critical task (CT). If the same CT covers more than one event, check the event where the CT started only.
8 Check this box if the event overlaps with another event on any of the last two NRC examinations. (Appendix D, C.1.f) 9 Based on the reviewers judgment, is the event as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 9.
10 Record any explanations of the events here.
In the shaded boxes, sum the number of check marks in each column.
In column 1, sum the number of events.
In columns 2-4, record the total number of check marks for each column.
In column 5, based on the reviewer's judgement, place a checkmark only if the scenario's LOD is not appropriate.
In column 6, TS are required to be 2 for each scenario. (ES-301, D.5.d)
In column 7, preidentified CTs should be 2 for each scenario. (Appendix D; ES-301, D.5.d; ES-301-4)
In column 8, record the number of events not used on the two previous NRC initial licensing exams. A scenario is considered unsatisfactory if there is < 2 new events. (ES-301, D.5.b; Appendix D, C.1.f)
In column 9, record whether the scenario as written (U)nacceptable, in need of (E)nhancement, or (S)atisfactory from column 11 of the simulator scenario table.
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Exam Date: March 1 Scenario 1
2 3
4 5
6 7
8 11 Event Totals Events Unsat.
TS Total TS Unsat.
% Unsat.
Scenario Elements U/E/S Explanation 1
9 3
3 S
2 8
2 2
S 3
8 2
2 E
Event 4 4
8 2
3 S
5 9
2 2
S 6
8 2
3 S
7 9
3 2
S Instructions for Completing This Table:
Check or mark any item(s) requiring comment and explain the issue in the space provided.
1, 3, 5 For each simulator scenario, enter the total number of events (column 1), TS entries/actions (column 3), and CTs (column 5).
This number should match the respective scenario from the event-based scenario tables (the sum from columns 1, 6, and 7, respectively).
2, 4, 6 For each simulator scenario, evaluate each event, TS, and CT as (S)atisfactory, (E)nhance, or (U)nsatisfactory based on the following criteria:
- a.
Events. Each event is described on a Form ES-D-2, including all switch manipulations, pertinent alarms, and verifiable actions. Event actions are balanced between at-the-controls and balance-of-plant applicants during the scenario. All event-related attributes on Form ES-301-4 are met. Enter the total number of unsatisfactory events in column 2.
- b.
TS. A scenario includes at least two TS entries/actions across at least two different events. TS entries and actions are detailed on Form ES-D-2. Enter the total number of unsatisfactory TS entries/actions in column 4. (ES-301, D.5d)
- c.
CT. Check that a scenario includes at least two preidentified CTs. This criterion is a target quantitative attribute, not an absolute minimum requirement. Check that each CT is explicitly bounded on Form ES-D-2 with measurable performance standards (see Appendix D). Enter the total number of unsatisfactory CTs in column 6.
7 In column 7, calculate the percentage of unsatisfactory scenario elements:
8 If the value in column 7 is > 20%, mark the scenario as (U)nsatisfactory in column 8. If column 7 is 20%, annotate with (E)nhancement or (S)atisfactory.
9 In column 9, explain each unsatisfactory event, TS, and CT. Editorial comments can also be added here.
Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario is marked by a (S)atisfactory resolution on this form.
2 + 4 + 6 1 + 3 + 5100%
ES-301 Operating Test Review Worksheet Form ES-301-7 Site name: Hatch Exam Date: March 1 OPERATING TEST TOTALS Total Total Unsat.
Total Total Unsat.
Explanation Edits Sat.
Admin.
JPMs 9
0 6
3 Sim./In-Plant JPMs 11 0
4 7
Scenarios 7
0 1
6 Op. Test Totals:
27 0
11 16 0
Instructions for Completing This Table:
Update data for this table from quality reviews and totals in the previous tables and then calculate the percentage of total items that are unsatisfactory and give an explanation in the space provided.
- 1.
Enter the total number of items submitted for the operating test in the Total column. For example, if nine administrative JPMs were submitted, enter 9 in the Total items column for administrative JPMs.
For scenarios, enter the total number of simulator scenarios.
- 2.
Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 and simulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.
- 3.
Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous tables. This task is for tracking only.
- 4.
Total each column and enter the amounts in the Op. Test Totals row.
- 5.
Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. Test Total) and place this value in the bolded % Unsat. cell.
Refer to ES-501, E.3.a, to rate the overall operating test as follows:
- satisfactory, if the Op. Test Total % Unsat. is 20%
- unsatisfactory, if Op. Test Total % Unsat. is > 20%
- 6.
Update this table and the tables above with post-exam changes if the as-administered operating test required content changes, including the following:
- The JPM performance standards were incorrect.
- The administrative JPM tasks/keys were incorrect.
- CTs were incorrect in the scenarios (not including postscenario critical tasks defined in Appendix D).
- The EOP strategy was incorrect in a scenario(s).
- TS entries/actions were determined to be incorrect in a scenario(s).
ES-401 BWR Examination Outline Form ES-401-1 Facility: Edwin I. Hatch Date of Exam: January 2021 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
Total A2 G*
Total
- 1.
Emergency and Abnormal Plant Evolutions 1
4 3
4 N/A 3
3 N/A 3
20 4
3 7
2 1
2 1
1 1
1 7
2 1
3 Tier Totals 5
5 5
4 4
4 27 6
4 10
- 2.
Plant Systems 1
2 3
2 2
3 2
2 2
3 2
3 26 3
2 5
2 1
1 1
1 2
1 1
1 1
1 1
12 0
2 1
3 Tier Totals 3
4 3
3 5
3 3
3 4
3 4
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
2 3
3 2
2 2
1 2
Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points, and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
- 7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply.) Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X
X AK1.02: Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Power/flow distribution AA2.05: Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Jet pump operability 3.3 3.4 37 83 295003 (APE 3) Partial or Complete Loss of AC Power / 6 X G.2.4.6: Knowledge of EOP mitigation strategies (Partial or Complete Loss of AC Power) 3.7 38 295004 (APE 4) Partial or Total Loss of DC Power / 6 X
X AK3.02: Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF D.C.
POWER: Ground isolation/fault determination G2.2.4: Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (Partial or Total Loss of DC Power) 2.9 3.6 39 85 295005 (APE 5) Main Turbine Generator Trip /
3 X
X AA1.07: Ability to operate and/or monitor the following as they apply to MAIN TURBINE GENERATOR TRIP: A.C. electrical distribution AA2.08: Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: Electrical distribution status 3.3 3.3 40 86 295006 (APE 6) Scram / 1 X G2.4.4: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures. (Scram) 4.5 41 295016 (APE 16) Control Room Abandonment
/ 7 X
AA1.06: Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: Reactor water level 4.0 46 295018 (APE 18) Partial or Complete Loss of CCW / 8 X
AA2.05: Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System pressure 2.9 47
ES-401 3
Form ES-401-1 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 X
X AK3.02: Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Standby air compressor operation AA2.02: Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Status of safety-related instrument air system loads (see AK2.1 - AK2.19) 3.5 3.7 48 87 295021 (APE 21) Loss of Shutdown Cooling /
4 X
AK3.01: Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING: Raising reactor water level 3.3 49 295023 (APE 23) Refueling Accidents / 8 X
AA2.02: Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS: Fuel pool level 3.4 51 295024 High Drywell Pressure / 5 X G2.4.8: Knowledge of how abnormal operating procedures are used in conjunction with EOPs. (High Drywell Pressure) 3.8 52 295025 (EPE 2) High Reactor Pressure / 3 X
EK2.06: Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: HPCI 3.8 53 295026 (EPE 3) Suppression Pool High Water Temperature / 5 X
EK1.02: Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Steam condensation 3.5 54 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 X
EK1.02: Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: Equipment environmental qualification 2.9 55 295030 (EPE 7) Low Suppression Pool Water Level / 5 X
X EK2.01: Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following: HPCI G2.2.12: Knowledge of surveillance procedures. (Low Suppression Pool Water Level)
G2.2.4: (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.
3.8 4.1 3.6 56 88
ES-401 4
Form ES-401-1 295031 (EPE 8) Reactor Low Water Level / 2 X
X EK1.01: Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling G2.4.9: Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. (Reactor Low Water Level) 4.6 4.2 57 89 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X
EK3.03: Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Lowering reactor water level 4.1 60 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 X
EA2.01: Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: Off-site 3.3 61 600000 (APE 24) Plant Fire On Site / 8 X
AK2.04: Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Breakers / relays / and disconnects 2.5 64 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 X
X AA1.03: Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Voltage regulator controls AA2.10: Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Generator overheating and the required actions 3.8 3.8 65 93 K/A Category Totals:
4 3
4 3
3/4 3/3 Group Point Total:
20/7
ES-401 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 295002 (APE 2) Loss of Main Condenser Vacuum / 3 X G2.4.35: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects. (Loss of Main Condenser Vacuum) 4.0 84 295007 (APE 7) High Reactor Pressure / 3 X
AK2.06: Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: PCIS/NSSSS 3.5 42 295008 (APE 8) High Reactor Water Level / 2 X
AK1.01: Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR WATER LEVEL: Moisture carryover 3.0 43 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /
5 295013 (APE 13) High Suppression Pool Temperature. / 5 X
AK2.01: Knowledge of the interrelations between HIGH SUPPRESSION POOL TEMPERATURE and the following:
Suppression pool cooling 3.6 44 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 X
AA1.08: Ability to operate and/or monitor the following as they apply to INCOMPLETE SCRAM: Process computer/SPDS/ERIS/CRIDS/GDS 2.7 45 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 X
AA2.03: Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS: CRD mechanism temperatures 3.1 50 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 X G2.1.28: Knowledge of the purpose and function of major system components and controls. (High Secondary Containment Area Radiation Levels) 4.1 58
ES-401 6
Form ES-401-1 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 X
EA2.02: Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: Cause of high radiation levels 4.2 90 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 X
EK3.02: Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment ventilation response 3.3 59 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 X
EA2.03: Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Cause of the high water level 3.8 91 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals:
1 2
1 1
1/2 1/1 Group Point Total:
7/3
ES-401 7
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 203000 (SF2, SF4 RHR/LPCI)
RHR/LPCI: Injection Mode X
K6.03: Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI INJECTION MODE: Emergency generator 3.7 4
205000 (SF4 SCS) Shutdown Cooling X
A4.12: Ability to manually operate and/or monitor in the control room (RHR Shutdown Cooling Mode): Recirculation loop temperatures 3.4 5
206000 (SF2, SF4 HPCIS)
High-Pressure Coolant Injection X
K4.17: Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Protection against draining the condensate storage tank to the suppression pool 3.4 6
207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)
Low-Pressure Core Spray X
K3.02: Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:
ADS logic 3.8 7
209002 (SF2, SF4 HPCS)
High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control X
X K1.01: Knowledge of the physical connections and/or cause effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following: Core spray line break detection G2.1.25: Ability to interpret reference materials, such as graphs, curves, tables, etc. (Standby Liquid Control) 3.0 4.2 8
76 212000 (SF7 RPS) Reactor Protection X
X K1.06: Knowledge of the physical connections and/or cause effect relationships between REACTOR PROTECTION SYSTEM and the following:
Control rod drive hydraulic system K2.01: Knowledge of electrical power supplies to the following: RPS motor-generator sets 3.5 3.2 1
10 215003 (SF7 IRM)
Intermediate-Range Monitor X
X K2.01: Knowledge of electrical power supplies to the following: IRM channels/detectors A3.03: Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including: RPS status 2.5 3.7 13 12
ES-401 8
Form ES-401-1 215004 (SF7 SRMS) Source-Range Monitor X
K5.03: Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM) SYSTEM: Changing detector position 2.8 14 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor X
K2.02: Knowledge of electrical power supplies to the following: APRM channels 2.6 15 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling X
A1.08: Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: Suppression pool temperature 3.5 16 218000 (SF3 ADS) Automatic Depressurization X
K3.01: Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following: Restoration of reactor water level after a break that does not depressurize the reactor when required 4.4 17 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff X
K6.03: Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Process radiation monitoring system 2.9 18 239002 (SF3 SRV) Safety Relief Valves X
X K5.06: Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES:
Vacuum breaker operation A2.01: Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open vacuum breakers 2.7 3.0 23 22 259002 (SF2 RWLCS) Reactor Water Level Control X
X A3.04: Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including: Changes in reactor feedwater flow G2.2.38: Knowledge of conditions and limitations in the facility license. (Reactor Water Level Control) 3.2 4.5 25 79 261000 (SF9 SGTS) Standby Gas Treatment X
X A4.07: Ability to manually operate and/or monitor in the control room: System flow A2.11: Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
High containment pressure 3.1 3.3 26 80 262001 (SF6 AC) AC Electrical Distribution X G2.4.1: Knowledge of EOP entry conditions and immediate action steps. (AC Electrical Distribution) 4.6 27
ES-401 9
Form ES-401-1 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)
X X
A3.01: Ability to monitor automatic operations of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) including:
Transfer from preferred to alternate source G2.1.32: Ability to explain and apply system limits and precautions. (Uninterruptable Power Supply (AC/DC))
2.8 3.8 28 29 263000 (SF6 DC) DC Electrical Distribution X
X A1.01: Ability to predict and/or monitor changes in parameters associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including: Battery charging/discharging rate G2.4.31: Knowledge of annunciator alarms, indications, or response procedures. (DC Electrical Distribution) 2.5 4.2 30 31 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG X
X K5.05: Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET): Paralleling A.C. power sources A2.02: Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Unloading prior to securing emergency generator 3.4 3.1 32 81 300000 (SF8 IA) Instrument Air X
A2.01: Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions 2.9 62 400000 (SF8 CCS) Component Cooling Water X
X K4.01: Knowledge of CCWS design feature(s) and or interlocks which provide for the following: Automatic start of standby pump A2.01: Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Loss of CCW pump 3.4 3.4 63 92 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals:
2 3
2 2
3 2
2 2/3 3 2 3/2 Group Point Total:
26/5
ES-401 10 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer X
A4.05: Ability to manually operate and/or monitor in the control room:
Rod insert error indication 3.2 9
202001 (SF1, SF4 RS) Recirculation X
A3.09: Ability to monitor automatic operations of the RECIRCULATION SYSTEM including: MG set trip (VFD) 3.3 2
202002 (SF1 RSCTL) Recirculation Flow Control X
K4.05: Knowledge of RECIRCULATION FLOW CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: Limiting recirculation pump speed mismatch 3.1 3
204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe X G2.1.31: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. (Traversing In-Core Probe) 4.6 11 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode X
K1.05: Knowledge of the physical connections and/or cause effect relationships between RHR/LPCI:
CONTAINMENT SPRAY SYSTEM MODE and the following: Keep fill system 2.9 19 230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode X
K2.02: Knowledge of electrical power supplies to the following:
Pumps 2.8 20 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup
ES-401 11 Form ES-401-1 234000 (SF8 FH) Fuel-Handling Equipment X
A2.01: Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Interlock failure 3.7 77 239001 (SF3, SF4 MRSS) Main and Reheat Steam X
K5.05: Knowledge of the operational implications of the following concepts as they apply to MAIN AND REHEAT STEAM SYSTEM: Flow indication 2.8 21 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating X
A2.08: Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Main turbine overspeed 3.3 78 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary X
K5.03: Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS:
Hydraulically operated valve operation 2.6 24 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste X
K3.04: Knowledge of the effect that a loss or malfunction of the RADWASTE will have on following:
Drain sumps 2.7 33 271000 (SF9 OG) Offgas X
A1.01: Ability to predict and/or monitor changes in parameters associated with operating the OFFGAS SYSTEM controls including: Condenser vacuum 3.3 34 272000 (SF7, SF9 RMS) Radiation Monitoring X G2.1.25: Ability to interpret reference materials, such as graphs, curves, tables, etc.
(Radiation Monitoring) 4.2 82 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation X
A2.05: Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Extreme outside weather conditions 2.6 35
ES-401 12 Form ES-401-1 290001 (SF5 SC) Secondary Containment X
K6.03: Knowledge of the effect that a loss or malfunction of the following will have on the SECONDARY CONTAINMENT:
SBGT 3.8 36 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals:
1 1
1 1
2 1
1 1/2 1 1 1/1 Group Point Total:
12/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Edwin I. Hatch Date of Exam: January 2021 Category K/A #
Topic RO SRO-only IR IR
- 1. Conduct of Operations 2.1.8 Ability to coordinate personnel activities outside the control room.
3.4 67 2.1.41 Knowledge of the refueling process.
2.8 66 2.1.3 Knowledge of shift or short-term relief turnover practices.
3.9 95 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
3.6 94 Subtotal 2
2
- 2. Equipment Control 2.2.22 Knowledge of limiting conditions for operations and safety limits.
4.0 68 2.2.35 Ability to determine Technical Specification Mode of Operation.
3.6 69 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
3.9 70 2.2.40 Ability to apply Technical Specifications for a system.
4.7 96 2.2.43 Knowledge of the process used to track inoperable alarms.
3.3 97 Subtotal 3
2
- 3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 73 2.3.11 Ability to control radiation releases.
3.8 71 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.2 72 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.8 98 Subtotal 3
1
- 4. Emergency Procedures/Plan 2.4.3 Ability to identify post-accident instrumentation.
3.7 75 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.
3.5 74 2.4.18 Knowledge of the specific bases for EOPs.
4.0 99 2.4.28 Knowledge of procedures relating to a security event (non-safeguards information).
4.1 100 Subtotal 2
2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 295030G2.2.12 SRO QUESTION Original K/A:
EPE: 295030 Low Suppression Pool Water Level G2.2.12 Knowledge of surveillance procedures.
(CFR: 41.10 / 45.13) 3.7 4.1 Surveillance procedures will not be performed with an EOP Low Suppression Pool Water Level.
AFTER PHONE CONVERSATION WITH CHIEF EXAMINER PHIL CAPEHART ON 6/24/2020, REPLACED K/A WITH THE FOLLOWING K/A:
New K/A:
EPE: 295030 Low Suppression Pool Water Level G2.2.4 (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.
(CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13) 3.6 3.6
ES-401 Written Examination Review Worksheet Form ES-401-9 Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts:
- 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2. Enter the level of difficulty (LOD) of each question a 1 (easy) to 5 (difficult); questions with a difficulty between 2 and 4 are acceptable.
- 3. Check the appropriate box if a psychometric flaw is identified:
- Stem Focus: The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
- Cues: The stem or distractors contain cues (e.g., clues, specific determiners, phrasing, length).
- T/F: The answer choices are a collection of unrelated true/false statements.
- Cred. Dist.: The distractors are not credible; single implausible distractors should be repaired, and more than one is unacceptable.
- Partial: One or more distractors are partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by the stem).
- 4. Check the appropriate box if a job content flaw is identified:
- Job Link: The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
- Minutia: The question requires the recall of knowledge that is too specific for the closed-reference test mode (i.e., it is not required to be known from memory).
- #/Units: The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
- Backward: The question requires reverse logic or application compared to the job requirements.
- 5. Check questions that are sampled for conformance with the approved K/A and those K/As that are designated SRO-only. (K/A and license-level mismatches are unacceptable.)
- 6. Enter questions source: (B)ank, (M)odified, or (N)ew. Verify that (M)odified questions meet the criteria of Form ES-401, Section D.2.f.
- 7. Based on the reviewers judgment, is the question, as written, (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 8. At a minimum, explain any U status ratings (e.g., how the Appendix B psychometric attributes are not being met).
Revision History Revision 0 - 9/18/2020, Pre-Submittal Items review Revision 1 - 1/12/2021: Draft Submittal NRC review Revision 2 - 1/22/2021: Revised (update) RO draft 2 review Revision 3 - 2/01/2021: Revised (update) SRO draft 2 review Revision 4 - 2/02/2021: Revised (update) draft 3 review Revision 5 - 2/12/2021: Final Submittal NRC review, Final references verification Q#
- 1.
LOK (F/H) (H%)
(50-60% H% RO)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N (Prev used)
- 7.
U/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 37/38 (51%)
11/14 (56%)
32/27/16 (24 RO) 8/7/10 (12 SRO) 0/75 0/25 RO - 14.7% Unsat SRO - 12% Unsat (if applicable) Post-Exam Comment xxx.
ES-401 2
Form ES-401-9 Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only Generic Comments:
- 1) Several previously reviewed and approved questions (from pre-submittal) were revised on the Draft submittal. Be aware that any changes to reviewed and approved Draft submittal questions may jeopardize final approval of the written examination.
- 2) As-written RO exam doesnt contain the criteria for # higher cognitive level exam questions (34.7% vs 50-60%).
- 3) As-written SRO exam doesnt contain the criteria for # higher cognitive level exam questions (44% vs 50%).
1 F
3 B
S Rev 1: T2/G1, Question is SAT 2
H 3
B (2011 Hatch)
S Rev 1: T2/G2, Question is SAT 3
H 3
N S
Rev 1: T2/G2, Revise stem information to state Unit 1 is (initially) operating at 80% RTP Revise second half question and answer choices: If subsequently desired to raise Recirc Pump 1A speed, use of the SPEED HOLD RESET pushbutton __(2)__
required. is/ is NOT Ensure distractor analysis is revised.
Rev 2: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 4
H 3
N S
Rev 1: T2/G1 Provided RWL, RPV & DW pressure not needed to answer question and can be removed.
Underlining of 1E and 1F bus names can be removed.
Provided timing of LPCI injection (i.e. 15 minutes) not required to answer question and can be removed.
It appears likely that questions may arise during administration concerning U2 status considering the LOSP casualty affecting U1. Unit 2 status should be provided in the stem information (e.g. Unit 2 remains at 100% RTP).
This is ultimately a power supply impact question, Im uncertain how the listed busses being de-energized correlate to the EDG failure? No evaluation of EDG failure required to answer the question. (Q=K/A)
Idea: incorporate knowledge of LPCI pump start timing (LOOP vs LOCA), if appropriate.
Rev 2: Question revised (rewrite) and SAT 5
H 3
M (2017 Hatch)
S Rev 1: T2/G1, Answer Choice A is potentially correct since an applicant can assume only a fractional amount of time has occurred.
Under what conditions can 4160 2F be aligned to 600V 2C/2D? Why is this not currently possible?
Spurious second half statements included in the first half question answer choices, (i.e. since RHR Loop &
since RHRSW pump 2C), these statements can be removed.
Rev 2: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 6
H 3
B (2013 Hatch)
S Rev 1: T2/G1, C.1/D.1 distractors are implausible based on given CST trend information (CST level lowers and stabilizes at 20).
With the given information, the applicant can only conclude that CST level stabilized b/c of the HPCI suction swap.
Additionally, answer choice C is implausible as it implies no change to HPCI status (although the question asks for a five-minute impact).
Revise opening statement to read: Unit 2 was operating at 100% RTP when a scram occurred. Minimum RWL reported was 15 inches.
Revise question stem information to read: Subsequently, CST level starts to lower before stabilizing.
Revise question statement to read: When CST level stabilized, 2E41-F004, CST Suction Valve, will ____ with HPCI operating ____.
Revise A.1/B.1 answer choices to read: be closed Revise A.2/C.2 answer choices to read: in injection mode Rev 2: Question revised and SAT 7
H 3
B S
Rev 1: T2/G1, Revise opening statement to read: Unit 2 has experienced a Station Blackout.
Remove the second given bullet under 0900: 4160 VAC Buses, All De-Energized Revise the second given bullet under 0905: Core Spray pump 2A discharge pressure is 150 psig (highest achieved)
Rev 2:
Question revised Current revision lists CS 2A disch pressure at 125#, yet facility feedback states value revised to 138#, why the difference?
Rev 4: Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 8
H 3
B S
Rev 1: T2/G1, Modify first half question statement to remove: that senses pressure ABOVE the core plate Use of the phrases (clockwise) and (counter clockwise) telegraph the first half answer choice. These phrases are not needed to answer the question and can be removed.
Rev 2: Question revised and SAT 9
H 3
N S
Rev 1: T2/G2, Justification statement does not address what an ALTERNATE position is or why this does not apply to the as-written question. How is this relevant for RWM IE K/A concept?
This question can incorporate LPSP/LPAP for KA match.
(would convert this question to higher cog level)
Rev 2: Question revised and SAT 10 F
3 B
S Rev 1: T2/G1, Question is SAT 11 F
3 N
S Rev 1: T2/G2, Question is SAT 12 H
3 M
(2015 Hatch)
S Rev 1: T2/G1, Revise the starting value for IRMS A -> D to read: 25/125 on Range 6 Revise Answer Choice D to read: 10:10 Rev 2: Question revised and SAT 13 F
3 M
(2017 Hatch)
S Rev 1: T2/G1, Justification statement mentions correct answer for IRM G, was it intended to state IRM H?
Rev 2: Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 14 H
3 B
S Rev 1: T2/G1, Justification write-up for this question is very confusing and fails to address the as-written question.
Modify stem information: As the SRM A detector is being withdrawn, SRM A indication reaches 190 cps.
Modify first half question to read: At the current SRM A indication, a control rod block ____ occurred.
Modify first half answers to read: has/has NOT Retract Permit is a light indication co-located on the DRIVE IN/OUT pushbutton. Im unsure what the justification statement means when it states: the wording on the Retract Permit Pushbutton.
Rev 2: Question revised and SAT 15 F
3 M
(2017 Hatch)
S Rev 1: T2/G1, Question is SAT 16 F
3 N
S Rev 1: T2/G1, Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 17 H
3 M
(2017 Hatch)
S Rev 1: T2/G1, Remove question stem bullet All DC power is available and reword opening statement (since there are no longer any concurrent casualties).
Why is answer choice A incorrect? There is no information provided in question stem to indicate a failure of the ADS Inhibit Switches (only the light indication is provided). Prints H-27472 and H-27473 not provided for review. As written, answer choice A is the correct answer choice since ADS remains inhibited.
Depending on discharge head of CBPs, Answer Choice C may also be correct (RPV pressure of 525# @ T=15).
Not certain of necessity for including graphic for this question. It appears that the intent of this question was to test system response following a failure of ADS lights. ADS system logic status typically communicated using annunciators (e.g. AUTO Blowdown Timers Initiated alarm in/out, AUTO Blowdown Relays Energized alarm in/out, ADS Inhibit Sw in INHIBIT alarm in/out)
Rev 2:
Technical accuracy of question remains, facility research required, potential to modify with additional ADS alarms indicating system inhibited (i.e. alarms dark), answer choice A is correct based on given conditions Rev 4: Reference added, Question revised and SAT.
Annunciator indicator graphic is required to be provided as a reference.
Rev 5: Question revised and SAT 18 H
3 N
S Rev 1: T2/G1, Remove Subsequently, statement from question stem.
C.1/D.1 distractors implausible. Modify first half question statement to read: Upscale indication of ____, will result in automatic isolation of the Fast Drywell Venting path.
Modify first half question choices to read: 2D11-K621A ONLY or 2D11-K621A AND 2D11-K621B Rev 2: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 19 H
3 B
(2013 Hatch)
S Rev 1: T2/G2, With receipt of annunciator 601-333, there is no need to include the information contained in the second bullet.
Remove the second bullet.
First half question statement A Core Spray Jockey Pump, is this meant to imply the A Core Spray Jockey Pump or A Core Spray Jockey Pump? Question on nomenclature.
Rev 2: Question revised and SAT 20 F
3 B
(2015 Hatch)
S Rev 1: T2/G2, Question is SAT 21 F
3 B
(2013 Hatch)
S Rev 1: T2/G2, Question is SAT 22 H
3 N
S Rev 0: T2G1, Revise stem control switch statement to read: An NPO has just completed cycling the control switch for 2B21-F013B, Safety Relief Valve.
Revise justification statements for A and C distractors.
As-written, there is no information provided that the main turbine tripped with bypass valve failed. All that is provided is that MSIVs are closed. Will LLS automatically re-initiate with the justification provided (i.e. RPV pressure @1120 psig, MSIVs closed, LLS logic reset)?
Rev 1: Question is SAT 23 F
3 N
S Rev 1: T2G1, Revise the first half question statement to read: Operation of the SRV tailpipe vacuum breakers, minimizes SRV discharge line __ for subsequent SRV operation.
Rev 2: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 24 F
3 N
S Rev 1: T2G2, Revise question statement to state within two (2) minutes vs the as-written in two (2) minutes Remove cue from question statement,, or the Main Generator will trip.
Revise Answer Choice C to read: 14,000 amps Rev 2: Question revised and SAT 25 H
3 B
(2015 Hatch)
S Rev 1: T2G1, Question is SAT (Ref leg pot D004A feeds LI R606B while D004B feeds R606A/C).
26 H
3 B
(2012 Hatch)
S Rev 1: T2G1, A.1/B.1 distractors are implausible. The as-written question describes normal transient operation of the system. What failure has occurred to imply a shutdown of either U2 SBGT (per justification statements)?
Suggestion to modify to Unit 1 question, supply low flow annunciator and modify first half question to ask how many SBGTs are in service at T=5 minutes. (would convert this question to higher cog level)
Rev 2:
Ensure final answer key/submittal reflects the correct answer choice. No other changes required.
Rev 4: Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 27 H
3 M
(2011 Hatch)
S Rev 1: T2G1, Potential overlap with #74?
First half question is tested elsewhere during the operating test. (overlap, multiple occasions)
Revise given information in the question stem to read:
Unit 2 was operating at 70% RTP when a Station Blackout occurred.
Revise first half question to read: Operator actions are required to be performed FIRST IAW 34AB-C71-001-2, Scram Procedure / 34AB-R22-003-2-100, Station Blackout Abnormal.
Revise second half question to read: IF entry is required, the 34AB-R22-002-2, Loss of 4160V Emergency Bus, step for ensuring affected buses have auto-started ___ an Immediate Operator Action.
Revise justification statement. (would convert this question to higher cog level)
Rev 2: Question revised and SAT 28 F
3 B
(2009 Hatch)
S Rev 1: T2G1, This question can be converted to a 1x4 format (de-conflict answer with Q29 stem). Remove first half question and revise answer choices for second half question to read:
o 120/208 V Essential Cabinet 2A o
600 V Essential Bus 2C o
600 V Essential Bus 2D o
240 V Vital AC Battery Rev 2: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 29 H
3 N
S Rev 1: T2G1, Justification statement for C distractor in error (refers to Bus D).
Revise question stem to include the following statement:
Subsequently, operators receive annunciator 240V VITAL AC BATT VOLTS LOW, 651-133.
Remove the following from the first half question statement, If the voltage from the Vital AC Batteries lowers to 206VDC Incorrect answer appears to be keyed for this question.
Annunciator response for 651-133-2 states that operator is to Transfer Vital AC load to Alternate Source per 34SO-R25-002-2. (Version 1.1, pg 35) Correct answer appears to be answer choice C.
Why does the question refer to 2R25-S063 as both Vital AC (in stem) and as Vital AC Bus (in second half question)? Which is it? Should only be present once.
Unsure how the second half question relates to the K/A or to the concept being tested (i.e. apply (UPS) system limits/precautions). 34AB-N21, Loss of FWH IOAs?
Additionally, what if the shift reactivity briefing sheet specifies performance of Step 3.1 IOA differently, could the second half answer be disputed?
It appears that modification to second half question is required. Ensure changes result in higher cognitive level question LOK.
Rev 2: Question revised and SAT 30 F
3 B
(2015 Hatch)
S Rev 1: T2G1, There appears to be a space missing (?) or just capitalization (?) in the Based on statement after the term 125 VDC And Rev 2:
Revise first half question answer choices to read: equal to
/ higher than Revise first half question to remove the word than after underline Rev 4: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 31 F
3 N
S Rev 1: T2G1, Remove the words for RWL control from second half question statement.
Rev 2: Question revised and SAT 32 F
3 B
(2016 Hatch)
S Rev 1: T2G1, Answer choices A.1/B.1 are technically correct. A reverse power trip is caused by a differential current.
Revise these answer choices to read: differential voltage Rev 2: Question revised and SAT 33 F
3 N
S Rev 0: T2G2, Revise 1st half question answers to read: did & did NOT (match tense to question statement)
Justification statements for first half question dont match.
Statements claim plausibility due to ability to isolate instrument sumps from FD sumps, yet question is asking if RB sump pumps AUTO trip on high level in FDCT. A more appropriate plausibility statement would indicate that a high-level condition in some tank results in AUTO trip of feeding pump discharge.
Rev 1: During question changes, subsequent alarm information designation for FDCT Hi Lvl alarm was cut-off G11-201-2, add this back in.
Rev 2: Question revised and SAT 34 H
3 N
S Rev 0: T2G2, Question is SAT Rev 1: Question modified following pre-submittal comments, Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 35 F
3 N
S Rev 0: T2G2, Somewhat confusing stem information: current weather conditions low teens and outside air temp is 39F Modify the provided information to read: Todays weather forecast for our area is high winds with anticipated outside ambient temperature in the low teens. The outside air temperature is currently 39F and slowly lowering.
Remove and complied with from 1st half question statement.
Rev 1: Question is SAT 36 H
3 B
(2011 Hatch)
S Rev 1: T2G2, Question is SAT 37 H
3 B
(2013 Hatch)
S Rev 1: T1G1, Reference Revise References provided in 401-5 information to include an unmodified copy of the N/F map.
Revise the question to add that a reference is provided.
Revise the References provided document to include a larger copy of the same N/F map used in the question (i.e.
without the points or limiter setpoints).
34SO-B31-001-1 does not include criteria that specifies the 78% load line (vs the MELLA load line) will be followed during a RRP runback. I dont think the questions IAW procedure is correct.
Rev 2: Question is SAT 38 H
3 M
(2017 Hatch)
S Rev 1: T1G1, Since 34AB-R22-003-1 is a Unit 1 procedure, there is no need to include the verbiage On Unit 1 for the first half question. These words can be removed from first half question statement.
Rev 2: Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 39 H
3 M
(2019 Hatch)
S Rev 1: T1G1, Reference Using the 34AB-R42-001-0 tables, there is no plausible reason to select answer choices C.1/D.1 (25 k) as these do not correspond to any combination of given switch position indications for any of the provided DC Bus tables.
In effect, this half question is a direct lookup with little discriminatory value.
First half question requires modification. Ensure modification results in a higher cognitive LOK.
One option for repair would be to ask which bus the ground is on (would require both pictures to be in the same direction and answer choices P Bus or N Bus).
Rev 2:
Reference is no longer required to answer this question since ground resistance determination removed. Remove reference 34AB-R42-001-0, Attachment 2 pages. (6 pages total) (cueing, direct lookup)
Rev 3:
8k ground provided, two half questions - 1st related to single/multiple grounds and effects, 2nd related to can/cannot exit procedure in effect (to be provided)
Rev 4: Question revised and SAT, ensure Reference removed (no longer required)
Rev 5: Reference removed 40 F
3 M
(2011 Hatch)
S Rev 1: T1G1, Provide 401-5 information which explains why answer choices A and B would have been correct prior to the 2020 outage.
Remove the wording (1A thru 1G) from question statement.
Reassess question based on revised 401-5.
Rev 2:
Changes incorporated, still require 401-5 information to assess answer choices Rev 4: Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 41 F
3 x
M (2011 Hatch)
S Rev 1: T1G1, The only parameter exceeding an EOP entry/SCRAM condition is RPV pressure. The additional information provided for each parameter in parenthesis is not required to answer the question.
Remove the (xxx reached) information from each stem parameter.
Rev 2: Question revised and SAT 42 F
3 N
S Rev 1: T1G2, Question is SAT 43 H
3 B
(2009 Hatch)
S Rev 1: T1G2, Question is SAT 44 H
3 M
(2017 Hatch)
S Rev 1: T1G2, Since PCC SP/T entry (100F Torus Temp) directs SPC IAW 34SO. Based on procedure use rules at Plant Hatch, should answer choice C be keyed as the correct answer?
Rev 2: Question is SAT 45 F
3 M
(2016 Hatch)
S Rev 1: T1G2, Question is SAT 46 F
3 M
(2016 Hatch)
S Rev 1: T1G1, Question is SAT 47 H
3 B
(2013 Hatch)
S Rev 1: T1G1, Revise the first half question statement to read, Based on the above conditions, annunciator HX PSW/RBCCW DIFF PRESS LOW, (650-238), _____ be ILLUMINATED.
Revise second half question to include the procedure in use: IAW 34SO-P42-001-2, to return PSW/RBCCW Hx dP to its original value, the SO will throttle 2P41-F491 in the
_____ direction.
Rev 2: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 48 F
3 M
S Rev 1: T1G1, Revise second half question statement to remove the word valves following the underline ___.
Revise answer choices B.2/D.2 to remove Supply Fans Disch verbiage.
Rev 2: Question revised and SAT 49 F
3 B
(2015 Hatch)
S Rev 1: T1G1, Answer choices A.1/C.1 are invalid distractors as technically, they are correct answers (increased inventory required for nat circ). This question can still validly hit the K/A by testing the amount of RWL rise required during the SDC casualty specified in the initial conditions.
Revise first half question to read: During recovery of RWL, the ___ instrument will be used to confirm desired level.
(answer choices R605/R606A) Ensure this becomes the second half question. (change answer choice assignments)
Revise the new first half question to read: RWL ___ be raised to a MINIMUM of 53 inches. (answer choices will/will NOT). Ensure 401-5 information updated.
Rev 2: Question revised and SAT Question remains (F)undamental cog level since 53 cold instrument level correction (i.e. 15) isnt used to answer this question, merely instrument selection and min RWL for nat circ. If desired to incorporate this concept (to make it high cog), question would have to be modified to ask (as an example) which one of the following instruments requires level correction. This is a tricky concept to make higher cog since RWL instruments are already designated as cold water vs hot water calibrated.
50 H
3 B
(2011 Hatch)
S Rev 0: T1G2, Question is SAT Rev 1: Question revised following pre-submittal comments, Question is SAT 51 H
3 M
(2011 Hatch)
S Rev 1: T1G1, Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 52 H
3 M
(2017 Hatch)
S Rev 1: T1G1, Question is SAT 53 H
3 B
(2016 Hatch)
S Rev 1: T1G1, Question is SAT 54 F
3 B
(2015 Hatch)
S Rev 1: T1G1, 120F Torus temperature not used as setpoint with regards to PCC or RC. Listed justification for answer choices B.1/D.1 invalid based on given question conditions.
Revise answer choices B.1/D.1 to read 101F. Justification is SPC threshold in SP/T leg of PCC. No other changes.
Rev 2: Question revised and SAT 55 H
3 B
(2011 Hatch)
S Rev 1: T1G1, Remove teaching cue in the question stem, resulting in a reactor scram.
Remove cue in first bullet, (all control rods did NOT fully insert). Rod configuration already implied due to 3%
power after ten minutes.
Rev 2: Question revised and SAT 56 H
3 M
(2017 Hatch)
S Rev 1: T1G1, Reference, Question is SAT 57 H
3 M
(2019 Hatch)
S Rev 1: T1G1, Question is SAT 58 F
3 M
(2019 Hatch)
S Rev 1: T1G2, Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 59 H
3 M
(2011 Hatch Audit)
S Rev 1: T1G2, Justification statement indicates that Answer Choice B would be a correct answer, yet D is keyed as correct. I believe the justification should be modified to state this is incorrect since the C001A fan would not be in a tripped state (i.e. breaker still shut with sheared shaft, like the reasoning used for Answer Choice C)
Is there a low flow trip for the U2 RB Exhaust fans? (not addressed in justification statement)
Revise Answer Choice B to read: remain relatively the same since 2T41-C001A tripped; 2T41-C001B and 2T41-C007B have automatically started Rev 2:
Changes incorporated Remove the phrases (less negative) from answer choices C and D (teaching cue that RB dp is initially negative)
Provided phrase trend towards is sufficient to describe answer choices Rev 4: Question revised and SAT 60 H
3 B
(2015 Hatch)
S Rev 1: T1G1, Revise the second half question to read: During performance of 31EO-EOP-017-2, CP-3 ATWS LEVEL Control, RWL will be controlled to ensure ___
Revise answer choices A.2/C.2 to read: core inlet subcooling is LOWERED Revise answer choices B.2/D.2 to read: core void fraction is RAISED Rev 2: Question revised and SAT (now high cog based on edits) 61 F
3 M
(2016 Hatch)
S Rev 1: T1G1, Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 62 F
3 M
(2017 Hatch)
S Rev 1: T2G1, The question stem implies that automatic plant response is being asked after component re-alignments are complete.
The first half question & answers imply that automatic plant response has yet to occur. This is confusing. Based on how the stem is constructed perform the following revisions.
Revise first half question to read: The Non-Essential Instrument Air Header Isolation Valve, 2P52-F015, is ___.
Revise Answer Choices A.1/B.1 to read: Open Revise Answer Choices C.1/D.1 to read: Closed Rev 2: Question revised and SAT 63 F
3 M
(2016 Hatch)
S Rev 1: T2G1, Question is SAT 64 F
1 M
(2019 Hatch)
S Rev 1: T1G1, Remove the control board graphic as it is not needed to answer this question.
As-written first half question is implausible. Do any facility procedures permit any plant equipment to remain energized while on fire? Additionally, since the question states that the incoming (normal) breaker was opened IAW plant procedures, the correct first half answer is provided by the question stem itself.
A new first half question is required Rev 2: Question revised and SAT 65 H
3 M
(2017 Hatch)
S Rev 1: T1G1, Revise second bullet of question stem to read: 230 KV switchyard voltage 231 KV and lowering Revise second half question to read: If the 230 KV switchyard voltage trend continues, 4160 VAC Bus 1E
_____ to its associated EDG.
Revise Answer Choices A.2/C.2 to read: will AUTOMATICALLY transfer Revise Answer Choices B.2/D.2 to read: must be MANUALLY transferred Rev 2: Question revised and SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 66 F
3 B
S Rev 1: T3, Question is SAT 67 F
3 B
(2013 Hatch)
S Rev 1: T3, Revise given unit power from 100% RTP to 25% RTP.
Revise second half question to read: At the current power level and IAW 34SO-B31-001-2, Reactor Recirculation Remove the word constant from the second half question as its use implies the correct answer.
Rev 2: Question revised and SAT 68 F
3 N
S Rev 1: T3, Question is SAT 69 F
3 B
S Rev 1: T3, Revise the first half question statement to read: Currently, the unit is in ____.
Revise the second half question statement to read: With ALL of the reactor vessel head bolts fully tensioned and the Reactor Mode Switch in REFUEL, the unit will be in ____.
Rev 2: Question revised and SAT 70 F
3 B
(2012 Hatch)
S Rev 1: T3, Question is SAT 71 F
3 B
(2016 Hatch)
S Rev 1: T3, Question is SAT 72 F
3 B
(2011 Hatch)
S Rev 1: T3, Question is SAT This question is identified as a Modified question.
However, no significant modification has been performed to this question from the version administered in 2011.
73 H
3 M
(2019 Hatch)
S Rev 1: T3, Question is SAT
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 74 H
3 M
(2013 Hatch)
S Rev 1: T3, Potential overlap with #27?
The second half question is a tack-on that has no K/A applicability.
Revise given DW pressure to be 2.0 psig Remove 34AB and 31EO procedures (i.e. remove 4th and fifth bullets)
Revise first half question to read: Actions in _____ take precedence over actions in any other procedure.
Remove second half question and all second half answer choices. (convert question to 1x4)
Revise Answer Choice B to read: 34AB-R22-002-2, Loss of 4160V Emergency Bus Revise Answer Choice C to read: 31EO-EOP-010-2, RC Flow Chart Revise Answer Choice D to read: 31EO-EOP-012-2, PC Flow Chart With the above modifications, this becomes (H)igher cognitive level question.
Rev 2: Question revised and SAT (higher cog modification) 75 F
3 B
S Rev 1: T3, Answer Choices B.2/D.2 are non-credible Revise Answer Choices B.2/D.2 to read: this valve is on the Technical Requirements Manual (TRM) Master Equipment Cross Reference list Rev 2: Question revised and SAT
76 H
3 N
S Rev 1: T2G1, Reference Question statements are leading (cueing) based on use of phrases Risk Assessment & limitations on changes.
Remove Based on the above sentence from the question stem.
Revise first half question to read: Based ONLY on the above conditions and IAW Technical Specifications, placing the Reactor Mode Switch to RUN _____
ALLOWED, IAW TS LCO _____.
Remove second half question.
Rev 3:
Revise question statement to include no risk assessments have been performed Rev 4: Question revised and SAT 77 H
3 B
(2013 Hatch)
S Rev 1: T2G2, Remove window dressing from question stem (first three sentences).
Revise opening statement to read: Unit 2 is in a refueling outage with control rod 26-27 previously declared inoperable and disarmed at position 00.
Remove the cue in second half question statement. Delete these words from the second half question: to permit refueling operations to proceed.
Rev 3: Question revised and SAT 78 H
3 N
S Rev 0: T2G2, Revise 2nd half question statement to read: At 11:00 on 6/10 and Add NOTE with title of TLCO 3.3.10.
Rev 1: Question is SAT 79 F
3 M
S Rev 1: T2G1, Revise given power level to read 29% RTP Revise first half question to read: Based on the conditions above, TS 3.3.2.2, Feedwater and Main Turbine High Water Level Trip Instrumentation, _____ currently APPLICABLE.
Rev 3: Question revised and SAT
80 F
3 N
S Rev 1: T2G1, This question doesnt currently hit the K/A at the SRO level as there is no tie to SBGT operation present.
One way to hit Containment Pressure with SBGT (procedurally) is using the TS Bases.
As an example: Unit 1 is operating End-Of-Cycle at 80%
RTP (prior to a refueling outage). Based on the conditions above, the basis for TS 3.6.4.3, Standby Gas Treatment (SGT), applicability is to mitigate the consequences of a fission product leak following a ___.
Fuel handling Accident o
Loss of Coolant Accident o
Failure of Secondary Containment Integrity Rev 3: Question replaced and SAT
81 H
N S
Rev 0: T2G1, Watts/VARS indications provided could be reflective of either running unloaded (post EDG output breaker open) or EDG tripped. There doesnt appear to be sufficient information provided in the stem (specifically regarding EDG output breaker status) to arrive at the correct answer.
The 2nd half question is worded in a way that cues the first half answer to tripped (i.e. stated that 3.8.1 is MET for INOP EDG 2A).
According to TS 3.8.1 (and Bases), inhibiting of EDGs is never required. TS completion times for Condition B allows completion time extensions (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days) when using EDG inhibiting. Otherwise more restricted completion time still exists when not using EDG inhibit. As-written, there doesnt appear to be a single correct answer for the 2nd half question.
Rev 1: Question revised Would the SO take action to bar an EDG that was running unloaded (provided 11:30 information, plausibility of A.1/B.1)? Why is this information included in question, i.e. what value does it add?
Justification information needs to be updated. It is not clear how SR 3.8.1.1 ties into 34SV-R43-001-2 performance. Or why the answer selected is correct. 3.8.1.1 is not credited during 34SV-R43-001-2 (per SV purpose).
Not enough information available to evaluate this question.
Rev 3:
Question revision in progress, second half question overlap with #96 (SR 3.0.2), candidate for HCL?
Rev 4: now has Reference Revise first half question to read: ____ trip on REVERSE POWER.
Add bullet under 1005 to read: Maintenance reports that 2A EDG will remain out of service for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Revise second half question to read: At 1605, the plant
____ REQUIRED to have entered Tech Spec LCO 3.0.3.
Now HCL Rev 5: Question revised and SAT
82 H
3 N
S Rev 0: T2G2, Reference Plausibility statements for 1st half question dont match requested information. RCS leakage from a primary system (3.C) is assessed for the Containment Barrier portion of the FP Barrier Matrix. There are no conditions in the question stem that identify any issue with containment barrier. The only plausible FP Barrier Matrix criteria available is loss/potential loss of the Fuel Clad Barrier portion (since unisolable leak is in SF pool). Additionally, radiation values provided do not rise above Max Safe values for consideration in 3.C. (Cred Distr)
Incorrect answer cued for Q82. As-written, the correct answer choice is answer choice C (based on alarming Table R1 monitors, RA2 criteria 2)
Remove the word Emergency from end of 2nd half question statement To correct distractor issue identified above, revise provided 2D21-K601M reading to be: 1500 mr/hr Revise 2nd half answer choices to read: Site Area Emergency/Alert With changes incorporated above, plausibility for 1st half question becomes entry into FS1/FA1 (RCS 3.A/Containment 3.C) vs RA2 (criteria 2)
Rev 1: Question is SAT
83 H
3 B
(2009 Hatch)
S Rev 0: T1G1, Reference Why is RRP speed (48%) mentioned in question stem and as a bullet. Can be removed from question stem Revise specific Jet Pumps used for d/p to be Loop B Jet Pumps (i.e. Jet Pumps 15 and 16) in question stem Rev 1:
First half question is only asking for one concept, whether the applicant can identify whether JP flow mismatch is a 3.4.1 requirement. Since JP flow mismatch is provided as a given condition, question can be revised.
Revise first half question to read: IAW Tech Spec Bases, the indicated differential pressure mismatch exceeds applicability criteria for T.S. _____.
Revise first half answer choices to read: 3.4.1 / 3.4.2 Revise given Jet Pumps to be Loop B Jet Pumps (i.e. 15 and 16) in question stem. (plausibility of A.2/C.2)
Rev 3: Question statements revised Remove second line of question statement: Reactor power stabilizes at 57% RTP with the following indications:
Inclusion of LCO 3.4.1 reference makes first half question a direct lookup with little to no discriminatory value. LCO 3.4.1 reference can be removed.
Rev 4: TS LCO 3.4.1 Reference can be removed, Reference still provided for question (TS LCO 3.4.2 non-surveillance remains),
Question is SAT Rev 5: Question (references) revised and SAT 84 H
3 N
S Rev 0: T1G2, Remove 34SO-N71-001-1 from question stem as pointing out this procedure is not necessary for the question Second half question tests specific procedure steps of an abnormal procedure. Revise second half question/answers to read: 34AB-N71-001/34AB-N71-001-1 contains the required steps to open the associated vent valves.
Revise SRO justification to be based on procedure selection Rev 1: Question is SAT
85 H
3 M
(2016 Hatch)
S Rev 1: T1G1, Use of plural language and stated direction to trip RFPTs in the second half question stem cues Answer Choice A.2/C.2, removing plausibility for B.2/D.2.
Revise second half question to read: When procedurally directed to modify RFPT alignment, trip pushbuttons are to be used to trip only ONE / both RFPT(s).
Rev 3: Question revised and SAT 86 H
3 N
S Rev 1: T1G1, Question is SAT 87 H
3 N
S Rev 1: T1G1, Correct procedure to use is cued by question statement, (i.e. IAW 34AB-P51-001-2), to correct, revise question stem to state: Based on the above conditions, which ONE of the choices below completes the following statements?
Rev 3: Question revised and SAT 88 H
3 M
(2012 Hatch)
S Rev 1: T1G1, Conditions stated in this question are unclear. Question stem states that Torus level is lowering due to an event concurrent with loss of most injection capability (SLC, condt). Additionally, RWL has been lowered. Wouldnt the plant have already performed an ED with these conditions (RC/L leg of RC chart when < -155 inches)?
Its likely that HPCI wouldnt be running due to low d/p at this point anyway. Is there a potential that A.1/C.1 could be construed as correct? Appears to me that the only disqualifier is prevented from operating, but that doesnt make sense since terminate/prevent is an ATWS-driven concept. Confirm isolation perhaps?
Can the second half question stem be re-tooled to remove the loss of RWL casualty so that the concept tested is solely use of the RC chart SP/L leg? (perhaps having the applicant identify use of either 102/115 SP lvls)
Rev 3: Reference Question revised; insert the word value after EAL threshold.
Rev 4: Question revised and SAT
89 H
3 B
(2012 Hatch)
S Rev 1: T1G1, Reference Answer choices A.1/B.1 are implausible as there is no physical tie directly between RHR and Fire Water system piping. This can be modified as ask which section of 31EO-EOP-110-1 is used for FW injection (i.e. RHR/LPCI vs RHR/RR injection piping flowpaths). Potential to convert this to higher cog question.
Use of the term maybe could be construed as meaning is likely (EAL SG1). High applicant risk based on use of imprecise wording to interpret EALs and potentially multiple correct answers.
Revise the fourth bullet at time 10:10 to read:
Maintenance reports that one (1) EDG will be in service by 15:00. In order to ensure hitting the RWL aspect of this K/A.
Revise RWL at time 10:20 to read: RWL (-) 200 inches, steady (no need to include a RWL rate at 10:10 and can be removed)
Rev 3: Question replaced Revise time 10:10 to read 10:15 for plausibility of SAE distractor.
Remove the words: during the event from first half question statement.
No other changes Rev 4: Question revised and SAT 90 H
3 B
(2011 Hatch)
S Rev 1: T1G2, Question is SAT 91 H
3 M
(2013 Hatch)
S Rev 1: T1G2, Question is SAT 92 F
3 B
S Rev 1: T2G1, Question is SAT 93 F
3 N
S Rev 1: T1G1, Reference, Question is SAT 94 F
3 N
S Rev 1: T3, Question is SAT 95 F
3 B
(2016 Hatch)
S Rev 1: T3, Question is SAT
96 F
3 B
(2011 Hatch)
S Rev 1: T3, Question is SAT 97 F
3 M
S Rev 1: T3, Correct spelling of the word annunciator in 2nd sentence of question stem.
Based on the wording contained in 31GO-OPS-014-0, the Shift Manager/SS are always the lowest organizational levels to supervise/approve deactivation of annunciators.
Whether its due to being a distraction or not. How is the Operations Support Manager a plausible choice here?
A more appropriate first half question to ask here may be:
A 50.59 screening evaluation is / is NOT REQUIRED to be completed prior to deactivating this annunciator.
To ensure plausibility, ensure the following is included in the first sentence: Safety-related annunciator XYZ-101 is alarming repeatedly and creating a distraction to the operating crew.
PRB review of safety related annunciators (14 day requirement) is also another concept that can be tested to this K/A.
Rev 3: Question revised Use of LOWEST vs HIGHEST doesnt remove the plausibility issue with the first half question.
Revise first half question to read: Following approval of the Compensatory Action, the manager responsible for approving the de-activation of Annunciator XYZ-101 is Rev 4: Question revised and SAT 98 F
3 B
(2015 Hatch)
S Rev 1: T3, Question is SAT 99 F
3 M
(2017 Hatch)
S Rev 1: T3, Include the noun names of each procedure as a Note:
31-EO-EOP-015-1, CP-1 Alternate Level Control, Steam Cooling, & Emergency RPV Depressurization 31EO-SAG-001-1, Reactor Vessel and Primary Containment Flooding Rev 3: Question revised and SAT
100 F
3 M
(2011 Hatch)
S Rev 1: T3, Potential for multiple correct answers if applicant makes an unstated assumption that > 30 minutes may have passed.
Revise opening question statement to read: Security just notified the control room that armed intruders penetrated the PA five minutes ago and are Rev 3: Question revised and SAT