ML13324A521

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Initial Exam 2013-301 Final Administrative Documents
ML13324A521
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 11/18/2013
From:
NRC/RGN-II
To:
Southern Nuclear Operating Co
References
50-321/13-301, 50-366/13-301
Download: ML13324A521 (49)
v • d • e


Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Hatch Examination Date: 9/3-19/20 13 1i Examinations Developed by:

Written / Operating Test T Chief Task Description (Reference) Examiners Initials

-180 1. Examination administration date confirmed (C. .a; C.2.a and b)

-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

-120 3. Facility contact briefed on security and other requirements (C.2.c)

-120 4. Corporate_notification_letter_sent_(C.2.d)

[-90] [5. Reference material due (C. 1 .e; C.3.c; Attachment 2)]

{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES 301-1, ES-301-2, ES-301-5, ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.I.e and f; C.3.d)

{-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)}

{-45} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)

-14 10. Final license applications due and Form ES-20l-4 prepared (C.l.l; C.2.i; ES-202)

-14 1 1. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

-7 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 14. Final applications reviewed; I or 2 (if>10) applications audited to confirm qualifications I eligibility; and examination approval and waiver letters sent (C.2.i;_Attachment_4;_ES-202,_C.2.e;_ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3 .i)

Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply} to examinations prepared by the NRC.

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: HATCH 2013-301 Date of Examination: 09-03-2013 to 09-19-2013 Initials Item Task Description

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 R b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KJA categories are appropriately sampled. 4 ,cJ4 T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

42

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. pj4
2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major S transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number and u mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed W among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

C

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified J -1 Lit, -

(3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
b. Assess whether the 10 CFR 5541/43 and 55.45 sampling is appropriate. l
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

R d. Check for duplication and overlap among exam sections.

L e. Check the entire exam for balance of coverage. Ji

f. Assess whether the exam fits the appropriate job level (RD or SRO). C

(\ i\ II Pri Dte

a. Author l1Thovt /
b. Facility Reviewer (*) 1kZI 4 /4 1

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c. NRC Chief Examiner (#) L c jr /s-  ;

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d. NRC Superiisor P?IWT6L. iWE/d 7 7

(?74/) Fo,? flZ F,e,civK Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines C;

ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of s of the date 4

_4 of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination - 9-%2e/3 To the best of my knowledge, ,t,did nt divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of13 7-/1rm the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination /

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination q q To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE(1) DATE SIGNATURE (2) DATE NOTE

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liP! 7/ZM .SVPV 4 NOTES:

Ball, Anthony R. **

From: Yang, Shenteng Ted [styang@tva.gov]

Sent: Thursday, September 19, 2013 4:13 PM To: Ball, Anthony R.

Subject:

RE: ES-201 -3, Security Agreement Hi, Ball This is Ted Yang. Thank you for your email. How Are you doing??

I am now working for WA at Soddy Daisy, TN, Sequoyah Plant. Still work in the Simulator Group.

Yes, I will be adherence with the statement you quoted in the email to me.

When you get chance, welcome to visit Sequoyah See hi to Friends in Hatch, and in Simulator Group John, Jeff, Mike, Neil.

Take care, S. Ted Yang From: Ball, Anthony R. [1]

Sent: Thursday, September 19, 2013 4:04 PM To: Ohmstede, Gary T.; stedyanacamaiI.com; Yang, Shenteng Ted

Subject:

ES-20 1-3, Security Agreement Greetings, The ILT-08 NRC Exam is complete. lAW NUREG 1021, I am again required to obtain your signature on ES-201-3, Security Agreement.

ES-201-3, Security Agreement, states:

To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 09-02-13 thru 09-19-13. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

Please respond to me stating your adherence with the above statement. I will then print your email and attach to the ES-201-3, Security Agreement.

Please contact me if you have any questions.

Thank you again for your support in the exam process.

ab Anthony Ball ILT-08 NRC Exam Author Nuclear Ops Plant Instructor 1

ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination j I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of as o the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
2. Post-Examination r7//°3

/ 1 1 c

/

To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

1. 4 CA kJ-C&
2. c 46- 1 Lj ei1fz 3 q,4/,

1 qRi 1/23/is

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7. )-wJ Vs 8.. Do u c.i1- - 9/t4//3 9.

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NOTES:

Ball, Anthony R.

From: Ohmstede, Gary T.

Sent: Friday, September 20, 2013 7:49 AM To: Ball, Anthony R.

Subject:

Re: ES-201-3, Security Agreement I adhered to the exam security agreement and did not divulge to any unauthorized persons any information concerning the NRC licensing examinations. You can sign me off the ESA.

Gary Ohmstede Sent from my iPad On Sep 19, 2013, at 3:03 PM, Ball, Anthony R. <arbalksouthernco.com> wrote:

Greetings, The ILT-08 NRC Exam is complete. lAW NUREG 1021, I am again required to obtain your signature on ES-201-3, Security Agreement.

ES-201-3, Security Agreement, states:

To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 09-02-13 thru 09-19-13 From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

Please respond to me stating your adherence with the above statement. I will then print your email and attach to the ES-201-3, Security Agreement.

Please contact me if you have any questions.

Thank you again for your support in the exam process.

ab Anthony Ball ILT-08 NRC Exam Author Nuclear Ops Plant Instructor 912-366-2000 ext. 2411 912-379-8395 (pager) arball@southernco.com

ES-301 Administrative Topics Outline RO FINAL Form ES-301-1 Facility: PLANT E. I. HATCH ILT 8 Date of Examination: 09/02/2013 Exam Level: RO SRO-l D SRO-U D Operating Test No.: 2013-301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations M, R Heat Stress Stay Time Determination G2.1.26 Admin 1 (3 .4/3.6) ALL Conduct of Operations N, R Determine if section 7.4 of the Control Room Admin 2 Surveillance checks, 345 V-SUV-019-2, requires Torus Cooling to be placed in service.

G2.L07 (4.4/4.7) ALL Emergency Procedures/Plan M, R Determine the Evacuation Route During an Admin 4 Emergency.

G2.4.39 (3.9/3.8) RO ONLY Radiation Control M, R Evaluate a Radiation Work Permit (RWP) and Admin 5 Survey Map.

G2.3.7 (3.5/3.6) ALL NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

C

ES-301 Administrative Topics Outline SRO-I FINAL Form ES-301-1 Facility: PLANT E. I. HATCH ILT 8 Date of Examination: 09/02/2013 Exam Level: RO D SRO-I SRO-U 0 Operating Test No.: 2013-301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations M, R Heat Stress Stay Time Determination G2.1.26 Admin 1 (3.4/3.6) ALL Conduct of Operations N, R Determine if section 7.4 of the Control Room Admin 2 Surveillance checks, 34S V-SUV-019-2, requires Torus Cooling to be placed in service.

G2.1.07 (4.4/4.7) ALL Equipment Control N, R Review a Required Action Sheet (RAS) for an Admin 3 inoperable Tech Spec component.

G2.2.23 (4.6) SRO ONLY Radiation Control M, R Evaluate a Radiation Work Permit (RWP) and Admin 5 Survey Map.

G2.3.7 (3.5/3.6) ALL Emergency Procedures/Plan D, R Determine a Protective Action Recommendation Admin 6 (PAR).

G2.4.9 (4.0) SRO Only C NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

C

ES-301 Administrative Topics Outline SRO-U FINAL Form ES-3d-i Facility: PLANT E. I. HATCH ILT 8 Date of Examination: 09/02/2013 Exam Level: RO SRO-I D SRO-U Operating Test No.: 2013-301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations M, R Heat Stress Stay Time Determination G2.1.26 Admin 1 (3.4/3.6) ALL Conduct of Operations N, R Determine if section 7.4 of the Control Room Admin 2 Surveillance checks, 34SV-SUV-019-2, requires Torus Cooling to be placed in service.

G2.1.07 (4.4/4.7) ALL Equipment Control N, R Review a Required Action Sheet (RAS) for an Admin 3 inoperable Tech Spec component.

G2.2.23 (4.6) SRO ONLY Radiation Control M, R Evaluate a Radiation Work Permit (RWP) and Admin 5 Survey Map.

G2.3.7 (3.5/3.6) ALL Emergency Procedures/Plan D, R Determine a Protective Action Recommendation Admin 6 (PAR).

G2.4.9 (4.0) SRO Only 0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

C

ES-301 Control Room/In-Plant Systems Outline RO FINAL Form ES-301-2 Facility: PLANT E. I. HATCH ILT 8 Date of Examination: 09/02/2013 Exam Level: RO SRO-I D SRO-U D Operating Test No.: 2013-301 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System! JPM Title Type Code* Safety Function SF- 1 CRISIM 1 Normal Start of Recirc ASD D, L, S Reactivity Control 202001K6.02 (3.1/3.2) RO ONLY SF-2 CR/SIM 2 Perform a Manual S/U of the Core A, EN, L, M, S Reactor Water Inventory Control Spray With 1st Injection valve failure 209001A4.05 (3.8/3.6) ALL SF-3 CRJSIM 3 ED Using Head Vents D, S Reactor Pressure Control 295025A1.01 (2.9/3.0) RO SF-4 CRJSIM 4 Perform A Manual Initiation of LPCI L, M, S Heat Removal From the Core From Shutdown Cooling 206000A4.06 (4.3/4.3) RO SF-5 CR/SIM 5 Verify An Automatic Isolation Of D, E, EN, S Containment Integrity PCIS Group 223002A3.02 (3.5/3,5) ALL SF-6 CRJSIM 6 Perform a D/G Manual Start A, D, S Electrical Surveillance (Trip Failure) 364000A4.04 (3.7/3.7) RO C,

SF-7 CR/SIM 7 Perform RC- 1, Alternate Path A, M, S Instrumentation 212000A4.01_(4.6/4.6)_RO SF-9 CR/SIM 8 Place Control Room HVAC Systems A, C, M Radiation Release in the Isolation Mode (1st C012 fan fails) 290003A4.01 (3.2/3.2) ALL In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

SF-i PLANT 1 Vent the Scram Air Header on Unit I D, E, L, R Reactivity Control 212000A4,17_(4.1/4.1)_ALL SF-5 PLANT 2 From the Unit 2 Remote Shutdown D, E, R Containment Integrity Panel, Start RHR in Torus Cooling 295013 AAI.01 (3.9/3.9) RO PLANT 3 Crosstie Unit 2 Instrument Bus B to SF-6 D, E, Electrical Instrument Bus A 26200 1A2.07 (3.0/3.2) ALL

ES-301 Control Room/In-Plant Systems Outline SRO-I FINAL Form ES-301-2 Facility: PLANT E. I. HATCH ILT 8 Date of Examination: 09/02/2013 Exam Level: RO D SRO-l SRO-U D Operating Test No.: 2013-301 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System! JPM Title Type Code* Safety Function SF-2 CRJSJM 2 Perform a Manual S/U of the Core A, EN, L, M, S Reactor Water Inventory Control Spray With 1st Injection valve failure 20900 1A4.05 (3.8/3.6) ALL CR/SIM 3 SF-3 ED Using Head Vents D, S Reactor Pressure Control 295025A 1.01 (2.9/3.0) SRO-I SF-4 CR/SIM 4 Perform A Manual Initiation of LPCI L, M, S Heat Removal From the Core From Shutdown Cooling 206000A4.06 (4.3/4.3) SRO-I SF-5 CR/SIM 5 Verify An Automatic Isolation Of D, E, EN, S Containment Integrity PCIS Group II 223002A3.02 (3.5/3.5) ALL SF-6 CR/SIM 6 Perform a DIG Manual Start A, D, Electrical Surveillance (Trip Failure) 364000A4.04 (3.7/3.7) SRO-I SF-7 CR/SIM 7 Perform RC-1, Alternate Path A, M, S C

Instrumentation 212000A4.0l_(4.6/4.6)_SRO-I SF-9 CR/SIM 8 Place Control Room HVAC Systems A, C, M Radiation Release in the Isolation Mode (1st C012 fan fails) 290003A4.01 (3.2/3.2) ALL In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

SF-i PLANT 1 Vent the Scram Air Header on Unit 1 D, E, L, R Reactivity Control 212000A4.17_(4.1/4.1)_ALL SF-S PLANT 2 From the Unit 2 Remote Shutdown D, E, R Containment Integrity Panel, Start RHR in Torus Cooling 295013 AA1.01 (3.9/3.9) SRO-1 SF-6 PLANT 3 Crosstie Unit 2 Instrument Bus B to D, E, Electrical Instrument Bus A 26200 1A2.07 (3.0/3.2) ALL C

ES-301 Control Room/In-Plant Systems Outline SRO-U FINAL Form ES-301-2 Facility: PLANT E. I. HATCH lET 8 Date of Examination: 09/02/2013 Exam Level: RO D SRO-I D SRO-U Operating Test No.: 2013-301 Control Room Systems@ (8 for AC); (7 for SAC-I); (2 or 3 for SRC-U, including 1 ESF)

System / 3PM Title Type Code* Safety Function CRJS1M 2 Perform a Manual S/U of the Core SF-2 A, EN, L, M, S Reactor Water Inventory Control Spray With 1st Injection valve failure 209001A4.05 (3.8/3.6) ALL CR/SIM 5 Verify An Automatic Isolation Of SF-5 D, E, EN, S Containment Integrity PCIS Group II 223002A3.02 (3.5/3.5) ALL CR/SIM 8 Place Control Room HVAC Systems SF-9 A, C, M in the Isolation Mode (1st C012 fan fails) Radiation Release 290003A4.Oi (3.2/3.2) ALL In-Plant Systems@ (3 for AC); (3 for SRO-I); (3 or 2 for SAC-U)

PLANT 1 Vent the Scram Air Header on Unit 1 SF-i D, E, L, R Reactivity Control 212000A4.17_(4.1/4.1)_ALL PLANT 3 Crosstie Unit 2 Instrument Bus B to SF-6 D, E, Instrument Bus A Electrical 26200iA2.07 (3.0/3.2) ALL

@ All AC and SAC-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for AC / SAC-I / SAC-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 / 1 I 1 (EN)gineered safety feature - / - / 1 (control room system)

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

(A)CA 1/1/1 (S)imulator

(

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: E. I. HATCH Date of Examination: 09-03-2013 Operating Test Number: 201 3-301 Initials

1. General Criteria a b* c#
a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10CFR55.45, operational importance, safety function distribution).
b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1.a.) 4_! i.
d. Overlap with the written examination and between different parts of the operating test is within e.

acceptable limits.

It appears that the operating test will differentiate between competent and less-than-competent L 4L.

,)

applicants at the designated license level. f.. (

2. Walk-Through Criteria -- --
a. Each JPM includes the following, as applicable:
  • initial conditions
  • initiating cues
  • references and tools, including associated procedures
  • reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee
  • operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable C

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-3d-i and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.
3. Simulator Criteria -- --

The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.

Printed Name / S nat r ate a.

b.

Author Facility Reviewer(*)

/ /a//oJ3

/j2ii3

c. NRCChiefExaminer(#) ZeLi r./L,>-c.-y &
d. NRCSupervisor mLCH

ç 1 L. /th/i3 (k17NG) FO P7 F ,ve NOTE: The facility signature is not applicable for NRC-developed tests.

  1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

C

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: E. I. HATCH Date of Exam: 09-03-2013 Scenario Numbers: 1 /3/4 / 5 Operating Test No.:2013-301 QUALITATIVE ATTRIBUTES Initials a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.

c_t:__ 2J

2. The scenarios consist mostly of related events. c#_,
3. Each event description consists of
  • the point in the scenario when it is to be initiated
  • the malfunction(s) that are entered to initiate the event
  • the symptoms/cues that will be visible to the crew p

. the expected operator actions (by shift position) 4_i

  • the event termination point (if applicable)
4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. C.- ,
5. The events are valid with regard to physics and thermodynamics. -
6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
7. If time compression techniques are used, the scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints.

Cues are given.

8. The simulator modeling is not altered. A4
9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

J

10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301.
11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios). (\J_i (,
12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301 -5 (submit the form with the simulator scenarios).
13. The level of difficulty is appropriate to support licensing decisions for each crew position.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1 /3/4/5

1. Total malfunctions (58) (7 9 I/

i 9

2. MalfunctionsafterEOPentry(12) J iA/i . 4f
3. Abnormal events (24) 3 /4 / 3 / Lj
4. Major transients (12) / I /?./ I 4S
5. EOPs entered/requiring substantive actions (12) 2 //2/ 2 ç
6. EOP contingencies requiring substantive actions (02) I // /

3 ,4L

7. Critical tasks (23) /j 3/ 3 ,4_

ES-301 Transient and Event Checklist Form ES-301 -5 Facility: E. I. HATCH Date of Exam: 09-03-2013 Operating Test No.:2013-301 A E Scenarios P V 1 3 4 T P 5 M E o I L N CREW CREW CREW CREW N T

I T POSITION POSITION POSITION POSITION A C S A B S A B S A B S A B L R T 0 R T 0 R T u

A T 0 A T 0 M(*)

N y 0 C P 0 C P 0 C P 0 C P RU T P E

RO AX 2 5 6 3 4110 X NOR 1 T7TT SRO-l I/C 3,5 4,6 3,5 2,4 2,4 3,5 2,5 3,4 16 4 4 2 SRO-U MAJ 7,9 7,9 6 6 7,9 7,9 6 6 6 2 2 1 D TS NA NA NA NA NA NA NA NA NA 0 2 2 AX 2 5 63 4110 RO NOR ii SRO-l I/C 3,4, 2,3, 2,3, 2,3, 16 4 4 2 X 5,6 4,5 4,5 4,5 SRO-U MAJ 7,9 6 7,9 6 6 2 2 1 TS 4,6 2,4,5 2,5,6 2,4,5 11 0 2 2 o- NOR

+/-z_li_

I/C 3,4, 2,3, 2,3, 2,3, 16 4 4 2 SRO-U 5,6 4,5 4,5 4,5 X MAJ 7,9 6 7,9 6 6 2 2 1 TS 4,6 2,4,5 2,5,6 2,4,5 11 0 2 2 NOR o-i I/C 442 SRO-U MAJ 2 2 1 D TS 022 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-i 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 SAOs 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 Instant SRO additionally series 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 instrument or component malfunctions on a 1 -for-i 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.

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ES-301 Competencies Checklist Form ES-301-6 Facility: Plant E. I. Hatch Date of Examination: 09/03/2013 Operating Test No.: 201 3-301 APPLICANTS RO X RO E RO E SRO-l D SRO-l X SRO-I SRO-U D SRO-U E SRO-U x Competencies SCENARIO SCENARIO 1 3 4 5 1 3 4 5 1 3 4 5 Interpret/Diagnose All All All All All All All All All All All All Events and Conditions Comply With and All All All All All All All All All All All All Use Procedures (1)

Operate Control All All All All All All All All N/A N/A N/A N/A Boards(2)

Communicate All All All All All All All All All All All All and Interact Demonstrate N/A N/A N/A N/A All All All All All All All All Supervisory Ability (3)

Comply With and N/A N/A N/A N/A 4,6 2,4,5 2,5,6 2,4,5 2,4,5 2,5,6 2,4,5 4,6 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

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.

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ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/2 233000K4.08 ORIGINAL K/A:

233000 Fuel Pool Cooling and Clean-up RO QUESTION K4. Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7)

K4.08 Pool cooling during loss of coolant accident:

BWR-6 2.6* 2.8 Plant Hatch is not a BWR-6.

1/1 295031EA1.0l ORIGINALK/A:

29503 1EA1.01 Reactor Low Water Level RO QUESTION EA 1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: (CFR: 41.7 / 45.6)

C EA1.04 High pressure core spray: Plant-Specific ... 43* 4.2 Plant Hatch does not have a High Pressure Core Spray System.

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rii4o1,Rev.9 BWR Examination Outline Form ES-481-1 Facility Hatch Dateof Exam: 2013 RO KIA Category Points SRO-Only Points Tier Group KKKKKKAAAAG A2 G* Total 1

2345 61 234* Total

1. i 433 34 20 4 3 7 I Emergency&

2 7T T T 7 2 1 3 Abnormal Plant NIA NIA EvOlUtions Tier Totals 5 5 6 4 10 27 1 32313223232 26 3 2 5 2.

Plant 2 TTT7rTT 12 0 2 1 3 Systems TlerTotals

3. GenerIc Knowledge and AbIlities 1 2 3 4 10 1 2 3 4 7 CategorIes 3 3 2 2 2 2 1 2
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K1A category shall not be less than two).
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 SF10-only exam must total 25 poInts.

3. Systemslevolutlons within each group are Identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally Important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selectIng a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K1As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SF10 ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers I and 2 from the shaded systems and KM categories.
7. The generic (G) KIAs In liars I and 2 shall be selected front Section 2 of the KM Catalog, but the topics must be relevant to the applicable evolution or system.
8. On the following pages. enter the KIA numbers, a brief description of each topic, the topics Importance ratings (IRs) for the applicable hcenae 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 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For TIer 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs,

ES-401, REV 9 T1G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295001AK2.06 Partial or Complete Loss of Forced 3.8 3.8 Reactor power Core Flow Circulation/i & 4 DIElElElElI El El 295003AK1 .02 Partial or Complete Loss of AC / 6 3.1 E1ElElEJElElElEl El El Load shedding 295004G2.1 .7 Partial or Total Loss of DC Pwr /6 4.4 4.7 Ability to evaluate plant performance and make ElElElElElElEl El operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

2950O5AK02 Main Turbine Generator Trip / 3 3.4 3.5 Recirculation pump downshift/trip: Plant-Specific...

El El El Li El LI El El LI LI 295008AA1.O1 SCRAM/i 4.2 4.2 El El El El El El El El LI El RPS 29501 SAA2.07 Control Room Abandonment / 7 3.2 3.4 El El El El El El El F] El El El Suppression chamber pressure 29501 8AK06 Partial or Total Loss of CCW / 8 3.3 3.3 Increasing cooling water flow to heat exchangers El El l El El El El El El El El 295019AA2.02 Partial or Total Loss of Inst. Air/8 3.6 3.7 Status of safety-related instrument air system loads (see El El El El El El El lI El El El AK2.1 AK2.19) 295021 G2.2.40 Loss of Shutdown Coding / 4 El Li El El El El El El El El It Ability to apply technical specifications for a system.

296023AA2.03 Refueling Acc Cooling Mode / 8 3.3 3.8 Airborne contamination levels El El El El El El El El El LI 295024EA2.06 High Dnjwell Pressure /5 4.1 4.1 ElElElElElElElL1ElEl Suppression pod temperature Page 1 of 2 12/4/2012 6:47 AM

ES-401, REV9 T1G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR 1(1 1(2 K3 1(4 1(5 K6 Al A2 A3 A4 (3 TOPIC:

RO SRO 295025(32.1.27 High Reactor Pressure / 3 3.9 4 [I LI OEJL1L Knowledge of system purpose and or function.

295026EK3.04 Suppression Pool High Water Temp.! 3.741 SBLC injection LI LI LI LI [IL]

5 295028EA1.03 High Drywell Temperature /5 3.9 3.9 Diywell cooling system LI II LI LI LI LI 295030EK1.02 Low Suppression Pool Wtr Lvi / 5 3.5 3.8 Pump NPSH

[I LI LILI DLI 295031 EAI.04 Reactor Low Water Level / 2 4.3 42 High pressure core spray: Plant-Specific LI iD LI LID 295037EK2.12 SCRAM Condition Present and Power 3.6 3.8 Rod control and information system: Plant-Specific...

Above APRM Downscale or Unknown DUEL JEI LID [ID

/1 295038EK1.01 High Off-site Release Rate! 9 2.5 3.1 Biological effects of radioisotope ingestion DE1LiL1 LID LIE]

600000AK1 .01 Plant Fire On Site/8 2.5 2.8 Fire Classifications by type E1DL1LJ JDIuLID 70O000K2.03 Generator Voltage and Electric Grid 3.0 3.1 Distrurbancecs DDDDEILILILJDLI Sensors, detectors, indicators Page 2012 12/4/2012 6:47AM

ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IA Ki K2 K3 K4 KS 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 296009AK1.02 Low Reactor Water Level /2 3.0 3.1 [] [] [] LI [] LI [ LI LI] Recirculation pump net positive suction head: Plant-Specific 2950IOAA2.06 High Drywell Pressure / 5 3.6 3.6 [] [j (] ]J [] [] )) Drywell temperature 295012AK3.01 High Drywell Temperature / 5 3.5 3.6 [] LI [I LI [1 LI LI LI LI LI Increased drywell cooling 29501 3G2.4.18 High Suppression Pool Temp. / 5 3.3 4.0 LI [] [] [] [] LI [ LI LI LI Knowledge of the specific bases for EOPs.

295017AA1.05 High Off-site Release Rate /9 2.7 3.2 LI LI LI LI LI LI [] fl ] fl ] SPDS/ERIS/CRIDSIGDS: Plant-Specific 295035EA1.01 Secondary Containment High 3.6 3.6 LI ( LI LI LI LI J LI LI LI LI Secondary containment ventilation system Differential Pressure / 5 5000008(2.07 High CTMT Hydrogen Conc. /5 3.2 3.7 [] [1 LI LI LI LI LI LI LI LI Drywell vent system Page 1 of 1 12/4/2012 6:47 AM

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ES-401, REV 9 T2GI BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 4.6 [J [] [] fl [] [] [] [] [] ] Ability to recognize system parameters that are entnf 264000G2.2.42 EOGs 3.9 ( level conditions for Technical Specifications

[] [] [] Air dryer and filter malfunctions 300000A2.O1 Instrument Air 2.9 2.8 [] [] [] [J [] [] []

Containment air 300000K1.03 Instrument Air 2.8 2.9 [J fl [] [] [] [] [] fl

[] [] fl [] CCW flow rate 400000A1.O1 Component Cooling Water 2.8 2.8 [] [] [] [] [] []

Page 3 of 3 12/4/2012 6:47 AM

ES-401, REV 9 T2G2BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki 1<2 1<3 1<4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 201 003A2.09 Control Rod and Drive MechanIsm 32 3.4 [] [] El El El El El 1 El LI [] Low reactor pressure 2040001<1.15 RWCLJ 3.1 3.2 [] [] El [1 C] [1 El C] C] C] Leak detection: Plant-Specific 215001A4.03 Traversing In-core Probe 3.0 3.1 C] C] [] [j C] LI C] [] [] C] Isdation valves: Mark-I&II(Not-BWR1) 21500202.4.4 RBM 4.5 4.7 C] C] C] C] [] [] [] [] [] [j )) Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

223001 A3.05 Primary CTMT and Aux. 4.3 4.3 [] C] C] C] C] C] C] C] )) [j C] Drywell pressure 226001K8.04 RHR/LPCI: CTMT Spray Mode 2.7 2.7 C] [] [] [] [] [] [] C] C] C] C] Keep fill system 2330001<4.08 Fuel Pool CoolingfCleanup 2.6 2.8 C] [J [] J C] [] C] [] [] [] [] Pool cooling during loss of coolant accident: BWR-6 239001 K5.05 Main and Reheat Steam 2.8 2.8 C] C] [] [] (j [J C] C] [] C] C] Flow indication 2410001<303 Reactor/Turbine Pressure Regulator 3.7 3.8 [] C] [] [] [] [] [] [] C] C] Reactor water level 245000K4.10 Main Turbine Gen. fAux. 2.6 2.7 [] C] [] ] El [1 C] C] [1 C] [] Extraction steam 268000A1.02 Radwaste 2.6 3.6 E1C]C]C]EIC] C]C] El LI Off-site release Page 1 of 2 12/4/2012 6:47AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki 1<2 1<3 K4 1<5 1<6 Al A2 A3 A4 G TOPIC:

HO SRO 286000K2.02 Fire Protection 2.9 3.1 LI i LI El LI El E] LI [I El El 1mWs Page2of2 12/4/2012 6:47AM

ES-401, REV9 T3 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 1(2 1(3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.l Conductof operatIons 3.8 4.2 [J LI [] [] El El E] E] El El Knowledge of conduct of operations requirements.

02.1.20 Conduct of operations 4.6 4.6 [1 Li El El El El El [1 El El Ii Ability to execute procedure steps.

02.1.8 Conduct of operatIons 3.4 4.1 El El El LI El El El El LI LI Ability to coordinate personnel activities outside the control room.

G2.2.21 Equipment Control 2.9 4.1 El LI El El El LI LI LI El El Knowledge of pre- and post-maintenance operability requirements.

G2.2.22 Equipment Control 4.0 4.7 El LI LI El LI El El El El Ii Knowledge of limiting conditions for operations and safety limIts.

G2.2.36 Equipment Control 3.1 4.2 El El LI El El El LI El El LI Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 02.3.11 Radiation Control 3.8 4.3 El El LI El LI LI El El El El II Ability to control radiation releases.

02.3.13 Radiation Control 3.4 3.8 El LI LI El El El El [I LI LI Knowledge of radiological safety procedures pertaining to licensed operator duties 02.4.16 Emergency Procedures/Plans 3.5 4.4 El El El El El El El El El El IJ Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

02.4.5 Emergency Procedures/Plans 3.7 El El El El El El El El El El Knowledge of the organization of the operating procedures network for normal, abnormal and emergency evolutions.

Page 1 of 1 1214/2012 6:47AM

ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 295004M2.02 Partial or Total Loss of DC Pwr /6 *° Extent of partial or complete loss of D.C. power 295015G2.2.37 Control Room Abandonment / 7 3.6 4.6 [] EJE1LWDLI Ability to determine operability and!or availability of safety related equipment 29501 9G2.1 .28 PartIal or Total Loss of Inst. Air! 8 4.1 4.1 C L1LiL1flU Knowledge of the purpose and function of major system components and controls.

296023AA2.02 Refueling Acc Coding Mode/ 8 3.4 3.7 [] UOEE11Ufl Fuel pool level 295024EA2.02 High Drywelt Pressure 15 3.9 4.0 [] UflLiÜLH1OL1E1 Drywell temperature 295037G2.4.49 SCRAM Condition Present and Power 4.6 4.4 Above APRM Downscale or Unknown

[] DLLLOfl1 Ability to perform without reference to procedures those actions that require immediate operation of system

/1 components and controls.

700000AA2.07 Generator Voltage and Electric Grid 3.6 4.0 Distrurbancecs

[] UDEJfliLHTh Operational status of engineered safety features Page 1 of 1 12/4/2012 6:47AM

ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1(1 K2 1(3 1(4 1(5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 4.1 4.1 [] [] I [] [] Reactor pressure 295007AA2.O1 High Reactor Pressure / 3 [] [J [] []

Knowledge of abnormai condition procedures.

295012G2.4.1 1 High Drywell Temperature / 5 4.0 4.2 Q fl [] [] [] [][] fl [J [] {}

295032EA2.03 High Secondary Containment Area 3.8 4.0 [] U LI LI LI LI I] []LI LI Cause of high area temperature Temperature 15 Page loll 12/4/2012 6:47AM

ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1(1 1<2 1(3 1(4 1<5 1(6 Al A2 A3 A4 G TOPIC:

Rb SHO 20900tG2A.49 LPCS 4.6 4.4 Ability to perform without reference to procedures those El El [] [] [] fl Q [] []

actions that require immediate operation of system components and controls.

21500ati2.05 IRM 3.3 3.5 fl El El El LI LI [] LI [] [] Faulty or erratic operation of detectors/system 218000A2.05 ADS 3.4 3.6 LI LI El El LI LI [1 F] LI [] [] Loss of A.C. or D.C. power to ADS valves 261000A2.08 SGTS 2.4 2.7 [1 LI [1 [1 LI El LI ll El LI LI D.C. electrical failure 263000G2.4.8 DC Electrical DistrIbution 3.8 4.5 [1 El LI El El LI LI LI Li LI I] Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Page 1 of 1 12/4/2012 6:47AM

ES-401, REV 9 SROT2G2 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 201 006A2.06 RWM 2.9 3.3 [] [] (} [] E] [] El j [] 0 fl Loss of reactor water level control Input: P- Spec(Not Excessive outleakage 290001A2.02 SecondaryCTMT 3.5 3.7 [] fl Q C LI [1 [1 ll [1 [1 LI Ability to recognize abnormal indications for system 290003G2.4.4 Control Room HVAC *5 [] LI [] LI [E] El U [] El Li i operating parameters wticIi are entry-level conditions for emergency and abnormal operating procedixes.

Page 1 of 1 12/412012 6:47 AM

ES-401, REV 9 SRO T3 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR k1K2K3K4K5K6A1A2A3A4 TOPIC:

RO SRO 02.1.3 Conduct of operations 3.7 3.9 ÜÜDDOLfl Knowledge of shift or short term relief turnover practices.

02.1.36 Conduct of operations 3.0 4.1 Knowledge of procedures and limitations Involved in core alterations G2.2.18 Equipment Control 2.6 3.8 DflLJLi Knowledge of the process for manang maintenance activities during shutdown operations.

02.2.30 Equipment Control 3.9 Knowledge of less than one hour technical specification action statements for systems.

02.3.4 RadIation Control 3.2 U1flüOLIL1L1L1 Knowledge of radiation exposure limits under normal and emergency conditions 02.4.38 Emergency Procedures/Plans 2.4 Ability to take actions called for in the facility emergency plan, includIng supporting or acting as emergency coordinator.

4.5 Ability to recognize abnormal indications for system G2.4.4 Emergency Procedures/Plans flI1IOE1Dl operating parameters which are entiy-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 12/4/2012 6:47 AM

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 HATCH NUCLEAR Plant 201 3-301 September 2013 SRO Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

Enter the level of difficulty (LOD) of each question using a 1 5 (easy

. difficult) rating scale (questions in the 2 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:

The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

The stem or distractors contain cues (i.e. clues, specific determiners, phrasing, length, etc).

The answer choices are a collection of unrelated true/false statements.

The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

Check the appropriate box if a job content error is identified:

Fhe 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).

Fhe 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).

Fhe question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

Fhe question requires reverse logic or application compared to the job requirements.

Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

. 6. Enter the question source: Bank (B), Modified (M), or New (N). Check that Modified (M) questions meet criteria of ES-401 Section D.2.f.

1. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

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

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only SRO ONLY Questions 1 LOD. Consider this a K/A match based on the fact that Hatch doesnt use RWLC inputs into RWM. Is it necessary to use (signature is NOT 76 H X M illowed)? (Accepted question as is. SRO is required to know what is required) 1 LOD. Why would anyone not open the CS pumps discharge valve after tarting the pumps? Is there a mm flow line. This question appears to e a direct lookup because this is open reference. The stem directs the 77 F X X N U pplicant to the date (4/12/2013). I do not see where a time of 02:00 ouId come from. (Changed pressure to 475 psig. Licensee xplained why it was not a direct lookup. Changed LOD to a 2.

uestion should have been S) 78 H 1 B S OK. Changed to 2) 3 Need to make sure the pressure reduction cannot be accomplished with 5/? lternate RPV pressure control (Rewrote question to make sure there 79 H M iere not two correct. As provided, there could have been two correct

[nswers. Question could have been identified as an U) 80 F 2 M S OK) 81 H 2 M S 82 F 1 N S LOD (OK. Changed LOD to 2) 83 H 2 N S OK) 2 Explain the plausibility of distractors B and D second part. It appears that 84 F/H his question can be answered with RO only knowledge. (LOD Will X X B U MOVE ON) (8/7 reviewed new question and concluded it was OK.

Jent from an F to and H with a LOD of 2) (Was a U) 2 Need to discuss references provided (Change NUE to Site Area 85 H M Emergency) 86 H 1 B S OK) 2 87 H M U/SI Need to discuss why this is an SRO question. As written it appears that he question can be answered with purely RO knowledge. (made a

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 HATCH NUCLEAR Plant 201 3-301 September 2013 SRO i thange distractors A & B. I still consider this an easy question) 88 H Need to make sure that this is a K/A match. Discuss purpose & function.

N OK) 1 LOD. Why do you consider this SRO? SPL is TS entry condition.

ollowing an isolation of a system, and the conditions which caused the 89 H isolation has not cleared, why would anyone consider restarting the M U ystem? What was the position of the bundle after the fall? It appears that his question can be answered with system knowledge. (OK as written.

Should not have been a U).

90 H 2 X? N S? Need to have discussion on why this is a K/A match (OK) 91 H 2 N S OK) 1 LOD. It appears that this question can be answered with system 92 H nowledge and knowledge of immediate scram actions. Also based on X N l_l/S knowing that all rods did not fully insert and RX power is at 8%, why would anyone not know to prevent injecting into the RPV? (OK) 93 H 3 M S OK) 2 onsider changing the time the scram was inserted. And changing the 94 F N E imes in the distractor to match another time in the stem. (Made changes.

)K) 95 F 2 M S OK) 96 F 2 N S OL) 2 Not sure why 30 minutes is plausible. Not sure of any procedure that requires a TS time requirement to be completed in 30 minutes. Consider 97 F M U using 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 15 minutes which is 125% of the action statement. (Identified 30 minute time and 2 times requirement. Made changes as necessary. OK Not a U) 1 LOD. This appears to be general rad worker training. Question 99 98 F appears to match this K/A and would be a better question (Look at N

hanging -- Will use question 99) (Discussed on 817 Question OK as ritten. Old question was U) 1 LOD (Will find new question) Moved to 98. Wrote new question.

99 F N Reviewed question on 8/7 and determined it was OK. LOD -P2).

2 Is there sufficient information in the stem concerning oil pressure? (Not a 100 H N S? problem with pressure. ( Need to figure out changes in oil pressure aver time that would cause EDG to trip. Removed highest from stem

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 HATCH NUCLEAR Plant 201 3-301 September 2013 SRO ES-401, Rev. 9 2 Form ES-401-9

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 HATCH NUCLEAR Plant 2013-301 September 2013 RO Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).

Check the appropriate box if a psychometric flaw is identified:

The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

The answer choices are a collection of unrelated true/false statements.

The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

Check the appropriate box if a job content error is identified:

he 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).

he 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).

he question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

he question requires reverse logic or application compared to the job requirements.

5 Check guestions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

. 6. Enter the question source: Bank (B), Modified (M), or New (N). Check that Modified (M) questions meet criteria of ES-401 Section D.2.f.

Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

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

Q#

1.

LOK 2.

LOD

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6. -E1 (F/H) Stem Cues T/F Cred. Partial Job- Minutia #/ Back-(1-5)

Focus Dist. Link units ward Q SRO U/E/S I Explanation K/A Only onsider adding information in the stem concerning accumulator CRD 1 H 3 X X N E emperature. This should add to the plausibility of the distractors. (Added RDM temperature. OK) 2 F 2 N S 3 H 2 N S onsider rewording the stem. Give a time for all conditions and add time 4 H 2 vhen RWL returned to normal. Then ask: Based on the given plant M E onditions, 2E1 1-F008, RHR SDC Suction valve will be and RHR

,ump will (Made change as suggested. OK)

1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 7.

(F/H) 5) Stem Cues T/F C 1 red. [Partial Job- Minutia #1 [Back- Q SRO B/M/N UIEIS Explanation Focus Dist. Link unitsi ward K/A Only 5 F 2 B S 6 H 2 N S 7 F 2 X heck to grammar in the stem. Is there a need to tell them the TS N F required flow rates? (Added flow rate. OK) 8 F 2 N S 9 H 3 M S 10 F 3 M S Please explain why maximizing CRD flow is plausible (maximizing CR0 low would have the opposite effect on stratification as explained by 11 H 2 N s, he licensee. Reviewed supporting information. RWCU is maximized

,nd effect stratification. OK) 12 H 2 Is TIP A has been given needed? (Removed information as M

wggested and reworded the stem. OK) 13 H 2 N S Is there a correct answer? Will depressing the Drive-In button once 14 F 2 X ,ccomplish the task? DistractorA is not plausible. Explain why turning B

power off and then on is plausible. (Made minor changes to stem and distractors. Question should have been an E. OK) 15 H 2 N S 16 F 2 M S 17 F 3 N S Look at the grammar in the stem. Add units to reactor pressure. Make 18 H 3 X N F ure there are not correct. Need to discuss HPCI injection. (HPCI will two have isolated based on plant condition. Therefore it will not start. OK).

19 H 2 - ---

M S Vhy do you consider distractors B and C plausible? Do we expect an RO 20 F 2 X N U/S? o know the information contained in the EOP? Changed distractor B & C (Wrote new question. OK. Question as submitted was U) 21 H 2 N S 22 F 2 B S

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 HATCH NUCLEAR Plant 201 3-301 September 2013 RO

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 7.

Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia r

(F/H) (1-5) #1 Back- Q SRO U/E/5 Explanation Focus Dist. Link unitsi ward K/A Only Need to discuss changing setpoint. Could a number lower than 170 be 23 F 2 N E used and still be incorrect? (Changed set point to include a Unit I

etpoint. OK) 24 F 2 N S 25 H 2 M S OK) 26 F 2 B S Distractors B and D are not plausible. I cannot think of any time when you vould stop to test trip circuit. Any testing of such would have been done 27 F 3 X B U before starting a component. (Discussed why B & D are acceptable.

Reviewed procedure which supported use of 3500 RPM. OK Should beE)

Explain plausibility of distractors. On a loss of bus is it true that the lampers go to their fail safe position? In this case, is it not open? Please xplain why anyone would want to start a SBGT fan with dampers close.

28 H 3 X X N U There are two answers given in the second part of the question. The answer given identifies the procedure and action required to be

,erformed. (This question test unit differences. Unit one fail open

,nd Unit 2 open OK. Question should have been a S)

I do not think this is an RO question. As written it ask the applicant to recall information from one of the EOP Flow Charts. Information 29 F 2 rovided doesnt provide sufficient information to support selection of N UI answer. According to licensee this question is acceptable based on lesson planlobjective. Changed one of the distractors. Should have been an E) Look at question 63) 30 H 3 M S 31 H 2 M S 32 F 2 N S 33 H 3 M S 34 H 2 M S 35 H 2 M S

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 7.

Q# LOK L0D Stem Cues T/F Cred. Partial Job- Minutia #1 Back- B/M/N (F/H) (1-5) Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 36 H 3 N S 37 H 2 M S 38 F 2 N S Added For the above conditions: OK) deed to make sure that this is an acceptable RO question. The question 39 F 3 N S? equires the applicant to recall TS bases. Is this require RO knowledge.

Made a change to wording in the stem. RO learning objective) 40 F 3 M S I do not see the plausibility of plant availability (distractors B and D). Plant 41 F 2 X availability could be seen as the purpose of any runback which prevents a B

  • reactor scram. (Changed distractors B & D to add only. OK after discussion. Should have been an E) 42 H 3 N S 43 F 3 N S 44 F 3 Is because this value exceeds a bases? (Expect RO knowledge N

is stated by the licensee. OK. S) 45 H 3 M S 46 F 3 N S 47 H 2 M S onsider rewording the stem. Based on the current plant conditions, 48 H 3 X B E ihich one of the following identify final MSIV position? (Revised as uggested. OK)

H3 B S Jeed to discuss location of main steam lines. Explain why anyone would 50 H 2 N 5? hink that the fuel pool racks would be uncovered (question is OK.

Discussed system design and procedural requirements) 51 F 2 .

M S 52 H 2 M S 53 H 2 M S 54 H 2 M S 55 H 3 B S

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 HATCH NUCLEAR Plant 201 3-301 September 2013 RO

1. 2. 3._Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 7.

Q# LOK LOD SRO B/M/N U/E/S (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q Explanation Focus Dist. Link units ward K/A Only 56 H 2 M S 57 F 2 Need to discuss when it might be necessary to operate both trains of B

  • SBGT.(question is OK) 58 H 2 B S 59 F 2 M S 60H3 N S 61 F 1 X LOD. Need to discuss plausibility of distractors C and D. (Question B LJIE determined to be acceptable OK) 62 F 2 Are there other panels with RBCCW indications? (Changed 700 to 602.

N

)K) 63 H 3 M S OK) 64 F 1 B S .00 65 H 3 M S 66 F 1 X .OD. Identify why six is plausible or is there some other number, such as B

, that is associated with another procedure. (Changed 6 to I OK) 67 F 2 M S OK) 68 F 1 X LOD. Based on my review of the procedure, the answer identified may N

not be correct. (Question determined to be acceptable OK) 69 H 2 )uestion 69 doesnt match what is in LXR (Provided new question. OK.

M Vas a U.)

70 H 3 M S 71 F 2 S S 72 F 2 M S 73 F 2 B S 74 H 2 M/N? S

1 2. 3. Psychometric_Flaws 4. Job Content Flaws 5. Other 6. 7. 7.

Q# LOK LOD B/M/N (F/H) (1-5) Stem Cues TIE Cred Partial Job Minutia #1 Back Q SRO UIEIS Explanation Focus] ward K/A Dist.

J Link [units] Only =

LOD 75 F 1 S

} ] }

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 HATCH NUCLEAR Plant 2013-301 September 2013 RO I I 1. I 2. I 3. Psychometric Flaws I 4. Job Content Flaws 5. Other II 6. I I 7. HII I #IL.cKl_.clI I I I I I I B/M/N I (F/H) (1-5) Stem ICuesi T/F Cred. Paa1 Job- Minutia #1 Back- I Q= SRO I U/E/S I Explanation Ii I Focus Dist. Link units ward K/A Only I 0

ES-401, Rev. 9 2 Form ES-401-9 ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Azc (Zt3-p ) Date of Exam: çf//9/,) Exam Level: RO 11 SRO Initials

. Item Description a b c

1. Clean answer sheets copied before grading M3K I
2. Answer key changes and question deletions justified and documented I41\ iV/4
3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations) 11T? -.
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as_applicable,_+/-4%_on_the_SRO-only)_reviewed_in_detail
5. All other failing examinations checked to ensure that grades j are justified qA.
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of_questions_missed_by_half_or_more_of the_applicants Printed Name/Si nature Date
a. Grader M
b. Facility Reviewer(*) Al/A
c. NRC Chief Examiner (*) ci
d. NRC Supervisor (*) /)/4-/r

(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

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0

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m Cl) 0 0)

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: ( o> Date of Exam: 1/i 9 (3Exam 4 Level: RO SRQ Initials Item Description a b c

1. Clean answer sheets copied before grading
2. Answer key changes and question deletions justified and_documented
3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations) 4
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, s applicable, +/-4% on the SRO-only) reviewed in detail Ni\
5. All other failing examinations checked to ensure that grades \/,,

are justified A//A

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants rdLS c Printed Name/Signature Date
a. Grader ojtz/13
b. Facility Reviewer(*)
c. NRC Chief Examiner (*) jcI, L .
d. NRC Supervisor (*) /t4Aih 4-$12c ,z)1l42

(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

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