ML22111A344

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E.I. Hatch 2021-302 2A-3 Admin
ML22111A344
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/21/2022
From:
NRC/RGN-II
To:
Southern Nuclear Operating Co
References
Download: ML22111A344 (50)
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Text

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

Facility: E. I. HATCH Date of Examination: 12/06/2021 Examination Level: RO SRO Operating Test Number: 2021-302

Administrative Topic (see Note) Type Describe activity to be performed Code*

Conduct of Operations RO Admin 1 D, R Heat Stress - Determine the Adjusted WBGT. G2.1.26 (3.4)

Conduct of Operations Calculate Four (4) Doublings For Control RO Admin 2 M, R Rod Movement IAW 34GO-OPS-001-2.

G2.1.37 (4.3)

Equipment Control RO Admin 3 D, R Determine the effect of the failure of a relay on system performance. G2.2.41 (3.5)

Radiation Control the RWP and survey map. G2.3.4 (3.2)

RO Admin 4 M, R Given a set of exposure conditions, evaluate

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 Administrative Topics Outline Form ES-301-1

Facility: E. I. HATCH Date of Examination: 12/06/2021 Examination Level: RO SRO Operating Test Number: 2021-302

Administrative Topic (see Note) Type Describe activity to be performed Code*

Conduct of Operations SRO Admin 1 D, R Determine Minimum Crew Staffing. G2.1.5 (3.9)

Conduct of Operations Determine the current Reactor mode and if SRO Admin 2 D, R Core Alterations can be performed.

G2.1.36 (4.1)

Equipment Control SRO Admin 3 M, R TRM/TS Evaluation Of Failed RWL Instruments G2.2.22 (4.7)

Radiation Control Given an inoperable ODCM Effluent Radiation SRO Admin 4 N, R detector, determine the required actions.

G2.3.11 (4.3)

Emergency Plan SRO Admin 5 D, R Determine PARS with Impediments G2.4.38 (4.4)

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

  • Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 (3) for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1) (2)

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

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

Facility: Plant E.I. Hatch Date of Examination: 12/6/2021

Exam Level: RO SRO-I SRO-U Operating Test Number: 2021-302

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 - Withdraw Control Rods SF-1 (Alternate Path for Uncouple) A, EN, D, S Reactivity Control 201003A2.02 (3.7/3.8)

CR/SIM 2 - Perform RC-2, HPCI Injection (Alternate SF-2 Path - Leak) A, EN, M, L, S Reactor Water Inventory Control 295031EA1.02 (4.5/4.5)

CR/SIM 3 - Override and Open Plant Service Water SF-8 Isolation Valves (Alt Path for Break in Turbine Building) A, D, L, S Plant Service Systems 295018AA2.05 (2.9/2.9)

CR/SIM 4 - Emergency Depress The Reactor Using HPCI E, EN, N, S SF-4 Heat Removal From the Core 295025EA1.04 (3.8/3.9)

CR/SIM 5 - Perform a Manual Initiation of Drywell SF-5 Sprays (Alternate Path - No flow) A, EN, D, L, S Containment Integrity 226001A4.03 (3.5/3.4)

CR/SIM 6 - Perform A Diesel Generator Manual Start SF-6 Surveillance (Alt Path) A, D, EN S Electrical 264000A4.04 (3.7/3.7)

CR/SIM 7 - IRM Instrument Failure, (Alternate Path) SF-7 Perform RC-1 A, EN, N, S Instrumentation 215003A3.03 (3.7/3.6)

SF-9 CR/SIM 8 - Swap Turbine Building Ventilation Fans D, S Radioactivity Release 288000A4.01 (3.1/2.9)

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U PLANT 1 - Align Emergency Nitrogen To U1 Drywell SF-3 Pneumatics D, E, L, R Reactor Pressure Control 218000A2.03 (3.4/3.6)

SF-6 PLANT 2 - Startup The RPS 120 VAC System D, EN, Electrical 212000A1.01 (2.8/2.9)

SF-8 PLANT 3 - Crosstie U2 Reactor Bldg Plant Service Water D, E, L, R Plant Service Systems 295018AA1.01 (3.3/3.4)

  • 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.
  • Type Codes Criteria for RO /SRO-I/SRO-U ES-301 Control Room/In-Plant Systems Outline - Form ES-301-2

(A)lternate path 4-6 (6) / 4-6 / 2-3 (C)ontrol room 0 (0) / 0 / 0 (D)irect from bank 9 (8) / 8 / 4 (E)mergency or abnormal in-plant 1 (2) / 1 / 1 (EN)gineered safety feature 1 (7) / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1 (5) / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 (3) / 2 / 1 (P)revious 2 exams 3 (0) / 3 / 2 (randomly selected)

(R)CA 1 (2) / 1 / 1 (S)imulator

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

Facility: Plant E.I. Hatch Date of Examination: 12/6/2021

Exam Level: RO SRO-I SRO-U Operating Test Number: 2021-302

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 - Withdraw Control Rods SF-1 (Alternate Path for Uncouple) A, EN, D, S Reactivity Control 201003A2.02 (3.7/3.8)

CR/SIM 2 - Perform RC-2, HPCI Injection (Alternate SF-2 Path - Leak) A, EN, M, L, S Reactor Water Inventory Control 295031EA1.02 (4.5/4.5)

CR/SIM 3 - Override and Open Plant Service Water SF-8 Isolation Valves (Alt Path for Break in Turbine Building) A, D, L, S Plant Service Systems 295018AA2.05 (2.9/2.9)

CR/SIM 4 - Emergency Depress The Reactor Using HPCI E, EN, N, S SF-4 Heat Removal From the Core 295025EA1.04 (3.8/3.9)

CR/SIM 5 - Perform a Manual Initiation of Drywell A, EN, D, L, S SF-5 Sprays (Alternate Path - No flow) Containment Integrity 226001A4.03 (3.5/3.4)

CR/SIM 6 - Perform A Diesel Generator Manual Start SF-6 Surveillance (Alt Path) A, D, EN S Electrical 264000A4.04 (3.7/3.7)

CR/SIM 7 - IRM Instrument Failure, (Alternate Path) SF-7 Perform RC-1 A, EN, N, S Instrumentation 215003A3.03 (3.7/3.6)

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

PLANT 1 - Align Emergency Nitrogen To U1 Drywell SF-3 Pneumatics D, E, L, R Reactor Pressure Control 218000A2.03 (3.4/3.6)

SF-6 PLANT 2 - Startup The RPS 120 VAC System D, EN, Electrical 212000A1.01 (2.8/2.9)

SF-8 PLANT 3 - Crosstie U2 Reactor Bldg Plant Service Water D, E, L, R Plant Service Systems 295018AA1.01 (3.3/3.4)

  • 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.
  • Type Codes Criteria for RO /SRO-I/SRO-U

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

(A)lternate path 4-6 / 4-6 (6) / 2-3 (C)ontrol room 0 / 0 (0) / 0 (D)irect from bank 9 / 8 (7) / 4 (E)mergency or abnormal in-plant 1 / 1 (2) / 1 (EN)gineered safety feature 1 / 1 (7) / 1 (control room system)

(L)ow-Power/Shutdown 1 / 1 (5) / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 (3) / 1 (P)revious 2 exams 3 / 3 (0) / 2 (randomly selected)

(R)CA 1 / 1 (2) / 1 (S)imulator

ES-301 Transient and Event Checklist Form ES-301-5

Facility: E. I. HATCH Date of Exam: 12/06/2021 Operating Test No.: 2021-302 A E Scenarios P V 1 2 3 T M P E O I L N CREW CREW CREW N I T POSITION POSITION POSITION T I C S A B S A B S A B A M A T R T O R T O R T O L U N Y O C P O C P O C P M(*)

T P E R I U RO RX 2 2 2 3 1 1 0 X NOR 1 1 1 3 1 1 1 SRO-I I/C 4,6 3,5 4,6 3,5 3,5 4,6 12 4 4 2

SRO-U MAJ 7 7 7,8 7,8 7,8 7,8 5 2 2 1 TS NA NA NA NA NA NA NA 0 2 2 RO RX 2 2 2 3 1 1 0 NOR 1 1 1 3 1 1 1 SRO-I I/C 3,4, 3,4, 3,4, X 5,6 5,6 5,6 12 4 4 2 SRO-U MAJ 7 7,8 7,8 5 2 2 1 TS 4,6 3,5 3,4 6 0 2 2

RO RX 1 1 0 SRO-I NOR 1 1 1 I/C 4 4 2 SRO-U 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 controlledabnormal conditions (refer to SectionD.5.d) but must be significant per SectionC.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 Transient and Event Checklist Form ES-301-5

Facility: E. I. HATCH Date of Exam: 12/06/2021 Operating Test No.: 2021-302 A E Scenarios P V 4 5 T M P E O I L N CREW POSITION CREW POSITION N I T S A B S A B T I C R T O R T O A M A T O C P O C P L U N Y M(*)

T P E R I U RO RX 6 4 2 1 1 0 X NOR 1 1 2 1 1 1 SRO-I I/C 3,4 2,5 3,5 2,7 8 4 4 2

SRO-U MAJ 7 7 8 8 2 2 2 1 TS NA NA NA NA NA 0 2 2 RO RX 6 4 2 1 1 0 NOR 1 1 2 1 1 1 SRO-I I/C 2,3, 2,3, X 4,5 5,7 8 4 4 2 SRO-U MAJ 7 8 2 2 2 1

TS 3,4,5 2,6 5 0 2 2 RO RX 1 1 0 SRO-I NOR 1 1 1 I/C 4 4 2 SRO-U 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) b ut 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 chi ef 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

Facility: E. I. HATCH Date of Examination: 12/06/2021 Operating Test No.: 2021-302

APPLICANTS RO RO SRO-I SRO-I SRO-U SRO-U

Competencies SCENARIO SCENARIO

1 2 3 4 5 Interpret/Diagnose 2,3,4,5, 2,3,4,5, 2,3,4,5, 2,3,4, 2,3,4,5, Events and Conditions 6,7,8 6,7,8,9 6,7,8,9 5,6,7,8 6,7,8,9

Comply with and 1,2,3,4, 1,2,3,4,5, 1,2,3,4,5, 1,2,3,4, 1,2,3,4,5, Use Procedures (1) 5,6,7,8 6,7,8,9 6,7,8,9 5,6,7,8 6,7,8,9

Operate Control 1,2,3,4, 1,2,3,4,5, 1,2,3,4,5, 1,2,3,4, 1,2,3,4,5, Boards (2) 5,6,7,8 6,7,8,9 6,7,8,9 5,6,7,8 6,7,8,9

Communicate 1,2,3,4, 1,2,3,4,5, 1,2,3,4,5, 1,2,3,4, 1,2,3,4,5, and Interact 5,6,7,8 6,7,8,9 6,7,8,9 5,6,7,8 6,7,8,9

Demonstrate N/A N/A N/A N/A N/A Supervisory Ability (3)

Comply with and N/A N/A N/A N/A N/A Use TS (3)

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.)

ES-301 Competencies Checklist Form ES-301-6

Facility: E. I. HATCH Date of Examination: 12/ 06/2021 Operating Test No.: 202 1-302

APPLICANTS RO RO SRO-I SRO-I SRO-U O -U

Comtei IO IO

1 2 3 4 5 I/Dinos Events Ctis 8 9 9 8 9

Cy witand UsProc (1) 8 9 9 8 9

OperCor Boar ( 8 9 9 8 9

Cmunice Iact 8 9 9 8 9

Dotr Svisy Ality ( 8 9 9 8 9

Cy witand 4,6 5 4 5 6 UsTS (

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.)

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

Facility Hatch Exam Date: Dec 2021 1 2 3 4 5 6 ADMIN Attributes Job Content Admin JPMs Topic LOD U/E/S Explanation and K/A (1 - 5) I/C Critical Scope Perf.

Focus Cues Steps (N/B) Overlap Std. Key Minutia Job Link

RO A1a G 2.1.26 >1 E Could we tell them that the job is considered light work?

Have them list the limitations and ask what the stay time would be?

Procedure states that the SRO shall do this. JPM SAT as written. D rl 12/1/2 021 RO A1b G2.1.23 1 U We need to talk about this one. I agree that it is important, but this does not provide any insight into their understanding of plant operation.

Also, this is more like equipment control than COO

Licensee agrees. JPM being rewritten. Drl 10/22/2021

JPM rew ritten. Now SAT. drl 12/1/202 1 RO A2 G2.2.41 2 S RO A3 G2.3.4 2 E Change question 3 to What RWP limits, if any, are expected to be exceeded?

Changed as discussed abo ve. Drl 10/22/2021 SRO A1a G2,1,5 2 E Change question 1 to read Does the crew.

Technicians). If not what pos ition or positions need filled?

Change question 3 to Assum e a ny positions required to be filled in question 1 has been met. If Mike has a medical, IAW Plant Hatch administrative procedure, what actions, if any, need to occur?

Essentially changed as discus sed. Drl 10/22/2021 SRO A1b G2.1.36 3 S SRO A2 G2.2.22 2 X E How is this different than evaluating TS during the scenarios? This may be an exam overlap issue.

It is a different TS evaluation than any of the scenario JPMs. This does meet all of the requirements for a valid JPM. Drl 10/22/2021 SRO A3 G2.3.11 3 S SRO A4 2.4.38 3 S 1

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

Simulator/In-Plant Safety JPMs Function and K/A

a 1 3 S b 2 3 E Why are steps 2, 3 and 11 not critical?

No affect on outcome. SAT 1 0/22/2021 c 8 3 E Lets talk about the initial conditions. What could cause the valves to isolate that was not a leak? Id rather not state that was no indication of a leak and then give them a leak.

Multiple conditions could cause this. Telling them that there is no leak is required in order for them to proceed with restoration. Drl 10/22/2021 d 4 3 S e 5 3 E Grammar on IC 8 links Have been OPENED

Corrected. Drl 10/22/2021 f 6 3 E Steps 1 and 3 look critical.

Step 6 may be critical.

Corrected. Drl 10/22/2021 g (RO) 7 2 E The steps to start withdrawing rods need to be included and they would be critical.

Lets look at when we insert this failure.

Failure occurs when they first move a rod. May back up to respond to plant conditions. Need to see this during prep week.

Left as written. Meets all requirements. Drl 12/1/2021 h 9 3 E Step 11 should allow for the B fan switch to go to standby if the applicant starts the A fan.

Corrected. Drl 10/22/2021 I 3 3 S j 6 3 S k 8 2 S 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 des cribes 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, c heck 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 -b ound JPM is marked by a (S)atisfactory resolution on this form.

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

Facility: Hatch Scenario: 1 Exam Date: Dec 2021

1 2 3 4 5 6 7 8 9 10

Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap

1 S 2 S 3 X S 4 S 5 X S 6 X S 7 X S 8 S What are the bases of the CTs? I think I see the first one: start the pump prior to the requirement to scram. But the 5 minutes for the second one needs some type of justification.

Ops Management st ates that this is how they are trained and this is a know expectation. Drl 12/1/2021 ES-301 Operating Test Review Worksheet Form ES-301-7

Facility: Hatch Scenario:2 Exam Date: Dec 2021 1 2 3 4 5 6 7 8 9 10

Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap

1 S 2 S 3 X S 4 S 5 X S 6 X E Could we ask the BOP to get something on the back panel? The examiner could delay him back there if needed.

Discuss during prep week. Drl 10/22/2021

Revised as stated above. Drl 12/1/2021 7 X S 8 E The Scenario guide states that Event 8 has a CT. The Event 8 write-up does not. I tend to agree that Event 8 has no CT. The CT is contained in Event 9. Youre thoughts?

Corrected. Not a CT. drl 10/22/2021.

9 X S

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 3 Exam Date: Dec 2021

1 2 3 4 5 6 7 8 9 10

Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap

1 S 2 S 3 X S 4 X S 5 X S 6 S Again, well discuss how to occupy the ATC.

Discuss during prep week. Drl 10/22/2021 Changed to call away the operator. SAT 12/1/2021 7 S 8 X S 9 X S

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Hatch Scenario: 4 Exam Date: Dec 2021

1 2 3 4 5 6 7 8 9 10

Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap

1 S 2 X E Is there a reason we want to restore the PSW pump auto start circuit?

TS gets overly complex if auto start function is not restored in a timely manner. This is done to minimize the time spent on the TS and keep the scenario to a reasonable length. SAT. drl 10/22/2021 3 S 4 X X E Typo on Critical Task page 12 met not meet.

Corrected. Drl 10/22/2021 5 E What effect would skipping steps 5 and 6 have on the applicants getting their required tasks? Is it possible to move 6 before 5 to minimize the impact?

Suggestion accepted. Event 6 has been moved. Drl 10/22/2021 6 X E Event Description on pages 17-20 need to identify this event as having a CT.

Corrected drl 10/22/2021 7 S 8 X S

Facility: Hatch Scenario: 5 Exam Date: Dec 2021

1 2 3 4 5 6 7 8 9 10

Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap

1 S 2 X X S 3 X S 4 S 5 S 6 S 7 S Potential TS call.

Not a TS. Drl 10/22/2021 ES-301 Operating Test Review Worksheet Form ES-301-7 8 X S 9 X S 10 X E Why are both methods acceptable to meet the CT? Is not one preferred or more expected?

This goes into how quickly the crew moves through the EOPs. Either is possible and acceptable. If the ED occurs, we need to look at why. If the crew did something wrong (besides being slow) to cause the need to ED, it may be a created CT. drl 10/22/2021

Facility: Hatch Scenario: 6 Exam Date: Dec 2021

1 2 3 4 5 6 7 8 9 10

Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap

1 S 2 S 3 S 4 X X S 5 X S 6 X X S 7 S 8 X S

Instructions for Completing This Table:

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

1 2 3 4 5 6 7 8 11

% Unsat.

Scenario Event Events TS TS CT CT Scenario U/E/S Explanation Totals Unsat. Total Unsat. TotalUnsat. Elements

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 -contro ls 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: 100% 2 + 4 + 6 1 + 3 + 5

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

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

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

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

Site name: Exam Date:

OPERATING TEST TOTALS Total Total Total Total %

Unsat. Edits Sat. Unsat. Explanation 9 1 4 4 Admin.

JPMs

11 0 6 5 Sim./In -Plant JPMs 6 0 3 2 Scenarios

Op. Test 26 1 13 11 3.8 Totals:

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 adm inistrative 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 O0%
  • 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.

x The administrative JPM tasks/keys were incorrect.

x CTs were incorrect in the scenarios (not including postscenario critical tasks defined in Appendix D).

x The EOP strategy was incorrect in a scenario(s).

x TS entries/actions were determined to be incorrect in a scenario(s).

f ES-401 BWR Examination Outline Form ES-401-1

Facility: Hatch Date of Exam: December 2021 Tier Group RO K/A Category Points SRO-O nly Points

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 4 3 4 3 3 3 20 3 4 7 Emergency and 2 1 1 1 N/A 2 1 N/A 1 7 1 2 3 Abnormal Plant Evolutions Tier Totals 5 4 5 5 4 4 27 4 6 10
2. 1 3 2 2 2 2 3 3 3 2 2 2 26 3 2 5 Plant 2 1 1 1 2 1 1 1 1 1 1 1 12 0 1 2 3 Systems Tier Totals 4 3 3 4 3 4 4 4 3 3 3 38 4 4 8
3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two).(One Tier 3 radiation control K/A is allowed if is replaced by a it 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. S ystems 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 SectionD.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. S ample 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 evol ution 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 IR s 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 Evolutions Tier 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 X 295001AA1.02; Ability to operate and/or 3.3 Forced Core Flow Circulation / 1 & 4 monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

RPS.

295003 (APE 3) Partial or Complete Loss of X 295003AA2.03; Ability to determine and/or 3.2 AC Power / 6 interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

POWER : Battery status.

295004 (APE 4) Partial or Total Loss of DC X 295004G2.1.23; Ability to perform specific 4.3 Power / 6 system and integrated plant procedures during all modes of plant operation.

295005 (APE 5) Main Turbine Generator Trip / X 295005AK2.02; Knowledge of the 2.9 3 interrelations between MAIN TURBINE GENERATOR TRIP and the following:

Feedwater temperature.

295006 (APE 6) Scram / 1 X 295006AK1.02; Knowledge of the 3.4 operational implications of the following concepts as they apply to SCRAM :

Shutdown margin.

295006G2.4.46; Ability to verify that the 4.2 X alarms are consistent with the plant conditions.

295016 (APE 16) Control Room Abandonment X 295016AK3.03; Knowledge of the reasons 3.5

/ 7 for the following responses as they apply to CONTROL ROOM ABANDONMENT:

Disabling control room controls.

295018 (APE 18) Partial or Complete Loss of X 295018AK3.06; Knowledge of the reasons 3.3 CCW / 8 for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

Increasing cooling water flow to heat exchangers.

295019 (APE 19) Partial or Complete Loss of X 295019AK2.18; Knowledge of the 3.5 Instrument Air / 8 interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: ADS.

295021 (APE 21) Loss of Shutdown Cooling / X 295021G2.1.19; Ability to use plant 3.9 4 computers to evaluate system or component status.

X 295021AA2.05; Ability to determine and/or 3.5 interpret the following as they apply to INADVERTENT CONTAINMENT ISOLATION: Reactor water level.

295023 (APE 23) Refueling Ac cidents / 8 X 295023AK3.02; Knowledge of the reasons 3.4 for the following responses as they apply to REFUELING ACCIDENTS: Interlocks associated with fuel handling equipment.

X 295023G2.2.38; Knowledge of conditions 4.5 and limitations in the facility license.

295024 High Drywell Pressure / 5 X 295024EA2.08; Ability to determine and/or 3.6 interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell radiation levels.

295025 (EPE 2) High Reactor Pressure / 3 X 295025EK1.03; Knowledge of the 3.6 operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE: Safety/relief valve tailpipe temperature/pressure relationships.

295026 (EPE 3) Suppression Pool High Water X 295026EA1.01; Ability to operate and/or 4.1 Temperature / 5 monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool cooling.

X 4.0 295026EA2.03; Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor pressure.

295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature X 295028EA1.02; Ability to operate and/or 3.9 (Mark I and Mark II only) / 5 monitor the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell ventilation system.

X 295028EA2.02; Ability to determine and/or 3.9 interpret the following as they apply to HIGH DRYWELL TEMPERATURE:

Reactor pressure.

295030 (EPE 7) Low Suppression Pool Water X 295030EK1.02; Knowledge of the 3.5 Level / 5 operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL:

Pump NPSH.

295031 (EPE 8) Reactor Low Water Level / 2 X 295031EA2.03; Ability to determine and/or 4.2 interpret the following as they apply to REACTOR LOW WATER LEVEL: Reactor pressure.

295037 (EPE 14) Scram Condition Present X 295037G2.2.44; Ability to interpret control 4.2 and Reactor Power Above APRM Downscale room indications to verify the status and or Unknown / 1 operation of a system, and understand how operator actions and directives affect plant and system conditions.

295038 (EPE 15) High Offsite Radioactivity X 295038EK3.02; Knowledge of the reasons 3.9 Release Rate / 9 for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: System isolations.

X 295038G2.1.25; Ability to interpret 4.7 reference materials, such as graphs, curves, tables, etc.

600000 (APE 24) Plant Fire On Site / 8 X 600000AK1.01; Knowledge of the 2.5 operation applications of the following concepts as they apply to Plant Fire On Site: Fire Classifications by type 700000 (APE 25) Generator Voltage and X 700000AK2.04; Knowledge of the 3.0 Electric Grid Disturbances / 6 interrelations between GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following:

Controllers, positioners.

700000G2.1.7; Ability to evaluate plant X performance and make operational 4.7 judgments based on operating characteristics, reactor behavior, and instrument interpretation.

K/A Category Totals: 4 3 4 3 3/3 3/4 Group Point Total: 20/7

ES-401 3 Form ES-401-1

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions Tier 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 295007 (APE 7) High Reactor Pressure / 3 X 295007AA2.02; Ability to determine and/or 4.1 interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor power.

295008 (APE 8) High Reactor Water Level / 2 X 295008AA1.02; Ability to operate and/or 3.3 monitor the following as they apply to HIGH REACTOR WATER LEVEL: Reactor water cleanup (ability to drain).

295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 X 295010AK3.01; Knowledge of the reasons 3.8 for the following responses as they apply to HIGH DRYWELL PRESSURE:

Increased drywell venting.

295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature / X 295012AA2.02; Ability to determine and/or 3.1 5 interpret the following as they apply to HIGH DRYWELL TEMPERATURE:

Drywell pressure.

295013 (APE 13) High Suppression Pool X 295013G2.2.25; Knowledge of the bases 4.2 Temperature. / 5 in Technical Specifications for limiting conditions for operations and safety limits.

295014 (APE 14) Inadvertent Reactivity X 295014G2.4.9; Knowledge of low 3.8 Addition / 1 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

295015 (APE 15) Incomplete Scram / 1 X 295015G2.4.21; Knowledge of the 4.6 parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

295017 (APE 17) Abnormal Offsite Release X 295017AA1.05; Ability to operate and/or 2.7 Rate / 9 monitor the following as they apply to HIGH OFF-SITE RELEASE RATE:

SPDS/ERIS/CRIDS/GDS.

295020 (APE 20) Inadvertent Containment X 295020AK2.06; Knowledge of the 3.8 Isolation / 5 & 7 interrelations between INADVERTENT CONTAINMENT ISOLATION and the following: HPCI.

295022 (APE 22) Loss of Control Rod Drive Pumps / 1

295029 (EPE 6) High Suppression Pool Wa ter Level / 5

295032 (EPE 9) High Secondary Containment Area Temperature / 5

295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9

295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9

295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen X 500000EK1.01; Knowledge of the 3.3 Concentration / 5 operational implications of the following concepts as they apply to HIGH CONTAINMENT HYDROGEN CONCENTRATIONS: Containment integrity.

K/A Category Point Totals: 1 1 1 2 1/1 1/2 Group Point Total: 7/3

ES-401 4 Form ES-401-1

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems Tier 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) X 203000K4.12; Knowledge of RHR/LPCI: 3.5 RHR/LPCI: Injection Mode INJECTION MODE (PLANT SPECIFIC) design feature(s) and/or interlocks which provide for the following: System redundancy.

205000 (SF4 SCS) Shutdown Cooling X 205000A2.07; Ability to (a) predict the 2.7 impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of motor cooling.

206000 (SF2, SF4 HPCIS) X 206000A4.01; Ability to manually operate 3.8 High-Pressure Coolant Injection and/or monitor in the control room: Turbine speed controls.

207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) X 209001K1.08; Knowledge of the physical 3.2 Low-Pressure Core Spray connections and/or cause-effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the following:

A.C. electrical power.

209001G2.4.18; Knowledge of the specific X bases for EOPs. 4.0

209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid X 211000A4.04; Ability to manually operate 4.5 Control and/or monitor in the control room: Reactor power.

211000A2.06; Ability to (a) predict the X impacts of the following on the STANDBY 3.3 LIQUID CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings.

212000 (SF7 RPS) Reactor Protection X 212000K5.01; Knowledge of the 2.7 operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM: Fuel thermal time constant.

215003 (SF7 IRM) X 215003K6.02; Knowledge of the effect that 3.6 Intermediate-Range Monitor a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM 24/48 volt D.C.

power.

X 215003 A2.05; Ability to (a) predict the 3.3 impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Faulty or erratic operation of detectors/system..

215004 (SF7 SRMS) Source-Range X 215004K2.01; Knowledge of electrical 2.6 Monitor power supplies to the following: SRM channels/detectors.

215005 (SF7 PRMS) Average Power X 215005K5.02; Knowledge of the 2.7 Range Monitor/Local Power Range operational implications of the following Monitor concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

Effects of voids on LPRM indication.

X 4.0 215005K3.01; Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM will have on following: RPS.

217000 (SF2, SF4 RCIC) Reactor X 217000A3.03; Ability to monitor automatic 3.7 Core Isolation Cooling operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: System pressure 218000 (SF3 ADS) Automatic X 218000A1.06; Ability to predict and/or 3.7 Depressurization monitor changes in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: Suppression pool temperature.

X 218000K6.03; Knowledge of the effect that 3.8 a loss or malfunction of the following will have on the AUTOMATIC DEPRESSURIZATION SYSTEM : Nuclear boiler instrument system (level indication).

223002 (SF5 PCIS) Primary X 223002A3.01; Ability to monitor automatic 3.4 Containment Isolation/ Nuclear Steam operations of the PRIMARY Supply Shutoff CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT - OFF including: System indicating lights and alarms.

X 223002A2.09; Ability to (a) predict the 3.7 impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM /

NUCLEAR STEAM SUPPLY SHUT - OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation.

239002 (SF3 SRV) Safety Relief X 239002A1.07; Ability to predict and/or 2.9 Valves monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including: Turbine load.

259002 (SF2 RWLCS) Reactor Water X 259002G2.1.30; Ability to locate and 4.4 Level Control operate components, including local controls.

261000 (SF9 SGTS) Standby Gas X 261000A2.14; Ability to (a) predict the 3.0 Treatment 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 system pressure.

X 261000G2.2.37; Ability to determine 4.6 operability and/or availability of safety related equipment.

262001 (SF6 AC) AC Electrical X 262001K2.01; Knowledge of electrical 3.3 Distribution power supplies to the following: Off - site sources of power.

262002 (SF6 UPS) Uninterruptable X 262002G2.2.40; Ability to apply Technical 3.4 Power Supply (AC/DC) Specifications for a system.

262002K1.07; Knowledge of the physical 2.8 X connections and/or cause-effect relationships between UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following: Rod worth minimizer.

263000 (SF6 DC) DC Electrical X 263000K3.02; Knowledge of the effect that 3.5 Distribution a loss or malfunction of the D.C.

ELECTRICAL DISTRIBUTION will have on following: Components using D.C. control power (i.e. breakers).

264000 (SF6 EGE) Emergency X 264000K4.05; Knowledge of 3.2 Generators (Diesel/Jet) EDG EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for the following:

Load shedding and sequencing.

X 3.2 264000K1.06; Knowledge of the physical connections and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEL/JET) and the following: Starting system.

300000 (SF8 IA) Instrument Air X 300000A2.01; Ability to (a) predict the 2.9 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.

400000 (SF8 CCS) Component X 400000A1.04; Ability to predict and / or 2.8 Cooling Water monitor changes in parameters associated with operating the CCWS controls including: Surge Tank Level.

X 400000K6.06; Knowledge of the effect that 2.9 a loss or malfunction of the following will have on the CCWS: Heat exchangers and condensers.

510000 (SF4 SWS*) Service Water (Normal and Emergency)

K/A Category Point Totals: 3 2 2 2 2 3 3 3/3 2 2 2/2 Group Point Total: 26/5

ES-401 5 Form ES-401-1

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems Tier 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 X 201001K4.03; Knowledge of CONTROL 2.7 ROD DRIVE HYDRAULIC SYSTEM design feature(s) and/or interlocks which provide for the following: Control rod drive mechanism cooling water flow.

201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive X 201003A2.08; Ability to (a) predict the 3.8 Mechanism impacts of the following on the CONTROL ROD AND DRIVE MECHANISM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low HCU accumulator pressure/high level.

201004 (SF7 RSCS) Rod Sequence Control

201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer

202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control X 202002K4.05; Knowledge of 3.1 RECIRCULATION FLOW CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: Limiting recirculation pump speed mismatch.

204000 (SF2 RWCU) Reactor Water Cleanup

214000 (SF7 RPIS) Rod Position Information

215001 (SF7 TIP) Traversing In -Core Probe

215002 (SF7 RBMS) Rod Block Monitor X 215002G2.2.22; Knowledge of limiting 4.0 conditions for operations and safety limits.

216000 (SF7 NBI) Nuclear Boiler Instrumentation X 216000G2.2.12; Knowledge of 4.1 surveillance procedures.

219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and 223001A1.06; Ability to predict and/or 3.1 Auxiliaries X monitor changes in parameters associated with operating the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES controls including: Oxygen concentration.

226001 (SF5 RHR CSS) RHR/LPCI: Containment X 226001A2.12; Ability to (a) predict the 2.6 Spray Mode impacts of the following on the RHR/LPCI:

CONTAINMENT SPRAY SYSTEM MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Pump runout.

230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment X 234000A4.02; Ability to manually operate 3.4 and/or monitor in the control room:

Control rod drive system.

239001 (SF3, SF4 MRSS) Main and Reheat Steam

239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure 241000K6.20; Knowledge of the effect 2.8 Regulating X that a loss or malfunction of the following will have on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM:

Main generator.

245000 (SF4 MTGEN) Main Turbine 245000K5.07; Knowledge of the 2.6 Generator/Auxiliary X operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: Generator operations and limitations.

256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater X 259001K1.08; Knowledge of the physical 3.6 connections and/or cause-effect relationships between REACTOR FEEDWATER SYSTEM and the following:

Reactor water level control system.

268000 (SF9 RW) Radwaste X 268000K3.04; Knowledge of the effect 2.7 that a loss or malfunction of the RADWASTE will have on following: Drain sumps.

271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring X 272000A3.01; Ability to monitor automatic 3.8 operations of the RADIATION MONITORING SYSTEM including: Main steam isolation indications.

286000 (SF8 FPS) Fire Protection X 286000K2.02; Knowledge of electrical 2.9 power supplies to the following: Pumps.

288000 (SF9 PVS) Plant Ventilation X 288000G2.2.25; Knowledge of the bases 4.2 in Technical Specifications for limiting conditions for operations and safety limits.

290001 (SF5 SC) Secondary Containment

290003 (SF9 CRV) Control Room Ventilation

290002 (SF4 RVI) Reactor Vessel Internals K/A Category Point Totals: 1 1 1 2 1 1 1 1/1 1 1 1/2 Group Point Total: 12/3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

Facility: Date of Exam:

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

2.1.34 Knowledge of primary and secondary plant chemistry 2.7 limits.

2.1.43 Ability to use procedures to determine the effects on 4.1 reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

2.1.44 Knowledge of RO duties in the control room during fuel 3.9

1. Conduct of handling such as responding to alarms from the fuel Operations handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

2.1.35 Knowledge of the fuel-handling responsibilities of SROs. 3.9 2.1.5 Ability to use procedures related to shift staffing, such 3.9 as minimum crew complement, overtime limitations, etc.

Subtotal 3 2 2.2.3 (multi-unit license) Knowledge of the design, procedural, 3.8 and operational differences between units.

2.2.39 Knowledge of less than or equal to one-hour Technical 3.9

2. Equipment Specification action statements for systems.

Control 2.2.5 Knowledge of the process for making design or 3.2 operating changes to the facility.

2.2.13 Knowledge of tagging and clearance procedures. 4.3 Subtotal 2 2 2.3.15 Knowledge of radiation monitoring systems, such as 2.9 fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3. Radiation 2.3.7 Ability to comply with radiation work permit requirements 3.5 Control during normal or abnormal conditions.

2.3.11 Ability to control radiation releases. 4.3 Subtotal 2 1 2.4.2 Knowledge of system set points, interlocks and 4.5 automatic actions associated with EOP entry conditions.

2.4.35 Knowledge of local auxiliary operator tasks during an 3.8 emergency and the resultant operational effects.

2.4.39 Knowledge of RO responsibilities in emergency plan 3.9

4. Emergency implementation.

Procedures/Plan 2.4.27 Knowledge of fire in the plant procedures. 3.9 2.4.30 Knowledge of events related to system operation/status 4.1 that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

Subtotal 3 2 Tier 3 Point Total 10 7

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

Tier/Group Randomly Reason for Rejection Selected K/A 1 / 2 295013G2.4.49 Unable to write a K/A to SRO level. Changed to 295013G2.2.25.

2 / 1 218000A1.02 Acoustical monitor not installed at Hatch. Changed to 218000A1.06.

2 / 1 218000K1.05 ADS and remote shutdown systems not interconnected.

Changed to 264000K1.06, 2 / 1 00000K6.04 No air refusal valve at Hatch. Changed to 18000K6.03.

1 / 2 295012AA2.03 No humidity instruments at Hatch. Changed to 295012AA2.02.

3 2.4.50 Unable to write a Tier 3 question to K/A. Changed to 2.4.39.

295010AK3.02 All procedural actions taken due to DW temperature instead of pressure. Re-selected new K/A. New K/A 295010AK3.01.

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

3. Psychometric Flaws 4. Job Content Flaws 5. Other
1. LOK 2. 6. Source 7. Status Q (F/H) LOD Stem (B/M/N) (U/E/S) 8. Explanation (1-5) Focus Cues T/F Cred. Partial Job Minutia #/Units Backward Q - K/A SRO Only Dist. Link 1 F 2 X B E 201003A2.08 K/A met Why would someone suspect the suction filter needed backwashed for the information? Would it make sense to simply state Return to procedure in use or whatever words that your site uses for alarm is clear go back to what you were doing.?

Incorporated suggestion; reworded the statement that the applicants complete.

Complete

Changes made as recommended above. Question is SAT 10/22/2021 2 F 2 M S 201001K4.03 K/A is met

3 F 3 N S 202002K4.05 Pre-submitted. Question was SAT.

K/A is met 4 H 3 B S 203000K4.12 K/A is met

5 H 3 N S 205000A2.07

  • This was a presubmitted question. The comment given was : The second question is sort of strange. I don t have access to the ARPs. Does the ARP for 650- 430 allow continued operation of the pump? I suspect not. I think a better question might be 34AB-E11-001-1 is/is NOT required to be entered. Of course, you would need to give some information about Loop A RHR that might make is NOT possible. Perhaps have that loop in standby.

Question amended prior to submittal. Now SAT

K/A is met 6 F 2 B S 206000A4.01 K/A is met

7 H 2 M S 209001K1.08 K/A is met 8 H 3 B E 211000A4.04 K/A is met Could we just use figure A and ask if Cold Shutdown Boron Weight has been injected?

Incorporated suggestion.

Only used Figure A, modified stem, and replaced the 2nd part with, Based on the above indication, COLD Shutdown Boron Weight _(Has/Has NOT) been injected into the RPV.

Changed from Bank to MOD Complete

Question was modified as suggested above.

Question is SAT. drl 10/22/2021 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 qu estion, as written, (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
8. At a minimum, explain any U status ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2 Form ES-401-9

3. Psychometric Flaws 4. Job Content Flaws 5. Other
1. 2. 6. Source 7. Status Q LOK LOD Stem (B/M/N) (U/E/S) 8. Explanation (F/H) (1-5) Focus Cues T/F Cred. Partial Job Minutia #/Units Backward Q - K/A SRO Only Dist. Link 9 F 3 B S 212000K5.01 K/A is met 10 H 2 N S 215002G2.2.22 K/A is met 11 F 2 N S 215003K6.02 K/A is met 12 F 2 B S 215004K2.01 K/A is met 13 H 2 M S 215005K3.01 K/A is met 14 H 2 N E 215005K5.02 K/A is met Small suggestion, how about we change the question to the change in power is due to void formation/void collapse?

Incorporated suggestion.

Changed 2nd part to read The INIT IAL power response is a result of __________. (void formation/void collapse).

Complete

I agree. The changes made make this question SAT. drl 10/21/2021.

15 F 2 N S 217000A3.03 K/A is met 16 H 2 M S 218000A1.06 K/A is met 17 H 2 X N U 218000K6.03 K/A is met The distractors here dont really work. It would be OK without the drawing, but from the drawing it is obvious that A and B are the same.

Since 2 answers cant be correct, they can be illuminated.Is there a way to tie in the 2 min timer circuitry to make new plausible distractors?

Talk with Lanyi about choices A and B and how does he view those as the same? Maybe a misread. Ensure And/Or recognized.

Develop V 5 Complete

This wasnt choices A or B but rather system A and B.

I understand that the part of the drawing handout that gave away the information will be blanked out. Based upon this information, the original question was SAT. drl 10/21/2021.

18 F 2 N S 223001A1.06 K/A is met 19 F 2 B S 223002A3.01 K/A is met 20 H 2 B S 234000A4.02 K/A is met 21 H 2 B S 239002A1.07 K/A is met 22 H 2 B S 241000K6.20 K/A is met 23 F 3 B E 245000K4.07 K/A is met This is OK if OPS agrees that knowing the 14000 amp limit from memory is testable.

OPS (A. Belcher) agrees that this information is testable from memory.

No Action Taken

Ops agrees that this is not minutia. Question is SAT. drl 10/21/2021 24 H 3 B S 259001K1.08 K/A is met 25 F 2 N E 259002G2.1.30 K/A is met This is OK if OPS agrees knowing the location of these breakers from memory is not minutia

OPS (A. Belcher) agrees that this information is testable from memory.

No Action Taken

Ops agrees that this is not minutia. Question is SAT. drl 10/21/2021 26 F 2 N S 261000A2.14 K/A is met 27 F 2 B S 262001K2.01 K/A is met 28 F 2 N E 262002G2.2.40 Could we ask this in Mode 4?

No, this would be a difficulty level 5 question from memory in Mode 4/5 when asking about Critical Instrument Buses due to having to know all supported systems from the CIB and systems required to be operable in these modes from memory.

I agree, the knowledge required for Mode 4 would be SRO knowledge. Therefore the original question was SAT. drl 10/21/2021 29 F 2 N S 262002K1.07 K/A is met 30 H 3 B S 263000K3.02 K/A is met 31 F 3 N E 264000K1.06 Is it 5 start attempts or 10? I believe 5 is correct, but your description states 10. I think both tanks blow down equally for each start attempt so only 5 attempts are available unless you isolate one tank. How about we change the 2nd question to per TS basis 3.8.3, the starting air system is required to have a minimum of __ successive EDG start attempts without recharging the air start receivers. Then toggle on 5 and 10.

Dave you are correct. The Bases does not mention 10 starts. We have corrected the question write-up to only mention 5 starts.

Modified stem to isolate 1 tank.

Complete

The stem was re-written to isolate one tank.

Then the question was re-written to toggle on 2 or 5 starts. Two being less than 1/2 since one tank is isolated. Question is now considered SAT. drl 10/21/2021 32 F 2 N S 264000K4.05 K/A is met 33 H 3 M S 268000K3.04 K/A is met 34 F 2 B S 272000A3.01 K/A is met 35 F 2 B S 286000K2.02 K/A is met 36 H 2 M U 295001AA1.02 X K/A is not met Tier 1 questions need to test how to operate the plant (See FAQ 401.55). This question is only system knowledge but does not test operating knowledge

Modified stems initial conditions to 100% RTP and Flow.

Modified stem to include a loss of FW heating and specific APRM indications.

Question now requires applicant to determine plant response and associated operator actions.

Complete

Question now asks for plant response and big picture operator response. Question is now Sat.

drl 10/21/2021 37 F 2 X N U 295003AA2.03 K/A is not met Tier 1 questions need to test how to operate the plant (See FAQ 401.55). This question is only system knowledge but does not test operating

Modified question to 2 by 2. 1st part no change.

2nd part asks if operator action is/is NOT required to restore battery charger.

Complete

Question now asks for plant response and big picture operator response. Question is now Sat.

drl 10/21/2021 38 H 2 B S 295004G2.1.23 K/A is met 39 H 3 M S 295005AK2.02 K/A is met 40 F 2 B E 295006AK1.02 K/A is met Could we put a specific procedure number and name in the steam?

Suggestion Incorporated

Modified stem to place the applicants in the 10 rods at 02 position. Changed to a 2 by 2. 1st part asks about Rx remaining shutdown. 2nd part asks about operator action (RWM) to insert control rods.

Complete

Question as modified is fully SAT. drl 10/21/2021 41 H 3 B S 295007AA2.02 K/A is met 42 H 2 M S 295008AA1.02 Pre-submitted. As long as Ops agrees that knowledge of which panel to use is not trivial this is SAT.

K/A is met

Verified Ops agreed this is not trivial knowledge. Drl 10/22/2021 43 H 3 B E 295010AK3.01 For the first question could we either toggle on high pressure scram/PCPL or have the is/is NOT due to PCPL?

Incorporated Suggestion.

1st part now toggles PCPL/High DW press scram

Complete

Question as modified is now SAT. drl 10/21/2021 44 H 3 B S 195014G2.4.9 Pre-submitted question was SAT K/A is met 45 F 3 N S 295016AK3.03 K/A is met 46 H 3 M S 295017AA1.05 K/A is met 47 H 3 B S 195018K3.06 K/A is met 48 H 3 X M E 295019AK2.18 K/A is met Not quite meeting the Tier 1 criteria. How about changing the first question to the procedure does

/does not require the operator to manually close F015?

Suggestion incorporated.

1st part now asks control to F015 is/is NOT required to place to CLOSE.

Complete

Question as modified is now SAT. drl 11/21/2021 49 F 2 X N U 295020A K2.06 K/A is not met Tier 1 questions need to test how to operate the plant (See FAQ 401.55). This question is only system knowledge but does not test operating We re looking more for what guidance the operators have when there is an inadvertent isolation when HPCI is needed.

Modified question to ask next procedure action

Complete

Question modified to ask operator response to automatic function. Question is now SAT.

drl10/21/2021 50 H 2 M E 295021G2.1.19 K/A is met Tier 1 intent not quite met. Change the second question to Entry into 34AB-E11-001-2, Loss of SDC is/is Not required

Suggestion Incorporated

Complete

Question was modified as discussed above.

Question is now SAT. drl 10/22/2021 51 F 2 B S 29013AK3.02 K/A is met 52 H 3 B E 29502EA2.08 K/A is met In the second bullet, is 2.0E2 the standard way to right it?

Yes. No Change.

Complete

No changes required. Question is SAT. drl 10/22/2021 53 H 2 B S 295025EK1.03 K/A is met 54 H 2 B S 295026EA1.01 K/A is met 55 F 3 X B E 295028EA1.02 K/A is sort of met. How about we give containment conditions and chilled water return temperature and ask D/W Coolers ___

A. Can B. Cannot because D/W temperature only is too high C. Cannot because Chilled water return temperature only is too high D. Cannot because D/W temperat ure and chilled water return temperature are both too high.

Incorporated D/W Coolers and gave DW temperature indications with a timeline. Asked LATEST time DW Coolers can be restarted.

Complete

Question modified to give similar changes to that discussed above. Question now is SAT. drl 10/22/2021 56 H 2 B E 295030EK1.02 K/A is met I need all of the discussion and references put into the exam with references

Send corrected documents

Corrected documents will be included in the final submittal. Drl 10/22/2021 57 F 2 B S 295031EA2.03 K/A is met 58 H 2 X B E/U 295037G2.2.44 K/A is met.

Where you have ARI information is confusing.

How about we state that ARI failed right after The OATC performed RC-1 ?

Change the stem to make the white lights NOT illuminated.

What would make an applicant think that venting the air header would not work in this situation?

Incorporated suggestion for moving ARI to later in STEM. Put conditions in the individual questions to eliminate concerns for operational validity. Asking procedurally required instead of will/will NOT effective.

Changed white lights to EXTINGUISHED.

If the Blue lights were illuminated, venting the scram air header would NOT be effective.

Complete

Changes were made to the question as described above. The question is now SAT. drl 10/22/2021 59 H 2 X B E 295038EK3.02 K/A is met Could we change the second question to One reason to secure one train is to maintain ALARA

/ Maintain Reactor Bldg to outside Air dP in band.

Of course, the first question would need to be changed to running both SGBT Trains is/is NOT prohibited.

Modified question to ask the reason for securing one train. 2nd part changed to ask if it is ALLOWED/PROHIBITED to restart 2nd train at a later time.

Complete

Changes were made to the question as described above. The question is now SAT. drl 10/22/2021 60 F 3 N S 300000A2.01 K/A is met 61 F 2 X B U 4000000A1.04 K/A is not met Tier 1 questions need to test how to operate the plant (See FAQ 401.55). This question is only system knowledge but does not test operating knowledge This one would be perfect to pull annunciator procedure.

Talk to Dave this is a tier 2 KA.

My mistake. This is a Tier 2 question. Original question was SAT as written. drl 10/22/2021 62 F 2 X N U 4000000K6.06 K/A is not met Tier 1 questions need to test how to operate the plant (See FAQ 401.55). This question is only system knowledge but does not test operating knowledge

Talk to Dave this is a tier 2 KA.

My mistake. This is a Tier 2 question. Original question was SAT as written. drl 10/22/2021 63 F 2 B S 5000000EK1.01 K/A is met 64 F 2 M S 6000000AK1.01 K/A is met 65 F 2 X N E 7000000AK2.04 K/A is met.

Intent of Tier 1 not really met. How about we give them the capability curve and ask them to move vars some place. Then give them the same switches but the second response would be raise or lower?

Suggestion to provide capability curved incorporated.

Suggestion to move VARs incorporated.

Suggestion to (RAISE/LOWER) incorporated.

Complete

Question changed as discussed above. Question is now SAT. drl 10/22/2021 66 F 4 B S G2.1.34 K/A is met 67 F 3 N S G2.1.43 K/A is met 68 F 2 B S G2.1.44 K/A is met 69 F 2 N S G2.2.3 K/A is met 70 F 2 B S G2.2.39 K/A is met 71 F 2 X B E G2.3.7 How about for the second one Periodic HP coverage will/will not be required ?

Did not use suggestion due to procedure wording. (Normally)

Modified 2nd part to ask about formal rad briefing requirements.

Complete

Question changed as discussed above. Question is now SAT. drl 10/22/2021 72 F 3 N S G2.3.15 K/A is met 73 F 2 M S G2.4.2 K/A is met 74 F 2 N S G2.4.35 K/A is met 75 F 2 B S G2.4.39 K/A is met SRO Questions 76 H 2 N S 209001G2.4.18 K/A is met 77 H 3 N S 211000A2.06 This was a pre-submitted question. Original comment:

  • I disagree with your second part answer. Since SBLC is inop due to the tank level, leaving the tank without an operator does not change it s status. Even if it was not OOS due to level, the operator can leave if ordered as long as it is declared inoperable while the operator was gone.
  • Also, the first question implies the answer to the second one (i.e., if it was not ok to reposition the valves why ask what time the system is inoperable).
  • Perhaps you can simplify the question by telling them that valves are being manually manipulated and the level is at 35 inches and asking if the system is inoperable and why
a. SBLC is operable
b. SBLC is inoperable because manual valves are out of position
c. SBLC is inoperable because level is too high
d. SBLC is inoperable because both

Question changed per comment. Now SAT.

K/A is met 78 F 3 B S 215003A2.05 K/A is met 79 H 2 N S 216000G2.2.12

This was a pre-submitted question. Original comment:

  • Reverse the questions.
  • To the second item add as allowed by TS 3.3.6.1 Note 2.
  • Re-write what is now the second question as Entry into TS 3.3.6.1 Condition A is/is NOT immediately required.

Question modified per comment now SAT.

K/A is met 80 H 3 M S 223002A2.09 K/A is met 81 N S 226001A2.12 This was a pre-submitted question. Original comment:

  • K/A is not really met.
  • Asking the applicants to determine the operability status of equipment during an accident doesnt really make sense. I think that the basic scenario works, but we should probably focus on EOP paths, ensuring that they need to evaluate the pump runout and determine the right path to take.

Question was rewritten and is now SAT

K/A is met 82 F 3 B S 261000G2.2.37 K/A is met 83 F 3 N E 288000G2.2.25 K/A is met The test with reference information needs cleaned up, some information is repeated and some missing

Made corrections to document.

Talk with Dave about how he wants the correction.

The reference information has been corrected. It will be updated with the final submittal. The question is SAT. drl 10/22/2021 84 H 3 M S 295006G2.4.46 K/A is met 85 H 2 M S 29012AA2.02 K/A is met 86 F 2 B E 295013G2.2.25 K/A is met Remove the word drywell in the second distractor

Incorporated Suggestion

Complete

Changes made as requested. Question is SAT.

drl 10/22/2021 87 H 2 X M E 295015G2.4.21 K/A is met Not fully clear that we are in RCA. Could we add something to definitely tell that we are not in cold shutdown rod configuration? Perhaps pick a rod and tell them that it is in position 10 (or something like that).

Suggestion incorporated

Complete

Reworded stem to make it clear that we are not in cold shutdown rod configuration. Question is SAT. drl 10/22/2021 88 H 3 B S 295021AA2.05 K/A is met 89 F 2 B E 295023G2.2.38 K/A is met.

In the second question, remove Pressurization Mode and add for a 30 day period following a DBE to the end.

Suggestions incorporated.

Complete

Reworded as suggested above. Question is now SAT. drl 10/22/2021 90 H 3 B S 295026EA2.03 K/A is met 91 H 3 X B U 295028EA2.02 K/A is met C is implausible based on question construction.

If an applicant determines that RC[A] entry is not required, why would they elect to invoke RC/P path usage? RC/P is only present in both RC[A] procedures. Justification statement doesnt make sense.

B is implausible for the same (yet backward) reasoning.

Both halves of this question are essentially testing knowledge of one EOP step in PCC.

Why not change the second question to ask the basis for EOP entry at 1025? We don t really want to ask directly about the 280 F.

Modified stem to provide initial conditions with a rate of change of DW temperature.

1st part now asked the earliest time a SCRAM is required.

2nd part asks at a later time what EOP path is controlling Rx pressure.

We think now High Cog

Complete

Question rewritten to address concerns.

Question is now SAT. drl 10/22/2021 92 H 2 M S 295038G2.1.25 K/A is met 93 F 2 N S 700000G2.1.7 K/A is met 94 F 3 B S G2.1.5 K/A is met 95 F 3 B E G2.1.35 K/A is met None of the second part answers are completely correct.

How about The fuel movement prerequisites must be completed prior to the initial fuel movement and ___. The second part would be at each shift changeover OR prior to restarting fuel movement after a delay of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

Incorporated suggestion.

Complete

Question rewritten as suggested above.

Question is now SAT. drl 10/22/2021 96 F 2 B S G2.2.5 K/A is met 97 F 2 B S G2.2.13 K/A is met 98 F 3 B E G2.3.11 K/A is met Is not logical. Why would someone think that off site release rates can be exceeded in an SO.

Why not change the second question to 31EO-EOP-101-2 is / is NOT the correct procedure to vent the PC ?

Incorporated suggestion in the 1st part.

Complete

Question changed as recommended above.

Question is now SAT drl 10/22/2021 99 F 2 N S G2.4.27 K/A is met 100 H 2 B E G2.4.30 K/A is met A not very plausible and D is weak Change the offsite release to 08:45.

Then A. would be 09:00 State and local.

Add a 08:00 Rx scram occurred and change D.

time to 0900

Suggestion to add Rx scram at 0800 incorporated.

Suggestion to change offsite release to 0845 incorporated.

Suggestion to modify D to 0900 incorporated and moved to A choice.

Modified notification time to state and locals to 0825

Modified general declaration to 0850

Reordered choices based on time.

Modified both time for notifying state and local in the choices.

Complete

Modifications strengthen the distractors plausibility. Question is now SAT. drl 10/22/2021

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