ML13347B137

301 Final Administrative Documents

ML13347B137
Person / Time
Site:	Vogtle
Issue date:	12/11/2013
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
Download: ML13347B137 (115)

Text

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-1gi Examination Preparation Checklist Form ES-201-1 Facility: VO Ti E RC/ ? 3/ Date of Exam ination:°64O/c Developed by: Written - Facility NRC D ii Operating - Facility NRC Target Chief Date* Task Description (Reference) Examiners Initials

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

-120 2. NRC examiners and facility contact assigned (C.1 .d; C.2.e) yti 7

-120 3. Facility contact briefed on security and other requirements (C.2.c) )27 jg

-120 4. Corporate notification letter sent (C.2.d) ?7

[-90] [5. Reference material due (C.1 .e; C.3.c; Attachment 3)] A1/,q

{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-ls, ES-401-112, 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 J4 licensee (C.2.h; C.3.e)} 0/f V1

{-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 any Form ES-201-3 updates), and reference materials due (Cle, 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 (CII; 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 (Cli; C.2.f and h; C.3.g) 1)7 j/{iV

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

-7 14. Final applications reviewed; I or 2 (if >10) applications audited to confirm qualifications I eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

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

-7 16. Approved scenarios, job performance measures, and questions ,j fr/

distributed to NRC examiners (C.3.i) 7/

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.

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oftJf3vI1J& xin1 ES-201 . Examination Outline Quality Checklist Form ES2O1-2 Facility: Date of Examination:

Initials Item Task Description a b c#

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a. Verify thatthe outline(s) fit(s)theappropriate model, in accordance with ES-401 .

44 44 R b. Assess whether the outline was systematically and randomly prepared in accordance with f j I Section D.1 of ES-401 and whether all KIA categoriasareappropriatelysanpled.

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

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ci. Assess whether the justifications for deselected or rejected KIA statements are appropriate. J,,

2. a Using Form ES-301-5. verify thatthe proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S and major transienis.

V M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integiity, 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 appIicants audit test(s), and that scenarios will not be repeated on subsequentdays. b 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.

4

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-3O1-2:

(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 g 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

/ 4 (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria ontheform. b b Verify thatthe administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from thelasttwoNRClicensing examinations C. Determine if there are enough different outlines to test the projected number and mix of applicants_and_ensure that no_items_are_duplicated_onsubsequentdays.

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

b. Assess whether the 10 CFR 55.41/43 and 55.45 samplIng is appropriate. 5 t

N C. Ensure that K!A importance ratings (except for plant-specific priorities) are at least 2.5.

d. Check for duplication and overlapamong exam sections.

A e. Checkthe entire exam for balance of coverage.

f. Assess whether the exam fits the appropriatejob level (RO orSRO).

I Printed Name uref Date

a. Author rk A/ hcrr111S6AI/ 77i4O IC i:7T ø1/

b. Facility Reviewer (*) /2 WAfM1ZIT, j 3fVf/2 C. NRC Chief Examiner(#) /flICi/4EL 47Et/ffáiAs tt

d. NRCSupeMsor L4LX&ALi, \VjD/J4J/4J/

Note: #lndependent NRC reviewer initial items in tolumn c; chief examiner concurrence required.

Not acolicable for NRC-oreoared examination outlines 1 Page 26 of 28

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HL-17 NRC ES-201 Examination Security Agreement Form ES-2O13

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of i4/fJ/iZ as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g. acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowl9gq. I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of ft((jfl. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations

, except as specifically noted below and authorized by the NRC.

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HL-17 NRC ES.201 Examination Security Agreement Form ES201-3

1. Pre*Exarnination I acknowledge that I have acquired specialized knovA edge about the NRC licensing examinations scheduled of my signature. 1 agree that I wi not knowingly divulg for the week(s) of as of the date e any information about these examinations to any NRC chief examiner. I understand that I am not to instruc persons who have not been authorized by the t, evaluate, or provide performance feedback to those these licensing examinations from this date until completion of examination administration, except as applicants scheduled to be administered (e.g., acting as a simulator booth operator or commu specifically noted below and authorized by the NRC nicator is acceptable if the individual does not select feedback). Furthermore, I am aware of the physic the training content or provide direct or indirect al security measixes and requirements (as docum understand that violation of the conditions of this ented In the facility Iicensees procedures) and agreem the facility licensee. 1 will immediately report to facility ent may result in cancellation of the examinations and/or an enforcement action against me or may have been compromised. management or the NRC chief examiner any indications or suggestions that examination security

2. PostExamination To the best of my knowt9Øgq I did not divulge to any unauthorized persons any information concerning during the week(s) of ((j(. From the date the NRC licensing examinations administered that I entered into this security agreement until the instruct, evaluate, or provide performance feedback completion of examination administration, I did not to those applicants who were administered these licensi below and authorized by the NRC. ng examinations, except as specifically noted PRINTED NAME JOB TITLE 1 RESPONSIBILITY GNATURE (1) DATE IGNATURE (2) DATE NOTE 1.14JA7.4LIKLqIr AIc.cps)LJcT..ø:4/. $jn/(,

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HL-17 NRC ES-201 Examination Security Agreement Form ES-201-3 I Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of Yk.f/i- as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provid e performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination admin istration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is accept 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 requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. PostExaminatign To the best of my knowledge, I did not divulge to any unauthorized person any s information concerning the NRC licensing examinations administered during the week(s) of ,674( (2,. From the date that I entered into this securit y agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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HL-17 NRC ES-201 - Examination Security Agreement Form ES-2013 I Pre-Examinaon 1 acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 965/i?...

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

2. PostExamination

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

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HL-17 NRC ES-201 Examination Security Agreement Form ES-2O13 I. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing -

examinations scheduled for the week(s) of 4 ft ) as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who NRC chief examiner. I understand that I am not to instruct, evaluate, or provide have not been authorized by the performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administratio n, except as specifically noted below and authorized by the NRC (e.g. acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowlege I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of /7/Co4i. From the date that I entered into this security agreement until the completion of examination administratio instruct, evaluate, or provide performance feedback to those applicants who were n, I did not administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201,Page27of28

HL-17 NRC ES-201 Examination Security Agreement Form ES-201-3 I . Pre-Examination

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

2. Post-Examination To the best of my knowlçdg9, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of t7Ro1t1v. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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NRC ES-201 Examination Security Aeme nt I .

PreExarnjnation 2 Form ES2O1-3 I acknowledge that I have acquired specialized knowledge about the of my signature. I agree that I will NRC licensing examinations schedule not knowingly divulge any informati d for the week(s) of NRC chief examiner. I understan on about these examinations to any *//. as of the date d that I am not to instruct, evaluate, persons who have not been authorize these licensing examinations from or provide performance feedback to d by the this date until completion of examinati those applicants scheduled to be adm (e.g. acting as a simulator boot on administration, except as specifica inistered h operator or communicator is acc lly noted below and authorized feedback). Furthermore, I am awar eptable if the individual does not sele by the NRC e of the physical security measure ct the training content or provide direc understand that violation of the cond s and requirements (as documented t or indirect in the facility licensees procedures) the facility licensee, I will immediat itions of this agreement may resul t in cancellation of the examinations and ely report to facility managemen and/or an enforcement action again may have been compromised. t or the NRC chief examiner any indication st me or s or suggestions that examination security

2. PstExaminatjpn To the best of my knowlçdgç, I did not divulge to any unauthorized per during the week(s) of 7.[C(t2-. sons any information concerning the NRC From the date that I entered into this licensing examinations administered instruct, evaluate, or provide perfo security agreement until the completi on of examination administration, below and authorized by the NRC rmance feedback to those applicants who were administered these licensing exam I did not

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HL-17 NRC ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 4i4i as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administratio n, except as specifically noted below and authorized by the NRC (e.g. acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowle,ge I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of g/,Lo//1_ From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

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EYfO 7b QéAr7>V 41ZQ 4 Yj ES-201, Page 27 of 28 ynqd

HL-17 NRC ES-201 Examination Security Apement Form ES 2014

1. Pre-Exarninatlon I acknowledge that I have acquired specialized knowledge about the NRC licensing of my signature. I agree that I will not knowingly divulge any information about examinations scheduled for the week(s) of

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

2. pst-Examination To the best of my knowie,rige 1 I did not divulge to any unauthorized persons any information concerning the during the week(s) of f((fi From the date that I entered into this security NRC licensing examinations administered agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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v J, ES2O1 Page 27 of 28

HL-17 NRC ES-201 Examination Security Agreement Form ES-201-3 t Pre-Examination 31(.t2/(Z I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g. acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowle,dge I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 1ffof1.. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

/ / 1 C)

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NOTES:

tr 4 rtzfl;#A/9 6;Aa ES-201, Page 27 of 28

HL-17 NRC ES-201 Examination Security Agreement Form ES-2013 I . Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 49 I I as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administratio n, except as specifically noted below and authorized by the NRC (e.g. acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

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

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE2DATE NOTE

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ES-201, Page 27 of 28

00 vi vi 00 00 vi U)

ES1 Examination Security mt -

I L.EpatIQn I acknowledge that I have acquire vi d specialized knowledge about of my signature. I agree that I will the NRC licensing examinations schedu not led OZ NRC chiefexaminer. I understand knowngIy divulge any information about these examinations to any perfor the week(s) of as ofthe date that I am not to inst nict 1evaluat sons wt have not been auth#oriz vi these licensing examinations from 2

this date umil completion of exa e or provide performance Teedbath to those applicants sdieduted to be admed by the (eg) acting as a s1mu1at boo th operator or communicator is acc mination admstraon except as spedficØy noted below and authoriz inistered feedback). 1 eptable If the individimI does it sele ed by the NRC Furthermore 1 am aware of the physical security measures and req ct the training content or provide direct or Indirec understand that violation of the con ufrements (as documented in the faclM t ty licensees proced 2 2

the facility licensee. I will immedia ditions of this agreement may result In cancellation of the examm C) tely report to facility managemen ations andlor an enforcement action ures) and may have been compromised t or the NRC chief examiner any Ind aga ications or suggestions that examin inst me or ation security 2 Pspljatiop To the best of my knowlelge, 1 did during the week(s) of fl(,ff not divulge to any unauthorized persons any Information con cerning the NRC licensing examin instruct, evaluate, or provide . From the date that I entered into this security agreement unt atio performance feedback to those il the completion of examination adm ns administered below and auth orized by the NRC. applicants who wer e administered these licensing examin inistration, I did not ations, except as specifically noted PRINTED NAME JOB TITLE! RESPONSIBILIT Y SI RE (1) DATE IGNATURE (2) DATE NOTE aJ  : -

Zi 3._____ --

z j-zj r:z?-

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7._____

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NOTES:

yo5 ES-201, P 27 of 28

HL-17 NRC ES2O1 Examination Security Agreement Form ES-201-3 1 Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 1//$%iZ as of the date of my signature. I agree that 1 will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable f the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowl9g I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of ff(1. From the date that I entered into this security agreement until the completion of examination administratio I did not n,

instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILITY GNATURE (I) DATE IGNATURE (2) DATE NOTE 1 C 4 W/MK I 1. Op s Jth;4(dLZ nnt Jh 4 A;F;;i L2z

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U U ES-201, Page 27 of 28

0 HL-17 NRC ES-201 Exammation Secjy Agreement Form ES2O13

1. PreExamination I acknowledge that I have acquired specia1zed know edge about the NRC licensing examinations scheduled for .i ,

of my signature. I agree that I will not knowingly divulg the week(s) of j[r as of the date e any information about these examinations to any person NRC chief examiner. I understand that I am not to instruc s who have not been authorized by the t, evaluate, or provide performance feedback to those applica these licensing examinations from this date until compl nts scheduled to be administered etion of examination administration, except as specifically (e.g., acting as a simulator booth operator or communicator noted below and authorized by the NRC is acceptable If the individual does not select the training conten feedback). Furthermore, I am aware of the physic al security measures and requirements (as documented in the t or provide direct or Indirect understand that violation of the condilions of this agreem facility licensees procedures) and ent may result in cancellation of the examinations and/or the facility licensee. I will immediately report to facility an enforcement action against me or management or the NRC chief examiner any indications or sugges may have been compromised. tions that examination security

2. Pst-Exajnlnatiq To the best of my knowiecge,,I did not divulge to any unauthorized persons any informatin concerning the NRC licensi during the week(s) of From the date that I entered into this security agreement until the ng examinations administered instruct, evaluate, or provide performance feedback to those compleon of examination administration I did not applicants who were administered these licensing examinations, except below and authorized by the NRC. as specifically noted PRINTED NAME JOB TITLE I RESPONSIB1LITY SIGNATURE(1) DATE SIGNATURE (2) DATE NOTE cN$a1 --

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H17 NRC ES-201 Form ES-201-3 1.

I acknowedge that f have acquired specialized knowledge about the NRC censing examtriatlons scheduled for the week(s) of jáZ. as ofthe date of my signature. I agree that I wIt not knowingly divulge any information about these examinations to any persons who have not been authonzed by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those app$icants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specfica1Iy noted below and authorized by the NRC (cg. acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or Indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result In cancellatkn of the examinations andlor an enforcement action against me or the facility licensee. I will immediately report to facihty management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Pjsanaj[on To the best of my know1çdg, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of tJ!i. From the date that I entered to this security agreement until the completion of examination administration, I dId oat Instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB T1TLE I RESPONSIBILITY j U

T RE DATE DATE NO1E

/ Sj4ATURE (2)

1. 0 JP iL_________

j.,o__)- t wL;?. q;4a..

z  : 7zL

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v 63;os;?2 ?O £6t17N (34 ES-201 Page 27 of 28

HL-17 NRC

_1__ xamnacnSItAement Farm2O14 1 .

I acknowIede that I hiv acquired ec1a1zed know1ed ahut the NRCItcnsin examTnation ccbedu1d for thc weeks)oLl/!t(T_ ofthe date ofrny sTgnitwe. 1 agree that lw!fl not knowngIy cITvlJ1e any information aboutthese examtnatioris to any per&ns who have notbeen authoi1zdtq the NRC chr examar. t widerstnd that) m riot tc Insrvct, evaluate, orprovde pormnc feedback to those apparits scheduled to be administered these Uceristn exarninatinns fr QiLs date uni1 competiort cfexwtdnation adm!sraUori exceptas spec4icarly noted beow and auiodaad bythe NRC (e,g.t acllng as a simulator booth uperator or communca1or is icceptebIe if the indMdual does not select the training contantor pMde dliectortadlrect eex3back). Furthermoro 1 lam aware cf the physical secuilty measures and requirements (as documented in the facility 1knss procadures) and undnrstand that Ao!atlori oTeconditlons ofthls agroementmayrasuftln canceaVon ofthe exemTnadcns 2nWoran e!1forcementaon agalnsfme or the facUty licensee. I Vw1t ImmediateTy rcporttofacilfty managemcntorthe NRC cfilefexarntnerany ndicaffons orsuggesons thatexaminaffon security may have been compromised.

a PomInatJj 1

To the bestofniy knov4 de,IdJd not din.dge to any unauthonzed persons any InformsUon concerning the NRC licensing exarnInation5 administered during theweek(s) is4tZ Prom the date that entered 1n this secwiy agreement until the completion ofexamlnetlon administration, I cRd flat lnstruct evaluate. orpwvlde performance feedback to those applicants who were administered these licensing examinations, except as pectffcaliy noted -

belowand authodzed by the NRC PRINTED NAME JOB TITLEI RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE(2) DATE NOTE 1:4744f JM a

3. __,ca L4Y 4_ 1L.PiA -

15.

NOTES

& 6?5SEO y 1y.

ES-201, Page 27 of 28

ES-301 Administrative Topics Outline Form ES-301-1 Facility: VogtIe 1 & 2 Date of Examination: 4/20/12 Examination Level: RO 1 SRO Operating Test Number:

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

R P V-NRC-JP-14915-HL17 ConductofOperations .

Perform AFD Monitoring

Description:

With data provided, candidate will perform 14915 Data sheet 6 for AFD monitoring.

G2.1 .37 (4.3 / 4.6)

V-NRC-JP-1 4005-HL1 7 Conduct of Operations R, D . .

Calculate Shutdown Margin-Keff Determination for Shutdown Bank Withdrawal

Description:

Reactor Startup in progress. Candidate will determine Keff for Shutdown Bank withdrawal.

G2.1.25 (3.9/4.2)

V-NRC-JP-NMP-AD-003-HL1 7 Equipment Control A, N . .

Determine Tagging Requirements

Description:

Candidate will determine appropriate fluid boundary points and their associated positions required for the Tagout of Containment Spray Pump 1A.

G2.2.13(4.1 /4.3)

V-NRC-JP-00930-HL1 7 Radiation Control R, D Proper RWP Implementation

Description:

Candidate will determine proper protective clothing requirements, projected dose and whether the RWP is appropriate for the job task.

G2.3.7 (3.5 / 3.6)

N/A Emergency Procedures/Plan N/A 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)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Vogtle 1 & 2 Date of Examination: 4/20/12 Examination Level: RO SRO SROU Operating Test Number: 201 2-301_

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

R P V-NRC-JP-14915-HL17 Conduct of Operations Evaluate Inoperable AFD Monitor Alarm

Description:

With data provided, candidate will select 14915 Data sheet 6 for AFD monitoring, evaluate data and take appropriate actions.

G2.1 .37 (4.3 I 4.6)

V-NRC-JP-1 4005-HL1 7 Conduct of Operations R, D . .

Calculate Shutdown Margin-Keff Determ nation for Shutdown Bank Withdrawal

Description:

Reactor Startup in progress. Candidate will determine Keff for Shutdown Bank withdrawal.

G2.1.25 (3.9/4.2)

V-NRC-JP-NMP-AD-003-HL1 7 Equipment Control R, N . .

Determine Tagging Requirements

Description:

Candidate will determine appropriate fluid boundary points and their associated positions required for the Tagout of Containment Spray Pump 1A. The candidate must also determine any Tech Spec required actions to allow this system to be tagged.

G2.2.13(4.1 /4.3)

V-NRC-JP-00930-HL1 7 Ald )7 I

Radiation Control O?//,

R, , Proper RWP Implementation

.iO/

1 AR I iziiIL fTil

Description:

Candidate will determine proper protective clothing er I

j-1ar requirements, projected dose and whether the RWP is appropriate for the job task.

G2.3.7 (3.5 / 3.6)

V-NRC-JP-NMP-EP-1 1 0-HL1 7 Emergency Procedures/Plan R, M . . . . .

Classification Determination and EN Form Completion

Description:

The candidate will classify the given emergency and complete the EN Form.

G2.4.41 (4.6)

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 & AC retakes)

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: VoQtle 1 & 2 Date of Examination: 4/20/12 Examination Level: RO SRO E SROU 1 Operating Test Number: 2012-301_

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

R P V-NRC-JP-14915-HL17 Conduct of Operations Evaluate Inoperable AFD Monitor Alarm

Description:

With data provided, candidate will select 14915 Data sheet 6 for AFD monitoring, evaluate data and take appropriate actions.

G2.1 .7 (4.4 I 4.7)

V-NRC-JP-1 4005-HL1 7 Conduct of Operations A, D . .

Calculate Shutdown Margin-Keff Determ nation for Shutdown Bank Withdrawal

Description:

Reactor Startup in progress. Candidate will determine Keff for Shutdown Bank withdrawal.

G2.1 .25 (3.9 I 4.2)

V-NRC-JP-NMP-AD-003-H Li 7 Equipment Control R, N . .

Determine Tagging Requirements

Description:

Candidate will determine appropriate fluid boundary points and their associated positions required for the Tagout of Containment Spray Pump 1A. The candidate must also determine any Tech Spec required actions to allow this system to be tagged.

G2.2.i3(4.i /4.3)

V-NRC-JP-00930-HL17 Radiation Control R, D Proper RWP Implementation

Description:

Candidate will determine proper protective clothing requirements, projected dose and whether the RWP is appropriate for the job task.

G2.3.7 (3.5 / 3.6)

V-NRC-JP-NMP-EP-i i0-HL17 Emergency Procedures/Plan R, M . . . . .

Classification Determination and EN Form Completion

Description:

The candidate will classify the given emergency and complete the EN Form.

G2.4.44 (4.4)

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)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Vogtle 1 & 2 Date of Examination: 4/2OI12 Exam Level: AC SAC-I E SAC-U Operating Test No.:

Control Aoom Systems@ (8 for AC); (7 for SAC-I); (2 or 3 for SAC-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. V-NAC-JP-14410-HL17 Perform Control Aod Operability Test-Alt A, M, S path (Two rods drop requiring a manual Aeactor Trip).

Description:

Candidate performs control rod operability test for Control bank A. This JPM is modified to drop two rods in a staggered sequence on CBA when CBB test is started. This will require a manual reactor trip per 1 8003-C, Aod Control System Malfunction.

001A2.17 (3.3 I 3.8)

(RO/SROI)

Alternate a. V-NAC-JP-13009-HL17 Perform a Manual Makeup To A,M,S VCT( Alt-loss off boric acid flow)

Description:

Candidate performs a manual makeup to VCT. This JPM is modified to simulate a blown control power fuse stops the running boric acid transfer pump requiring stopping the makeup.

004A4.12 (3.8 I 3.3)

(AC I SACI)

b. V-NRC-JP-19013-HL17 Transfer ECCS Pumps To Cold Leg A, D, EN, L, S 2 Aecirc (Cold Leg Aecirc path not available)

Description:

Equipment failures will prevent cold leg recirculation. Candidate is required to identify a loss of emergency coolant recirculation.

006A4.05 (3.9 I 3.8)

(AO/SAOl/SRCU)

c. V-NAC-JP-19030-HL17 Depressurize ACS To Aeduce Break ID A P L S Flow to Auptured SG (Normal Pressurizer Spray Not available and 1st POAV Block Valve fails to open)

Description:

A SGTR has occurred. The candidate task is to Depressurize the ACS beginning with 1 9030-C step 34, until one termination criterion is met. Normal spray controllers will not function. Candidate should use a PORV with complications.

038EA1 .04 (4.3 I 4.1)

(AC I SACI I SACU)

d. V-NRC-JP-13003-HL17 Start a RCP with a Seal Failure A, D, L, S 4P

Description:

Plant is in Mode 3 at 557°F, 2235 psig with three RCPs running. The candidate must start RCP 2 per SOP 13003-1 On start, the #1 seal fails requiring pump shutdown.

003A2.02 (3.7 I 3.9)

(RO I SROI)

Alternate d. V-NRC-JP-1 301 1 -HL-1 7 Place an RHR Train In Service D,L,S 4P for RCS Cooldown

Description:

The candidate must place a train of RHR in service for RCS cooldown per SOP 1 301 1 -1.

005A4.01 (3.6 I 3.4)

(RO/SROI)

e. V-NRC-JP-13610-HL17 Transfer AFW Suction Source to CST 2 D, EN, L, S 45

Description:

The candidate must transfer the AFW suction source to CST 2 with AFW in service per SOP 13610-1.

061 G2. 1 .23 (4.3 I 4.4)

(RO I SROI)

f. V-NRC-JP-13130-HL17 Dilute ContainmentWith Service Air D, L, P, S 5

Description:

The candidate will be required to use SOP 131 30-1 section 4.4.2 to align service air to containment to dilute hydrogen.

028A4.01 (4.0 I 4.0)

(RO/SROI)

g. V-NRC-JP-13427-HL17 Returning ESF Bus from Diesel M, S 6 Generator to Normal Supply

Description:

The candidate will parallel RAT 1 B to DG1 B in preparation for DG1 B shutdown.

062A4.07 (3.1 I 3.1)

(RO I SROI)

h. V-NRC-JP-13301-HL17 Manually Actuate CR1 Due to Smoke M, S RO ONLY

Description:

A brush fire on site is causing smoke to enter the 8 control room air intakes. The candidate must perform a Control Room Isolation.

067AA1 .05 (3.0 / 3.1)

(RO)

Alternate V-NRC-JP-18001-HL17 Place Steam Pressure Bistables in C, D 7 the Tripped Condition

==

Description:==

Steam Pressure Channel 2P1-524 has failed and the associated Bistables and Master Test switch will be placed in Test.

012A4.04 (3.3 I 3.3)

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

i. V-NRC-JP-18019-HL17 Establish RWST Gravity Drain Through D, E, L, R, P 4P RHR Pumps to RCS Hot Legs (Cold Legs Not Available)

Description:

During a loss of RHR at midloop level, establish gravity drain to the hot legs per 1 801 9-C Attachment A section C.

025G2.1 .20 (4.6 I 4.6)

(RO I SROI I SROU)

j. V-NRC-JP-1 8038-HL1 7 Establish Local Control of 1 E A, L, N, E 8 Switchgears

Description:

The candidate musttake local control of the 4160 V switchgear breakers and verify an ACCW pump in service per 1 8038-2. ACCW will not be in service and RCP shutdown and letdown isolation must be performed.

068AA1 .21 (3.9 I 4.1)

(RO/SROI/SROU)

k. V-NRC-JP-13405-HL-17 Energize RHR Inverter 1DD1I6 D, E, L, M 6

Description:

With Unit 1 cooling down to Cold Shutdown, the RHR Loop Suction Valve 1-HV-8702A will be energized using Inverter 1 DD1 16.

063G2.1 .30 (4.4 I 4.0)

(RO/SROI/SROU)

@ 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 I SRO-l I SRQ-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irectfrom bank 9/814 (E)mergency or abnormal in-plant 1 I 1 1 1 (EN)gineered safety feature - I - I 1 (control room system)

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

(R)CA 1I:1/1 (S)imulator

ES-301-3 Operating Test Quality Checklist Facility: Vogtle 1 & 2 Date of Examination: 3/26/12, 4/9/12, 4/16/12 Operating Test Number: 201 2-301 Initials

1. General Criteria

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).

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 audittest(s). (see Section D.1 a.)

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

&oz

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:

y_ initial conditions y_ initiating cues

.7 references and tools, including associated procedures 4 J_/_

reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee JJ 7

7 operationally important specific performance criteria that include:

/ detailed expected actions with exact criteria and nomenclature

-.?. system response and other examiner cues v statements describing important observations to be made by the applicant

- criteria for successful completion of the task sé identification of critical steps and their associated performance standards 4__ 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 testto deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified 47 on those forms and Form ES-201-2.

3. Simulator Criteria -- --

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

Printed Name I Signature Date

a. Author Thad N. Thompson I Ernest M. 12

b. Facility Reviewer(*) Greg C. Wainwriaht I /

c. NRC Chief Examiner (#) fCA646/_

11 f i#/V d.

NOTE:

NRC Supervisor A4Q W/DA1-M1Ai

/

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

j o4q

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

ES-301 Simulator Scenario Quality Checklist Form ES-3014 Facilty: Vogtle 1 & 2 Date of Exam: 3/26/12, 4/9/12, 4/16/12 Scenario Numbers: 1 I 2 I 3 Operating Test No.: 2012-301 QUALITATIVE ATTRIBUTES Irutials a b* c#

-t(

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.

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)

. the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g. pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. 4

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 I I complete evaluation results commensurate with the scenario objectives. /7/

7. If time compression techniques are used, the scenario summary clearly so indicates. .

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

Cues are given.

8. The simulator modeling is not altered. j Y

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 0. 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 .

d 11 . All individual operator competencies can be evaluated, as verified using Form ES-301-6 f?

(submit the form along with the simulator scenarios). ..

a,

12. Each applicant will be significantly involved in the minimum number oftransients and events specified on Form ES-301 -5 (submit the form with the simulator scenarios). b D

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

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

1 . Total malfunctions (58) 8 / 10 / 8

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

3. Abnormal events (24) 4 / 5 / 4

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

5. EOPs entered/requiring substantive actions (12) 1 / 1 / 1

6. EOP contingencies requiring substantive actions (02) 0 / 0 / 0

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

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Vogtle 1 & 2 Date of Exam: 3/26/12, 4/9/1 2, 4/16/12 Scenario Numbers: 4/5 /6 Operating Test No.: 201 2-301 QUALITATIVE ATTRIBUTES Inftials a b* c#

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

2. The scenarios consist mostly of related events. j

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)

. the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g. pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. 1

5. The events are valid with regard to physics and thermodynamics. 3

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.

Cuesaregiven. 4,

8. The simulator modeling is not altered.

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 f) j to ensure that functional fidelity is maintained while running the planned scenarios. 5W 1 0. 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 .

4 11 . All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number oftransients and events specified on Form ES-301-5 (submit the form with the simulator scenarios). r

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

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

1 . Total malfunctions (58) 9 / 10 / 9

2. Malfunctions after EOP entry (12) 3 / 3 / 4

3. Abnormal events (24) 5 / 5 / 5

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

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

6. EOP contingencies requiring substantive actions (02) 1 / 0 / 1 r(

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

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Faciltv: Voqtle 1 & 2 Date of Exam: 3/26/12, 4/9/12. 4/16/12 Scenario Numbers: 7 / / Ooerating Test No.: 2012-301 QUALITATIVE ATTRIBUTES Irutials a b* c#

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

2.

3.

The scenarios consist mostly of related events.

Each event description consists of 4

. 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)

. the event termination point (if applicable) c.

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. .

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. 1

7. If time compression techniques are used, the scenario summary clearly so indicates.

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

Cues are given.

8. The simulator modeling is not altered.

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 0. Every operator will be evaluated using at least one new or significantly modified scenario.

All other scenarios have been altered in accordance with Section D.5 of ES-301 .

11 . All individual operator competencies can be evaluated, as verified using Form ES-301 -6 (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number oftransients and events specified on Form ES-301-5 (submitthe form with the simulator scenarios). (1

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

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

1 . Total malfunctions (58) 9 / / 4f

2. Malfunctions after EOP entry (12) 3 / /

3. Abnormal events (24) 4 / /

4. Major transients (12) 1 / /

5. EOPs entered/requiring substantive actions (12) 4 / /

6. EOP contingencies requiring substantive actions (02) 0 / /

7. Critical tasks (23) 3 / /

ES-301 Transient and Event Checklist Form ES-301 -5 Facility: Vogtle 1 and 2 Date of Exam: 3-26, 4-9, 4-16, 4-30 Operating Test No.: 201 2-301 A E Scenarios P V 2 3 4 T M P E 0 I L N CREW CREW CREW CREW T N I T POSITION POSfl1ON POSITION POSfl1ON A I

C S A B S A B S A B S A B L j A T R T 0 R T 0 R T 0 R T 0 M*

N Y 0 C P 0 C P 0 C P 0 C P RU T P E

NOR

£ZEEZ_

171 I/C 2,4,5, 1 3,4, i 2,4, i 2,3, 26 4 4 2 Il_I 6,9, 5,8,9 5,8,9 4,5,6, SRO-U 10,11 7 MAJ 7,8 7 7 8 5 221 E

TS 2,3,6, 1,2,4, 1,4,6 1,3,5 14 0 2 2 7 5 RO RX 1 2 6 3 110 E NOR 6 32111 SRO-l I/C 2,6,9, 1,5, 2,4,9 1,3,4, 13 4 4 2 E

SRO-U MAJ 7,8 7 7 8 5 2 2 1 D TS RO RX 0 110 NOR 12 SROI I/C 45 349 158 257 12 4 4 2 E 11 SRO-U MAJ 7,8 7 7 i: S 8B 5 2 2 1 D TS 4 \

0 0 2 2 Instructions:

1 . Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs 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 additionallyserves 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: Date of Exam: Operating Test No.:

A E Scenarios P V 7 T M 6

P E 0 I L N CREW CREW CREW CREW T N I T POSfl1ON A I

C S A B S A B S A B S A B L j A T R T 0 R T 0 R T 0 R T 0 M*

N Y 0 C P 0 C P 0 C P 0 C P RU T P E

I:

SROI NOR :::z:::

P0 RX 2 6 1 3 110 171 lU I/C 1 ,3,4, 1 2,4, 2,3,5, [ 23 4 4 2 6,8,9, 5,8,9, 6,7, SRO-U 10,11 10 11 55S MAJ 9 7 8,9 4 221 TS 4,5,6 2,3,4 4,5,6 9 0 2 2 RO RX 2 6 1 3 110 E NOR SROI I/C 18 24 357 9 4 4 2 E

SRO-U MAJ 9 7 8,9  :. 4 2 2 1 D

RO TS S RX 0 110

!:io59 Instructions:

F

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-301-6 Competencies Checklist Facility: Vogtle 1 & 2 Date of Examination: 3-26, 4-9, 4-16, 4-30 Operating Test No.: 2012-301 APPLICANTS Competencies RO SRO-I X SRO-U__X SCENARIO______ SCENARIO 1 2 3 4 1 2 3 4 Interpret/Diagnose 2, 4, 5, 1, 2, 3, 1, 2, 3, 1, 2, 3, 4, 5, 2, 4, 5, 1, 2, 3, 1, 2, 3, 4, 1,2,3,4,5,

.. 678 456 456 678 678 456 5678 678 Events and Conditions

, 7, 8, 9 7, 8, 9 9, 10, 7, 8, 9 9 11 11 Comply With and 1, 2, 4, 1, 2, 3, 1, 2, 3, 1, 2, 3, 4, 5, 1, 2, 3, 1, 2, 3, 1, 2, 3, 4, 1,2,3,4,5, 567 456 456 678 456 456 5678 678 Use Procedures (1) 8,9, 7,8,9 7 8 9 7 8 9 7 8 9 9 10, 11 10, 11 1 , 2, 4, 1 , 2, 3, 1 , 2, 3, 1 , 2, 3, 4, 5, r:: j Operate Control r 5, 6, 7, 4, 5, 6, 4, 5, 6, 6, 7, 8 Doarus k) i-i 8, 9, 7, 8, 9 7, 8, 9 bI 10,11 Communicate 1,2,3, 1,2,3, 1,2,3, 1,2,3,4,5, 1,2,3, 1,2,3, 1,2,3,4, 1,2,3,4,5,

.J I 4 4, 5, 6, 4, 5, 6, 4, 5, 6, 6, 7, 8 4, 5, 6, 4, 5, 6, 5, 6, 7, 8, 6, 7, 8 anu InLeract 7, 8, 9, 7, 8, 9 7, 8, 9 7, 8, 9, 7, 8, 9 9 10, 11 10, 11 Demonstrate 4 I 1 2 3 1 2 3 1 2 3 4 67 8 1 2 3 4 5 6 7 8 Supervisory Ability (3) j Comply With and 1 2 4 1 4 6 1 3 5 Use Tech. Specs. (3) [:..

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301 6 Competencies Checklist Facility: Vogtle 1 & 2 Date of Examination: 3-26, 4-9, 4-1 6, 4-30 Operating Test No.: 2012-301 APPLICANTS Competencies RO SRO-l X SRO-U__X SCENARIO______ SCENARIO 5 6 7 5 6 7 Interpret/Diagnose 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 4,

.. 456 456 456 456 456 5678 Events and ConditIons 7 8, , 7, 8, 9, 7, 8, 9, 7, 8, 9, 7, 8, 9, 9, 10, 11, 10, 11, 10, 11 10, 11, 10, 11, 10, 11 12 12 12 12 Comply With and 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 4, 456 456 456 456 456 5678 Use Procedures (1) , 8, 9, 7, 8, 9, 7, 8, 9, 7, 8, 9, 7, 8, 9, 9, 10, 11, 10, 11, 10, 11 10, 11, 10, 11, 10, 11 12 12 12 12 Operate Control 1 2, 3,

, 1 2, 3,

, 1 2, 3, 456 456 456 Boards (2) 7, 8, 9, 7, 8, 9, 7, 8, 9, 10, 11, 10, 11 10, 11, 12 12 f . .

Communicate 1,2,3, 1,2,3, 1,2,3, 1,2,3, 1,2,3, 1,2,3,4, 456 456 456 4,56 456 5678 and Interact 7,8,9, 7,8,9, 7,8,9, 7,8,9, 7,8,9, 9,10,11, 10,11, 10,11 10,11, 10,11, 10,11 12 Demonstrate 1,2,3, 1,2,3, 1,2,3,4, Supervisory Ability (3)

ComplyWith and 4 5 6 2 3 4 456

[

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 appilcants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-401 PWR Examination Outline Form ES-401-2 Facility: VOGLE Date of Exam: MARCH 2012 ROK/ACaqojyPcnts SAC-Only_Points Tier Group KKKKKKAAAAG A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total 1 . 1 i 1. 1. 18 3 3 6 Emergency &

Abnormal 2 N/A 2 2 N/A 9 2 2 4 Plant Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 1 3 2 3 3 3 3 2 3 2 2 2 28 3 2 5 2.

Plant 2 L_L L2+/- L.L L+/- 10 0 2 1 3 Sys ems Tier Totals 4 3 4 4 4 3 3 4 3 3 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 Li 2 3 4 7 Categories I 2 3 3 2 [1 2 2 2 Note: 1 . Ensure that at least two topics from every applicable KJA 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 K/A 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. Systems/evolutions 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/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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, selecttopics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 1 0 CFR 55.43.

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 007EG2.4.2 - -

Reactor Trip Stabilization Recovery 4.5 4.6 Knowledge of system set points, interlocks and automatic LI LI LI LI LI LI D LI LI LI i actions associated with EOP entry conditions.

/1 008AK3.04 Pressurizer Vapor Space Accident I 3 4.2 4.6 LI LI El LI LI D LI LI LI El RCPtrippingrequWements 015AK2.1O RCP Malfunctions/4 2.8 2.8 LI LI LI LI D D LI LI LI El RCP indicators and controls 022AG2.2.42 Loss of Rx Coolant Makeup I 2 3.9 4.6 LI LI LI LI LI LI LI LI LI LI Ability to recognize system parameters that are entry-level conditions for Technical Specifications 025AK2.03 Loss of RHR System /4 2.7 2.7 LI LI LI LI LI LI [] [] [ [] Service water or closed cooling water pumps 026AA1 .03 Loss of Component Cooling Water /8 3.6 3.6 LI LI LI SWSasabackuptotheCCWS 029EK1.01 ATWS/ 1 2.8 3.1 1 LI LI LI LI LI LI LI LI [] [] Reactor nucleonics and thermo-hydraulics behavior O4OAA1 .20 -

Steam Line Rupture Excessive Heat 4.1 4.2 Containment pressure and temperature trends Transfer / 4 LI LI LI J 054AA2.02 Loss of Main Feedwater /4 4.1 LI LI LI LI LI LI LI LI LI [] Differentiation between loss of all MFW and trip of one MFW pump 055EA2.02 Station Blackout /6 4.4 4.6 LI LI LI LI LI LI LI [i LI LI LI RCS core cooling through natural circulation cooling to S/G cooling 056AK1 .03 Loss of Off-site Power /6 3.1 3.4 LI LI LI LI LI LI LI LI LI LI Definition of subcooling: use of steam tables to determine it Page 1 of 2 2/22/2013 12:30PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 058AK3.O1 Loss of DC Power I 6 3.4 3.7 j j j Use of dc control power by DIGs 062AA2.03 Loss of Nuclear Svc Water I 4 2.6 2.9 j j j j j J The valve lineups necessary to restarttheSWS while bypassing the portion of the system causing the abnormal condition 065AK3.04 Loss of Instrument Air I 8 3 3.2 j j j j Cross-over to backup air suppes 077AK1 .02 Generator Voltage and Electric Grid 3.3 3.4 Over-excitation Disturbances I 6 WEO4EA1 .3 LOCA Outside Containment /3 3.8 4.0 j J Desired operating results during abnormal and emergency situations.

WEO5EK2.l -

Inadequate Heat Transfer Loss of 3.7 3.9 Components and functions of control and safety systems, Secondary Heat Sink / 4 including instrumentation, signals, interlocks, failure modes and automatic and manual features.

well EG2.4.6 Loss of Emergency Coolant Recirc. /4 3.7 4.7 El El El El El El El El El Knowledge symptom based EOP mitigation strategies.

Page 2 of 2 2/22/2013 12:30PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO1AA1 .02 Continuous Rod Withdrawal I 1 3.6 3.4 j J j j J j Rod in-out-hold switch 036AK3.03 Fuel Handling Accident I 8 3.7 4.1 j J j j Guidance contained in EOP for fuel handling incident 037AK1 .02 Steam Generator Tube Leak I 3 3.5 3.9 j j j Leak rate vs. pressure drop 051AA2.02 Loss of Condenser Vacuum I 4 3.9 4.1 j j J j Conditions requiring reactor and/or turbine trip 068AA2. 1 0 Control Room Evac. / 8 4.2 4.4 j j j j Source range count rate 074EA1 .25 mad. Core Cooling / 4 3.8 3.8 j ] j Atmospheric dump valve controllers and indicators WEO3EK2.1 LOCA Cooldown - Depress. / 4 3.6 4.0 j j Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEO8EK3.4 -

RCS Overcooling PTS /4 3.4 3.7 RO or SRO function within the control room team as El appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

wel5EG2.l .32 Containment Flooding / 5 3.8 4.0 El El El El El El El El El El Ability to explain and apply all system limits and precautions.

Page 1 of 1 2/22/2013 12:30PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K2.02 Reactor Coolant Pump 2.5 2.6 j j j J j j CCW pumps 004A2.21 Chemical and Volume Control 2.7 2.7 J J J J J J Excessive letdown flow, pressure and temperatures on ion exchange resins (also causes) 004K3.06 Chemical and Volume Control 3.4 3.6 J J J RCS temperature and pressure 005A1 .03 Residual Heat Removal 2.5 2.6 j j Closed coolingwater flow rate and temperature 006G2.2.4 Emergency Core Cooling 3.6 3.6 j j (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

007A2.06 Pressurizer Relief/Quench Tank 2.6 2.8 j j j j j J j Bubble formation in PZR 008A3.08 Component Cooling Water 3.6 3.7 j j Automatic actions associated with the CCWS that occur as a result of a safety injection signal 010K5.02 Pressurizer Pressure Control 2.6 3.0 j j Constant enthalpy expansion through a valve 010K6.03 Pressurizer Pressure Control 3.2 3.6 j ] j j Ej J j PZR sprays and heaters 01 2K1 .06 Reactor Protection 3.1 3.1 LI LI LI LI LI LI LI LI LI LI T/G 0121<4.09 Reactor Protection 2.8 3.1 LILILILILILILILILILI Separation of control and protection circuits Page 1 of 3 2/2212013 12:30PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 013A4.Ol Engineered Safety Features Actuation 4.5 4.8 j j j ESFAS-initiated equipment which fails to actuate 022A4.Ol Containment Cooling 3.6 3.6 j J CCS fans 026A1 .06 Containment Spray 2.7 3.0 j j j Containment spray pump cooling 039G2.l .25 Main and Reheat Steam 3.9 4.2 j j Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

039K5.08 Main and Reheat Steam 3.6 3.6 j j j Effect of steam removal on reactivity 059K4.08 Main Feedwater 2.5 2.7 j j j Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch) 061A3.04 Auxiliary/Emergency Feedwater 4.1 4.2 Automatic AFW isolation 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 J J Pumps 062A2.l 1 AC Ecffical Distribution 3.7 4.1 Ej j El El El El Aligning standby equipment with correct emergency power source (DIG) 062K2.01 AC Electrical Distribution 3.3 3.4 El El El El El El El El El El Major system loads 063K3.01 DC Electrical Distribution 3.7 4.1 El El El El El El El El El El ED/G Page 2 of 3 212212013 12:31 PM

0 ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 063K4.04 DC Electrical Distribution 2.6 2.9 LI LI LI LI LI LI LI LI Trips 064K6.07 Emergency Diesel Generator 2.7 2.9 j J Air receivers 073K5.03 Process Radiation Monitoring 2.9 3.4 j J j Relationship between radiation intensity and exposure limits 076K1 .09 Service Water 3.0 3.1 LI LI LI LI LI LI LI LI LI LI Reactor building closed cooling water 078K3.01 Instrument Air 3.1 3.4 LI LI LI LI LI LI LI LI LI LI Containment air system 103K1 .08 Containment 3.6 3.8 LI LI LI LI LI LI LI LI LI LI SIS, including action of safety injection reset Page 3 of 3 2/22/2013 12:31 PM

ES-401 , REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001A3.06 Control Rod Drive 3.9 3.9 j j RCS temperature and pressure 01 1 K2.O1 Pressurizer Level Control 3.1 3.2 j J Charging pumps 015G2.4.45 Nuclear Instrumentation 4.1 4.3 j j j j j Ability to prioritize and interpretthe significance of each annunciator or alarm.

016K1.09 Non-nuclear Instrumentation 3.7 3.7 El ESFAS 028A2.02 Hydrogen Recombiner and Purge 3.5 3.9 LI LI j LOCA condition and related concern over hydrogen Control 041 K3.02 Steam Dump/Turbine Bypass Control 3.8 3.9 El LI LI LI El El LI LI LI LI RCS O7lAl .06 Waste Gas Disposal 2.5 2.8 LI LI LI LI LI LI ] LI LI LI LI Ventilation system 072K5.02 Area Radiation Monitoring 2.5 3.2 LI LI LI LI LI LI LI LI LI LI Radiation intensity changes with source distance 075K4.01 Circulating Water 2.5 2.8 LI LI LI LI LI LI LI LI LI LI Heat sink 086A4.06 Fire Protection 3.2 3.2 LI LI LI LI LI LI LI LI LI [] LI Halon system Page 1 of 1 2/22/2013 12:31 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l .29 Conduct of operations 4.1 4.0 El El ElElEl ElElElEl El Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.1.8 Conduct of operations 3.4 4.1 El El ElElEl ElElElEl El Ability to coordinate personnel activities outside the control room.

G2.2.1 Equipment Control 4.5 4.4 El El ElElEl ElElElEl El Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.17 Equipment Control 2.6 3.8 El El ElElEl ElElElEl El Knowledge of the process for managing maintenance activities during power operations.

G2.2.3 Equipment Control 3.8 3.9 El El ElElEl ElElElEl El (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.3.1 1 Radiation Control 3.8 4.3 El El ElElEl ElElElEl El Ability to control radiation releases.

G2.3.l3 Radiation Control 3.4 3.8 El El ElElEl ElElElEl El Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 El El ElElEl ElElElEl El Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.31 Emergency Procedures/Plans 4.2 4.1 El El ElElEl ElElElEl El Knowledge of annunciators alarms, indications or response procedures G2.4.46 Emergency Procedures/Plans 4.2 4.2 ElElElElElElElElElEl Ability to verify that the alarms are consistent with the plant conditions.

Page 1 of 1 2/22/2013 12:31 PM

ES-401, REV 9 I

SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 008AG2.1 .19 Pressurizer Vapor Space Accident! 3 3.9 3.8 j J j j J j Ability to use plant computer to evaluate system or component status.

054AG2. 1 .7 Loss of Main Feedwater ! 4 4.4 4.7 j j j j j J Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

055EA2.Ol Station Blackout! 6 3.4 3.7 El Existing valve positioning on a loss of instrument air system 058AG2.4.9 Loss of DC Power! 6 i84.2 Knowledge of low power! shutdown implicaUonsin accident (e.g. LOCA or loss of RHR) mitigation strategies.

077AA2.08 Generator Voltage and Electric Grid 4.3 4.4 Criteria to trip the turbine or reactor Disturbances! 6 WEO5EA2.2 -

Inadequate Heat Transfer Loss of 3.7 4.3 Adherence to appropriate procedures and operation Secondary Heat Sink! 4 within the limitations in the facilitys license and amendments.

Page 1 of 1 2!22!2013 12:31 PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO1AA2.03 Continuous Rod Withdrawal / 1 4.5 4.8 LI LI LI LI LI LI LI LI [ Proper actions to be taken if automatic safety functions have not taken place 037AA2.1O Steam Generator Tube Leak / 3 3.2 4.1 LI LI LI LI Tech-Spec Umits for RCS leakage weO6EG2.4.18 Degraded Core Cooling / 4 3.3 4.0 LI LI LI LI LI LI LI LI LI LI Knowledge of the specific bases for EOPs.

wel 0EG2.4.47 Natural Cwc. With Seam Void/ 4 4.2 4.2 LI LI LI LI LI LI LI LI LI LI Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Page 1 of 1 2/22/2013 12:31 PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 012G2.2.40 Reactor Protection 3.4 4.7 Ability to apply technical specifications for a system.

039G2.l.28 Main and Reheat Steam 4.1 4.1 LI LI El LI LI LI Knowledge of the purpose and function of major system components and controls.

063A2.Ol DC Electrical Distribution 2.5 3.2 LI LI LI LI LI LI LI LI E] LI Grounds 076A2.02 Service Water 2.7 3.1 LI LI LI LI LI LI LI [] [ Service water header pressure 1 03A2.02 Containment 2.2 3.2 LI LI LI LI LI LI LI [] LI LI LI Necessary plant conditions for work in containment Page 1 of 1 2/22/2013 12:31 PM

0 ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 014A2.04 Rod Position Indication 3.4 3.9 j j j J Misaligned rod 028A2.03 Hydrogen Recombiner and Purge 3.4 4.0 j The hydrogen air concentration in excess of limit flame Control propagation or detonation with resulting equipment damage in containment 071 G2.1.23 Waste Gas Disposal 4.3 4.4 El LI LI LI El LI LI LI El LI Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Page 1 of 1 2/22/2013 12:31 PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.38 Conductof operations 3.7 3.8 [] [ [ LI LI Knowledge of the stations requirements for verbal communication when im plamenting procedures G2.2.13 Equipment Control 4.1 4.3 LI LI LI LI LI LI LI LI LI LI Knowledge of tagging and clearance procedures.

G2.2.18 Equipment Control 2.6 3.8 LI LI LI LI LI LI LI LI LI LI Knowledge of the process for managing maintenance activities during shutdown operations.

G2.3.12 Radiation Control 3.2 3.7 LI LI LI LI LI LI LI LI LI LI Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.6 Radiation Control 2.0 3.8 LI LI LI LI LI LI LI LI LI LI Ability to aprove release permits G2.4.12 Emergency Procedures/Plans 4.0 4.3 LI LI LI LI LI LI LI LI LI LI Knowledge of general operating crew responsibilities during emergency operations.

G2.4.37 Emergency Procedures/Plans 3.0 4.1 LI LI LI LI LI LI LI LI LI LI Knowledge of the lines of authority during implamentation of an emergency plan.

Page 1 of 1 2/22/2013 12:31 PM

ES-401 Record of Rejected KIAs Form ES-401 -4 Tier I Randomly Reason for Rejection Group Selected K/A 2/ 1 1 03 KI .07 No Containment Vacuum System at Vogtle.

Chief Examiner Under Instruction (U/I) randomly and systematically selected new K/A:

I 03 K .08 Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: SIS, including action of safety injection reset (CFR: 41.2 to 41.9 /45.7 to 45.8) 2/1 026A1 .02 Unable to write a discriminating question to examine the effects of the containment spray system on containment temperature. The containment spray system is specifically designed to mitigate the effects of a high containment pressure condition, not containment temperature Chief Examiner Under Instruction (U/I) randomly and systematically selected new K/A:

026A1 .06 026 Containment Spray System (CSS)

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment spray pump cooling (CFR: 41.5 /45.5)

SRO T1/2 OOIAA2.O1 Unable to write a discriminating question at the SRO level to meet this K/A.

Chief Examiner Under Instruction (U/I) randomly and systematically selected new K/A:

OOIAA2.03 001 APE: Continuous Rod Withdrawal Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal : Proper actions to be taken if automatic safety functions have not taken place (CFR: 43.5 /45.13)

SRO T2/1 0 1 2G2. 1 .27 Unable to write a discriminating question at the SRO level to meet this K/A.

Chief Examiner Under Instruction (U/I) randomly and systematically selected new K/A:

012G2.2.40 012 Reactor Protection System (RPS)

Ability to apply Technical Specifications for a system.

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

T2/G1 026K2.O1 Unable to write a discriminating question that contains plausible distractors due to the common-knowledge nature of power supplies to the Containment Spray pumps.

Chief Examiner Under Instruction (U/I) randomly and systematically selected new K/A:

062K2.O1 062 A.C. Electrical Distribution K2 Knowledge of bus power supplies to the following:

(CFR: 41.7) 1(2.01 Major system loads 3.3 3.4 SRO T2/2 015A2.05 Unable to write a discriminating question at the SRO level to meet this K/A.

Chief Examiner Under Instruction (U/I) randomly and systematically selected new K/A:

014A2.04 014 Rod Position Indication System (RPIS)

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 /43.5 /45.3 /45.13)

A2.04 Misaligned rod 3.4 3.9

ES-401 Written Examination Quality Checklist Form ES4O1-6 Facility: Vogtle Units 1 & 2 Date of Exam: 4/20/2012 Exam Level: RO E SRO Initial Item Description 1

2.

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

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

3

-r

• -r

b. Facility learning objectives are referenced as available. (SIi Ii(

4

3. SRO questions are appropriate in accordance with Section D.2.d of ES-401

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_CL_program_office).

5. Question duplication from the license screening/audit exam was controlled Th3 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 Jhe examinations were developed independently; or Vthe licensee certifies that there is no duplication; or other (explain)

6. Bank use meets limits (no more than 75 percent Bank I Modified I New from the bank, at least 1 0 percent new, and the rest I I new or modified); enter the actual RO I SRO-only 14 I 3 16 I 5 I 45 I 1 7 question distribution(s) at right. I I

7. Between 50 and 60 percent of the questions on the RO Memory I C/A exam are written at the comprehension/ analysis level; I the SRO exam may exceed 60 percent if the randomly II selected K/As support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right.

/

I 42 / 4 11fl

8. References/handouts provided do not give away answers (J or aid in the elimination of distractors. 6

-513-

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; j deviations are justified. .4

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

- a;

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 / Signatre Date

a. Author TI4 f 7tdtlb SVJ 11-

b. Facility Reviewer (*)

Jf z

c. NRC Chief Examiner (#) 4. B/

,$n z.

(C

d. NRC Regional SupeMsor Note: The facility reviewers initials/signature are not applicable for NRC-developed examinations.

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

VOGTLE Nuclear April 2012 ILO Exam ES-401 Written Examination Review Worksheet Form ES-401-9 1 . 2. 3._Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD 8.

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

2.

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

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

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

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

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

The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable One or more distractors is (are) partially correct (e.g., ifthe applicant can make unstated assumptions that are not contradicted by stem).

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

The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e. it is not required to be known from memory).

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

6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

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

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

I I L J

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H)

T1 (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back-I Q SRO B/M/N UIEIS Explanation Focus Dist. Link K/A Only 1.ht5 ward H 2 X Y N/A N E K/A 001A3.06 1 Q=K/A, Q is at RO level.

2. Stem focus. Need to separate the two parts of the Q with the two plant conditions.

We need to provide a Vogtle-specific magnitude of RCS Pressure drop to ensure that a valid OT Delta T runback would occur. Also need an initial Rx power level. Consider the following recommendation for the Q stem, no changes to the distractors:

Unit 1 Initial Conditions:

-Power=100%, all control systems is normal alignment.

-An RCS pressure control malfunction reduces RCS pressure [to a value of

-Tavg is constant.

-A turbine runback initiates.

Current Conditions:

-Control rods are inserting in automatic

-Tavg is 4 degrees F > Tref Which one of the following is the initiating event (based on the jgjti[ conditions), AND the current expected rod speed, considering only the temperature deviation (based on the current conditions)?

03/15/2012 1 . Licensee modified Q as requested by NRC, Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

{ 21

VOGTLE Nuclear April 2012 ILO Exam

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 2 F 2 Y N/A N

/A OOIAA1 .02 1 . Q=K/A, Q is at RO level.

,. Cred Dist: A is non plausible, because checking rod motion stopped is not an action 0 perform. C is also non plausible, whenever would the operations team open the Rx rip breakers at 70% power and not perform E-O?

J. Check/ensure correct answer: wouldnt the in-hold-out switch already be in the hold position for these conditions, so the OATC would only be verifying the switch position and not actually repositioning the switch?

Potential overlap issue with one of the simulator scenario events that includes an utomatic rod withdrawal abnormal event.

i. Potential fix for A plausibility is to specifically ask what is the procedural step instead of the next action).

is U due to multiple non-plausible distractors.

3/15/2012

1. Licensee presented a slightly modified Q, NRC gave recommendations to make the

) clearly ask the next procedural step vs. the next action taken by the OATC. NRC also ave a recommendation to fix the plausibility of distractor C. Licensee modified Q per RC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 1

1. J

VOGTLE Nuclear April 2012 ILO Exam 1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= ISRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A jOnly 3 H 3 X Y N/A N E K/A 003K2.02

1. Q=K/A, Q is at RO level.

2. Stem focus: Need to ensure the Q statement is clear concerning the timing of the Q and the lack of operator actions. Appendix E also covers the lack of operator actions, preference to state that whenever possible for clarity? Disciss w/licensee. Consider the following modification to the Q statement:

Based on the current conditions, which one of the following correctly describes the status of the ACCW pumps after the DG1A load sequence is complete, if no operator actions occur?

03/15/2012 1 . Licensee modified Q as requested by NRC, Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

4 H 3 X Y N/A M E K/A 004A2.21 1 Q=K/A, Q is at RO level

2. Stem focus: need to include RCS boron concentration in Q stem, perhaps at extreme BOL or EOL, to enhance plausibility of C. and D. Also need to be specific with what 5 degrees low meansfor example state, TE-0130 fails 5 degrees below setpoint.

3. Potential overlap issue with this Q and simulator scenario event with T-O1 30 failure.

O.k. as written for now.

03/15/2012 I . Licensee modified Q as requested by the NRC. Q now appears SAT.

0 04/16/2012 1 Q as shown in final submittal appears SAT w/no other changes needed MKM

{4

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 5 H 3 X X Y N/A M E K/A 004K3.06 1 Q=K/A, Q is at RO level.

2. Stem focus: Need to give an initial position for 1 HS-1 12A (i.e., in To VCT position?).

3. Cred. Dist: C is not plausible, how would letdown flow that is already maximized go up based on beginning a flush ofthe demin? All of the orifice isolation valves should be open to get to 120 gpm, is it physically possible? Consider a different approach to distractor C.

03/15/2012 1 Licensee modified Q as requested by NRC, and provided a new distractor for C.

Licensee will verify that C is incorrect.

04/16/2012 I . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

6 F 2 X Y N/A N E K/A 005A1.03 1 Q=K/A, Q is at RO level.

2. Stem focus: what specific temperature instrument is used to make the determination for the second part Q? e.g. RHR system temperature as read on Tl-XXX, RHR Suction Temperature (or whatever is used). Otherwise RHR system temperature is vague.

03/15/2012 1 Licensee procedure does not specify where the RHR system temperature is taken; NRC requested licensee modify second part of the Q statement to refer to the procedure and title 04/16/2012 41 j

} 1 Q as shown in final submittal appears SAT w/no other changes needed MKM

_(5}

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only 7 F 2 x Y N/A M E A 006G2.2.4

1. Q=K/A, Q is at RO level.

2. Cred Dist: more clear to state both unit 1 and unit 2 for second part of distractors A.

and C.

03/15/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

8 H 2 x Y N/A N K/A 007A2.06 1 . Q=K/A, Q is at RO level.

. Stem focus: Slightly modify the first part Q statement as follows: ALB12-E03 is an alarm for the given plant conditions, and I. Cred dist: Do we need to spell-out what RMWST stands for in the distractor tatements, or is it a common enough abbreviation?

L Cred. Dist: How is first part of choices A or B plausible? You would need to have a V open or safety leaking to get a high temp PRT alarm, in what way would that be of the evolution of drawing a bubble in the PRZR?

Q is U due to multiple non plausible distractors.

03/15/2012 I Licensee modified Q to change conditions in the stem to give a RCS pressure transient vs. asking expected alarms for drawing a pressurizer bubble. First part of Q s systems knowledge of whether RHR suction or discharge valve relieves to Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 6 1 L

VOGTLE Nuclear April 2012 ILO Exam I . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 9 H 2 X X Y N/A M E A 007EG2.4.2 1 Q=K/A, Q is at RO level.

2. Cred Dist: D is a non plausible distractor. When would the operators ever be in ES-0.1 following a SI? Distractor D needs to be another plausible Rx trip.

3. Stem focus: It is always a good practice to differentiate between automatic and manual Rx trips. Modify second bullet to read: An automatic Reactor trip occurs.

03/15/2012 1 Licensee modified Q to give a new distractor D that was a reactor trip and not an SI signal. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

10 H 2 X Y N/A N E K/A 008A3.08 1 Q=K/A, Q is at RO level.

2. Stem focus: Need to include additional information, and resolve timing concerns with Q statement. E.g. consider the following modifications:

Current conditions:

-An automatic Safety Injection occurs with NO loss of offsite power.

Based on the current conditions, which one of the following will be the correct status of the CCW pumps following the completion of the load sequencer, and no additional operator actions occur?

03/15/2012 1 . Licensee modified Q as requested by NRC. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

{7}

VOGTLE Nuclear April 2012 ILO Exam

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F I Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 11 H 2 I K/A 008AK3.04 1 Q=K/A, Q is at RO level.

2. Cred Dist: D is a non plausible distractor, because it is such a weak choice when compared with C. i.e. D would only reduce a concern vice preventing a worse RCS depletion. A is a non plausible distractor because the second part of A is not a reason (which is what the Q is asking for), i.e. its a cue that A is not the correct choice.

I Credibility of B would be enhanced by providing lowering RCS temperatures in stem.

I Q is U as written due to multiple non plausible distractors.

15/2012

1. Licensee modified Q as requested. Plausibility of D still uncertain. NRC provided recommendation for changing D distractor to include loss of seal injection (loss of CCPs given in the stem). Q now appears SAT.

04/16/2012 I Q as shown in final submittal appears SAT w/no other changes needed. MKM.

12 H 2 I K/A 010K5.02 1 Q does NOT meet K/A, Q is at RO level. The operational implications required in the K/A statement are not being tested. This Q is also exclusively GFES-level and needs to be written to be a site-specific Q.

2. Q is actually higher cog level because ofthe calculations required (i.e. not simple memory recall offacts, etc.)

3. Cred Dist/Job-Link: Second part of Q is non-plausible and is not operationally valid.

When would operators need to differentiate between constant entropy and constant nthalpy process (outside of GFES?) Also, Second Law of Thermo states that entropy s always increasing, so constant entropy process is non plausible.

is U due to multiple non-plausible distracters and not meeting the K/A.

3/15/2012

. Licensee modified Q as requested by NRC. NRC requested that licensee modify first part of distractor to be different from 650 vs. 278.

)4/1 6/2012 Q as shown in final submittal appears SAT w/no other changes needed. MKM.

8 *1 I

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 13 H 2 X X Y N/A B E K/A 010K6.03

1. Q=K/A, Q is at RO level.

2. Stem focus: Must be careful to specifically delineate the timing of the Q statement with plant conditions or other ways. For example, consider the following modification to the Q statement: Based on the current conditions, which one of the following states what effect the 1 PIC-455 failure will have on PRZR Backup (B/U) heaters and spray

valves? In your answer consider the timeframe that the unit remains at power, also consider that no operator actions occur.

3. Cred. Dist.: The interplay of choices for distractor B are not plausibleit doesnt make sense that a failure in one direction causes a simultaneous occurrence of the B/U

heaters to turn on (which is a reaction to low pressure) and the spray valves to open

.; (which is a reaction to high pressure).

,j .

03/15/2012 I NRC proposed modifications to the Q statement to ask about PRZR heaters and status of PRZR block valve response in automatic immediately following the failure 9.

Also modified the failure from master pressurizer controller failure to make it a pressure

channel failure. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

14 H 2 X Y N/A M E K/A 011K2.O1 1 Q=K/A, Q is at RO level.

2. Stem focus: careful with the timing aspect of these Qs again. Consider the following modifications to the Q statement: Based on the current conditions, if no operator actions occur which one of the following is correct regarding the charging pump status at the completion of the load sequencer?

3. Stem focus: Question for licenseedo we need to include the switch positions for all charging pumps in the initial conditions; e.g. NCP handswitch in RUN, red light on/green light off; CCP A handswitch in AUTO, etc. This will make it clear what is intended by all systems in normal alignment statement.

03/15/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I L

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

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

units ward K/A Only 15 F 2 X Y N/A N E K/A 012K1.06 1 Q=KIA, Q is at RO level.

2. Stem focus: need to have a Reactor power level in Q stem to make this Q work, use something close to turbine trip-reactor trip permissive setpoint (i.e. not 100% power).

03/15/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

16 F 2 Y N/A B K/A 012K4.09 1 . Q=K/A, Q is at RO level.

. Cred. Dist: Distractors A and D are non plausible. It is common knowledge that control and protection functions are channelized or separated in order to prevent any negative effects from propagating. Furthermore, the fault is non-specific, and not enough information is provided to determine if the fault would cause the channel to trip

)r not to trip (if it did, in fact, affect the protection side).

,) is U due to multiple non-plausible distractors.

03/15/2012 1 Licensee modified Q per NRC request to make four separate answer choices. NRC required to modify one of the four answer choices to make it plausible. Q now appears T.

)4/1 6/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 10 L

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 17 H 3 X X Y N/A N E K/A 013A4.O1

1. Q=KIA, Q is at RO level.

2. Stem focus: Ensure the S/G levels are specified to be narrow range

3. Cred Dist: Use of the only modifier may not be the best word choice for these conditions. Slight modifications to distractors B, C, and D recommended as follows:

B. expected, the AFW actuation signal is blocked under the current conditions per 1 2004-C.

C. NOT expected, BOTH MDAFW pumps should have started. The TDAFWP should not have started.

D. NOT expected, BOTH MDAFW pumps and the TDAFWP should have all started.

! 03/15/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

18 F 2 Y N/A M KJAOI5AK2.10 1 Q=KJA, Q is at RO level.

2. Cred. Dist.: This JPM overlaps with a simulator JPM for starting a RCP, Q needs to be changed. Distractors are not credible because the operators will have just done this volution on the simulator.

I. Need to put the applicants in a different reason for starting RCP5maybe starting RCPs to sweep voids out of U-tubes? (or an alternate equivalent)

s U due to multiple non-plausible distractors (only non plausible from the overlap standpoint).

03/15/2012 I Licensee presented modified Q to NRC. NRC provided extensive input to change the

) and to make it meet the standard without overlap with the simulator JPM. First part ow tests the circuitry and interlock behind the blue light on the RCP oil lift pump, cond part Q now tests which RCP breaker has the interlock with the RCP oil lift pump lue light.

)4/1 6/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

C I L J

VOGTLE Nuclear April 2012 ILO Exam I . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 19 H 2 X Y N/A N E A 015G2.4.45 1 Q=K/A, Q is at RO level

2. Stem focus: Shift if any phrase in Q statement to the end of sentence, i.e. Based on the current conditions, which one of the following is/are annunciator window(s) that will be LIT (if any)?

03/15/2012 I . Licensee modified Q as per NRC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

20 H 2 Y N/A N

. K/A 016K1.09

1. Q=K/A, Q is at RO level.

2. Q appears SAT at this time.

04/16/2012 t:.

Q as shown in final submittal appears SAT w/no other changes needed. MKM.

r 12

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 21 F 2 X X Y N/A M E K/A 022A4.O1 1 Q=K/A, Q is at RO level.

2. Stem focus: Include specific lights/nomenclature that are going to be lit/not lit on QMCB.

3. Cred. Dist: The combination for distractor D is not plausible. How is it possible that the coolers would not be running at the lower pressure condition and the higher pressure condition?

03/15/2012 1 . Licensee presented modified Q, still needs some work on the plausibility of distractor 03/16/2012

1. Licensee presented re-modified Q, better conditions in Q stem and better plausibility in the distractor choices. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

r 13

VOGTLE Nuclear April 2012 ILO Exam

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 22 H 2 Y N/A N K/A 022AG2.2.42 1 Q=KIA, Q is at RO level.

2. Cred. Dist: with a CCP tripped and inoperable, how would second part of distractors B and D ever be plausible? Operators will always enter LCO 3.5.2 under these conditions.

3. Stem focus: should we remove the statement about real LCOs? Is real LCO defined in a plant procedure (conduct of ops?)? Need to be clear about Technical Specification LCOs vs. commonly used spoken phrase in an LCO. If the plant is in a condition where an LCO applies, the plant is either meeting the LCO or not meeting the LCO. A good way to ask these questions is to ask whether the Condition of the LCO is (or is NOT) met.

Q is U due to multiple non-plausible distractors.

03/15/2012 I Licensee presented modified Q based on the NRC comments. Q stem changed to place the NCP in standby, distractors changed to ask whether required actions of two TRM specs were/were not required to be taken. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

23 F 2 x Y N/A M E K/A 025AK2.03

1. Q=K/A, Q is at RO level.

2. Cred. Dist.: Use of the modifier only may not be the best option for distractors A.

and B. because applicant will have to read other choices to determine what it means.

Better way to state may be:

A. 1A RHR Hx and 1A RHR pump seal cooler. 1A RHR pump motor cooler did NOT lose CCW flow.

B. 1 B RHR Hx and 1 B RHR pump seal cooler. 1 B RHR pump motor cooler did NOT lose CCW flow.

03/15/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

.4 I 14 I J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 24 F 2 X Y N/A N E A 026A1 .06 1 Q=K/A, Q is at RO level.

2. Cred Dist. : How is it plausible that operators would run a spray pump test without providing miniflow protection to the pump, potentially damaging a safety-related SSC due to rising temperatures? Second part of B and D not plausible. Also, there is a timing part to the Qare we absolutely sure that temperatures would be stable at all times during the pump test (or, e.g. would they slightly rise and then stabilize).

3. Potential fix: for the second part of the Q, test on what the pump line-up will be, e.g.

will there be a recirc lineup to the RWST valved in, or is the recirculation line up not required.

Q is E due to multiple non-plausible distractors, but benefit ofthe doubt given due to ease of correction 03/15/2012 1 . Licensee modified Q based on NRC recommendations. Q appears SAT at this time.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

25 H 3 Y N/A B 1-: K/A 026AA1.03

-;: 1. Q=K/A,QisROlevel.

2. Q appears SAT at this time.

15

{

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 26 F 2 X Y N/A M K/A 026K2.O1

1. Q=K/A, Q is RO level.

-,. Cred. Dist. : Containment Spray pumps are major safety-related SSCs, it is not ausible that they would be powered from 480V buses at Vogtle. Second part of listractors A and C is not plausible.

J. Stem focus: Ensure stem contains language specifying no operator actions occur, testing whether or not the spray pump will auto-start or not.

is U due to multiple non-plausible distractors.

VI 5/2012 1 NRC will consider changing the K/A to see if there is a way to get plausible distractors.

03/16/2012 I . NRC chose new random K/A 26 F 2 X x Y N/A  ? E K/A 062K2.O1 (new replacement K/A) 1 QK/A, Q is at the RO level.

2. We need to know Q history (i.e. bank/modified/new) and pedigree (if applicable), also distractor analysis needed.

3. Potential for partial overlap with one simulator scenario event deemed acceptable.

4. Stem focus and cues: replace The plant with Unit 1 Simply state the conditions of the buses (other information not strictly needed). Question would then look like this:

Unit 1 tripped from 78% power.

-1 NAA is de-energized.

-1NAB is energized.

Based on the given conditions, if no operator actions occur, which one of the following pumps WILL be running?

A. {answer choices as given, etc.}

04/16/2012 1 Licensee accepted NRC recommendations as listed above and modified the Q as requested. Q as shown in final submittal appears SAT w/no other changes needed.

MKM.

I 16 L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 27 F 3 N/A N K/A 028A2.02 1 Q does NOT meet K/A, Q is at RO level.

2. Applicant can answer both parts ofthe Q using systems knowledge to obtain the correct answer; knowledge of the procedure to mitigate the condition is not required.

Understand that the procedure also includes the information, however due to the other concerns K/A match is not strong enough.

Q is U due to not meeting the K/A.

03/15/2012 1 Licensee presented modified Q; however, first part of Q still could be answered using systems knowledge. Table this Q and attempt a re-direct to find a procedural avenue to asking the Q.

03/16/2012

1. Licensee presented a newly re-modified version of this Q during review, Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

28 H 3 x x x Y N/A B E K/A 029EK1 .01 1 Q=K/A, Q is at RO level.

2. Cred Dist/partial correct: Second part of B. and C. is potentially a correct action, the only wrong thing is 2185 psig vs. 2135 psig as stop pressure point. Second parts of distractors B. and C. are also subsets of second part A. and D; i.e. lowering RCS pressure to increase charging/emergency boration flow is an other action that does NOT cooldown the RCS or add positive reactivity.

3. Potential fix: Modify the Q statement to read: Based on the current conditions, per 1 921 1-C Also modify the second part of distractors A. and D. to exactly match the language from the FR-S.1 step: initiate actions of other Functional Restoration Procedures in effect 03/15/2012

- 1. Licensee modified Q as per NRC request. Q now appears SAT.

I L J

VOGTLE Nuclear April 2012 ILO Exam EJ 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 29 H 2 X 036AK3.03 Y N/A N E I Q=K/A, Q is at RO level.

2. Partial: do the exhaust filtration units contribute to a negative pressure in the FHB?

If so, is C. a potentially correct answer? Do we need to know the specific alarms that occurred that would have caused the automatic actuation (add to stem?)?

03/15/2012 1 Licensee provided answers to NRC concerns; however, c is still a potentially correct A answer. Recommend table this Q and have licensee re-visit.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

30 H 2 X Y N/A B K/A 037AK1.02 i Q=K/A, Q is at RO level.

I 2. Stem focus: Consider changing SHUTDOWN in Q statementto power reduction for clarity, SHUTDOWN may also carry the connotation of post-trip activities.

I 3. Job link: how is it operationally valid to tell an applicant that a geometric size does not change? What indications would be provided/how would an operator know this in the control room?

4. Cred. Dist: Psychometically/logically, the second part of distractors C and D are not needed to make the answer choice unique; therefore, they can be deleted; however, this also causes D to be non plausible.

i. Are there situations in SGTR backfill conditions where delta-P between the RCS and ruptured S/G are monitored/controlled? A situation like that would make the Q more operationally sat.

. is U due to operational validity concerns. Q should be able to be re-worked.

1 Licensee presented modified Q. NRC intervention required to make the Q meet NUREG criteria. Q should now be SAT.

I 18

VOGTLE Nuclear April 2012 ILO Exam

=

3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 31 H 3 X X Y N/A N E K/A 039G2.1.25

1. Q=K/A, Q is at RO level with provided references.

2. Stem focus/Cues: grammatical tense in Q statementuse Valve(s) instead of Valves as this is a minor tip-off. Instead of asking the Q how many valves exceed tolerance, ask how many valves are not in tolerance? Exceed is a tip-off because of the low pressure given for the third MSSV.

03/15/2012

1. Licensee modified Q per NRC request. Q now appears SAT.

32 H 2 X Y N/A B K/A 039K5.08 1 Q=K/A, Q is at RO level.

2. Stem focus: After the Q statement, add something like For your answer, consider kit no operator actions are taken to mitigate or compensate for the below events.

3. Cred. Dist.: B and D are causing the exact same effect (lowering S/G pressure/temperature) which then causes the exact same effect on the RCS (lowering I

Tave, which adds positive reactivity). Therefore, since both distractors are doing the same thing, and there is only one correct answer, neither distractor could be plausible.

Potential fix: consider changing one of the distractors to involve a Xe transient that is adding positive reactivity (i.e. Rx startup in the 12-24 hr window when Xe is burning out?).

Q is U due to multiple non plausible distractors.

03/15/2012

1. Licensee modified Q per NRC request (Xe transient occurring 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> post-trip). Q now appears SAT at this time.

I 04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

1 19 I L

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 33 H 2 X X Y N/A N E K/A O4OAAI.20

1. Q=K/A, Q is at RO level.

2. Stem focus/partial correct: need to be careful with the timing of the Q, inserting rods may be required as part of the power reduction with the turbine. Ensure second part of the Q statement reads something like: Per 18008-C, the FIRST action the operators will perform is to . Delete the phrase to lower reactor power because it weakens the plausibility of inserting rods and is not needed.

03/15/2012

1. Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

20

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 34 H 2 X Y N/A N E K/A 041K3.02 I Q=K/A, Q is at the RO level

2. Stem focus: we need more information than is provided to determine the correct answer. Consider the following modifications:

Unit I Initial Conditions:

-Power=100%

-Steam dumps are in the TAVG mode Current Conditions:

-Main Turbine automatically trips

-Reactor Trip Breaker A opens

-Reactor Trip Breaker B is CLOSED and cannot be opened Based on the current conditions, which one of the following correctly completes the following statement, if no other operator actions are performed?

RCS Tavg will be controlled at due to Steam Dumps controlling on the controller.

03/15/2012

1. Licensee modified Q statement per NRC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

C 21

VOGTLE Nuclear April 2012 ILO Exam

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 35 H 2 X X Y N/A N E K/A 051AA2.02 1 Q=KJA, Q is at the RO level.

2. Stem focus: Slight clarification to the first part Q statement: Based on the current conditions, a manual Reactor trip required by 1 8040-C, and

3. Cred. Dist.: Interplay between D choices is not plausible. If a reactor trip is NOT required, why would things be so bad that steam dumps would NOT operate. Mindset would be that vacuum allows the plant to stay at power although the steam dumps would not work.

03/15/2012 1 Licensee modified Q per NRC request. Licensee provided further information that resolved concerns over plausibility of distractor D. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

36 H 2 E Y N/A B E K/A 054AA2.02 1 Q=K/A, Q is at the RO level.

2. Cred. Dist: D is not plausible because how would MFW Pump A not trip on SI? No conditions are given in the stem to make anyone consider this choice. C and D are close to implausible for MFW pump B because manual operator action is too strong of a choiceno one would allow the B pump to continue to run until the low Tavg condition is reached, manual trip to back-up the assumed failed SI trip makes sense, the others do not.

Q is E due to one non plausible distractor (D).

03/15/2012 1 Licensee presented Q with no changes, D still not plausible. NRC provided several ideas to licensee to fix the Q, asked licensee to present option later on.

03/16/2012 1 Licensee presented newly revised Q based upon NRC recommendations from the previous day. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

22

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 37 H 3 Y N/A N K/A 055EA2.02 1 Q=K/A, Q is at RO level.

2. Cred Dist: not plausible that steam dumps would be available in a post-ECA-O.O situation; no circ water pumps running, no condenser vacuum. There are also some overlap concerns/double jeopardy with Q 35 (dealing with loss of vacuum and effects on steam dumps).

3. Is there any situation in ECA-0.1 where steam dumps are placed in service? Maybe by creating the other option as the right answer resolves the plausibility concerns.

Q is U due to multiple non-plausible distractors.

03/15/2012

1. Licensee presented alternate Q. NRC intervention required to assist in developing satisfactory alternative to second part of the question, testing a different method of power restoration and what ARVs would be able to be automatically operated.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

r 23 L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 38 H 2 X x Y N/A N E K/A 056AK103 1 Q=K/A, Q is RO level.

2. Stem focus: add approximately to the Q statement, for example: Based on the given conditions, the current subcooling value is approximately

3. Job link: Is there a plant document that specifies that subcooling is calculated using CETs instead of Thot? A better way to ask the Q is to state that qualified SPDS (or whatever that is Vogtle specific) subcooling monitor is reading erratically. The 55 directs you to verify the reading by manually calculating subcooling margin. Based on the given conditions, the correct reading as displayed on SPDS TI-XXX, Subcooling, should be approximately I.e., this introduces a little bit of operational validity to the exercise of using steam tables. Another suggestion would be to give five highest CET values, see if applicant knows to use average of 5 highest, or the very highest L value 4 Cred Dist when would operators ever average Thots and CETs (making distractor B non plausible)?

03/15/2012 1 Discussed at length w/licensee. NRC position is that it is better to provide hot leg and cold leg temperature values and CET values, and then ask what the subcooling monitor calculates (more operationally valid). Licensee agreed to table the Q.

04/16/2012 1 Licensee agreed w/NRC recommendations and modified the Q as recommended. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 24 1

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 39 F 2 X X Y N/A N E K/A 058AK3.O1

1. Q=K/A, Q is atRO level.

2. Combustion air appears in every choice of the first part Q, consider re-write to ask whether fuel is shut off, or whether fuel is NOT shut off.

3. Consider minor re-write of second part Q statement and second part distractors as follows:

The DG1 B output breaker is required to be opened using the jj breaker

. . . TRIP pushbutton

. . . handswitch 03/15/2012 1 . Licensee modified the Q per NRC request. Q appears SAT at this time.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

40 H 2 Y N/A B S 059K4.08

1. Q=K/A,QisatROlevel.

Q appears SAT at this time.

3/15/2012 1 . Q appears SAT at this time.

04/16/2012 1 Q as shown in final submittal appears SAT w/no other changes needed MKM 25 I

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 41 H 3 X X Y N/A NI K/A 061A3 04 1 Q is a borderline K/A match, Q is at RO level.

2. Minor tweak to second column heading: MDAFW B mini-flow handswitch on Shutdown Panel B to ensure parallelism with other column heading/clear any confusion over what Q is asking.

3. Partial correct: there is a timing aspect to this Q; the mini-flow on A pump will be fully open when the pump initially starts, and then will throttle closed eventually over the long term. Will need to bound the Q in time somehow to attempt to make the Q work.

4. Cred. Dist: First part of distractors A and B non plausible. The conditions in the stem for the A MDAFWP are completely normal; therefore, why would the applicant think that the mini-flows would stay fully open, instead of throttling (even a little bit) once the pump starts to deliver flow to the S/Gs?

.2 is U due to multiple non plausible distractors.

03/15/2012 1 . Licensee provided modified Q that included AFW flow ratestherefore addressing Lhe plausibility concerns that were inherent in the initial Q statement. NRC recommended several changes to enhance the modified Q. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

42 F 2 x X Y N/A B E K/A 061K6.02 1 Q=K/A, Q is at RO level.

2. Cred Dist: D is not plausiblewhat machine or component in the plant resets itself when speed lowers below a mechanical overspeed trip setpoint?

3. Partial: Is A technically correct? Specificially, would the amber light extinguish when the limit switch is reset, after manually reseting the mechanical trip linkage? Discuss w/licensee.

03/15/2012 1 Licensee proposed modified based on Q NRC comments; however, modified Q still had plausibility issues with the D distractor NRC intervened to propose a different plausible distractor for the ID choice Q now appears SAT

04/16/2012

,v -

1 Q as shown in final submittal appears SAT w/no other changes needed MKM 26 I L

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 43 F 2 x x Y N/A N E K/A 062A2.11

1. Q=KIA, Q is at RO level.

2. Cred. Dist/Partial: All distractors need to be specific as to which components; e.g. A ACCW Pump instead ofjust ACCW Pump 03/15/2012 1 . Licensee modified the Q per NRC request. Q appears SAT at this time.

04/16/2012 I . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

44 F 4 Y N/A N S.; K/A 062AA2.03

1. Q=K/A, Q is at RO level.

Q appears SAT at this time.

14/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

45 F 2 Y N/A N S 1, K/A 063K3.01

1. Q=K/A, Q is at RO level.

2. Q appears SAT at this time.

27

VOGTLE Nuclear April 2012 ILO Exam

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 46 F 2 Y N/A N K/A 063K4.04 1 Q=K/A, Q is at RO level.

2. Cred. Dist: Plausibility of first part of distractors A and B appears weak; ifthe loss

)f the B train DC bus affects the B CCP the obvious effect will be to de-energize control power, which causes the main control board handswitch lights to go out. Plausibility of the interplay between B and D also appears weak; if the loss of DC bus affects the pump one way, why would it cause an opposite effect on the lights?

2 is U due to multiple non-plausible distractors.

103/15/2012 1 . Licensee presented modification to first part of Q distracters, Q now appears SAT.

I 04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

47 F 3 Y N/A B K/A 064K6.07 i . Q=A, Q is at RO level.

I . Cred. Dist: Because DG1 B has the higher start air pressures, logically it is the better choice. A is NP because if both diesels will accept an emergency start, why would only DG1A (the worse choice) accept a normal start? B is NP because if both dieselfwould normal start, why would only DG1A (the worse choice) accept an nergency start? Logically the Q can be eliminated down to either C. or D. and nowledge of whether the normal start or the emergency start requires the higher

)ressures.

_) is U due to multiple non plausible distractors.

03/16/2012

1. Licensee presented new Q that deals with entry into LCO 3.8.3 based on starting air pressure, Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 28 L

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 48 H 2 Y N/A N K/A 065AK3.04

1. Q=K/A, Q is at RO level.

2. Cred. Dist: having to manual Rx trip is too strong of an option, with immediate urgency, when compared with losing the SFP gate seals, which is a casualty that does not have the same immediate urgency. Also, there are multiple backup mechanisms to the SFP seals (i.e N2 backup tanks). Would a SFP gate seal completely failing and draining with no makeup ever uncover the fuel (or is the gate physically above the top of fuel in the SFP?) This makes the first part of distractors C. and D. non plausible.

Plausibility of 70 psig is also weak; at what pressure would a Rx trip be required?

Q is U due to multiple non plausible distractors.

03/16/2012 1 Licensee presented modified Q that changed the second part of distracters C and D; however issues remained with ensuring the reason for cross-tying instrument air (because there is no AOP background document). NRC presented modification to the Q that directly addressed the procedural step in the AOP (1 5). K/A is met because knowledge of the procedural step, which is all that is available to use, is knowledge of the reasons for the procedural step. Q now appears SAT.

49 H 2 x Y N/A N E K/A 068AA2.10 1 Q is a very borderline K/A match, Q is at RO level.

2. K/A match: As written the knowledge required to answer the Q deals with location of components and correct switch positioning, the erratic NI indications are not part of the determination of the correct answer. Willing to accept.

3. Stem focus: Consider deleting all of the information above the Q statement and re word the second part Q as follows:

If a fire results in a Unit 1 control room evacuation, per I 8038-1 Operation From Remote Shutdown Panels the Test/Status Control Switch in the Control Building is required to be placed in the position.

. *: 03/16/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 29 L

VOGTLE Nuclear April 2012 ILO Exam 1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD 8.

I (F/H) (1-5) Stem Cuesi TIF Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 50 F 3 X Y N/A B E K/A 071A1.06

1. QK/A, Q is at RO level.

2. Stem focus: need to slightly re-word the Q statement to be more precise in what Q is asking, for example:

Based on the given conditions, which one of the following correctly completes the following statement?

The Auxiliary Bldg HVAC will and per procedure XXXXXX, the operators are required to A. (1) automatically trip B. (1) automatically trip (2) continue to monitor the radiation monitors. No additional actions with regards to Auxiliary Bldg HVAC are required.

C.

D. (2) continue to monitor the radiation monitors. No additional actions with regards to Auxiliary Bldg HVAC are required.

03/16/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

( 1 L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 51 H 2 X X Y N/A N E K/A 072K5.02 1 Q=K/A, Q is at RO level.

2. Operational Validity discussion: This Q is not very operationally valid; however, the K/A is itself not operationally valid and is more of a GFES-type K/A that was randomly selected for the site specific exam. The difference between this Q and others, which may be rejected for operational validity concerns, is that in the other cases the K/A is more conducive to writing an operational valid Q, whereas in this case there is almost no way to write an operationally valid Q to this K/A. Willing the accept this Q on the test per this discussion.

3. Stem focus: Enhance by providing a reason for the very high rad trash? e.g., first bullet to read Unit 1 is in MODE 5 and containment clean-up is in progress following a substantial primary coolant leak. After the bullet stating the RE-004 is reading 5 mr/hr, add bullet stating e.g. For your answer, consider that all of the RE-004 reading is due to the high rad trash container.

3. Cred. Dist: Is using the square root of the distances plausible (distractor D)?

Perhaps using the distances cubed (raised to the third power) is a more plausible option.

03/16/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

52 H 2 X X Y N/A M E K/A 073K5.03

1. Q=K/A, Q is at ROlevel.

2. Stem focus: Pie-planning vs. not pre-planning the work is not part of the determination of the correct answer; simply state in the stem how long the work is going to take in the radiation field.

3. Cues: All distractors need to be carried out to two decimal places to match distractor A.

03/16/2012

1. Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

31 J

VOGTLE Nuclear April 2012 ILO Exam I . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD [

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Linkj units ward K/A Only 53 H 2 Y N/A N KJAO74EA1.25 1 QK/A, Q is at the RO level.

2. Cred. Dist.: With the operators in FR-C.1 and major disaster imminent (true anytime operators are in FR-Cl), setting atmospheric controls to an arbitrary setpoint of 25% is not plausible. In what other EOPs does the EOP specify a particular controller setpoint; r, they specify cooldown rates using either steam dumps or ARVs.

ecommendation: change all instances of 25% to throttled as needed to maintain a cool down rate of < 100 degrees F/hr in the cold legs.

is u as written due to multiple non-plausible distractors.

03/16/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

/1 6/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

54 H 2 X Y N/A N K/A 075K4.O1 i Q=K/A, Q is at RO level.

I 2. Cred. Dist: There is a lot of overlap with this Q and with at least two other Qs dealing with condense loss of vacuum/loss of circ water and loss of steam dump functions.

I Second part of B and D are no plausible, all the applicant is given in the stem is that here are no circ water pumps running, so without any further information about vacuum, how would anyone think the steam dumps would function as required?

) is U due to multiple non plausible distractors.

/1 6/2012 1 Licensee presented new Q that went away from steam dump operation in the second part of the Q, newly written Q now appears SAT.

Wi 6/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

32 I L

VOGTLE Nuclear April 2012 ILO Exam I . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 55 F 2 Y N/A B Si K/A 076K1 .09

1. Q=KJA, Q is at RO level.

2. Q appears SAT at this time.

03/16/2012

1. Slightly modified Q to prevent a minor cue based on a previous Q concerning NSCW and ACCW. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

56 H 2 X X Y N/A N E K/A 077AK1 .02 1 Q=K/A, Q is at RO level.

2. Partial: could an operator determine that a unit trip was required instead of lowering excitation? Need to ensure D is to absolute correct answer, check with licensee.

3. Cred. Dist: Need to use plant-specific nomenclature for the distractors B, C, D. For example: take HS-XYZ, MAIN GEN EXCITATION [or whatever] to the RAISE position until generator is at 200 MVARs lagging.

03/16/2012 I Licensee modified Q per NRC request. However, the modifications to the distracters were not precise enough and could lead an applicant to believe that there was no single correct anser. NRC proposed modifications to the Q to make the answer choices technically correct/technically wrong. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

tr

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 57 F 2 Y N/A N

(/A 078K3.01 I . Q=K/A, Q is at RO level.

. Distractors A and B and non plausible, because the consequences ofthese valves ailing open under the given conditions are too severe to the plant when the applicant is considering these failures vs. the valves in distractors C. and D. Furthermore, the interplay between distractors A and D does not make sensewhy would the normal RZR spray valves fail in a different direction that the auxiliary spray valves (i.e. they would have to because there is only one correct answer).

I ) is U due to multiple non plausible distractors.

/1 6/2012 1 . Licensee modified the Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

58 F 2 y N/A N K/A 086A4.06 1 Q=K/A, Q is at RO level.

2. Not credible that one detector failure would cause a Halon activation when the gas is so rare&expensivesimilar to single failure criteria. Would it be credible that a single detector failure could actuate a halon system worth so much $$? Potential ecommendation to compare two detectors vs. three detectors actuation in second part 2

3. There are also credibility issues with the first part of distractors C and D. Is there any other plant alarm that has C&T as a primary location for receipt of the alarm?

Q is U as written due to multiple non plausible distractors.

03/16/2012 I . Licensee modified Q per NRC recommendations. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 1 L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 59 F 3 x Y N/A B E K/A103K1.08

1. Q=K/A, Q is at ROlevel.

2. Cred. Dist.: Any SI signal is too strong a choice (i.e. including manual actuation?)

when compared to only the Containment Hi-i actuation signal, and makes the first part of distractors A. and B. non-plausible.

3. Q is considered an E; although Q has multiple non plausible distractors there is a relatively easy editorial change to make the Q work.

4. Consider the following recommendation:

An automatic Containment Isolation Phase A (CIA) is directly actuated by and the circuitry logic allows the CIA signal to be reset Also change first part of distractors C. and D. to read any automatic SI signal.

03/i 6/2012 i . Licensee modified the Q per NRC request. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

60 F 2 X Y N/A B E K/A G2.1.29 I Q=K/A, Q is at RO level.

2. Distractor A is non plausible. It is common knowledge throughout the plant that manual valves are only checked in the close direction and never in the open.

3. Distractor C is borderline. Consider modifying the second statement in distractor C to read as follows: Align valve in the required position, notify the 55 once the valve is properly aligned, and do NOT continue until 55 permission to resume the line-up is obtained.

03/i 6/2012 i . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012 1 Q as shown in final submittal appears SAT w/no other changes needed MKM 35

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8 Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only

61 F 2 Y N/A N K/A G2.1.8 1 Q=K/A, Q is at RO level.

2. Cred. DistlCues: Use of preferred in second part Q statement implies just one method, makes second part of distractors A. and B. almost NP. Recommend changing second part of distractors A. and B. to read: Bridge Phone Ext 3145, codes 123# or 234#.

Further plausibility issues with first part of distractors B and D. Whenever would an I alternate safe shutdown procedure rely on extra shift personnel, who may not be ivailable in the first place, to operate Shutdown Panel A?

) is U due to multiple non plausible distractors.

03/16/2012 1 . Licensee modified Q per NRC request; however new Q had overlap with in plant

1. NRC input changed the Q to resolve the overlap concern and Q now appears i/i 6/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

62 F 2 N/A B K/A G2.2.1 i . does not meet K/A, Q is at RO level. How is the Q testing operation of controls I hat could affect reactivity? At most the operators in the Q are monitoring SR and using he plant page system.

2. Cred. Dist: There is a subset issue here in that immediately evacuating Containment would stop Core Alterations, which makes second part of distractors A and C non plausible.. Also, the use of the modifier only is rarely the best choice when dealing with ictions operators will take---there is almost always other actions that are required to be taken.

is U as written due to multiple non plausible distractors.

/1 6/2012 1 Licensee presented new Q, which had multiple issues. NRC recommended a pathway forward with a slightly different approach. Licensee agreed to develop a new Q o this same K/A.

I 36 L

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD f (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link unitsj ward K/A Only 62 H 2 X Y N/A 9 K/A G2.2.1 (new Q for same K/A) 1 Q=KIA, Q is at RO level.

2. We need to know Q history (i.e. bank/modified/new) and pedigree (if applicable), also tractor analysis needed.

. Stem focus: we cannot test on proper course of action; we have to test eciuirements.

Cred. Dist.: Delete phrase and repeat the ECC calculation. from the second part f distractors B. and D. because it is not needed to differentiate an answer. The second part of distractors A. and C. are not plausible. If a 1/M plot predicts Rx critical below an insertion limit, how is it credible for safe Rx operation to continue with the startup?

2 is U as written due to multiple non-plausible distractors.

I 37 L J

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 62 [Continuation of Q 621 Consider the following recommendation for Q replacement:

Given the following:

-Time=0700.

-12003-C, Reactor Startup (Mode 3 to Mode 2) is in progress.

SR NIS counts are 400 cps and increasing slowly.

The 1/M projects criticality to occur below the insertion limit.

1/M value is at 0.08.

-Time=0707.

-OATC has inserted control bank rods 770 pcm.

-After all rod motion stops, SR NIS counts are 300 cps and increasing slowly.

-Time=0730.

-No rod motion has occurred since 0707.

-SR NIS counts have stabilized at 680 cps.

Which one of the following correctly completes the below statements?

In accordance with 12003-C, at 0730 the audio count rate (1) required to be in service.

In accordance with 12003-C, at 0730 a manual reactor trip (2) required.

A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is NOT D. (1) is NOT (2) is Ans: B.

04/16/2012 1 Licensee accepted NRC recommendation/written Q as shown above with no additional comments or changes. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

r 38 L J

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 63 F 2 X Y N/A M E K/A G2.2.17

1. Q=KIA, Q is at RO level.

2. Because plant manager is stronger than OSM, need qualifier to bound the subset.

Consider the following modification to the second part Q statement:

the MINIMUM level of authorization required to approve MSPI equipment removal from service that results in a 25% reduction of remaining MSPI margin is the 03/16/2012 1 Licensee presented modified Q per NRC requests; however, during review it was recognized that the modified Q was testing on the SRO-only level. Modified Q to test on four different components, which one is NOT a MSPI component. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

64 F 2 Y N/A B G223 1 . Q=K/A, Q is at the RO level.

. Cred. Dist: The analysis ofthis Q is similar to the previous Q concerning containment spray pump power suppliesthe divergeance in bus voltages makes the second part of distractors C and D to be non plausible. DG fuel oil transfer pumps are small pumps, its not plausible thatthey would be powered from major safeguards 4160 V buses.

c s U as written due to multiple non plausible distractors.

03/16/2012 1 . Licensee presented modified Q based on NRC comments. Q now appears SAT.

14/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

(I 1 39 J-

VOGTLE Nuclear April 2012 ILO Exam I . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 65 F 2 Y? N/A B K/AG2.311 1 Q=K/A, but it is borderline. Q is at RO level.

2. Need to be more precise with distractors. For example, Adjust SG #3 ARV automatic setpoint to 1 125 psig. And Place SG #3 ARV in MANUAL and maintain SG pressure LESS THAN 1125 psig. (or equivalent)

3. Cred. Dist: Why would any applicant choose to place a controller in manual when an automatic option is available? Makes C and D non plausible. There is no condition in I the stem to make the applicant think that there is a reason automatic control will not work.

) is U as written due to multiple non plausible distractors.

03/16/2012

1. Licensee modified Q per NRC request and presented new Q. NRC recommended Dr changes to second part distracters C and D to ensure the verbage was clear about uncontrolled depressuriation of the ruptured S/G. Q now appears SAT.

ii 6/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 40 I L J

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD T I (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIEIS Explanation Focus jj Link units ward K/A Only 66 F 2 X X Y N/A M E KIAG2 3.13

1. Q=K/A, Q is at RO level.

2. Stem focus/Partial: 55 appears in all answer choices. Better way to write Q statement might be as follows:

Per 93300-C, Conduct of Refueling Operations, the OATC have the authority to suspend core alterations and per 18006-C, Fuel Handling Event, the Containment evacuation page announcement will instruct personnel to First part of distractors are now Does/Does NOT 03/16/2012 1 . Licensee modified Q per NRC request. Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

67 H 2 Y N/A B K/A G2.3.14 1 QK/A, Q is at RO level.

2. Second part of Q distractors are non plausible due to overlap with Sim JPM H which specifically directs the RO when to close the outside air supply damplers.

Q is U due to multiple non plausible distractors. Plausibility concerns in this case are due to overlap, not the specific psychometrics ofthe Q.

03/16/2012 1 Licensee modified second part Q to move away from isolation of dampers/overlap concerns. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 41 1

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 68 F 2 X X Y N/A B E A G2.4.31 1 Q=KIA, Q is at RO level.

2. Cred. Dist: B is not plausible because ofthe first sentence, which contradicts common sense.

3. Could D be a potentially correct answer?

4. Modify final clause of answer choice A to read: . . . as prioritized by the operating crew. Doesnt make sense that EOPs would specifically prioritize alarm response, which is one way to read the last part of distractor A.

03/16/2012 1 Licensee presented modified Q, that still had similar issues. NRC recommended pathway forward using different alarm response criteria from NMP-007-OO1 sections on alarm response.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

69 H 2 X Y N/A B E K/A G2.4.46 1 Q=K/A, Q is at RO level.

2. Add second bullet between the two current bullets in current conditions that explicitly states that DG1A did in fact start when the button is pushed.

03/16/2012

1. Licensee modified the Q per NRC request, Q now appears SAT.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

42

VOGTLE Nuclear April 2012 ILO Exam I . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 70 H 2 x Y N/A M E K/A WEO3EK2.i

1. Q=KIA, Q is at RO level.

2. Cred. Dist: A is not plausible because the type of SI signal generated is not specified (i.e. perhaps make the choice a Containment Hi-i signal in all distractors it appears?)

03/16/2012

1. Licensee modified the Q per NRC request. Q now appears SAT.

04/1 6/20i 2 i . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

71 H 2 Y N K/A WEO4EA1 .3 1 QK/A, Q is NOT at RO level. Internal EOP transitions (beyond entrance criteria) are considered SRO only knowledge, therefore as written the second part of the Q is SRO only.

2. Cred. Dist: It is not plausible to transition to E-i (an optimal recovery procedure) if the LOCA outside containment is not isolated.

Q is U due to license level mismatch (SRO only Q on RO exam).

03/16/2012 1 Licensee modified Q per NRC request. However, RVLIS level plausibility was questioned during the review. NRC recommended testing on whether or not RCS pressure was the ONLY parameter that was used by ECA-i .2 to determine whether the leak was isolated or not. Licensee was going to develop this Q, as well as potential alternatives, and present a final version to the NRC following validation(s).

04/i 6/2012

1. Modified Q after validations questions knowledge of whether to use RCS pressure vs.

PRZR pressure as the parameter to verify response. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

C 1 L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back-I Q= SRO B/M/N U/E/S Explanation Focus Dist. Link junits ward K/A Only 72 H 2 X X Y N/A N E K/A WEO5EK2 1

1. Q=K/A, Q is RO level.

2. Stem focus: Q needs to be very clear as to what adequate means. For example, include the following statement in the stem: For the purposes of this question, adequate as defined by procedure 19231-C will NOT direct further adjustments to the RCS Feed Path or RCS Bleed path (or equivalent.)

03/16/2012 1 . Licensee modified the Q per NRC request. Q now appears SAT.

04/16/2012

. 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

73 H 3 Y B K/A WEO8EK3.4 1 Q=KIA, Q is a weak RO level match.

2. Cred. Dist: Pressurized thermal shock concerns to the S/G shell is not a plausible reason; the entire procedure is focused on brittle fracture concerns of the reactor vessel.

Potential fix to compare tensile vs. compressive stresses (GFES-type?)?

Q is U due to multiple non plausible distractors.

03/16/2012

1. Licensee modified the Q per NRC request. Q now appears SAT.

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

74 F 2 Y Y N S K/A WE1 1 EG2.4.6 1k

1. Q=K/A, Q is at RO level.

2. Q appears SAT at this time.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 1 I. J

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

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

&A WEI 5EG2. 1.32 1 Q=K/A borderline, Q is a weak RO level match.

2. Cred. Dist: Potential thermal shock to the Reactor Vessel is not plausible due to the excessively large amounts of water that it would take to make it a concern. Also, is it ever possible to have RED path due to containment flooding for Westinghouse plants?

is U due to multiple non-plausible distractors.

1 . Licensee presented modified Q, NRC gave further guidance and feedback to make he Q meet the standards required by the NUREG. Still a memory level question, Q now appears SAT.

1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I I I. J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

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

SRO Questions 76 H 2 K/A OO1AA2.03 Y N 1 Q=K/A. SRO-only is NOT met.

2. Cues: In Q stem, to state . . . SRO will directly enter procedure a tip-off cue that entry into E-O is correct.

3. Multiple correct answers. First part of the Q, SDM limits are power distribution and reactivity limits (subset) due to the imprecision of the phrase power distribution and reactivity limits. Was not able to verify the listed correct answer as correct, TS bases of LCO 3.1 .4 mentioned SDM, but did not mention power distribution and reactivity limits given a continuous unwarranted rod motion condition.

4. Q is not SRO-only level for TS bases because the information used from TS bases is not exclusive to the SRO position, and is not knowledge of TS bases that is used to analyze TS required actions and terminology

5. Second part of Q contains multiple non-plausible distractors. With a first-out annunciator given in the stem, all operators know that a reactor trip and entry into E-0 is required, so second part of distractors A and C are not credible.

Q is UNSAT per the above discussions.

03/14/2012 1 Modified Q presented in office review.

2. Minor changes made to Q statement, required to vs. will.

3. Q now has references (EAL chart), deleted statement that outward rod motion was not noticed, added statement that OATC continues to insert rods in MANUAL, added statement to not consider ED judgment as a basis for declaration.

04/16/2012 1 . Final submitted version appears SAT. MKM.

r 46 1 I. J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q#LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 77 H 2 x x Y N K/A 008AG2.1.19 1 Q=K/A. SRO-only is NOT met due to the references provided.

2. Cred. Dist.: Not plausible to give references that contain less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action statements, which are required to be known from memory.

Q is U due to multiple non-plausible distractors and not meeting SRO-only.

3/14/2012 1 Licensee presented Q as is without references. Q would not work without references because it would still be asking greater than one hour Tech Spec actions without a reference provided.

2. NRC provided recommendations to licensee personnel as to an alternative way to get I the Q to work; perhaps by using two pictures of IPC computer points. First half Q:

operable/inoperable; second half Q are all required TS actions complete (based on the given pictures)?

04/16/2012 1 Licensee presented revised Q in final submittal: is PORV block valve required to be de-energized/what is lift pressure for B PORV 456A.

2. Change slowing rising to slowly rising for third bullet under Current Conditions.

3. With modification of 2. above, Q now appears SAT for final submittal. MKM.

78 H 2 x Y Y N E A 012G2.2.40 I Q=K/A. Q=SRO only.

2. Stem focus: Place the second bulleted statement at the end of the given conditions, change it to read as follows: Time of discovery of the missed surveillance was 1 600 on 05-01-2012. Change Q statementto read as follows: Which one ofthe following correctly completes the following statement? Consider that a risk evaluation will NOT be performed. To delay declaring the LCO being NOT met, the surveillance is required to be performed satisfactorily no later than 03/14/2012 1 . Licensee modified the Q as requested, Q now appears SAT.

04/16/2012 i:

1. No changes from in-office review, Q is SAT for final submittal. MKM I *1 47 L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 79 H 2 x Y N K/A 015A2.05 1 Q=K/A. Q is NOT SRO only.

2. Stem focus: add statement All RCPs are NOT running, or equivalent.

3. Stem focus: slightly change statement to read: At the onset of core void formation, as void fraction rises, SR NI response will initially . Also change first part of Q distracters to rise vice rises to grammatically match the tense.

4. SRO only. Neither the first part nor the second part of this Q is SRO only because first part is systems knowledge, second part can be answered with knowledge of major on categories only, which is RO-level knowledge.

Q is U due to not meeting SRO-only.

1 Licensee presented a modified Q. However, Q still does not meet requirements of

.UREG.

2. NRC agreed to provide a new K/A for this Q.

79 H 3 x x Y I

K/A 014A2.04 (replacement K/A, entirely new Q) 1 Q=K/A, Q is NOT at SRO level because the operability determination does not require SRO level knowledge (see below).

2. We need to know Q history (i.e. bank/modified/new) and pedigree (if applicable), also distractor analysis needed.

3. Given the initial conditions with rods more than 12 steps divergent, rod group alignment limits are not metthis is RO level knowledge above the line. Because the Q stem clearly states that l&C determines that the rod control system is demanding motion properly but the rod will not move, it is clear that the rod is somehow mechanically stuck. This determination does not require any specific knowledge of TS bases and is something any operator could determine. For example, an ECCS pump breaker that trips obviously renders the pump mopthis is an operability determination, but not at the SRO level. Therefore, the second part of distractors A. and C. are non-plausible.

4. All verbage after OPERABLE or INOPERABLE is unnecessary and should be deleted.

Q is U due to multiple non-plausible distractors.

I 48 I L

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 79

[continuation of Q 79 wlrecommended replacementi:

Consider the following recommendation for replacement Q:

Initial Conditions:

-Time=0900.

-Unit I is at 60% power following a refueling outage.

-OATC is withdrawing rods when one DRPI is seen g moving with its group.

-OATC immediately stops withdrawing rods, and all rod motion stops.

-CBD Rod H-8 DRPI indicates 198 steps.

-CBD step counters indicate 212 steps.

Current Conditions:

-TimeO945.

-No rod motion has occurred since 0900.

-l&C has verified no faults on the DRPI system.

-I&C has verified that the rod lift coil for Control Rod H-8 is failed.

Which one of the following correctly completes the below statements?

Based on the utial conditions, at 0900 Control Rod H-8 was in accordance with the Bases of TS 3.1 .4, Rod Group Alignment Limits.

Based on the current conditions, at 0945 Control Rod H-8 was in accordance with the Bases of TS 3.1 .4, Rod Group Alignment Limits.

Rod H-8 Status Rod H-8 Status at 0900 at 0945 A. OPERABLE INOPERABLE B. INOPERABLE INOPERABLE C. OPERABLE OPERABLE D. INOPERABLE OPERABLE Ans: D 04/16/2012 1 Licensee accepted above NRC recommended Q w/no changes. Q appears SAT in final submittal. MKM.

I I ii

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N UIEIS Explanation Focus Dist. Link units ward K/A Only 80 H 2 X E E Y Y B E K/A 028A2.03 1 Q=K/A. Q=SRO only.

2. Stem Focus: have to re-word second part Q statement to ask what SS is required to do, not what the SS will do; e.g. the Shift Supervisor is required to direct the UO to FIRST perform section (or some other equivalent Q statement). Also must potentially add statement in stem that no other method of hydrogen concentration reduction has yet been performed (cf. CAUTION statement on p. 14 of 13130-1).

3. Cred DistJNP distracters: subset issue in that if the explosive limit has been exceeded, then the flammable limit has also been exceeded. Therefore, it would not be logical for any student to pick choices A or B, because either C or D must also be correct. One way to fix this issue is to test whether the explosive limit is or is not A exceeded

-i 03/14/2012 1 . Licensee modified Q as requested by NRC. Q is now SAT as written.

04/16/2012 1 . No additional changes needed to Q in final submittal, Q appears SAT. MKM.

81 F 2 X Y Y N E K/A 037AA2.10 1 Q=K/A. Q=SRO-only

2. Cred Dist: Why would any applicant choose second part of distracters A and C without any information regarding primary coolant activity levels? Recommend adding a primary coolant activity value to the stem to enhance the plausibility. Also ensure second part of Q is asking the basis of the specific limit, potentially add the specific TS bases section (3.4.17) for clarity?

03/14/2012 1 Licensee modified Q as requested by NRC. Q is now SAT as written.

04/16/2012

1. No additional changes needed to Q in final submittal, Q appears SAT. MKM.

50

{

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 82 F 2 Y Y N S K/A 039G2.1.28

1. Q=KIA. Q=SRO-only

) appears SAT as written.

I 04/16/2012 1 . No additional changes needed to Q in final submittal, Q appears SAT. MKM.

83 H 2 x Y N K/A 054AG2.1.7 1 QKA. Q is NOT SRO only

2. Stem focus: must also state something like no other annunciators lit in stem to allow applicant to differentiate what is going on.

3. SRO-only. Applicant is essentially diagnosing the cause of the annunciators and letermining the procedure to enter based on the diagnosis, which is RO-level

nowledge.

) is U due to not meeting SRO-only.

1 . Licensee presented new Q.

,. Modified this Q to change statements to enhance plausibility of raising MFPT speed n manual, SRO only met with first part Q on LCO 3.3.2. function of MFPT trip causing

.I VV actuation met or not met (MFPT5 need to be pumping forward for the LCO to be net), basis knowledge.

3. Q potentially SAT as written.

04/16/2012 1 E change to final submittal Q: change second part of distracters B. and D. to read take manual control of MFPT B speed as necessary to restore NR level between 60%

and 70%.

2. Final submittal Q should be SAT with above change. MKM.

I 51

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 84 H 3 x Y N 055EA2.01

• does not meet K/A on the SRO-only level. Q is SRO-only for procedure selection.

2. Stem focus: consider adding bulletto state: operating crew is atthe step to select the recovery procedure. Add more detail to bullet with BIT valves, maybe say HV O1A and HV-8801B (BIT DISCH ISOLATION) valves are BOTH closed. Modify I ,J part of Q statement to ask required procedure transition, not what SS will do:

based on the current conditions, the 55 is required to transition to We need to ensure the conditions given are not simply determining whether an SI is required or not (which could potentially also be RO-level knowledge).

3. K/A match: valve failure positions are RO-level knowledge, therefore the K/A is not met on the SRO-only level.

Q is U due to not meeting K/A on the SRO level.

03/14/2012 1 Licensee presented modified Q based on NRC comments. Modified Q statement was changed by NRC to ensure there were no partially correct answers (to put the SS at the specific point in the procedure where instrument air is being checked.).

2. Independent review of K/A match at the SRO level recommended before calling Q potentially SAT.

03/15/2012

1. Based on independent review of K/A match at the SRO level, further modified the Q to ensure SRO-only level was met based on procedural selection of placing safety-grade charging in service.

04/16/2012

1. No additional changes needed to Q in final submittal, Q appears SAT. MKM.

r 52 II L

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD 8.

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back-Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 85 H 3 X Y Y M K/A 058AG2.4.9 1 Q=K/A. Q is SRO-only

2. Stem focus: Better way to organize Q statement: Based on the current conditions, which one of the following correctly completes the following statement? Per 18034-1, the letdown orifice isolation valves Second part Q must ask what LCO(s) is/are required to be entered, not what 55 will do. For example: the Shift Supervisor is required to enter LCO 3.7.5, Auxiliary Feedwater,

3. Partial: in accordance with the rules for TS entry, wouldnt the 55 be required to enter both conditions A and B? i.e. given the conditions in the stem, one steam supply valve could be mop (cond A) and a train is also mop (cond B). Answer/Distractor analysis provided for this Q is confusing.

4. Potential fix to test whether enter LCO A and B, or A only?

Q is U due to potential for no correct answer as currently written, need to discuss with ir. licensee operability issues above. Rating of this Q can change based on discussions.

03/14/2012 1 Discussed this Q with licensee personnel in the office. To remove doubt over potentially two correct answers, change second part of the Q to only test whether condition B is required to be entered yes/no.

2. Q considered E now.

04/16/2012 1 Potentially need to modify second part of Q statement due to cues/teaching in the stemperhaps use the language out of the TS statement itself? Need to discuss with MAB.

2. Final submittal Q should be o.k. with the above change made. MKM.

86 H 3 Y Y B S K/A 063A2.01 III 1 Q=K/A. Q=SRO only L 2. Provided answer/distractor analysis does not support the second part of the Q. Need to update to match the Q.

04/16/2012 1 Final submittal Q answer/distractor analysis still needs to be updated. Will provide feedback w/licensee. Otherwise, Q on final submittal appears SAT. MKM.

f I L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 87 F 2 Y Y N K/A 071G2.1.23 1 .Q=K/A. Q=SRO only

2. Cred. Dist: since Q is asking >1 hr actions, we would need to provide a reference for Q, which makes the Q as currently worded a direct look-up and the second parts of

3. And D. non plausible. Also as currently worded, analysis of B. And D. would not occur until the next day (after the release).

is U due to multiple non-plausible distractors.

03/14/2012 1 Licensee provided two different modifications to the Q. Neither was completely acceptable. NRC modified Q statement and second part of all distractors to achieve a Q hat would meet NUREG requirements, by testing whether additional actions were required in the ODCM vs. timing requirements for samples, etc.

Wi 6/2012 1 Answer/distractor analysis needs to be updated for this Q to reflect final version of Q.

No additional changes needed to actual Q in final submittal, Q appears SAT. MKM.

88 H 4 x Y Y N K/A076A2.02 1 .Q=K/A. Q=SRO only.

2. Stem focus: Must ask required actions; is entry into INFO LCOs ever required?

. Cred dist: D is not plausible. With all NSCW pumps in both trains in PTL, how is hat NOT LCO 3.0.3? C is also not plausible because why would the operators decide 0 PTL all train A NSCW pumps when the LO PRESS condition has cleared?

03/14/2012 I Licensee provided modified Q for discussion. NRC provided recommendations for fixing the Q, Q should be now SAT. First part: is/is not required to place all NSCW pumps in PTL; second part: is/is not required to immediately enter LCO 3.0.3?

2. Licensee will table the Q and ensure that the Q is operationally valid and acceptable or lLO applicant level.

04/16/2012 I Modified Q as above and submitted with final submittal appears SAT. However, answer/distractor analysis lists two correct answersverify w/licensee error will be corrected. Otherwise ready to appear on written exam. MKM.

I I

L J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back-Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 89 H 2 x Y K/A 077AA2.08 1 Q=KIA. Q is NOT SRO only, because it tests on whether applicant is required to trip Rx or not. Criteria to trip the Reactor are essentially entry conditions into E-O and these conditions are RO-level knowledge.

2. Stem focus: Recommended changes to the Q statement, need to test requirements and be clear that voltages were constant during period under review:

Based on the current conditions, which one of the following correctly completes the following statement?

If bus voltages were a steady 3595V, the Normal Incoming Breakers would have tripped after and the Shift Supervisor is required to .

Q is U due to not meeting SRO-only.

03/14/2012 I Licensee presented argument that due to Rx trip requirement being buried in the OP that Rx trip requirements in this case would not be normal entry in E-0. NRC

4 recommended to licensee in second part of Q whether or not parallel procedure performance (i.e. E-0 and AOP) orjust E-0 was required or not. Licensee accepted NRC recommendation.

I 04/16/2012

1. Q as modified during in-office review now appears SAT w/no additional changes needed as reflected in the final submittal. MKM.

90 F 2 Y K/A 103A2.02

1. Q=K/A. Q is SRO only.

2. Q appears SAT at this time.

I 04/16/2012

1. Q as reflected in the final submittal appears SAT. MKM.

I 1 IL J

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 91 F 3 Y Y N S G2.1.38 1 Q=K/A Q=SRO only 2 First part Q statement consider asking is required to instead of has to 3 Q appears SAT at this time 04/16/2012 I . Q as shown in the final submittal appears SAT. MKM.

92 F 2 X Y Y M E C 2.2.13 1 Q=K/A, Q=SRO-only

2. Stem focus: Should add responsible for the work being performed after Department Supervisor.

03/14/2012 1 . Licensee modified Q as requested by NRC. Q now appears SAT.

04/16/2012 1 . Q as shown in the final submittal appears SAT. MKM.

93 F 2 X Y Y N E G2.2.18 1 Q=K/A, Q=SRO only

2. Stem focus. Second part Q worded a little awkward. Consider the following: If neither CCP is restored to operable status, the unit is required to be in MODE 4 not later than after CCP A was declared inoperable.

03/14/2012 1 Licensee modified Q as requested by NRC. Also deleted extra information in stem concerning Mode 3 conditions. Q now appears SAT.

04/16/2012 1 . Q as shown in the final submittal appears SAT. MKM.

56

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 94 F 2 Y Y M K/A G2.3.12 1 Q=K/A, Q=SRO only.

2. Distractor C is not plausible, it is common sense that declared pregnant females will ot be assigned to receive emergency doses. We also need to specify the gender of the other operators. Distractor A is also not plausible when compared with DA operator is both younger and has more dose than D.

is U due to multiple non plausible distractors.

03/14/2012 1 Licensee proposed modified Q. NRC re-proposed a better three-column format with volunteer status required or not, then modified it into a 2x2 Q. Q now appears SAT.

95 F 3 x Y Y N E KIAG23.6 I Q=K/A, Q=SRO only

2. When would ops release a tank without Shift Manager authorization? Potential multiple correct answers? Recommend modifying second part Q statement as follows:

In addition to the 55/555, the Chemistry Manager the simultaneous release.

Second part distracters would be is required to approve and is NOT required to approve.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

96 F 2 Y Y N S

G2.4.12 i Q=A, Q=SRO only.

I nd

2. Need to ensure 2 pa of B and D. read Site Are Emergency is otherwise SAT.

I I . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I L

VOGTLE Nuclear April 2012 ILO Exam 1 . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 97 F 2 x Y Y M E K/A G2.4.37 1 Q=K/A, Q=SRO only

2. Cred Dist: Distractor B is not plausible as written. Consider the following recommendation: Recommending protective actions to offsite agencies, after the initial notifications have been made and the TSC is fully staffed.

03/14/2012 1 . Licensee made modifications to Q as recommended by NRC.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

98 H 2 X X Y Y M E K/A WEO5EA2.2

1. Q=K/A, Q=SRO only.

2. Stem focus: Must add RCS pressure value for bleed and feed determination (i.e.

bullet with RCS pressure = 2280 psig or equivalent).

3. Cred dist: Potential subset issue with A. and B; if B is true A is also true. Also C is not plausible based on the given conditions.

4. Potential fix? Change Q to make either A or B the correct answer?

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I. 58

VOGTLE Nuclear April 2012 ILO Exam

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

Q# LOK 8.

LOD ir T (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back-f Q= SRO B/M/N U/E/S Explanation Focus Dist. Link! units ward K/AOnly 99 H 3 x x Y Y N E K/A WE06EG2.4. 18

1. Q=K/A, Q is SRO only

2. Cred Dist.: First part of C. and D. unclear wording of Number 1 seal requirements, and it is also not clear when the RCPs would be stopped under those conditions.

For the first part of the Q, test on whether it is required to stop the RCPs or NOT.

3. Stem focus: Change Regarding the SG depressurization... to During the SG depressurization... for additional clarity.

03/14/2012

1. Licensee made adjustments to Q statement as requested by NRC.

04/16/2012

1. Q as shown in final submittal appears SAT w/no other changes needed. MKM.

I 1 J

VOGTLE Nuclear April 2012 ILO Exam I . 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other Q# LOK LOD ETE 8.

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 100 H 4 X X Y Y N E K/A WE1 OEG2.4.47 1 Q=K/A, Q is SRO only

2. Based on the information in the Q, correct answer to the Q is A because step 23 RNO would first require repressurization before a transition to ES-O.3. Also try to keep Q on one page if at all possible.

Consider re-write of the Q as follows:

Current conditions:

-Cooldown per 19002-C, ES-O.2 Natural Circulation Cooldown is in progress.

-The SS is at the step in I 9002-C to check that a steam void in Reactor Vessel does NOT exist.

-The following data is noted:

lime RVLIS Upper Range PRZR Level 10:00 100 25 10:15 100 25 10:30 98 28 10:45 84 58 Based on the current conditions, the NEXT action required by 19002-C is to AND The MAXIMUM cooldown rate allowed for the procedure to be implemented is A. (1) repressurize RCS within limits ofTS LCO 3.4.3 to collapse potential voids in system and continue cooldown in 19002-C.

(2) 50 F/hr B. (1) repressurize RCS within limits ofTS LCO 3.4.3 to collapse potential voids in system and continue cooldown in 1 9002-C.

(2) 100 F/hr C. (1) GO TO 19003-C, ES-0.3 Natural Circulation Cooldown With Void in Vessel (With RVLIS).

(2) 50 F/hr D. (1) GO TO 19003-C, ES-0.3 Natural Circulation Cooldown With Void in Vessel (With RVLIS).

(2) 1 00 F/hr 03/14/2012 1 . Licensee made adjustments to Q as recommended by NRC. Q now appears SAT.

04/16/2012 1 . Q as shown in final submittal appears SAT w/no other changes needed. MKM.

60

{

VOGTLE Nuclear April 2012 ILO Exam

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 61 J

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: 110C7TL E Date of Exam: Exam Level: RO L SRO L Initials Item Description a b c 1 . Clean answer sheets copied before grading )%-f71 /4 120

2. Answer key changes and question deletions justified ,t/)

and_documented

3. Applicants scores checked for addition errors (reviewers spot check > 25% of examinations) 4ø?

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail f-W

5. All other failing examinations checked to ensure that grades are justified *T

6. Performance on missed questions checked for training i deficiencies and wording problems; evaluate validity A of questions missed_by_half or more of the_applicants Printed Name/Signature Date

a. Grader llcHiEt 2

f k

b. Facility Reviewer(*)

49

c. NRC Chief Examiner (*) 4 tA . L/z

d. NRC Supervisor (*) A1L&LLt T. \VLJA4J/ -

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