Text

Initial Exam 2012-302 Final Administrative Documents
	ML13274A665
Person / Time
Site:	Sequoyah
Issue date:	09/27/2013
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	Download: ML13274A665 (53)
	v • d • e

ES-201 Examination Preparation Checklist Form ES-201-1 December Facility: Sequoyah Date of Examination: 2012 lj Examinations Developed by:

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

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

-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)] , 4

{-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-Ps, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.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-201-4 prepared (C.1.l; C.2.i; ES-202)

-14 11. 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; 1 or 2 (if>10) applications audited to confirm qualifications / 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) 1

-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 FitY Sequoyah Nuclear Station Unit 1 & 2 Date of Examination: 12/03/12 Initials Item Task Description b*

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1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

41, R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. r

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.

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, S and major transients. 47 _**

I .

b. Assess whether there are enough scenario sets (and spares) to test the projected number

--b M

u and 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 A at least one new or significantly modified scenario, that no scenarios are duplicated -

T from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

0 c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

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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 W distributed 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 / L 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 C on the form.

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 mod ified b j (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 y of applicants and ensure that no items are duplicated on subsequent days. a

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. -Lb

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

N c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 3 r

d. Check for duplication and overlap among exam sections. . -.X .1 A e. Check the entire exam for balance of coverage. ir L

f. Assess whether the exam fits the appropriate job level (RO or SRO). X, r D

a. Author Michael Buckner

b. Facility Reviewer (*) Steven Tuthill I ,..

IIf2/,L NRC C[ef Examiner (#) i/

Note: # Independent NRC reviewer initial items in Column C; chief examiner concurrence required.

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ES-201, Page 25 of 27 C.

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

1. Pre-Examination I acknowledge that I have acquired spe aUzed knowledge about the NRC licensing examinations scheduled for the week(s) of 12103-1012012 as of the date of my signature. I agree that I will not knowin y divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner, understand that I am not to struct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until compl on of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceabIe 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 req cements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation oi ne examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examine my indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not ( uIge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 12/03-1012012 . From the nte that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to tho 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 spe ialized knowledge about the NRC licensing examinations scheduled for the week(s) of 12103-1012012 as of the date of my signature. I agree that I will not knowinc iy 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 nstruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until compi on of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acci able 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 req. ements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation ol re examinations and/or an enforcement action againstme or the facility licensee. I will immediately report to facility management or the NRC chief examinE any indications or suggestions that examination security may have been compromised.,

2. Post-Examination To the best of my knowledge, I did not c vulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 12103-1012012 . From the ?.te that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to tho 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 A9reement Form ES-201-3

1. Pre-Examination I acknowledge that have acquired spel alized knowledge about the NRC licensing examinations scheduled for the week(s) of 12103-10/2012 as of the date of my signature. I agree that I will not knowinJy 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 nstruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until compL on of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is accE table 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 rec :ements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation o[ ;ne examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examino any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not c ulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 12/03-10/2012 . From the tethatl entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to thc . applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-301 Administrative Topics Outline Form ES-301 -1 Facility: Seguovah Nuclear Station 1 & 2 Date of Examination:12/3-7 2012 Exam Level: RO LI SRO X Operating Test No: 2012-302 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations R, D K/A 2.1.25 (4.2) Determine The Operability Of A Boric Acid Tank Before Use.

Conduct of Operations R, D K/A 2.1.7 (4.4) Perform A RCS Void Determination And Apply The Result To Determine RCS Pump Sweep Requirements.

Equipment Control R, N K/A 2.2.14 (4.3) Perform a Risk Assessment Using EQOS. (New Plant Process)

Radiation Control R, N K/A 2.3.14 (3.8) Determine Reporting Requirements For A Contaminated And Injured Person.

Emergency Procedures/Plan R, M K/A 2.4.41 (4.6) Classify The Event Using The EPIP-1 and Determine Protective Action Recommendations..

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)

A.1.a While acting as the on-shift Unit Supervisor, the examinee will interpret Boric Acid Tank level and boron concentration and apply the data using the Technical requirements Manual Section 3.1.2.6 figure to determine if the Boric Acid Storage Tank may be placed in service.

A.1.b While acting as an on-shift Unit Supervisor during a refueling outage, the examinee will calculate the volume of water required to fill the voids in the RCS and to raise pressure and determine that individual RCP Pump sweeps are required to restore the RCS from the outage condition.

A.2 While acting as the Operations Work Control SRO and given a hypothetical maintenance situation, the examinee will perform a Risk Assessment using the Equipment Out of Service computer program. As a result of performing the test case, the examinee will conclude the Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multipliers change and the LERF indicator changes from green to orange.

A.3 While acting as an on-shift Unit Supervisor during a refueling outage, the exam inee will receive the report of a contaminated injured man. The examinee will be directed to list all required reports to outside agencies and to list by title, the internal TVA notification requirements.

A.4 While acting as the Site Emergency Director and given data for a plant emergency, the examinee will use EPIP-1 EMERGENCY PLAN CLASSIFICATION MATRIX and interpret the data to determine the correct Emergency Classification of General Emergency. The examinee will then use EPIP-5 GENERAL EMERGENCY to determine the correct Protective Action Recommendation.

ES-301 Administrative Topics Outline Form ES-301 -1 Facility: Sepuoyah Nuclear Station I & 2 Date of Examination:12/3-7 2012 Exam Level: RO X SRO Operating Test No: 2012-302 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations R, D K/A 2.1.26 (3.4) Perform a Containment Formaldehyde Stay Time Calculation.

Conduct of Operations R, M K/A 2.1.7 (4.4) Monitor Critical Safety Status Trees for Degraded Core Cooling.

Equipment Control R, M K/A 2.2.12 (3.7) Perform A Reactivity Balance Calculation For A Power Ascension.

Radiation Control N/A Not Examined.

Emergency Procedures/Plan R, N K/A 2.4.39 (3.9) Complete a NRC Event Notification Worksheet. (New Plant Process)

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)

A.1.a While acting as an extra RO, the examinee will perform a Containment Formaldehyde Stay Time Calculation using 0-Tl-OPS-000-001 .0, Containment Formaldehyde Stay Time Calculation in preparation for a Containment entry.

A.1.b While acting as a member of the operating crew and given the conditions of a plant emergency, the examinee will interpret and apply plant conditions using 1-FR-O UNIT 1 STATUS TREES to determine that the Safety Functions for Core Cooling, Pressurized Thermal Shock and Containment are all severely challenged.

A.2 While acting as an extra RO, the examinee will perform a Reactivity Balance for a power ascension using 0-SO-62-7, Boron Concentration Control Appendix E, Reactivity Balance.

A.3 Not examined.

A.4 While acting as the Site Communicator and given data for a plant emergency, will use EPIP-5 GENERAL EMERGENCY Appendix D and complete a NRC Event Notification Worksheet.

ES-301 Control Roomlln-Plant SvstemsOutline Form ES-301 -2 Facility: Seciuoyah Nuclear Station 1 & 2 Date of Examination: 12/3-7 2012 Exam Level: RO X SRO-l SRO-U Operating Test No: 2012-302 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System / JPM Title Type Code* Safety Function

a. K/A EPE 029 EA 1.02 (3.6/3.3) Establish Emergency Boration Using The S, A, M 1 Normal Boration Flowpath.

b. K/A 004 A4.06 (3.6/3.1) Remove Excess Letdown from Service. 5, D 2

c. K/A EPE 011 EA1 .11 (4.2/4.2) Transfer To Hot Leg Recirculation With A S, A, M, EN, L 3 Safety Injection Pump Trip.

d. K/A APE 025 AK1 .01 (3.9/4.3) Respond To A RHR Pump Trip And Establish 5, N, L 4P RHR Flow Using The Standby RHR Pump.

e. K/A EPE E05 EA2.1 (3.4/4.4) Establish Secondary Heat Sink Using Main 5, M, L 4S Feedwater.

f. K/A EPE E14 EA 1.1 (3.7/3.7) Respond To High Containment Pressure 5, A, D, L 5 Condition By Placing RHR Spray In Service.

g. K/A APE 056 AA1 .04 (3.2/3.1) Restore Offsite Power From The Emergency S, M, L 6 Diesel Generator To The Shutdown Board.

h. K/A 015 A4.02 (3.9/3.9) Perform a calibration of the Power Range Nuclear S, M 7 Instrumentation.

In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

i. K/A 061 A2.05 (3.1/3.4) Locally Reset the TD AFW Mechanical Overspeed A, R, M, E 4S with No Power Available to the Governor Valve.

j. K/A APE 068 AA1 .01 (4.3/4.5) Operate Steam Generator Atmospheric Dump N, L, E 8 PCV-1-12 Locally. (New Plant Modification)

k. K/A EPE 055 EA2.03 (3.914.7) Reset The lA-A EDG Overspeed Trip N, L, E 6 All RO and SRO-l 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 RD / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 I I / 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power/Shutdown 1 / 1 i1 (N)ew or (M)odified from bank including 1 (A) 2I 2/ I (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1I1I1 (S)imulator

a. The examinee will assume the shift as the ATC during an ATVVS condition. The examinee will be directed to initiate Emergency Boration using EA-68-4 EMERGENCY BORATION section 4.2. During the alignment the emergency borate valve will fail to operate. The examinee uses the alternate path to establish emergency boration flow through the normal boration flowpath.

b. The examinee will assume the shift with Excess Letdown in service. The examinee will remove Excess Letdown from service using 1-SO-62-6, Excess Letdown Section 7.0.

c. The examinee will assume the shift five hours after a LOCA. The ECCS was placed in Cold Leg Recirculation using ES-i .3, Transfer to RHR Containment Sump. The examinee will be directed to place the ECCS in Hot Leg Recirculation using ES-i .4, Transfer to Hot Leg Recirculation. During the alignment, the 1A Safety Injection pump trips. The examinee uses the alternate path to establish Hot Leg recirculation flow through the 1 B Safety Injection pump.

d. The examinee will assume the shift in MODE 5 and the A Train RHR pump in service in the Shutdown Cooling mode with a slight cooldown in progress. While monitoring plant operation the A Train RHR pump trips and the examinee will respond to the condition using AOP-R.03, RHR SYSTEM MALFUNCTION.

The examinee will place the B Train RHR pump in service and re-establish control of RHR temperature with a slight cooldown.

e. The examinee will assume the shift in MODE 3 with no AFW flow available. The examinee will use EA 2, Establishing Secondary Heat sink using Main Feedwater or Condensate section 4.4 and start a Main Feed pump and control feed flow using a Main Feed Regulating Bypass Valve.

f. The examinee will assume the shift after a LOCA and a High Containment Pressure condition. The examinee will use FR-Z. 1, High Containment Pressure, starting at step 13 to establish RHR Spray flow to reduce Containment pressure. During the alignment, the B Train RHR Spray flow isolation valve FCV 41 fails to operate. The examinee uses the alternate path to re-establish B Train RHR to the injection mode and establishes A Train RHR to the Containment Spray mode.

g. The examinee will assume the shift in MODE 3 following a Loss of Power event to the 1A 6.9kv Shutdown Board with the 1A EDG supplying power to the board. The examinee will restore power using EA-202-1 Restoring Offsite Power to 6900V Shutdown Boards. The examinee will parallel the 1A EDG to offsite power using the normal supply breaker and ultimately unload stop the 1A EDG.

h. The examinee will assume the shift in MODE I and perform a calibration check and adjustment of the Power Range Nuclear Instrumentation.

The examinee will assume the shift in MODE 3 with a mechanical overspeed trip condition on the TD AFW pump. The examinee will use the locally posted instructions to utilize the alternate path to manually operate the TD AFW pump steam admission valve operator and manually reset the mechanical overspeed trip.

j. The examinee will assume the shift in MODE 3 and a Control Room Evacuation in progress. The examinee will be directed to take local control of PCV-1-5, S/G #1 Atmospheric Dump valve using AOP C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.1. The examinee attempts to locally operate PCV-1-5, SIG #1 Atmospheric Dump valve but discovers the valve to be immoveable. The examinee uses the alternate path to take local control of PCV-1 -12, S/G #2 Atmospheric Dump valve.

The local controls for PCV-i-i2, S/G #2 Atmospheric Dump valve are a recently added plant modification.

k. The examinee will assume the shift in MODE 3 following a major grid disturbance and Unit 1 in a Loss of All AC power. The examinee will be directed to reset the overspeed trip mechanisms on the 1A EDG. The examinee will reset both overspeed trip mechanisms and subsequently reset the 1A EDG lockout relay to start the IA EDG.

E$-301 Control Roomlln-Plant Systems Outline Form ES-301 -2 Facility: Seguoyah Nuclear Station I & 2 Date of Examination: 12/3-7 2012 Exam Level: RO El SRO-l X SRO-U El Operating Test No: 2012-302 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System / JPM Title Type Code* Safety Function

a. K/A EPE 029 EA 1.02 (3.6/3.3) Establish Emergency Boration Using The S, A, M 1 Normal Boration Flowpath.

b. K/A 004 A4.06 (3.6/3.1) Remove Excess Letdown from Service. S, D 2

c. K/A EPE 011 EA1 .11 (4.2/4.2) Transfer To Hot Leg Recirculation With A S, A, M, EN, L 3 Safety Injection Pump Trip.

d. N/A

e. K/A EPE E05 EA2.1 (3.414.4) Establish Secondary Heat Sink Using Main S, M, L 4S Feedwater.

f. K/A EPE E14 EA 1.1 (3.7/3.7) Respond To High Containment Pressure S, A, D, L 5 Condition By Placing RHR Spray In Service.

g. K/A APE 056 AA1 .04 (3.2/3.1) Restore Offsite Power From The Emergency S, M, L 6 Diesel Generator To The Shutdown Board.

h. K/A 015 A4.02 (3.9/3.9) Perform a calibration of the Power Range Nuclear S, D 7 Instrumentation.

In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

i. K/A 061 A2.05 (3.1/3.4) Locally Reset the TD AFW Mechanical Overspeed A, R, N, E 4S with No Power Available to the Governor Valve.

j. K/A APE 068 AA1 .01 (4.3/4.5) Operate Steam Generator Atmospheric Dump N, L, E 8 PCV-1-12 Locally. (New Plant Modification)

k. K/A EPE 055 EA2.03 (3.9/4.7) Reset The lA-A EDG Overspeed Trip N, L, E 6 All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

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

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

(R)CA I (S)imulator

a. The examinee will assume the shift as the ATC during an ATWS condition. The examinee will be directed to initiate Emergency Boration using EA-68-4 EMERGENCY BORATION section 4.2. During the alignment the emergency borate valve will fail to operate. The examinee uses the alternate path to establish emergency boration flow through the normal boration flowpath.

b. The examinee will assume the shift with Excess Letdown in service. The examinee will remove Excess

( Letdown from service using 1-SO-62-6, Excess Letdown Section 7.0.

c. The examinee will assume the shift five hours after a LOCA. The ECCS was placed in Cold Leg Recirculation using ES-i .3, Transfer to RHR Containment Sump. The examinee will be directed to place the ECCS in Hot Leg Recirculation using ES-i .4, Transfer to Hot Leg Recirculation. During the alignment, the 1A Safety Injection pump trips. The examinee uses the alternate path to establish Hot Leg recirculation flow through the I B Safety Injection pump.

d. Not examined.

e. The examinee will assume the shift in MODE 3 with no AFW flow available. The examinee will use EA 2, Establishing Secondary Heat sink using Main Feedwater or Condensate section 4.4 and start a Main Feed pump and control feed flow using a Main Feed Regulating Bypass Valve.

f. The examinee will assume the shift after a LOCA and a High Containment Pressure condition. The examinee will use FR-Z. 1, High Containment Pressure, starting at step 13 to establish RHR Spray flow to reduce Containment pressure. During the alignment, the B Train RHR Spray flow isolation valve FCV 41 fails to operate. The examinee uses the alternate path to re-establish B Train RHR to the injection mode and establishes A Train RHR to the Containment Spray mode.

g. The examinee will assume the shift in MODE 3 following a Loss of Power event to the iA 6.9kv Shutdown Board with the 1A EDG supplying power to the board. The examinee will restore power using EA-202-1 Restoring Offsite Power to 6900V Shutdown Boards. The examinee will parallel the 1A EDG to offsite power using the normal supply breaker and ultimately unload stop the 1A EDG.

h. The examinee will assume the shift in MODE 1 and perform a calibration check and adjustment of the Power Range Nuclear Instrumentation.

i. The examinee will assume the shift in MODE 3 with a mechanical overspeed trip condition on the TD AFW pump. The examinee will use the locally posted instructions to utilize the alternate path to manually operate the TD AFW pump steam admission valve operator and manually reset the mechanical overspeed trip.

j. The examinee will assume the shift in MODE 3 and a Control Room Evacuation in progress. The examinee will be directed to take local control of PCV-1-5, S/G #1 Atmospheric Dump valve using AOP C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.i. The examinee attempts to locally operate PCV-i-5, S/G #1 Atmospheric Dump valve but discovers the valve to be immoveable. The examinee uses the alternate path to take local control of PCV-i -12, S/G #2 Atmospheric Dump valve.

The local controls for PCV-i-12, S/G #2 Atmospheric Dump valve are a recently added plant modification.

k. The examinee will assume the shift in MODE 3 following a major grid disturbance and Unit 1 in a Loss of All AC power. The examinee will be directed to reset the overspeed trip mechanisms on the iA EDG. The examinee will reset both overspeed trip mechanisms and subsequently reset the IA EDG lockout relay to start the 1A EDG.

ES4OI Control Ropmlln-Plpnt SysiemsOutline Form ESO1 -2 Facility: Seguoyah Nuclear Station 1 & 2 Date of Examination: 12/3-7 2012 Exam Level: RO El SRO-l El SRO-U X Operating Test No: 2012-302 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. N/A

b. K/A 004 A4.06 (3.6/3.1) Remove Excess Letdown from Service. 5, D 2

c. K/A EPE 011 EA1 .11 (4.2/4.2) Transfer To Hot Leg Recirculation With A 5, A, M, EN, L 3 Safety Injection Pump Trip.

d. N/A

e. N/A

f. K/A EPE E14 EA 1.1 (3.7/3.7) Respond To High Containment Pressure 5, A, D, L 5 Condition By Placing RHR Spray In Service.

g. N/A

h. N/A In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. K/A 061 A2.05 (3.1/3.4) Locally Reset the TD AFW Mechanical Overspeed A, R, N, E 4S with No Power Available to the Governor Valve.

j. K/A APE 068 AAI .01 (4.3/4.5) Operate Steam Generator Atmospheric Dump N, L, E 8 PCV-1-12 Locally. (New Plant Modification)

k. N/A All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

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

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

(R)CA (S)imulator

a. Not examined.

b. The examinee will assume the shift with Excess Letdown in service. The examinee will remove Excess Letdown from service using i-SO-62-6, Excess Letdown Section 7.0.

c. The examinee will assume the shift five hours after a LOCA. The ECCS was placed in Cold Leg Recirculation using ES-i .3, Transfer to RHR Containment Sump. The examinee will be directed to place the ECCS in Hot Leg Recirculation using ES-i .4, Transfer to Hot Leg Recirculation. During the alignment, the iA Safety Injection pump trips. The examinee uses the alternate path to establish Hot Leg recirculation flow through the 1 B Safety Injection pump.

d. Not examined.

e. Not examined.

f. The examinee will assume the shift after a LOCA and a High Containment Pressure condition. The examinee will use FR-Z. 1, High Containment Pressure, starting at step 13 to establish RHR Spray flow to reduce Containment pressure. During the alignment, the B Train RHR Spray flow isolation valve FCV 41 fails to operate. The examinee uses the alternate path to re-establish B Train RHR to the injection mode and establishes A Train RHR to the Containment Spray mode.

g. Not examined.

h. Not examined.

i. The examinee will assume the shift in MODE 3 with a mechanical overspeed trip condition on the TD AFW pump. The examinee will use the locally posted instructions to utilize the alternate path to manually operate the TD AFW pump steam admission valve operator and manually reset the mechanical overspeed trip.

j. The examinee will assume the shift in MODE 3 and a Control Room Evacuation in progress. The examinee will be directed to take local control of PCV-1-5, SIG #1 Atmospheric Dump valve using AOP C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.1. The examinee attempts to locally operate PCV-i-5, S/G #1 Atmospheric Dump valve but discovers the valve to be immoveable. The examinee uses the alternate path to take local control of PCV-1-12, S/G #2 Atmospheric Dump valve.

The local controls for PCV-1 -12, SIG #2 Atmospheric Dump valve are a recently added plant modification.

k. Not examined.

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Sequoyah Nuclear Station I & 2 Date of Examination: 12103/2012 Operating Test Number: 2012-302 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., 10 CFR 55.45, operational importance, safety function distribution). T

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.)

d. Overlap with the written examination and between different parts of the operating test is within acceptable limits.

e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level. =

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: 15 11 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

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 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 4 ç 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.

L.

Printed Name / ignature Date

a. Author Michael Buckner

b. Facility Reviewer(*) Steven Tuthill

c. NRC Chief Examiner(#) Lh b - i

d. NRC Supervisor i

/

NOTE:

The facility signature is not applicable for NRC-developed tests.

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

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Sequoyah Station I & 2 Date of Exam: 12I0312012 Scenario Numbers: 1! 213/ Operating Test No.: 2012-302 QUALITATIVE ATTRIBUTES Initials a b*

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.

2. The scenarios consist mostly of related events. A r

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

. the expected operator actions (by shift position) 7t/1 T 5

the event termination point (if applicable) V

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.

4 r 5

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.

L 1

8. The simulator modeling is not altered. YZs -

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. 1

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 .4,.,

form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and events , j 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. 1IZ r 3

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

1. Total malfunctions (58) 6/6/5 r

2. Malfunctions after EOP entry (12) 2 /2 / 1

3. Abnormal events (24) 3/3/3 c r

3 -

4. Major transients (12) 1 /2/1 Sr

5. EOP5 entered/requiring substantive actions (12) 1 / 1 /2 Sr

6. EOP contingencies requiring substantive actions (02) 1 I 1 I0

7. Critical tasks (23) 2/3/2

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 12/3/2012 Operating Test No.: 2012-302 A E Scenarios 1 2 TM L N CREW CREW T N I T POSITION POSITION c _A M

A T S A B S A B L R T u

KI Il T

0 R T 0 MI*

0 C P 0 C P k T

R IU E

RO RX 1 1110 NOR 42 SRO-I X I/C 12,5 2,3 5 4 4 2 SRO-U MAJ 6 5,7 3 2 2 1

TS 2,3 2022 RO RX 4 1 110 LI SRO-I NOR 1 1111 x I/C 1,2 2,3,4 5 4 4 2 SRO-U MAJ 6 5,7 3 2 2 1 LI TS 23 2022 RO RX 110 SRO-I X

NOR I/C zz:ziii: 442 MAJ 221 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 SROs 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 serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional 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.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 12/3/2012 Operating Test No.: 201 2-302 A E Scenarios 1 3 TM L N CREW CREW T N I T POSITION POSITION c A M

S A B S A B A T R T 0 R T 0 L u N Y M*

0 C P 0 C P T P R lU E

RO RX 1 1 110 NOR 4 2 111 SRO-l X I/C 1,2,5 2,3, 4 4 2 6

SRO-U MAJ 6 5,7 3221 TS 2,3 2022 RO RX 4 1 110 D

SRO-l NOR 1 1111 x I/C 1,2 2,3,4 5 4 4 2 SRO-U MAJ 6 5,7 2 2 3 1 D TS 3 2022 RO RX 110 SRO-I NOR 111 SO-U MAJ 221 TS 022 Instructions:

3. 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 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 serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

4. 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.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 12/3/2012 Operating Test No.: 2012-302 A E Scenarios 1 2 3 TM L N CREW CREW CREW I T T N POSITION POSITION POSITION c M A T S A B S A B L R T 0 R T U N 0 Mf*

-,- 0 C P 0 C P -s--

I P R lU E

RO RX 1 1110 x NOR SRO-l 4 2 2 1 1 1 I/C 4 4 2 23 SRO-U j MAJ 6 7 3 2 2 1 TS 0022 RO RX 4 1 110 NOR 1 SROI I/C 1,2 4,6 4 4 4 2 SRO-U MAJ 6 5,7 3 2 2 1 D TS 0022 RO RX 0110 NOR SRO-l I/C 1,2,5, 4 4 2 SRO-U x MAJ 6 1 221 TS 3 2022 RO RX 110 NOR SRO-l D

SRO-U I/C 442 MAJ 2 2 1 TS 0 22 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 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 serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional 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.

ES-301 Transient and Event Checklist Form ES-301 -5 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam; 12/3/2012 Operating Test No.: 2012-302 A E Scenarios 1 3 TM L N CREW CREW CREW CREW N T

I T POSmON POSITION POSITION POSITION A C S A B S A B S A B S A B L A T R T 0 R T 0 R T 0 R T M(*

N Y C P 0 C P 0 C P 0 C P ---

R IU T

E RO RX 4 1 110 NOR 1 SRO-l I/C 1,2 1

IL 4,6 4 4 4 2 SRO-U MAJ 6 5,7 3 2 2 1 TS 022 RX 1 RO X NOR 4 1 111 SRO-I 5,6, I/C 23,5 6 4 4 2 L_J 7 MAJ 6 5,7 3 2 2 1 U

TS 022 RD RX 110 NOR SRO-I EJ SRO-U I/C 1,2,5, 4 4 4 2 x MAJ 6 1221 TS 2,3 2022 RD RX 110 NOR SROI I/C 442 SRO-U MAJ 2 2 1 D TS 022 Instructions:

3. 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 RD applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs 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 serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

4. 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.

ES-301 Competencies Checklist Form ES-301-6 Facility: Sequoyah Nuclear Station 1 & 2 Date of Examination: 12/3/2012 Operating Test No.: 2012-302 APPLI CANTS RO X RO El RO El RO El SRO-I El SRO-l X SRO-I El SRO-l El SRO-U El SRO-U LI SRO-U X SRO-U El Competencies SNIO CRlO EN!RLQ 123 123 12 3 lnterpretfDiagnose 1,2, 1,2, 2,3, 1,2. 1,2, 2,3, 1,2, 1,2, 2,3,4,5, Events and Conditions

8

8 i

8 6,7 Comply With and 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2,3,4, Use Procedures (1)

: : : : : : : 5,6,7 Operate Control 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, i 3,4, 3,4, 3,4, 3,4, 3,4, 3,4, B oarus k4 5,6, 5,6, 5,6, 5,6, 5,6. 5,6.

7 7,8 7 7 7,8 7 Communicate 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2,3,4, J I 4 3,4, 3,4, 3,4, 3,4, 3,4, 3,4, 3,4, 3,4, 5,6,7 anu interact 5,6, 5,6, 5,6, 5,6 5,6, 5,6, 5,6, 5 6, 7 7,8 7 7 7,8 7 7 7,8 Demonstrate 1,2, 1.2, 1,2, 1,2, 1,2, 1,2,3,4, Supervisory Ability (3) 7 7,8 7

7 3:4:

7,8 5,6,7 Comply With and 2,3 2,3 2,3 2,3 2,3 2,3 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 eveiy applicable competency for every applicant.

ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility Hatch Date of Exam: 2013 RO KIA Category Points SRO-Only Points Tier Group KKKKKKAAAAG A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total i 433343 20 4 3 7 Emergency &

Abnormal Plant 2 T T 2 1 1 7 2 1 3 NIA NIA Evolutions Tier Totals =

27 6 4 10 1 32313223232 26 3 2 5 2.

Plant 2 TT 12 0 2 1 3 Systems Tier Totals 3

T =

3. Generic Knowledge and Abilities 2 3 4 10 1 2 Categories 1 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 KIA 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 SRO-only exam must total 25 poInts.

3. Systemslevolutions 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 KIAs having an Importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.

7. The generic (G) KIAs in Tiers I and 2 shall be selected from Section 2 of the K1A 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 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 other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note

1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-4014. Umit SRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1(1 1(2 1(3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 295001 AK2.06 Partial or Complete Loss of Forced 3.8 3.8 Core Flow CIrculation /1 & 4 j [] [] [] [] [] [] [] [J [] Reactor power 295003AK1.02 Partial or Complete Loss of AC? 6 3.1 3.4 fl [] [] [} fl [] [] [] [] Load shedding 295004G2.1.7 Partial or Total Loss of DC Pwr /6 4.4 4.7 [] [] [] [J [] [] [] [J [] j Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

295005AK3.02 Main Turbine Generator Trip / 3 3.4 3.5 J J fl Recirculation pump downshiftltrip: Plant-Specific...

295006AA1.01 SCRAM/i 4.2 4.2 c] LI Li [1 LI LI (l [1 LI [] [] RPS 295016AA2.07 Control Room Abandonment / 7 3.2 3.4 [] [] [] LI [] ] f [] [] Suppression chamber pressure 29501 8AK3.06 Partial or Total Loss of CCW / 8 3.3 3.3 [] [] [] [] E] (J [] [] Increasing cooling water flow to heat exchangers 295019AA2.02 Partial or Total Loss of Inst. Air/ 8 3.6 3.7 [] [] [] [] [] E] [I [] Status of safety-related instrument air system loads (see AK2.l AK2.i9) 295021 G2.2.40 Loss of Shutdown Cooling / 4 3.4 4.7 [] ] [] LI [J [] [] [] [] [j Ability to apply technical specifications for a system.

295023AA2.03 Refueling Ace Cooling Mode / 8 3.3 3.8 [] [] [] [] [] LI [] [] [] Airborne contamination levels 295024EA2.06 High Drywell Pressure / 5 4.1 4.1 LI LI LI [1 Li LI LI 1I LI LI LI Suppression pool temperature Page 1 of 2 12/4/2012 6:47 AM

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES4O1-1 KA NAME / SAFETY FUNCTION: IR Ki K2 1(3 K4 KS 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 295025G2. 1.27 High Reactor Pressure / 3 3.9 4 El ElELJL1E1ElEEIEl Knowledge of system purpose and or function.

295026EK3.04 Suppression Pool Hli Water Temp. I 3.7 5

OElLILILiEILI SBLC injection 295028EA1.03 High Drywell Temperature /5 3.9 3.9 El LiE LILI LI LI El El LI Drywell cooling system 295030EK1.02 Low SuppressIon Pool Wtr Lvi /5 3.5 3.8 LI [lEO LI LI LI LI El LI Pump NPSH 295031EA1.04 Reactor Low Water Level / 2 4.3 4.2 LI EELII1LJL1LiD High pressure core spray: Plant-Specific 295037EK2.12 SCRAM Condition Present and Power 3.6 Above APAM Downscale or Unknown 3.80 LIE LHZIE El LI LI LI Rod control and information system: Plant-Specific...

/1 295038EK1.O1 High Off-site Release Rate / 9 2.5 3.1 EU El LI LI LI LI Li LI Biological effects of radioisotope ingestion 600000AK1.O1 Plant Fire On Site /8 2.5 2.8 EDLILILILILI Fire Classifications by type 700000AK2.O3 Generator Voltage and Electric Grid 3.0 3.1 Distrurbancecs EELIUEEIE1ELILI Sensors, detectors, indicators Page 2 of 2 12/4/2012 6:47AM

ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: 1R K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 295009AK1 .02 Low Reactor Water Level / 2 3.0 3.1 Ofl]L1L1 Recirculation pump net positive suction head: Plant-Specific 29501 OAA2.06 High Drywell Pressure /5 3.6 3.6 DryweU temperature 295012AK3.01 High DryweN Temperature / 5 3.5 3.6 DLJLJL1 Increased drywell cooling 295013G2.4.18 High Suppression Pool Temp. / 5 3.3 4.0 L1L1L1DL1LJLJIZJLJL1t1 Knowledge of the specific bases for EOPs.

295017AA1.05 High Off*site Release Rate /9 2.7 3.2 SPDS/ERISJCRIDSIGDS: Plant-Specific 295035EA1 .01 Secondary Containment High 3.6 3.6 Secondary containment ventilation system Differential Pressure /5 500000EK2.07 High CTMT Hydrogen Conc. / 5 3.2 üE1LLL1L1D Drywell vent system Page 1 of 1 12/4/2012 6:47AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:

RO Sf0 2030001(6.02 RHPJLPCI: Injection Mode 2.8 3.0 D.C. electrical power fl fl fl El Li [] El El El El El 2050001(5.02 Shutdown CoolIng 2.8 2.9 [1 [] El El ] El El El El El El Valve operation 2050001(5.03 Shutdown Cooling 2.8 3.1 El El El El El El El El El El Heat removal mechanisms 206000A1.OO HPCI 4.1 4 El El El El [] [] f [] [] [] System lineup: BWR-2,3,4 209001 1(3.01 LPCS 3.8 3.9 Reactor water level El [] [] El El El El [ [] El 2090011(3.03 LPCS 2.9 3.0 El El El El El El El El El El Emergency generators 2110001(2.02 SLC 31 32 Explosive valves El (] [] [] ) [] [] [] [J 212000A3.02 RPS 3.2 3.5 Individual system relay status: Plant-SpecifIc El El El El El El El El Ei LI El 212000A4.15 RPS 3.9 3.8 El El El El El El El El El El Recirculation pump trip/EOC APT 2150031<4.05 IRM 2.9 3.0 El El El I El El El El El El El Changing detector position 2150041(1.05 Source Range Monitor 2.8 3.0 LI El El El El El El El El El Display control system: Plant-Specific Page 1 of 3 12/4/2012 6:47 AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 1(2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 215005A4.06 APRM I LPIRM 3.6 3.8 LI LI LI LI Li LI Li LI LI [1 LI Verification of proper functioning! operability 2170001(5.06 RCIC 2.7 2.7 [] LI LI {J [] LI [] [] Turbine operation 2180001(3.01 ADS 4.4 4.4 LI [ [] [] LI LI LI Restoration of reactor water level after a break that does not depressurize the reactor when required 223002A2.11 PCIS/Nuclear Steam Supply Shutoff 3.8 3.9 LI LI LI LI LI LI LI Si LI LI LI Standby liquid initiation 2390021(2.01 SRVs 2.8 3.2 LI ] LI LI LI LI LI LI LI LI LI SRV solenoids 259002A4.08 Reactor Water Level Control 4.5 4.5 [J LI LI LI LI LI LI LI LI (] LI Manually initiate FWCI: FWCI 281 000AZO7 SGTS 2.7 2.8 LI LI LI LI LI LI LI LI LI LI A.C. electrical failure 261000K1.03 SGTS 2.9 3.1 J fl LI LI LI LI LI LI LI LI LI Suppression pool 262001 K6.03 AC Electrical Distribution 3.5 3.7 LI LI LI LI LI j [3 [3 LI LI LI Generator tnp 262002G2.4.4 UPS (AC!DC) 4.5 4.7 LI LI LI U [] LI [] fl Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

263000A3.01 DC Electrical Distribution 3.2 3.3 LI LI LI LI LI [3 LI [1 LI LI Meters, dials, recorders, alarms and indicating lights Page 2 of 3 12/4/2012 6:47 AM

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 Ability to recognize system parameters that are entry-264000G2.2.42 EDGs 3.9 4.6 [] [] [] fl [] [) [J [] [] [] level conditions for Technical SpecificatIons Air dryer and filter maltunctions 300000A2.Ol Instrument Air 2.9 2.8 [] [] [] [] fl [] [] ( [] [J []

3000001(1.03 Instrument Air 2.8 2.9 C] C] C] Li C] C] LI C] C] C] Containment air 400000A1.O1 Component Cooling Water 2.8 2.8 C] Li LI LI C] C] 1 C] Ci C] [] CCW flow rate Page 3 of 3 12/4/2012 6:47 AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 1(2 1(3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 201 003A09 Control Rod and Drive MechanIsm 3.2 3.4 [] [] [] fl [] [] [] j fl [] [] Low reactor pressure 2040001(1.15 RWCU 3.1 3.2 Leak detection: Plant-Specific fl [] [] fl [] [] [] [] [] []

215001A4.03 Traversing In-core Probe 3.0 3.1 [] [] [] [} [] [] [] [] J [] Isolation valves: Mark-l&ll(Not-BWR1) 215002G2.4.4 RBM 4.5 4.7 Ability to recognize abnormal indications for system J J J 1j operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

223001A3.05 Primary CTMT and Aux. 4.3 4.3 LI L] LI LI LI LI LI LI 11 LI [] Drywell pressure 226001 K6.04 RFiRILPCI: CTMT Spray Mode 2.7 2.7 LI LI LI LI LI l LI LI LI LI LI Keep fill system 2330001(4.08 Fuel Pool CoolinglCleanup 2.6 2.8 LI LI LI 1 LI LI LI LI LI LI LI Pool cooling during loss of coolant accident: BWR-6 239001 K5.05 Maui and Reheat Steajii 2.8 2.8 LI LI LI LI LI LI LI LI LI LI Flow indication 2410001(3,03 Reactor/Turbine Pressure Regulator 3.7 3.8 LI LI [J LI LI LI LI LI LI LI LI Reactor water level 2450001(4.10 Main Turbine Gen. / Aux. 2.6 2.7 LI LI LI {j LI LI LI LI LI LI LI Extraction steam 268000A1.02 Radwaste 2.6 3.6 LI LI LI LI LI LI (] LI [] LI LI Off-site release Page 1o12 12/4/2012 6:47AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES4O1-1 KA NAME I SAFETY FUNCTION: IR Ki 1<2 K3 K4 K5 1<6 Al A2 A3 A4 G TOPIC:

RO SRO 286000K2.02 Fre PntectIon 2.9 3.1 LI ] El LI LI LI LI LI LI LI LI Pumps Page 2 of 2 12/4/2012 6:47 AM

ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO Sf0 G2.l.l Conduct of operations 3.8 4.2 Li LI LI Li LI Li LI LiLiLi Knowledge of conduct of operations requirements.

02.1.20 Conduct of operations 4.6 4.6 LI LI LI LI LI LI Li Li Li Li II Abiflty to execute procedure steps.

G2.1.8 Conduct of operations 3.4 4.1 [] L] Li LI LI LI LI Li LI LI S] Ability to coordinate personnel activities outside the control room.

G2.2.21 Equipment Control 4.1 2.9 LI LI Li Li LI LI LI Li Li LI 1I Knowledge of pre- and post-maintenance operability requirements.

G2.2.22 Equipment Control 4.0 4.7 Li LI Li LI LI Li LI Li LI Li I Knowledge of limiting conditions for operations and safety limits.

02.2.36 Equipment Control 3.1 4.2 LI Li LI Li LI Li LI Li LI LI I) 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 LI Li Li LI Li LI LI Li El Li IJ Ability to control radiation releases.

02.3.13 Radiation Control 3.4 Knowledge of radiological safety procedures pertaining to 3.8 LI LI LI LI Li LI Li Li Li LI lI licensed operator duties 02.4.16 Emergency Procedures/Plans 3.5 4.4 [1 LI Li Li LI Li LI LI LI Li [l Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

02.4.5 Emergency Procedures/Plans 3.7 4.3 LILILILILiLILiELILI Knowledge of the organization of the operating procedures network for normal, abnormal and emergency evolutions.

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

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

RO SRO 295004AA2.02 Partial or Total Loss of DC Pwr /6 3.5 3.9 jFJ Extent of partial or complete loss of D.C. power 295016G2.2.37 Control Room Abandonment / 7 3.6 4.6 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 FJJj Knowledge of the purpose and function of major system components and controls.

295023AA2.02 Refueling Acc Cooling Mode /8 3.4 3.7 Fuel pool level 295024EA2.02 High Drywell Pressure / 5 3.9 4.0 rjrj Drywell temperature 29503702.4.49 SCRAM Condition Present and Power 4.6 4.4 Ability to perform without reference to procedures those Above APRM Downscale or Unknown actions that require immediate operation of system 11 components and controls.

700000AA2.07 Generator Voltage and Electric Grid 3.6 4.0 L1D1E1D Operational status of engineered safety features Distrurbancecs Page 1 of 1 12/4/2012 6:47AM

ES-401, REV 9 SROT1G2 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 295OO7AA2.0 High Reactor Pressure / S 4.1 4.1 Reactor pressure 29501 2G2.4.1 1 High Drywell Temperature /5 4.0 4.2 flUEL1EflELiL Knowledge of abnormal condition procedures.

295032EA2.03 High Secondary Containment Area 3.8 4.0 Cause of high area temperature Temperature /5 Page 1 of 1 12/4/2012 6:47AM

ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 K2 1(3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 209001 G2.4.49 LPCS 4.6 44 [] [J [] [] [] [] j Ability to porform without reference to procedures those actions that require immediate operation of system components and controls.

215003A2.05 IRM 3.3 3.5 Faulty or erratic operation of detectors/system

[] fl Q [] [j fl j [] [] []

218000A2.05 ADS 3.4 3.6 [] LI El [] [] [] [] ] [] [] [] Loss of A.C. or D.C. power to ADS valves 261 000A2.08 SGTS 2.4 2.7 LI El LI El LI LI LI {] [] [] [] D.C. electrical failure 263000G2.4.8 DC Electilcal DIstribution 3.8 4.5 Knowledge of how abnormal operating procedures are El El El LI El El LI El El LI used in conjunction with EOPs.

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

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

RO SRO 201006A2.06 RWM 2.9 3.3 fl Loss of reactor water level control input: P- Spec(Not 3.5 3.7 [] [3 [3 [3 Excessive outleakage 290001A2.02 Secondary CTMT [J [] [] []

Ability to recognize abnormal indications for system 290003G2.4.4 Control Room I-P/AC L1L3E1Li[3E[3LJLlU operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 1214/2012 6:47AM

ES-401, REV 9 SRO T3 BWR EXAMINA1 ION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 1(2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 02.1.3 Conduct of operations 3.7 3.9 [] Li [1 fl [J [ [} E] [1 [] [] Knowledge of shift or short term relief turnover practices.

G2.1.38 Conduct of operations 3.0 4.1 [] [3 [3 [3 Li [3 [] [] [] [] [] Knowledge of procedures and limitations Involved in core alterations 02.2.18 Equipment Control 2.6 3.8 [3 [] [3 [3 [1 Li LI [] [] [3 ] Knowledge of the process for managing maintenance activities during shutdown operations.

02.2.39 Equipment Control 3.9 4.5 [3 [] [3 Li [] [3 [3 [] [] Knowledge of less than one hour technical specification action statements for systems.

02.3.4 Radiation Control 3.2 3.7 [3 [) [3 [3 [3 [] [3 [3 [3 [] Knowledge of radiation exposure limits under normal and emergency conditions 02.4.38 Emergency Procedures/Plans 2.4 4.4 [3 LI [1 Li LI Li LI LI Li Li Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.

G2.4.4 Emergency Procedures/Plans 4.5 4.7 [3 [3 [3 [] Li [1 LI [I LI Li Il Ability to recognize abnormal indications for system operating parameters which are ently-level conditions for emergency and abnormal operating procedures.

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

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RO Ti Gi 029 G2. 1.25 Unable to write an operationally valid question for this K/A due to not using graphs or curves when dealing with selected emergency event.

(Rejected and randomly reselected 029 G2. 1.30)

T2G 1 061 K2.03 Due to plant design SQN does not have the selected equipment.

(Rejected and randomly reselected 061 K2.0 1)

T2G2 011 Al .04 Unable to write an operationally valid question to this KJA.

(Rejected and randomly reselected 011 Al .04)

SRO T1G1 065 AA2.02 Due to plant design unable to write an operationally valid question at the SRO level. (Rejected and randomly reselected 065 AA2.08)

T2/Gl 003 G 2.2.41 Unable to write an operationally valid question at the SRO level.

(Rejected and randomly reselected 003 G2.2.25)

T2/G1 007 A2.07 Due to plant design the equipment selected does not exist at SQN.

(Rejected and randomly reselected 007 A2.01)

T2/Gl 076 G2.4.34 Due to plant design the ROs do not perform any actions outside the control room associated with this system. (Rejected and randomly reselected 076 G2.4.34)

T3 G2. 1.14 Unable to write an operationally valid question at the SRO level for this K/A. (Rejected and randomly reselected G2. 1.36)

T3 G2.4. 13 Unable to write an operationally valid question at the SRO level for this K/A. (Rejected and randomly reselected G2.4. 13)

T2/Gl 008 A2.03 Unable to write an operationally valid question at the SRO level for this KJA. (Rejected and randomly reselected 008 A2.02)

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Sequoyah Nuclear Station 1& 2 Date of Exam: 1210312012 Exam Level: RO X SRO X 7

Initial Item Description a b* c#

1. Questions and answers are technically accurate and applicable to the facility. .

f7

2. a. NRC K/As are referenced for all questions.

b. Facility learning objectives are referenced as available. Er

3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 16 T 4 The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office).

5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or T the examinations were developed independently; or z the licensee certifies that there is no duplication; or other (explain)

6. Bank use meets limits (no more than 75 percent from Bank Modified New the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only question 48 / 10 7/4 20 / 11 iZ distribution(s)_at_right.

7. Between 50 and 60 percent of the questions on the RO Memory C/A exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter 34 / 3 41 / 22 Y the_actual_RO_/_SRO_question_distribution(s)_at_right.

8. References/handouts provided do not give away answers or aid in the elimination of distractors.

9jjg 5. k J.

9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are 1 justified.

ç 5

10. Question psychometric quality and format meet the guidelines in ES Appendix B.

11. The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet.

Printed Name / Signature Date

a. Author Michael Buckner I 2

b. Facility Reviewer (*) Steven Tuthill

c. NRCChiefExaminer(#) .4cJ-..ii L /.d :i.,.,

2

d. NRC Regional Supervisor ,t99,V // I Note: The facility reviewers initials/signature are not applicable for NRC-developed examinations.

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

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 SEQ Nuclear Plant 2012-302 December 2012 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).

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

5 Check questions that are samDled 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).

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. IPartial Job- Minutia #/ j Back- Q SRO U/E/S Explanation Focus Dist. j Link unitsi ward K/A Only s written there doesnt appear to be a correct answer. If charging flow is dequate to overcome the leak rate and make RCS pressure rise, then CP flow will actually drop per the CCP pump curve until break flow natches leak flow or until shutoff head. Perhaps change C and D to start owering and make D the answer.

H 3 U?

ecommend changing the stem to state that the block valve goes to ntermediate. Does not appear that charging flow would be capable of aking up for a fully open PORV and block valve.

XXXX)(X Made change to stem (added immediately to stem. Question is

)K. Should not have been a U. XXXXX

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 T/F Cred. Partial Job- Minutia #/ Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only (1) and D(1) distractors are not plausible. Do not think that reflux boiling would never transition into natural circulation without some input from the perator or automatic system.

2 F 2 U Veak question structure. A better question would provide post LOCA lata and have the applicant determine if NC or reflux boiling is occurring md perhaps use the definitions of refiux boiling to give second part XXXXXX Replaced question with one revised from previous exam.

uestion was a U. XXXXXXX uestion is SAT. However, consider the following which might make it a etter question:

. Change the last bullet to CET T/Cs all indicate> 1200 °F.

. Add a bullet, B NR SG level is 30% and rising.

. Add a bullet, the B RCP is AVAILABLE and STOPPED.

3 E/S

Remove the third and fourth bullets.

Change question stem to FR-Cl, Inadequate Core Cooling directs that an RCP (XXXXXXX Made enhancements. Provided additional information ustifying question> XXXXXXXX Question is Sat.XXX)(X 4 S

)orrect answer can be chosen without knowing the answer to the first luestion. Make this a true 2 part question. Use the second answer from B and C in place of the ones for A and D. This would make knowing the low band necessary to answer the question and would fully meet the K/A.

This would then be SAT. XXXXXX Made minor changes to stem and nade answer a two part question. E. XXXXXXXXX 6 S 7 S 8 5 re the requirements of 0-SI-SXX-068-1 27.0 required to be known by the 9 SI? RO applicants? XXXXXX Made a small change to wording in stem.

uestion should have been S/E. XXXXXXX

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 SEQ Nuclear Plant 2012-302 December 2012

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 TIF Cred. Partial Job- Minutia #/ Back- Q Explanation Focus Dist. Link units ward K/A Only Distractor D is not plausible. Will stopping the feed to the ruptured SG ay lengthen the TD AFW availability. XX)O(XXXXX ChanQed distractor 10 and D. Used second part of bases for C. Will fix D. XXXXXXXX E

Reviewed and accepted new distractor based on the fact that this would e true is you were in ECA 2.1. Accepted change based after reviewing ases.1 1/15/2012. XXXXXXXXX 11 H 2 M/B S 12 H 2 B S 13 H 3 M/B S 14 H 2 B S 15 F B S 16 F X orrect the wording in the stem: RCS depressurization is XXXXXX B E/S

,ade minor change to stem.XXXXXXXXXX---

Doncern with the Order of priority. Should it say per FR-H. 1 and are ROs 17 F 2 X required to know this from memory? X)(XXXXXXX per the licensee, this B S is an acceptable RO question. Only made one minor change to stem.

(xxxxx 18 B S rhe question ask for reason then function. Distractior are not written in 19 hat order. Provide documentation that shows reason. XXXXXXX B E Dhanged wording in the stem and the distractors OK as rewritten.

Major changes. Should haven an U/E. XXXXXXXXX Theck grammar in the stem. Consider: The preferred method of cooling 20 N 5? i leaking steam generator.. .XXXXXXXX Made a few changes to the tern. Question is OK with changes. XXXXXXXXXX 21 F 1 B S Unnecessary information in the stem. Appears as if you only need to say:

22 F 1 X N E The AB is isolated during an AGW release event to: T/F question.

XXXXXX will continue here on Wednesday

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

Q# LOK LOD r

°v (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus Dist. Link unitsi ward K/A Only LOD very. Need to do a better job of explain why the distractors are 23 H 1 X N U lausible. XXXXXXXX Will revisit the question. Looking at providing a revised/new question XXXXXXXXX Reviewed new question and found it to be acceptable 11/15/2012 XXXXXXX 24 H 1 9 Please explain why destractors are plausible??? XXXXXXXX will think B

thout thisXXXXXXX 25 H 3 5/9 Is this an RO question? XXXXXXX licensee says this is not an SRO only N

iuestion. Decided to keep as RO question. XXXXXXXXXX 26 H 2 M/B S 27 H 2 B S 28 H 2 B S 29 Need to discuss this question. Appears to be GFES question XXXXX B S/

iccepted question as isXXXXXXXX 30 H 2 B S 31 H 2 B S Not sure if distractors are plausible. The question ask why the CCP handswitches are required to be placed in PULL TO LOCK. The correct 32 F 1 nswer containes CCP. XXXXXX identified procedures where several of N

he distractors are addressed in procedural notes/cautions. Also system perational issues that could occur when establishing charging and etdown. Accepted question as is. XXXXXXXX 33 B S 34 B 35 B S

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 SEQ Nuclear Plant 201 2-302 December 2012

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

Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO B/M/N U/F/S Explanation Focus Dist. Link units ward KJA Only red Dist: A If the pressure control setpoint is lowered heaters coming n would not be plausible. C Pressure remaining constant is not lausible.

36 X U/F Rec: IF the applicants are required to know the normal setpoint (-67%),

hen substitute changed for lowered, then have two answers having ieaters coming on and two having the spray valves opening. )(XXXXX dade change in the stem and made a change to distractor D. Accepted luestion. Should have been an E XXXXXXXXX re applicants required to know that the BYA breaker would be closed ihen doing the Train-A SSPS testing?

37 F/S Vould the Protection System Train-B Trouble alarm be in? XXXX made hange. With change, pure the licensee this becomes as question that an be answered with system knowledge. Question as revised is OK.

Should have been and E.XXXXXXXXX Stem Focus: Does the annunciator alone mean that there has been a loss f the 6900v Shutdown board? If the charger failed/breaker opened, the

)attery would still be providing power for some period of time.

Does the CH II Vital 120v AC come from the bad system inverter? Is 38 F/S here an auto swap to a regulated power supply such that losing the DC ower wouldnt result in losing the AC. i.e. would losing the DC result in osing the AC and therefore prevent the AFW pump from starting?

O(XXXXX Did not make changes to question. Question should have een identified as Sat.XXXXXXXXX red Dist: Substitute A or B. What is different between upper & lower ompartment coolers such that I would pick one over the other? i.e., if nothing distinguishes one from the other, obviously neither can be correct.

39 E?

lso, the incore instrument room cooler seems to be the odd one out vhen looking at these four coolers. XXX)(XXX No changes required.

uestion should have been an S.XXXXXXXXXX

.0 X S ould D not be correct? Since the minimum time has already been met, 41 F/S ou could say that it also means immediately. X)(XXXX made a minor hange in stem. F/S. acceptable question. XXX)(XXXXX

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

Q# LOK (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus Dist. Link units ward K/A Only larification: The annunciator that I found on 1-XA-55-6B has alarm A3 PS-A-2AR HIGH NEGATIVE RATES STEAMLINE PRESSURE LOOP 1 Then B3 & C3 would be loops 2 & 3. Is this the same alarm?

The attachment provided UNIT 1&2 CYCKE DATA SHEET states the 42 U/E etpoint as 100 psig decreasing in a 50 sec time constant. The alarm loesnt mention anything about time. If the alarm comes in and then goes ut as stated in the question stem, it looks like you will get the alarm but till you get the isolation if you are at the setpoint only for a second? This needs to be clarified. i.e. could A be correct also? XXXXXXXXX Added larm. Question is/was S. XX)(XXXXX LOD: GFES question and a weak one at that. Need to limit the number 01 hese on the exam. XXXXXXXXX at this point there are not too many 43 2

uestions of this type. Accept questions. Should have/is an S.

xxxxxxxx re the applicants required to know the functions of various transmitters using number only (no noun names)?

Stem Focus: The correct answer states PT-3-1 but the answer analysis C states PT-1-33. Which one is correct?

44 ? Partial: The question states that the indications are flow going up and level going up. What about placing FRVs in manual and controlling level s an Immediate Action is incorrect? The question needs to be more lefinitive on why addressing pump speed is correct and taking control of FRVs is ALWAYS incorrect. XXXXXXXX Added noun names. Edited wo distractors. nothing major. Question is S. OK. XXXXXXXXX 45 X S Distractors A & D are not plausible. Do not think anyone would consider hat cooling water on any system would be routed to the floor drain. Do 46 not see K/A match. XXXXXXXX There are other components whose U

ooIing water goes to the floor drain collector tank/sump. Fire water wmps goes to a sump. Accepted question as is Should have been an 5, xxxxxxxx Distractors A & B are not plausible. Stem as for procedural actions.

47 X ctions are not identified in A & B. XXXXXXX Made changes to parts of U

he distractors. Question should have been an E. Question is now an Sat. XXXXX 48 S

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 SEQ Nuclear Plant 201 2-302 December 202

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

Q# LOK (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 Explain how the question addresses automatic operation. XXXXXX will rovide a different question. As written the question is/was a U.XXXXXX 49

Revisting question Accepted new Question..11/15/2012. Question hould have U based on not matchinq K/A 50 S Explain why you consider this a K/A match. XXXXXXX after discussion 51 X U? igreed with the licensee that the question matches the K/A. Made one listractor change. Question should have been an E. XXXXXXXX 52 S Distractors A & B are not plausible. Cant think of any situation for the 53 U onditions given that a component would trip and immediately reclose.

DCXXX Changed /modifier.Question is Ok. is Question is OK.

54 S 55 S 56 S 57 59 s the required for an RO? XXXX Licensee said this is RO knowledge.

uestion is Sat. XXXX 58 S Dist: A Rod Bottom light lit when at 28 steps is not plausible.

KA: There is no relationship between the two in the question. Its an event 59 X X U hat happens to affect both items in the KA (i.e. the rod position indication has no effect on the Nis in this question). X)CXXXX question should have een and E. Made a few changes. Question is Sat XXXXXXXX Dist: B- Is there any equipment powered by the MOV board other than 1OVs? If not, its not plausible.

60 X E/S Explain in more detail why D is plausible. XXXXX Question is S. Should have been S.

Stem needs to reference the procedure that directs the actions. If not, 61 X E vouldnt either method reduce temperature? XXXXXXX Added rocedure information. E. Question is OK. XXXXXXXXXX

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

Q# LOK (F/H)

LOD (1-5) Stem Cues TIF Cred. Partial r

Job- JMinutia

1 Back- Q SRO B/M/N U/E/S Explanation Focus j Dist. Link units ward K/A Only Need additional information supporting plausibility the reasoning for a 62 E/S ystem selecting a higher of two signals doesnt seem plausible. XXXXX

)uestion is Sat. Should not have been identified as Sat. XXXXX 63 5 64 S Part: B, the correct answer can not happen unless D is correct. C, If he discharge valve is not fully open, will pump get a trip signal after some 65 U ime delay? If so, then this could be correct also. There are too many ubset issues going on with this question. XXXXXXX Minor changed vording in stem. Should have been an S/E. Question is OK. XXXXXXXX LOD. Consider the following: Is there a procedure element that we can incorporate into this question? If between the lines, are they to 66 xtrapoIate or go to the next highest line (press). At least put the S

)perating point between two of the pressures stated on the graph.XXXX fill provide a new question 11/14/2012 XXXXXXX Provided new uestion and it was acceptable 11/15/2012 S/,L XXXXXX Spray line temperature low temperature being caused by excessive spray low is doesnt appear to be plausible (B & D). Same alarm being caused 67 U y surge line temperature rising not too plausible either. XXXX Licensee igreed that distractors B & D are not plausible. Is a U. modified Question rovide is acceptable. XXXXXXXX dd trend to count rate.

red Dist: With the information given, why would the applicant think that ne or both SR Nis were inoperable?

Rec: Suspend CR movement... yes/no 68 X E Initiate Emergency Boration. . . yes/no XXXX Made changes as suggested in stem. Changed distractors C & D However question not acceptable. Will provide a new question.

11/14/2012. XXXXXXX Reviewed and accepted new question with iinor changes. Should have been a U. 11/15/2012, XXXXXXXX Vhat has cycled? The stem states a safety, the analysis for B sounds like he PORV.

69 X X E/S Distractor D is not plausible. Is there any TS that requires placing the unit n MODE 3 within 15 minutes? XXXXXX Changed be in mode 3 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months based on exceeding RCS pressure safety limit. Accepted change

xxxxx

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 SEQ Nuclear Plant 2012-302 December 2012

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 #1 Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only Need to make sure there is no subset issue. If the reactor trips now, it will lefinitely trip if I continue to lower power. Would it not be better to say the 70 S? reactor tripped at the current conditions... .XXXX)O(X Revised distractorA B to eliminate possible subset issues. SAT question Enhanced xxxxx LOD. There is only one answer D that lists a rad monitor for each steam 71 me. Could the question be reworded and still keep distractors a, b and

? XXXXXX Revised parts of the question to address concerns.

ccepted revised question. Should have been an E. XXXXXXXXXX 72 S 73 S Put trend on Tavg and power.

red Dist: Why would Tave be decreasing with an Uncontrolled Rod 75 U Vithdrawal? Not plausible (A&B). XXXXXXX made a change to istractors A & B. Leave as U. Acceptable with change. XXXXXXXXX

Generic Comments

1. If the stem of the question has the word correctly in it, please remove it from the question.

2. When writing questions, should it be Unit One or Unit 1?

3. need to establish a convention concerning how to emphasize adjectives. For example, underline, bold, bold and underline, etc.

SRO ONLY Questions ppears as if question can be answered with RO system knowledge/procedural usage. Distractors A & C do not appear 76 U to be plausible. XXXXX changed information in stem.

Removed information from distracters A & C. concluded question should have been an E. XXXXXXX 77 S 78 uestion can be answered with system/RO knowledge only XXXXXX U

uestion is good (5) as written should be as only changed info in stem.

eaching in stem. Tells the applicant what will happen on a occurs. l his something you would expect them to know? Is there ONE case in the.

,hole of TS that allows the unit to operate without one of its Vita nstrument power boards being lost? This really does not seem to b 79 U lausible. If you lost a VITAL, it would seem that you could not operat ONTINUOUS without it. Therefore A & C do not appear to be plausibi (XXXXX Revised information in stem to have the applicant be required to dentify mode. Should not have been a U based information provided. I ou were in mode 5 the unit could remain in .... XXXXXXXX.

1ay want to add information to stem. Should the question include information about/identifying start up rate/ power level. You provide power 80 S/E level in distractr D. XXXXXXXX Added information about startup rate.

lso revised distractor D. XXXXXXX an be answered with RO only knowledge. XXXXX procedures that are

,ntered are not from immediate actions. However, question can be answered with RO knowledge. Question is U as initially identified. Will 81 U york on question. Consider making it a two part question XXXXXSSSS n 11/13 provided a new question that was determined to be acceptable.

4ew question is acceptable. Will revisit and make a two part question.

Identifying question as a U was correct. SSSSSSS.

Distractors C and D are not plausible. Why would you expect the crew to refer to T.S. before taking the actions of the procedure? XXXXX 82 U/E )hanged stem format and distractor format. Ok to call the question a U based on changes made. Question is OK with change.

(XXXXXXXXXXXXXXX 83 U )o not think this is SRO. Any RO would know that you only need to trip

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401 -9 SEQ Nuclear Plant 2012-302 December 2012 he turbine if you are above 30% power XXXXXXXXX Changed power evel to 35% and changed answer to D. Not a U. U/E 84 S ould be two correct answers. Is this SRO only. It appears that question 85 an be answered with RO knowledge of procedure usage. Look at Step 5 of E-0. XXXXXXXXXX Decided to accept question following iscussion. Question should not have been a U.

onsider making this a two part question XXXXXX Made this one a two 86 E art question. Changes are acceptable. XXXXXXXX 87 S ppears as if question can be answered with RO knowledge. XXXX Decided question was OK and is a SRO based on first part more than econd. Question should have been a S. No chanaes were made.

O(XXX -

2uestion can be answered with RO knowledge... XXXX Will select a new 89 (IA. Too many chances for a challenge A2.02 is the new K/A. XXXXX UP Reviwed Provided new question. Question was acceptable. Should have been a U. 11/15/2O12XXXXXXX 90 S 91 S 92 Not SRO only. Appears to be memory level question XXXXXX agreed to iccept question. Question should have been a S. XXXXXXXX

\nswer given in stem. You tell the applicant that AOP-N.08 is 93 implemented and the time it is implemented. Therefore, other distractors U

ire not plausible. XXXXXX Decided to accept question as is. Should have been a S XXXXXX deed to look at OPDP-1 to address correct answer and determine 94 ? )lausibility of using 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months requirement... .XXXX)(X Question is Ok. S (xxx 4eed clarification on RCS & SFP boron concentration. May be two 95 E? orrect answers. XXXXX Changed dilution value from 2000 ppm to 2200 pm. Question is OK. XXXXXXX 96 Do not think this is SRO only. Explain why! XXXXX they explained it is

. UP 3RO only. Question should have been a S.XXXXXXXX Do not think this is SRO only. Need clarification of difference between 97 LCO tracking log and narrative log. XXXXXX decided question is OK.

U/E Did not need to change question. Question should have been a S.

(xXXX

ou ask the applicant to identify the sections of the procedure. Two of the 99 J listractors have only one section.... Therefore you have two implausible XXXXXChanged distractors. questions was a U/E XXXXXX 100

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 SEQ Nuclear Plant 2012-302 December 2012 ES-401, Rev. 9 2 Form ES-401-9

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Date of Exam: Exam Level: ROEI SROE Initials Item Description a b c

1. Clean answer sheets copied before grading (a?- (/FI Ef

2. Answer key changes and question deletions justified

-sj/

1 and documented

3. Applicants scores checked for addition errors (reviewers_spot_check>_25%_of examinations) 9,

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, fi,,

as applicable, +/-4% on the SRO-only) reviewed in detail - 4P .4

5. All other failing examinations checked to ensure that grades are justified /9I -

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/Signature Date

a. Grader CkI i

b. Facility Reviewer(*)

c. NRC Chief Examiner (*) ,5

d. NRC Supervisor (*)

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

ES-403, Page 6 of 6

ML13274A665

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