Sequoyah Initial Exam 2012-302 Final Administrative Documents. · 2013. 10. 7. · Outline Quality...

ES-201 Examination Preparation Checklist Form ES-201-1

DecemberFacility: Sequoyah Date of Examination: 2012

ljExaminations Developed by:

Written / Operating Test

T ChiefargetTask Description (Reference) Examiner’sa e

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, asapplicable (C.1.e and f; C.3.d)

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

{-45} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, asapplicable), 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 andh; C.3.d)

-30 9. Preliminary license applications (NRC Form 398’s) 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 confirmqualifications / 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 toNRC examiners (C.3.i)

* Target dates are generally based on facility-prepared examinations and are keyed to the examination dateidentified in the corporate notification letter. They are for planning purposes and may be adjusted on acase-by-case basis in coordination with the facility licensee.[Applies only] {Does not apply} to examinations prepared by the NRC.

C.— S--

ES-201, Page 25 of 27

C

ES-201 Examination Outline Quality Checklist Form ES-201-2

FitY Sequoyah Nuclear Station Unit 1 & 2 Date of Examination: 12/03/12

InitialsItem Task Description — — —

a b* c#

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. 41,w

——.---

R b. Assess whether the outline was systematically and randomly prepared in accordance withI 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 numberof normal evolutions, instrument and component failures, technical specifications,

S and major transients. 47 _••I

. —--bM b. Assess whether there are enough scenario sets (and spares) to test the projected numberu and mix of applicants in accordance with the expected crew composition and rotation scheduleL without compromising exam integrity, and ensure that each applicant can be tested usingA 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 qualitativeR and quantitative criteria specified on Form ES-301-4 and described in Appendix D. 1)13 .- k

--

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 formI (2) task repetition from the last two NRC examinations is within the limits specified on the form / LT (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.

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 coveredin 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 rd. Check for duplication and overlap among exam sections.

. -.X .1A e. Check the entire exam for balance of coverage. ‘“ irL

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

a. Author Michael BucknerD

b. Facility Reviewer (*) Steven Tuthill I ,.. IIf2/,LNRC C[ef Examiner (#) i/

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

ES-201 Examination Security Agreement

0

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 mysignature. 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 chiefexaminer, understand that I am not to struct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensingexaminations from this date until compl on of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulatorbooth operator or communicator is acceabIe if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware ofthe physical security measures and req cements (as documented in the facility licensee’s procedures) and understand that violation of the conditions of thisagreement may result in cancellation oi ne examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facilitymanagement 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 theweek(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 theNRC.

SIGNATURE (1)

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PRINTED NAME B TITLE / RESPONSIBILITY. 0

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DATE NOTE

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 licensee’s 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 facilitymanagement 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 theweek(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.

PRINTED NAME

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ES-201

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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 licensingexaminations 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 licensee’s 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.

PRINTEDNAME J.)BTITLE/RESPONSIBILITY SIGNATURE(1) DATE SIGNATURE(2) DATE NOTE

1. Ccc P1e4c On 4- [ç12. flI1bv Cé’J\ &YLCW U: Oico C I/Jf//Z.

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4. 5. — _..-— / 25. S r’- ,‘r ( . (_) /1- ZJ/

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NOTES:

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

Facility: Seguovah Nuclear Station 1 & 2 Date of Examination:12/3-7 2012Exam Level: RO LI SRO X Operating Test No: 2012-302

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

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

Conduct of Operations R, D K/A 2.1.7 (4.4) Perform A RCS Void Determination AndApply The Result To Determine RCS Pump SweepRequirements.

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

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

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

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking 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 leveland boron concentration and apply the data using the Technical requirements Manual Section3.1.2.6 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 anddetermine that individual RCP Pump sweeps are required to restore the RCS from the outagecondition.

A.2

While acting as the Operations Work Control SRO and given a hypothetical maintenancesituation, 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 CoreDamage Frequency (CDF) and Large Early Release Frequency (LERF) Multipliers change andthe 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 receivethe 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 2012Exam Level: RO X SRO Operating Test No: 2012-302

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

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

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

Equipment Control R, M K/A 2.2.12 (3.7) Perform A Reactivity BalanceCalculation 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 NotificationWorksheet. (New Plant Process)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking 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 2012Exam 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 1Normal 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 3Safety 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 4PRHR 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 4SFeedwater.

f. K/A EPE E14 EA 1.1 (3.7/3.7) Respond To High Containment Pressure 5, A, D, L 5Condition 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 6Diesel 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 7Instrumentation.

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 4Swith 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 8PCV-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 5SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the controlroom.

* 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 i 1(N)ew or (M)odified from bank including 1 (A) 2 I 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 directedto initiate Emergency Boration using EA-68-4 EMERGENCY BORATION section 4.2. During thealignment the emergency borate valve will fail to operate. The examinee uses the alternate path toestablish emergency boration flow through the normal boration flowpath.

b. The examinee will assume the shift with Excess Letdown in service. The examinee will remove ExcessLetdown 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 LegRecirculation using ES-i .3, Transfer to RHR Containment Sump. The examinee will be directed to placethe 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 Legrecirculation 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 ShutdownCooling mode with a slight cooldown in progress. While monitoring plant operation the A Train RHR pumptrips 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 temperaturewith a slight cooldown.

e. The examinee will assume the shift in MODE 3 with no AFW flow available. The examinee will use EA-2-2, Establishing Secondary Heat sink using Main Feedwater or Condensate section 4.4 and start a MainFeed 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. Theexaminee will use FR-Z. 1, High Containment Pressure, starting at step 13 to establish RHR Spray flow toreduce Containment pressure. During the alignment, the B Train RHR Spray flow isolation valve FCV-72-41 fails to operate. The examinee uses the alternate path to re-establish B Train RHR to the injectionmode 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 6.9kvShutdown Board with the 1A EDG supplying power to the board. The examinee will restore power usingEA-202-1 Restoring Offsite Power to 6900V Shutdown Boards. The examinee will parallel the 1A EDG tooffsite 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 thePower Range Nuclear Instrumentation.

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

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

k. The examinee will assume the shift in MODE 3 following a major grid disturbance and Unit 1 in a Loss ofAll AC power. The examinee will be directed to reset the overspeed trip mechanisms on the 1A EDG. Theexaminee will reset both overspeed trip mechanisms and subsequently reset the 1A EDG lockout relay tostart 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 2012Exam 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 1Normal 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 3Safety 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 4SFeedwater.

f. K/A EPE E14 EA 1.1 (3.7/3.7) Respond To High Containment Pressure S, A, D, L 5Condition 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 6Diesel 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 7Instrumentation.

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 4Swith 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 8PCV-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 5SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the controlroom.

* 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 3 I 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 directedto initiate Emergency Boration using EA-68-4 EMERGENCY BORATION section 4.2. During thealignment the emergency borate valve will fail to operate. The examinee uses the alternate path toestablish 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 LegRecirculation using ES-i .3, Transfer to RHR Containment Sump. The examinee will be directed to placethe 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 Legrecirculation 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-2-2, Establishing Secondary Heat sink using Main Feedwater or Condensate section 4.4 and start a MainFeed pump and control feed flow using a Main Feed Regulating Bypass Valve.


g. The examinee will assume the shift in MODE 3 following a Loss of Power event to the iA 6.9kvShutdown Board with the 1A EDG supplying power to the board. The examinee will restore power usingEA-202-1 Restoring Offsite Power to 6900V Shutdown Boards. The examinee will parallel the 1A EDG tooffsite 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 thePower Range Nuclear Instrumentation.

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

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

k. The examinee will assume the shift in MODE 3 following a major grid disturbance and Unit 1 in a Loss ofAll AC power. The examinee will be directed to reset the overspeed trip mechanisms on the iA EDG. Theexaminee will reset both overspeed trip mechanisms and subsequently reset the IA EDG lockout relay tostart 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 3Safety 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 5Condition 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 4Swith 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 8PCV-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 5SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the controlroom.

* 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 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) 2 I 2 I 1(P)revious 2 exams 3 I 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 ExcessLetdown 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 LegRecirculation using ES-i .3, Transfer to RHR Containment Sump. The examinee will be directed to placethe 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 Legrecirculation flow through the 1 B Safety Injection pump.

d. Not examined.

e. Not examined.


g. Not examined.

h. Not examined.

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

j. The examinee will assume the shift in MODE 3 and a Control Room Evacuation in progress. Theexaminee 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

Initials1. 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 withinacceptable limits.

e. It appears that the operating test will differentiate between competent and less-than-competentapplicants 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 4 ç—criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specifiedon 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 - id. 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 ‘r3. 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 5T• the event termination point (if applicable) V

4. No more than one non-mechanistic failure (e.g. pipe break) is incorporated into the scenariowithout a credible preceding incident such as a seismic event. 4 5r —

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 obtaincomplete 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. L 1Cues are given.

—

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. Allother 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 , jspecified 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 3r —Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes — -- --

1. Total malfunctions (5—8) 6 / 6 / 5 r

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

3. Abnormal events (2—4) 3 / 3 / 3 c3r-

4. Major transients (1—2) 1 / 2 / 1 Sr5. EOP5 entered/requiring substantive actions (1—2) 1 / 1 / 2 Sr6. EOP contingencies requiring substantive actions (0—2) 1 I 1 I 0

7. Critical tasks (2—3) 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 NI T POSITION POSITIONT

c _A MA T S A B S A B L uKI , R T 0 R T 0 MI*I’l T

0 C P 0 C P —k——TR IU

E

RO RX 1 1110

SRO-INOR 42

X I/C 12,5 2,3 5 4 4 2SRO-U MAJ 6 — 5,7 — 3 2 2 1‘— TS 2,3 2022

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

SRO-I NOR zz:ziii:X I/C 442

MAJ 221TS 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 ATCposition. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer toSection D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normalevolutions 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 thatrequire verifiable actions that provide insight to the applicant’s competence count toward the minimumrequirements specified for the applicant’s 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 TML N CREW CREW

T NI T POSITION POSITIONc A MA T S A B S A B L uR T 0 R T 0 M*N Y

0 C P 0 C PT PR lU

E

RO RX 1 1 110

SRO-lNOR 4 2 111

X I/C 1,2,5 2,3, 6 4 4 2SRO-UMAJ 6 5,7 3221TS 2,3 2022

RO RX 4 1 110

D NOR 1 1111SRO-lx I/C 1,2 2,3,4 5 4 4 2SRO-U MAJ 6 5,7 3 2 2 1D TS 3 2022RO RX 110

SRO-I NOR 111

SO-UMAJ 221TS 022

Instructions:3. Check the applicant level and enter the operating test number and form ES-D-1 event numbers for each




ES-301 Transient and Event Checklist Form ES-301-5Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 12/3/2012 Operating Test No.: 2012-302

A E Scenarios

1 2 3 TML N CREW CREW CREW NI T POSITION POSITION POSITION

Tc MA T S A B S A B L UN R T 0 R T 0 Mf*-,- 0 C P 0 C P —-s--—I P

R lUE

RO RX 1 1110xSRO-l NOR 4 2 — 2 1 1 1

I/C 23 4 4 2SRO-Uj MAJ 6 — 7 — — 3 2 2 1

TS 0022RO RX 4 1 110

SROINOR 1

I/C 1,2 — 4,6 — 4 4 4 2SRO-U MAJ 6 5,7 3 2 2 1D TS 0022RO RX 0110

SRO-lNOR

I/C 1,2,5, 4 4 2SRO-Ux MAJ 6 1 221

TS 3 2022RO RX 110

SRO-lNOR

D I/C 442SRO-U 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




ES-301 Transient and Event Checklist Form ES-301 -5Facility: 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 T NI T POSmON POSITION POSITION POSITION A

C S A B S A B S A B S A B LA 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 —---—T R IU

ERO RX 4 1 110

SRO-l NOR — 1 1 ILI/C 1,2 4,6 4 4 4 2

SRO-U MAJ 6 5,7 3 2 2 1TS 022

RORX 1

X NOR 4 1 111SRO-I I/C 5,6, 23,5 6 4 4 2L_J 7

MAJ 6 5,7 3 2 2 1U

TS 022RD RX 110

SRO-INOR

EJ I/C 1,2,5, 4 4 4 2SRO-U .. —x MAJ 6 1221

TS 2,3 2022RD RX 110

SROINOR

I/C — — 442SRO-U MAJ 2 2 1D TS 022Instructions:

3. Check the applicant level and enter the operating test number and Form ES-D-i event numbers for eachevent 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 ATCposition. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.


3, Whenever practical, both instrument and component malfunctions should be included; only those thatrequire verifiable actions that provide insight to the applicant’s competence count toward the minimumrequirements specified for the applicant’s 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 ElSRO-I El SRO-l X SRO-I El SRO-l ElSRO-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‘‘ : ‘ ‘‘ : ‘ i 6,7

8 8 8

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,

B‘i” 3,4, 3,4, 3,4, 3,4, 3,4, 3,4,oarus k’4 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, 5,6,7anu 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) : : : : 3:4: 5,6,7

7 7,8 7 7 7,8

Comply With and 2,3 2,3 2,3 2,3 2,3 2,3Use 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 theexaminers 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 PointsTier Group —

KKKKKKAAAAG A2 G* Total1 2 3 4 5 6 1 2 3 4 * Total

i 433343 20 4 3 7Emergency &

2 T T 2 1 1 7 2 1 3Abnormal Plant — — — NIA — — NIAEvolutions Tier Totals = 27 6 4 10

1 32313223232 26 3 2 5

2.2 TT 12 0 2 1 3Plant

Systems Tier Totals 3= = = T = =

3. Generic Knowledge and Abilities 2 3 4 10 1 2Categories 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 ROand 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 tablebased 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 donot apply at the facility should be deleted and justified; operationally important, site-specific systems that arenot included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regardingthe elimination of Inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolutionIn 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 beselected. 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 topicsmust 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’ importanceratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enterthe group and tier totals for each category in the table above; if fuel handling equipment is sampled in otherthan 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-401-1KA 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 j [] [] [] [] [] [] [] [J [] Reactor powerCore Flow CIrculation /1 & 4

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 makeoperational judgments based on operatingcharacteristics, reactor behavior and instrumentinterpretation.

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 (seeAK2.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

295025G2. 1.27

295026EK3.04

295028EA1.03

295030EK1.02

295031EA1.04

295037EK2.12

295038EK1.O1

600000AK1.O1

High Reactor Pressure / 3

Suppression Pool Hli Water Temp.5

High Drywell Temperature /5

Low SuppressIon Pool Wtr Lvi

Reactor Low Water Level / 2

SCRAM Condition Present and PowerAbove APAM Downscale or Unknown/1

High Off-site Release Rate / 9

Plant Fire On Site /8

I

/5

ElELJL1E1ElEEIEl

OElLILILiEILI

LiE LILI LI LI El El LI

LI [lEO LI LI LI LI El LI

EELII1LJL1LiD

LIE LHZIE El LI LI LI

EU El LI LI LI LI Li LI

EDLILILILILI

—Knowledge of system purpose and or function.

SBLC injection

Drywell cooling system

Pump NPSH

High pressure core spray: Plant-Specific

Rod control and information system: Plant-Specific...

Biological effects of radioisotope ingestion

Fire Classifications by type

Sensors, detectors, indicators

RO SRO

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

43.9

3.7

3.9

3.5

4.3

3.6

2.5

2.5

El

3.9 El

3.8

4.2 LI

3.80

3.1

2.8

700000AK2.O3 Generator Voltage and Electric GridDistrurbancecs

3.0 3.1 EELIUEEIE1ELILI

Page 2 of 2 12/4/2012 6:47AM

ES-401, REV 9

KA NAME I SAFETY FUNCTION:

295009AK1 .02 Low Reactor Water Level / 2

29501 OAA2.06 High Drywell Pressure /5

295012AK3.01 High DryweN Temperature / 5

295013G2.4.18 High Suppression Pool Temp. / 5

295017AA1.05 High Off•site Release Rate /9

295035EA1 .01 Secondary Containment HighDifferential Pressure /5

500000EK2.07 High CTMT Hydrogen Conc. / 5

T1G2 BWR EXAMINATION OUTLINE

1R K1K2K3K4K5K6A1A2A3A4G

SRO

3.1 Ofl]L1L1

3.6

3.6 DLJLJL1

4.0 L1L1L1DL1LJLJIZJLJL1t1

3.2

3.6

üE1LLL1L1D

TOPIC:

Recirculation pump net positive suction head: Plant-Specific

DryweU temperature

Increased drywell cooling

Knowledge of the specific bases for EOPs.

SPDS/ERISJCRIDSIGDS: Plant-Specific

Secondary containment ventilation system

Drywell vent system

FORM ES-401-1

RO

3.0

3.6

3.5

3.3

2.7

3.6

3.2

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 fl fl fl El Li [] El El El El El D.C. electrical power

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 El [] [] El El El El [ [] El Reactor water level

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 El (] [] [] ) [] [] [] [J Explosive valves

212000A3.02 RPS 3.2 3.5 El El El El El El El El Ei LI El Individual system relay status: Plant-SpecifIc

212000A4.15 RPS 3.9 3.8 El El El El El El El El El El Recirculation pump trip/EOC APT

2150031

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1KA 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 doesnot 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 systemoperating parameters which are entry-level conditions foremergency 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

264000G2.2.42 EDGs 3.9 4.6 [] [] [] fl [] [) [J [] [] [] Ability to recognize system parameters that are entry-level conditions for Technical SpecificatIons

300000A2.Ol Instrument Air 2.9 2.8 [] [] [] [] fl [] [] ( [] [J [] Air dryer and filter maltunctions

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 fl [] [] fl [] [] [] [] [] [] Leak detection: Plant-Specific

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 J J J 1j Ability to recognize abnormal indications for systemoperating parameters which are entry-level conditions foremergency 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

ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1

Knowledge of conduct of operations requirements.

Abiflty to execute procedure steps.

Ability to coordinate personnel activities outside thecontrol room.

Knowledge of pre- and post-maintenance operabilityrequirements.

Knowledge of limiting conditions for operations and safetylimits.

Ability to analyze the effect of maintenance activities,such as degraded power sources, on the status oflimiting conditions of operations

Ability to control radiation releases.

Knowledge of radiological safety procedures pertaining tolicensed operator duties

Knowledge of EOP implementation hierarchy andcoordination with other support procedures or guidelines.

RO Sf0

KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

G2.l.l Conduct of operations 3.8 4.2 Li LI LI Li LI Li LI LiLiLi

02.1.20 Conduct of operations 4.6 4.6 LI LI LI LI LI LI Li Li Li Li II

G2.1.8 Conduct of operations 3.4 4.1 [] L] Li LI LI LI LI Li LI LI S]

G2.2.21 Equipment Control 2.9 4.1 LI LI Li Li LI LI LI Li Li LI 1I

G2.2.22 Equipment Control 4.0 4.7 Li LI Li LI LI Li LI Li LI Li I

02.2.36 Equipment Control 3.1 4.2 LI Li LI Li LI Li LI Li LI LI I)

02.3.11 Radiation Control 3.8 4.3 LI Li Li LI Li LI LI Li El Li IJ

02.3.13 Radiation Control 3.4 3.8 LI LI LI LI Li LI Li Li Li LI lI

02.4.16 Emergency Procedures/Plans 3.5 4.4 [1 LI Li Li LI Li LI LI LI Li [l

02.4.5 Emergency Procedures/Plans 3.7 4.3 LILILILILiLILiELILI Knowledge of the organization of the operatingprocedures network for normal, abnormal and emergencyevolutions.

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

ES-401, REV 9

KA NAME / SAFETY FUNCTION:

295004AA2.02 Partial or Total Loss of DC Pwr /6

295016G2.2.37 Control Room Abandonment / 7

29501 9G2.1 .28 Partial or Total Loss of Inst. Air / 8

295023AA2.02 Refueling Acc Cooling Mode /8

295024EA2.02 High Drywell Pressure / 5

29503702.4.49 SCRAM Condition Present and PowerAbove APRM Downscale or Unknown11

700000AA2.07 Generator Voltage and Electric GridDistrurbancecs

SRO T1G1 BWR EXAMINATION OUTLINE

IR K1K2K3K4K5K6A1A2A3A4G

RO SRO

3.5 3.9 jFJ

3.6 4.6

4.1 4.1 FJJj

3.4 3.7

3.9 4.0 rjrj

4.6 4.4

3.6 4.0 L1D1E1D

FORM ES-401-1

TOPIC:

Extent of partial or complete loss of D.C. power

Ability to determine operability and/or availability of safetyrelated equipment

Knowledge of the purpose and function of major systemcomponents and controls.

Fuel pool level

Drywell temperature

Ability to perform without reference to procedures thoseactions that require immediate operation of systemcomponents and controls.

Operational status of engineered safety features

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

ES-401, REV 9

KA NAME / SAFETY FUNCTION:

295OO7AA2.0 High Reactor Pressure / S

29501 2G2.4.1 1 High Drywell Temperature /5

295032EA2.03 High Secondary Containment AreaTemperature /5

SROT1G2 BWR EXAMINATION OUTUNE

IR K1K2K3K4K5K6A1A2A3A4G

RO SRO

4.1 4.1

4.0 4.2 flUEL1EflELiL

3.8 4.0

FORM ES-401-1

TOPIC:

Reactor pressure

Knowledge of abnormal condition procedures.

Cause of high area temperature

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 thoseactions that require immediate operation of systemcomponents and controls.

215003A2.05 IRM 3.3 3.5 [] fl Q [] [j fl j [] [] [] Faulty or erratic operation of detectors/system

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 El El El LI El El LI El El LI Knowledge of how abnormal operating procedures areused 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

Ability to recognize abnormal indications for systemoperating parameters which are entry-level conditions foremergency and abnormal operating procedures.

KA NAME / SAFETY FUNCTION: IR 1

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 corealterations

02.2.18 Equipment Control 2.6 3.8 [3 [] [3 [3 [1 Li LI [] [] [3 ] Knowledge of the process for managing maintenanceactivities during shutdown operations.

02.2.39 Equipment Control 3.9 4.5 [3 [] [3 Li [] [3 [3 [] [] Knowledge of less than one hour technical specificationaction 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 andemergency 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 emergencyplan, including supporting or acting as emergencycoordinator.

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 systemoperating parameters which are ently-level conditions foremergency 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 RejectionGroup Selected K/A

RO

Ti Gi 029 G2. 1.25 Unable to write an operationally valid question for this K/A due tonot using graphs or curves when dealing with selected emergencyevent.

(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 questionat 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 thecontrol room associated with this system. (Rejected and randomlyreselected 076 G2.4.34)

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

T3 G2.4. 13 Unable to write an operationally valid question at the SRO level forthis 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 forthis KJA. (Rejected and randomly reselected 008 A2.02)

‘2

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 7Initial

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 ‘T4 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 indicatedbelow (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly developed; orthe 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; orother (explain)

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

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

8. References/handouts provided do not give away answers or aid in the elimination of 9jjg 5. J.distractors. k9. 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’ 5ç—justified.

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 iscorrect and agrees with the value on the cover sheet.

Printed Name / Signature Date

a. Author Michael Buckner I 2b. Facility Reviewer (*) Steven Tuthillc. NRCChiefExaminer(#) .4cJ-..’ii L€ /.d :i.,.,d. NRC Regional Supervisor ,t99,V // I

Note: * The facility reviewer’s 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-401-9SEQ 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 reviewer’s 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 ExplanationFocus Dist. j Link unitsi ward K/A Only

s written there doesn’t appear to be a correct answer. If charging flow isdequate to overcome the leak rate and make RCS pressure rise, thenCP 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 startowering and make D the answer.

H 3 U?ecommend changing the stem to state that the block valve goes tontermediate. Does not appear that charging flow would be capable ofaking 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 boilingwould never transition into natural circulation without some input from theperator or automatic system.

2 F 2 U Veak question structure. A better question would provide post LOCAlata and have the applicant determine if NC or reflux boiling is occurringmd 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 aetter 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 informationustifying question> XXXXXXXX Question is Sat.XXX)(X

4 S

)orrect answer can be chosen without knowing the answer to the firstluestion. 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 thelow band necessary to answer the question and would fully meet the K/A.This would then be SAT. XXXXXX Made minor changes to stem andnade 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 the9 SI? RO applicants? XXXXXX Made a small change to wording in stem.

uestion should have been S/E. XXXXXXX

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 TIF Cred. Partial Job- Minutia #/ Back- Q SRO U/E/S ExplanationFocus Dist. Link units ward K/A Only

Distractor D is not plausible. Will stopping the feed to the ruptured SGay lengthen the TD AFW availability. XX)O(XXXXX ChanQed distractor

10 Eand D. Used second part of bases for C. Will fix D. XXXXXXXX

Reviewed and accepted new distractor based on the fact that this woulde true is you were in ECA 2.1. Accepted change based after reviewingases.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 B E/Sorrect the wording in the stem: RCS depressurization is XXXXXX,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 B Srequired to know this from memory? X)(XXXXXXX per the licensee, thisis 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 B E hat order. Provide documentation that shows reason. XXXXXXXDhanged 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 cooling20 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

ES-401, Rev. 9 Written Examination Review WorksheetSEQ Nuclear Plant 2012-302

December 2012

Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 7.Q# LOK LOD — — — —r — —

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO°‘v”

U/E/S ExplanationFocus Dist. Link unitsi ward K/A Only

LOD — very. Need to do a better job of explain why the distractors are23 H 1 X N U lausible. XXXXXXXX Will revisit the question. Looking at providing arevised/new question XXXXXXXXX Reviewed new question and found

it to be acceptable 11/15/2012 XXXXXXX

24 H 1 B 9Please explain why destractors are plausible??? XXXXXXXX will think

• ‘thout thisXXXXXXX

25 H 3 N 5/9 Is this an RO question? XXXXXXX licensee says this is not an SRO onlyiuestion. Decided to keep as RO question. XXXXXXXXXX

26 H 2 M/B S

27 H 2 B S

28 H 2 B S

29 B S/Need to discuss this question. Appears to be GFES question XXXXXiccepted question as isXXXXXXXX

30 H 2 B S

31 H 2 B S

Not sure if distractors are plausible. The question ask why the CCPhandswitches are required to be placed in PULL TO LOCK. The correct

32 F 1 N nswer containes CCP. XXXXXX identified procedures where several ofhe distractors are addressed in procedural notes/cautions. Also systemperational issues that could occur when establishing charging and

etdown. Accepted question as is. XXXXXXXX

33 B S

34 B

35 B S

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 — — —

— B/M/N(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO U/F/S Explanation

Focus Dist. Link units ward KJA Only

red Dist: “A” If the pressure control setpoint is “lowered” , heaters comingn would not be plausible. “C” Pressure remaining constant is notlausible.

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 havingieaters coming on and two having the spray valves opening. )(XXXXXdade change in the stem and made a change to distractor D. Acceptedluestion. Should have been an E XXXXXXXXX

re applicants required to know that the BYA breaker would be closedihen doing the Train-A SSPS testing?

37 F/S Vould the Protection System Train-B Trouble alarm be in? XXXX madehange. With change, pure the licensee this becomes as question thatan 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 lossf 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? Is38 F/S here an auto swap to a regulated power supply such that losing the DC

ower wouldn’t result in losing the AC. i.e. would losing the DC result inosing the AC and therefore prevent the AFW pump from starting?O(XXXXX Did not make changes to question. Question should haveeen identified as Sat.XXXXXXXXX

red Dist: Substitute A or B. What is different between upper & lowerompartment coolers such that I would pick one over the other? i.e., ifnothing 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

ES-401, Rev. 9

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 ExplanationFocus 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 alarmloesn’t mention anything about time. If the alarm comes in and then goesut as stated in the question stem, it looks like you will get the alarm buttill 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 Addedlarm. Question is/was S. XX)(XXXXX

LOD: GFES question and a weak one at that. Need to limit the number 01

43 ‘2 hese on the exam. XXXXXXXXX at this point there are not too many• uestions of this type. Accept questions. Should have/is an S.

xxxxxxxxre 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 andlevel going up. What about placing FRVs in manual and controlling level‘s an Immediate Action is incorrect? The question needs to be morelefinitive on why addressing pump speed is correct and taking control ofFRVs is ALWAYS incorrect. XXXXXXXX Added noun names. Editedwo distractors. nothing major. Question is S. OK. XXXXXXXXX

45 X S

Distractors A & D are not plausible. Do not think anyone would considerhat cooling water on any system would be routed to the floor drain. Do

46 Unot see K/A match. XXXXXXXX There are other components whoseooIing water goes to the floor drain collector tank/sump. Fire waterwmps goes to a sump. Accepted question as is Should have been an

5, xxxxxxxxDistractors A & B are not plausible. Stem as for procedural actions.

47 X Uctions are not identified in A & B. XXXXXXX Made changes to parts ofhe distractors. Question should have been an E. Question is now an

Sat. XXXXX

48 S

Written Examination Review WorksheetSEQ Nuclear Plant 201 2-302

December 202

ES-401, Rev. 9 Form ES-401-9

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 ExplanationFocus Dist. Link units ward K/A Only

Explain how the question addresses automatic operation. XXXXXX will

49 rovide a different question. As written the question is/was a U.XXXXXX• 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 discussion51 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. Can’t think of any situation for the53 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 event59 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 haveeen and E. Made a few changes. Question is Sat XXXXXXXX

Dist: B- Is there any equipment powered by the MOV board other than1OVs? If not, its not plausible.

60 X E/SExplain in more detail why D is plausible. XXXXX Question is S. Shouldhave been S.

Stem needs to reference the procedure that directs the actions. If not,61 X E vouldn’t 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 LOD —r —

— B/M/N(F/H) (1-5) Stem Cues TIF Cred. Partial Job- JMinutia #1 Back- Q SRO U/E/S ExplanationFocus j Dist. Link units ward K/A Only

Need additional information supporting plausibility - the reasoning for a62 E/S ystem selecting a higher of two signals doesn’t 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”, Ifhe 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 manyubset issues going on with this question. XXXXXXX Minor changedvording in stem. Should have been an S/E. Question is OK. XXXXXXXX

LOD. Consider the following: Is there a procedure element that we canincorporate into this question? If between the lines, are they to

66 SxtrapoIate or go to the next highest line (press). At least put the)perating point between two of the pressures stated on the graph.XXXXfill provide a new question 11/14/2012 XXXXXXX Provided newuestion and it was acceptable 11/15/2012 S/,L XXXXXX

Spray line temperature low temperature being caused by excessive spraylow is doesn’t 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 thatne or both SR Nis were inoperable?

Rec: Suspend CR movement... yes/no68 X E Initiate Emergency Boration. . . yes/no

XXXX Made changes as suggested in stem. Changed distractors C & DHowever question not acceptable. Will provide a new question.11/14/2012. XXXXXXX Reviewed and accepted new question withiinor changes. Should have been a U. 11/15/2012, XXXXXXXX

Vhat has cycled? The stem states a safety, the analysis for B sounds likehe PORV.

69 X X E/S Distractor D is not plausible. Is there any TS that requires placing the unitn MODE 3 within 15 minutes? XXXXXX Changed be in mode 3 in 1hour based on exceeding RCS pressure safety limit. Accepted change:xxxxx

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9SEQ 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 ExplanationFocus Dist. Link units ward K/A Only

Need to make sure there is no subset issue. If the reactor trips now, it willlefinitely 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 distractorAB to eliminate possible subset issues. SAT question Enhanced

xxxxxLOD. 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 Rod75 U Vithdrawal? Not plausible (A&

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