ML13156A089

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Initial Exam 2013-301 Final Administrative Documents
ML13156A089
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 06/05/2013
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
Download: ML13156A089 (79)
v • d • e


Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Turkey Point 2013-301 Date of Examination: 03/04/2013 Examinations Developed lit NRC by: Written I Operating Test Written / Operating Test Ta t Chief Date* Task Description (Reference) Examiners Initials

-180 1. Examination administration date confirmed (Cia; C.2.a and b) 6/26/2012

-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) 6/26/2012

-120 3. Facility contact briefed on security and other requirements (C.2.c) 9/18/2012

-120 4. Corporate_notification_letter sent_(C.2.d)

[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] 01/18/2013

{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES 301-1, ES-301-2, ES-301-5, ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as 12/17/2012 applicable (C.1.e and f; C.3.d)

{-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility 12/24/2012 licensee (C.2.h; C.3.e)}

{-45} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301 -3, ES-301 -4, 01/18/2013 ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202) 02/04/2012

-14 10. Final license applications due and Form ES-201-4 prepared (CII; C.2.i; ES- 2/1812013 202)

-14 11. Examination approved by NRC supervisor for facility licensee review N/A (C.2.h;_C.3.f)_(Licensee_prepared_examination).

-14 12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g) 2/18/2013

-7 13. Written examinations and operating tests approved by NRC supervisor 2/25/2013 (C.2.i; C.3.h)

-7 14. Final applications reviewed; I or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; 2/25/2013 Attachment 4;_ES-202,_C.2.e;_ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee 2/25/2013 (C. 3. k)

-7 16. Approved scenarios, job performance measures, and questions distributed to 2/25/2013 NRC examiners (C.3.i)

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

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

ES-201 Examination Outline Quality Checklist Form ES-201-2 (Rev_021813)

Facility: Turkey Point Date of Examination: 3/4/13 Initials Item Task DescrIption i 1 a. Verify that the outline(s) fit(s) the appropriate model per ES-401

b. Assess whether the outline was systematically and randomly prepared in accordance W with Section 0.1 of ES-401 and whether all K/A categories are appropriately sampled.
c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. -

T d. Assess whether the justifications for deselected or rejected KJA statements are T appropriate.

E M -

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

I b. Assess whether there are enough scenario sets (and spares) to test the projected M number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; and ensure that each applicant U can be tested using at least one new or significantly modified scenario, that no L scenarios are duplicated from the applicants audit test(s), and scenarios will not be 5 IA)

A repeated on subsequent days.

T c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and 0

R quantitative criteria specified on Form ES-301-4 and described in Appendix 0.

J j3

3. a. Verify that systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks, W distributed among the safety functions as specified on the form

.- (2) task repetition from the last two NRC examinations is within the limits specified on the form, (3)* no tasks are duplicated from the applicants audit test(s)

(4) the number of alternate path, low-power, emergency and RCA tasks meet the criteria on the form.

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

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.  !)
a. Assess whether plant-specific priorities (Including PRA and IPE insights) are covered in -, f the appropriate exam section. -Y
b. Assess whether the 1 OCFR 55.41/43 and 55.45 sampling Is appropriate.
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
d. Check for duplication and overlap among exam sections.
e. Check the entire exam for balance of coverage. ..4., -
f. Assess whether the exam fits the appropriate job level (RO or SRO).

Printed Name! Signature Date

a. Author David Lazarony&Vestern Technical Services, Inc.

fr4 2/I 8/13

b. Facility Reviewer (j .t) A

,1

c. NRC Chief Examiner (#) )J. )j) af2zf13
d. NRC Supervisor /(ALf4L-?-

NOTE: # Independent NRC reviewer initial items in Column c, chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines NUREG-1 021, Revision 9

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

1. Pre-Examination lI3L, 42 jL I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of t.zo,3as 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 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 I RESPONSIBILITY SIGNATU (1) DATE SIGNATURE (2) DATE NOTE 1.

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NOTES:

ES-201, Page 27 of 28

S2O E,camnation SeczrEtrAreement Form ES-2014

1. Pre.aniTnetior, a, fy%jC t ow$ede thati hme acqukedspac)elfzetl outilie NRC flcenslng em ns-schededfor1b wee) of -zt, s of the date offflysiialuze. Iree that will notknowng1y divuIgeany ln1orman aboutthes nabonstoanypersons wio have notban autho)zcibythe NRC chief emlner. I undorstend that lam not ins ja.gvalueia. o prclde performazca $aedba ctotboseiapplkrsnls solieduledlo bministe,etf these Ilnr aons1mmsdata TcompIedan of ecamlnaon admTnstn, ptpeclcafly qotad h wamsuthodzad b)rtbe NRC

{e actaig bporomunrisacceptle if the indlvtdoal does no se4ectiha ntertor prode tbectorindirect feedback). Fwthermore. I amvan of the phyacai sc2iriLy m swes and reqz eruenrs (as documented I thefacility fl enseespfocedwes) and unddthat?olatI ofthecondTtIozs&th1s a meet may resosoncelheion of the examlnattoflsandfor en anfomemanteofon againatmo or the fa IIcensee I wilt Inwiediately roportta rrnianagementcr the NRC chief examlnerany Irdcrsugg tatetrtinaon Sectaity rnayfmve been compromised, To the b lModge I did notdiuIge to any utiaut11onze persons anyl ifoorndorz concsm the NRC licensIng xaonirfstareci ducng the wee!c(s) of______ Fsomtha data Ihati entered into this se coeroentuntli tie complalforrot aninalon admtr alfon, I did not Tnsuuc4. evaluate, or provide per cafeedbacicto those applicants who were administered these Ticecumg mmirtafions, ceptasspadilicafly noted below and outhnrized by the NC RtNTED NAME JO1ThE/RESPONSlUJW SI NATURE Cfl DATE SIGNATURE (2) DATE NOTE I 0< I4t. _- I 4!;w z 4.(5e& tt. ,tf4IJAL diVlW _

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NOTES:

ESGt, lage 27 of 25

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42a EmtoecuyAgromrnit Form E-2Oi4

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!*% 1 jc, 3 taowd9ethatT have acquedspeda!Ized deaboutthe1RC Ucenstn e,otrflTnaijonssthed4jledforlhe Wee) of as aTihe date of mysigrture I agree tbaU will notknowlngly C 2e any 1nfonpan u!outUesemtnabons xypersors wfio have enauthod2edtythe NflQ emer. undoreland that lemnot ns vatu. arpde performance 1Iio ffcet enihaons*omihisdate ucuilcomptean of am!nafanathitnsatlon, e opt as specWcslty ncwdb awand.mIlilodzed by the NRC actilig os urbcohcpereluiorMmuntcrisacceptle ftbe tdvtdual does notseloctihe arün contern or provide dlieccrincfirect feedback). Furt more, I amawam ofthe pheicel security meeswes and reulremenrs (as dcume?ited iti e faclllty flcensees procedures) and undiofthecndilOrsofthla acre ttcsncelludon o sand/or an anfartemanrscfon aainstme or thcerLsee. iwlil idmedIate{y roportla facbyrnanagementar the NRC ohtef ecamInsrany may have been compzarntsed, To the bestofmyXnowlodge. did nctga to any unauthonzad petsonsa jInfonnalior cencoratng the NRC ricenslng oxen aliens admintstare ducng me wae&Cs) & . Forntlw dote ihatlenrerad inteUo timctViecornjeono1 o naflon adminhasifon. 1 dId nor Insut evaluate, or provide pockiu ce(eodbacccto thas oppl nrs who va?Ie adrnTnstanrd theeelcensin e,m?na1ions, ccep1asspecTtlrafly noted below and heiaed by Vie NRC

?RttTTED NAME JOB TraE/RESPONSIB1LFTY NA7UE (l DATE SIQNATUR (2) DATE NOTE p2- -

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5L7 Y ES-201 Examination Security Agreement Form ES-201-3

1. Pre.Examlnetiori t ,S I acicriowtsilge that have acquired specialized knowledge ahout the NFC licensing examinations scheduled for the week(s) of _as Of the date of my signature, agree that I will not knowingly divulga any irilormativn about these examlnationsto any persons who have not bans authorized byihe NRC chief examiner. understand that am not to Instruct, evaluate, or provide perthrrnsnce feedback tottiose applicants scheduled to be administosed these licensing examinations from this date until completion of examination administration, except as specifically noted below anti authorized by the NRC (e.g.. acting as a sistulator booth openttor or communicator is acceptable if the individual does riot selactths training content or ptovide direct or indirect feedback). Furthrmora. lam aware of the physical security measures and requirements (as documented in the facility rcensees procedures) and understand that violation of the conditions of this agreement may result In cancellation of the examinations and/or an enforcement action against ma Dr the facility licensee. I will Immediately report t facility management or the NRC chief examiner any indictians or suggestions that examination security may have been compromised.

a PpgtEicaminstlon 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? entered intO thia security agreement until the completion of examination administration, I did riOt insmjct, evaluate, or provide performance faedbackto lhosa applicants who were administered these licensing examinations, except as SpGdfitally noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBIUri S,)llAThRE (1) DATE SiGNATURE (2) DATE NOTE 7.

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ES-201, Page 27 of 28

\A+/- 3 ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination L/ ,

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 knowledge, I cud not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 3l4-3fii From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE 1.cR9,E ItoyØ1b(

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cf 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 Ad/Qi as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations any persons to 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 knowedge I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 3.4 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 administered n, I did not these licensing examinations, except as specifically noted below and authorized by the NRC.

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NOTES: /___

ES-201, Page 27 of 28

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

1. Pre-Examination iiick I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of fl.,. U .rt 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 licenseWs procedures) and understand that violation of the conditions of this agreement may result n 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 lentered 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 iiVSe!1 JOPL.tv TV F4 /pp j /7_ 13 I/.J ( /i NOTES:

ES-201, Page 27 of 28

ETA) L- /-/ AJj ES-20l xaminati n Security Agreement Form ES-201-3

1. Pre-Exarnination I acknowledge that I have acquired speclalizd knowledge about /c-k tl23 the IRC licensing examinations scheduled for the week(s) of of my signature. I agree that I will riot knowirig1y divulge any inform n- U ras of the date NRC chief examiner. I understand that! am not to instruct, evalua at n about these examinations to any persons who have not beenauthoriZed by the te, r provide performance feedback to those applicants scheduled to these licensing examinations from this date until completion f be administered exami ation administration, except as specifically noted below and author (e.g., acting as a simulator booth operator oricornmunioator is accept ized by the NRC feedback). Furthermore, I am aware of the jhysical security measu ble if the indMdual does not select the training content or provide direct or indirect i s and requirements (as documented in the facility licensees proced understand that violation of the conditions ofithis agreement may res ures) and the facility licensee. I wlil immediately reporto facility manag It in cancellation of the examinations and/or an enforcement action agains ement t me or*

may have been compromisecL r the NRC.chief examiner any indications or suggestions that examination securit y

2. Post-Examination To the best of my knowledge, I did not divulge to any unauth orized p rsoris any information concerning the NRC licensing examinations during the week(s) cf . From the date that I entered into th $ security agreement until administered Instruct, evaluate, or provide performance fedback to those the completion of examination administration, I did not*

applican who were administered these licensing examinations, except below and authorized by the NRC. as specifically noted PRINTED NAIvIE JOB TIUE RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE:

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ES- 01, Page 27 of 28

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

1. Pre-Examination fr1c.k LU2P3 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of n. I re 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 beenauthorized 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 knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of sf-3/s.. 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 / RESPONSIBILITh SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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ES-201, Page 27 of 28

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-/3 cJQ 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 3/412013 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 knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 3/4/2013 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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ES-201, Page 27 of 28

ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (Rev_021813)

Facility: Turkey Point Date of Examination: 314113 Examination Level: RO Operating Test Number: L-13-1 Administrative Topic Type Code* Describe activity to be performed (see_Note) 2.1.7 (4.4) Ability to evaluate plant performance and Conduct of Operations make operational judgments based on operating characteristics, reactor behavior, M, R and instrument interpretation.

JPM: Calculate QPTR 2.1.37 (4.3) Knowledge of procedures, guidelines, or Conduct of Operations limitations associated with reactivity M, R management.

JPM: Verify Adequate Shutdown Margin 2.2.40 (3.4) Ability to apply Technical Specifications for Equipment Control a system.

D, R JPM: Perform Accident Monitoring Instrument Channel Checks 2.3.12 (3.2) Knowledge of radiological safety principles Radiation Control pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked P.M. R high-radiation areas, aligning filters, etc.

JPM: Evaluate conditions for restart of Refueling Preshuffle in the spent fuel pit.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (4)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank (> 1) (3)

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

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (Rev_021813) ty: Turkey Point Date of Examination: 3/4/13 Examination Level: SRO Operating Test Number: L-13-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.7 (4.7) Ability to evaluate plant performance and Conduct of Operations make operational judgments based on operating characteristics, reactor behavior, M, R and instrument interpretation.

JPM: Calculate QPTR 2.1.23 (4.4) Ability to perform specific system and Conduct of Operations integrated plant procedures during all Mode of plant operations.

N, R JPM: Determine Contingency Actions for a Loss of RHR in Mode 5 and the loops are not available.

2.2.40 (4.7) Ability to apply Technical Specifications for Equipment Control a system.

D,R JPM: Perform Accident Monitoring Instrument Channel Checks 2.3.12 (3.7) Knowledge of radiological safety principles Radiation Control pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked P, M, R high-radiation areas, aligning filters, etc.

JPM: Evaluate conditions for restart of Refueling Preshufflein_the_spent_fuel_pit.

2.4.4 1 (4.6) Knowledge of the emergency action level Emergency thresholds and classifications.

Plan/Procedures M, R IJPtVL Classify the Event and Issue PARs NOTE: All items (5 total) are required for SROs. RD applicants require only 4 items unless they are retaking only the administrative tocs, when Sare required.

  • Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5)

. (D)irect from bank ( 3 for ROs; 4 for SROs & RD retakes) (1)

(N)ew or (M)odified from bank (> 1) (4)

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

NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV 021813)

Facility: Turkey Point Date of Examination: 3/4/2013 Exam Level (circle one): Reactor Operator Operating Test No.: L-13-1 Control Room Systems@ (8 for RO; 7 for SRO-i; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function A. 001 Control Rod Drive System (001 A4.14(3.013.4)]

S,M,A 1 Respond to Control Bank D Demanded Past 230 Steps B. APE 028 PZR Level Control Malfunction [028 AA1 .05(2.7/2.8)]

S,N,A 2 Place Excess Letdown in Service C. 010 Pressurizer Pressure Control System [010 A2.03(4.1/4.2)]

SM,A 3 Respond to PORV Leakage D. 005 Residual Heat Removal System [005 A4,01(3,6/3,4)]

SD,L 4P Place RHR in service E. 061 Auxiliary Feedwater System [061 A2.01(2,9/2.8)]

N,S 4S Shutdown of AFW Pump(s) from Emergency Plant Operation F. 064 Emergency Diesel Generators [064 A4.01(4.0/4.3)]

S,D,A,EN 6 Perform EDG Normal Start Test G. 012 Reactor Protection System [012 A4.04 (3.3/3.3))

. S,D 7 Trip Bistables for LT-474 Failure H. 007 PRT/Quench Tank System [007 A1.03 (3.3/3.3))

S,N 5 Reduce PRT Temperature In-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)

I. APE 068 Control Room Evacuation [068 AAI.02 (4.3/4.5)]

D,E 8 Locally Align AFW Flow for Safe Shutdown J. 062 AC Electrical Distribution System [062 A4.04 (2.6/2.7)]

N,E 6 Restore Power to 120V Vital Instrument Bus K. 068 Liquid Radwaste System [068 A4.02 (3.2/3.1)]

D,R 9 Perform a Liquid Release from Recycle Monitor Tank A NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV 021 813>

Faculty: Turkey Point Date of Examination: 3/4/2013 Exam Level (circle one): Senior Reactor Operator (I) Operating Test No.: L-13-1 Control Room Systems@ (8 for RO 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Codes Safety Function A. 001 Control Rod Drive System [001 A4.14(3.0/3.4)]

SM,A 1 Respond to Control Bank D Demanded Past 230 Steps B. APE 028 PZR Level Control Malfunction [028 AA1.05(2.712.8)]

SN,A 2 Place Excess Letdown in Service C. 010 Pressurizer Pressure Control System (010 A2.03(4.1/4.2)]

S,M,A 3 Respond to PORV Leakage D. 005 Residual Heat Removal System [005 A4.01 (3.6/3.4)]

S,D,L 4P Place RHR in service E. 061 Auxiliary Feedwater System [061 A2.01(2.9/2.8)]

N,S 4S Shutdown of AFW Pump(s) from Emergency Plant Operation F. 064 Emergency Diesel Generators [064 A4.D1 (4.014.3)]

SD,AEN 6 Perform EDG Normal Start Test G. 012 Reactor Protection System [012 A4.04 (3.3/3.3)]

S,D 7 Trip Bistables for LT-.474 Failure H. NA In-Plant Systems© (3for RO; 3 for SRO-l; 3 or 2 for SRO-U)

I. APE 068 Control Room Evacuation [068 AA1.02 (4.3/4.5)]

D,E 8 Locally Align AFW Flow for Safe Shutdown J. 062 AC Electrical Distribution System [062 A4.04 (2.6/2.7)]

N,E 6 Restore Power to 120V Vital Instrument Bus K. 068 Liquid Radwaste System [068 A4.02 (3.2/3.1)]

D,R 9 Perform a Liquid Release from Recycle Monitor Tank A NUREG-1 021, Revision 9

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 DRAFT (REV_021813)

Facility: Turkey Point Date of Examination: 3/4/2013 Exam Level (circle one): Senior Reactor Operator (U> Operating Test No.: L-13-1 Control Room Systems@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Function A. NA B. APE 028 PZR Level Control Malfunction [028 AA1.05(2.7/2.8>]

SN,A 2 Place Excess Letdown in Service C. NA D. 005 Residual Heat Removal System [005 A4.01(3.613.4)]

SD,L 4P Place RHR in service E. NA F. 064 Emergency Diesel Generators [064 A4.01(4014.3)]

SD,AEN 6 Perform EDG Normal Start Test G. NA HNA In-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)

I. APE 068 Control Room Evacuation [068 AA1.02 (4.314.5)]

D,E 8 Locally Align AFW Flow for Safe Shutdown J. NA K. 068 Liquid Radwaste System [068 A4.02 (3.2/3.1)]

D,R 9 Perform a Liquid Release from Recycle Monitor Tank A

@ 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.

j NUREG-1 021, Revision 9

ES-301 Operating Test Quality Checklist Form ES-301-3 (Rev_021 813)

Facility: Turkey Point Date of 3/4)13 Operating Test Number: L-13-1 Examination:

Initials

1. GENERAL CRITERIA a b*
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). 1

b. There is no day-to-day repetition between this and other operating tests to be administered 41/

during this examination.

c. The operating test shall not duplicate items from the applicants audit test(s) (see Section p L

/

1 D.1.a). i3L

d. Overlap with the written examination and between different parts of the operating test is within acceptable limits. (4/
e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.
2. WALK-THROUGH CRITERIA - -
a. Each JPM includes the following, as applicable:

initial conditions initiating cues references and tools, including associated procedures reasonable and validated time limits (average time allowed for completion) and specific C,6 designation if deemed to be time-critical by the facility licensee I operationally important specific performance criteria that include:

- detailed expected actions with exact criteria and nomenclature

- system response and other examiner cues

- statements describing important observations to be made by the applicant

- criteria for successful completion of the task

- identification of critical steps and their associated performance standards

- restrictions on the sequence of steps, if applicable

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

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

j/

Printed Name! Signature Date IMt1

a. Author David Lazarony, Western Technicalervices, Inc. 2/18/13
b. Facility Reviewer (*) EAJJ ,fj JL 211l3 1

Z

c. NRC Chief Examiner (#) fJii.
d. NRC Supervisor 4 P/

JJJLco4J.T.WIWJ)1 1 2/22,13 NOTE:

  • The facility signature is not applicable for NRC-deve oped tests.
  1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

NUREG-1 021, Revision 9

ES-301 Simulator Scenario Quality Checkilsi Form ES-301-4 (Rev 021813)

Facility: Turkey Point Date of Exam: 3/4/13 Scenario Numbers: 1 24 Operating Test L-13-1 No.:

QUALITATIVE ATTRIBUTES Initials a b*lc#

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 a the malfunction(s) that are entered to initiate the event A

a the symptoms/cues that will be visible to the crew (lt.

  • the expected operator actions (by shift position)
  • the event termination point (if applicable)

J

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without j.j a credible preceding incident such as a seismic event.
5. The events are valid with regard to physics and thermodynamics. i _
6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete . ij.

evaluation resuLts commensurate with the scenario objectives.

7. If time compression techniques are used, the scenario summary clearly so indicates. Operators js have sufficient time to carry out expected activities without undue time constraints, fl
8. The simulator modeling is not altered. I _
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 J fidelity is maintained while running the planned scenarios. 1 ç J-4
10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section 0,5 of ES-301. /r ,
11. All individual operator competencies can be evaluated, as verified using Form ES-301 -8 (submit the 4.

L form along with the simulator scenarios).

4

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
13. The level of difficulty is appropriate to support licensing decisions for each crew position.

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

Scen Scen Scen 1 2 4

1. Total malfunctions (5-8) 7 7 10
2. Malfunctions after EOP entry (1-2) 1 1 3
3. Abnormal events (2-4) 4
4. Major transients (1-2) 4 3

Ø,,

5. EOPs entered/requiring substantive actions (1-2) 1 1 2 4 1 1 1 j,
6. EOP contingencies requiring substantive actions (0-2) 1 0 3
7. Critical taka (2-3) 2 2 3 NUREG-1 021, Revision 9

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 (Rev 021813)

Facility: Turkey Point Date of Exam: 3/4113 Scenario Numbers: 5 Operating Test L-1 3-1 No.:

QUALITATIVE ATTRIBUTES Initials a b*

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

  • 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. *. if
5. The events are valid with regard to physics and thermodynamics, j-
6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives. 4 S
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. 4.*-
8. The simulator modeling is not altered.

I:: -

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. 0
10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301. 4r _
11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios). r 4
12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
13. The level of difficulty is appropriate to support licensing decisions for each crew position.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes i4r L -

Scen 5

1. Total malfunctions (5-8) 5
2. Malfunctions after EOP entry (1-2) 0 3.

4.

Abnormal events (2-4)

Major transients (1-2)

L. .

1

5. EOPs entered/requiring substantive actions (1-2) ij +4
6. EOP contingencies requiring substantive actions (0-2) 2 j
7. Critical tasks (2-3) 1 L..

NUREG-1021, Revision 9

ES-301 Transient and Event Checklist Form ES-3O15 (Revj2181 3)

Facility: Turkey Point Date of Exam: 3/4113 Operating Test No.: L-13-1 A E Scenarios P V L-13-11 L13-1-2 L-13-1-4 L-13-1-5 T M P E (Spare> 0 L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y T P S A B S A B TK B S A B R I U E R T 0 R T 0 RT 0 R T 0 NOR4E1__

1,2. 1,2 8 4 4 2 SROU-1 I/C 3,6 3,4 MAJ 6 2 2 2 1 5

TS 2.3 1,4 1 4 0 2 2 R412 1 11 10 4 4 2 SROI-1 I/C 1,2 1,3 2,3.

4,5 3

MAJ 6 5 6.6 4 2 2 1 2,3 3A 4 Q 2 TS 2 RX 4 1 ii 0 NOR 1 1 1 1 3 1,2, 2.3, 10 4 4 2 SROI-2 I/C 3.4 45 MAJ 6 6,5 4 2 1 2

TS 1.43A 1 4 0 2 2 RX 1 1 1 j 0 NOR 4 1 1 1 4 2 SROT-3 IC 1,2, 1,2 2,5 10 MAJ 65 4

] 2 - i Instructions:

1. Check the applicant level and enter the operating test number arid Form ES-D-i event numbers for each event type; TS are not applicable for RO applicants ROe must service in both the at-the-controls (ATC) and balance-of-plant (BOPI positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (tIC) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position. one tIC malfunction can be credited toward the two hG malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under nOrmal or confm!led abnormal conditions (refer to Section D.5.d) but must be significant per Section C,2.a of Appendix C.). I) Reactivity end 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 spaciliad for the applicants license level in the right-hand columns, NUREG 1021 Revision 9

ES3O1 Transient and Event Checklist Fom ES-301-5 (Rev 021813)

Facility: Turkey Point Date of Exam: 3/4/13 Operating Test No.: L-13-11 A E Scenarios P V P E L-13-1-1 L-13-1-2 L-13-1-4 L-13-1-5 (Spare) 0 T { M L N L I

CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I C

L M NOR 3i 21i 1 RO-1 iC 1,3 2.4 1 6 4 2 MM 5 4 2 2 1 TS j 0 0 2 2 RX 1 1 1 NOR 1 1 1

-t I RO-2 IC 2.5 j 2,5 4 4 4 2 MAJ 6 TS 6.8 J 3 2 2 1 0 0 2 2 RX NOR 2

1 1 1 1 0 4 1

[ 2 1 1 1 RO-3 I/C 25 1.3 j

6 4 4 2 MM 4 2 2 1 TS RX EEE 0 0 1

2 1

2 NOR 3J i i RO-4 I/C MAJ

] 1565 2.4 2.5 4 4 2 3 2 2 1 Instructions:

TS ZIZJZZ]ZZZZLji ° o

1. Checlr 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 applicants. ROs must service in both the at-the-controls (ATC) and balartce-of-plant (SOP) positions; Instant SRO5 must serve in RD ATC positions, including at least two instrument or component (llC) both the malfunctions and one major transient, in the ATC position. If an Instant SRO and the additionally serves in the SOP position, one IC rnaifunction can be credited toward the two IC malfunctions required for the ATC position. SRO
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section O.5.d) but must be significant C.2.a of Appendix D () Reactivity and normal evolutions may be per Section replaced with additional instrument or component malfunctions on 1-for-i a basis.

3 Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that applicants competence count toward the minimum requirements specified provide insight to the for the applicants license level in the right-hand columns, NUREG 1021 Revision 9

ES-301 Transient and Event Checklist Form ES-301-5 (Rev_021 813)

Facility: Turkey Point Date of Exam: 3/4/13 Operating Test No.: L-13-1 A E Scenarios P V P E L-13-11 L-131-2 L-13-1-4 F L-13-1-5 T M (Spare) 0 I L N CREW CREW CREW CREW T N I T C

POSITION POSITION I POSITION POSITION A I L M A T N Y u

T P S A 8 S A B S A E R T 0 R T B S AEB R I u 0 R T 0 R TOj 0 C P 0 C P 0 C P 0 C P___

RX i 1 1 1 0 NOR 3 1 2j 1 1 1 R05 I/C jF ]34 6

[ 4 4 2 MAJ 6 5 6.8 4 2 2 1 lj TS RX J 21 0 0 2 2 1 0 NOR 1 1 1 RO-6 I/C MAJ 2,5 6

1,3 5

j 1 2 4 4 2 2 2 1 TS I 0 O2 2 NOR 1 1 1 1 I/C 4 2 MAJ F I 12 2 1 TS RX I 0 2 2 1 1 0 NOR MAJ TS H

2 0j l 1 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. ROe must service in beth the at-the-controls (ATCy and balance-of-plant (80P) positions, ATC positions, including at least two instrument or component IIIC) malfunctions and Instant SROs must serve in both the SRCI and the one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5,d) but must be significant per Section C,2.a of Appendix 0. (*) Reactivity arid 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.

NUREG 1021 Revision 9

ES-301 Competencies Checklist Form ES-301-6 (Rev 021813)

Facility: Turkey Date of Examination: 3/4/13 Operating Test No.: L-1 3-1 Point APPLICANTS SRO (U/I) RO/ATC BOP Competencies SCENARIO SCENARIO SCENARIO 1 214151245 124 5 Interpret/Diagnose Events and 1-7 1-6 1-9 1-6 1-7 1-6 1-9 1-6 1-7 1-6 1-9 1-6 Conditions Comply With and Use 1, 1-6 1-9 1-6 1-7 1-6 1-7 1-6 1-9 Procedures (1)

Operate Control 1, 12, 1,2,5 1.3 24123 134 1,4,5 NA NA NA NA 7,8 Boards (2) 3,4,6 5746 8 6 Communicate and 14 16 19 16 1-7 1-6 1-9 1-6 1-7 1-6 1-9 1-6 Interact Demonstrate Supervisory Ability 1-7 1-6 1-9 1-6 NA NA NA NA NA NA NA NA (3)

Comply With and Use Tech.Specs.(3)

Notes; (1) Includes Technical Specification compliance for RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

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

NUREG-1 021, Revision 9

ES-40 I Record of Rejected K/As Form ES-401-4 Tier/Group Randomly Selected KA Reason for Rejection 037/AA2.07 1 I2 replaced by 037 / Transposed in Error AA2.07 059 / AA2.01 1 /2 replaced by 037 I Transposed in Error AA2.07 014 / K4.O1 replaced 2/2 The subject K/A isnt relevant at the subject facility.

by_014_I_K4.06 059 IAK1.05 1 I2 replaced by 059 It isnt possible to prepare a psychometrically sound question AK1.01 related to the subject K/A.

076 I 2.4.31 replaced 2 1, Too much overlap for test items developed in subject area by_005_/_2.4.31

ES-401, Rev. 9E PWR Examination Outline Form ES-401-2 Facility: Turkey Point 201 3-301 March 2013 RO K/A Category Points SRO-OnIy Points Tier Group KKKKKKAAAAIG A2 G* Total 1 2 3 4 5 6 1 2 3 Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal Plant 2 2 1 2 N/A 1 2 N/A 1 9 2 2 4 Evolutions Tier Totals 5 4 5 4 5 4 27 5 5 10 1 23233233223 28 2 3 5 2.

Plant 2 11011111111 10 1 2 3 Systems TierTotals 34244344334 38 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2 Note:1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, 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.
e. Absent a plant-specific priority, only those K/As having an importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 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.

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. Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, Rev. 9 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 1 (RO / SRO)

E/APE#/Name/SafetyFunction K K K A A G K/ATopic(s) lR 12312 000007 (BW/E02&E1 0; CE/E02) Reactor Trip X OO7EA1 .02 Ability to operate and monitor the 3.8/3.7

- Stabilization Recovery I 1

- following as they apply to a reactor trip: MEW System.

000008 Pressurizer Vapor Space Accident / 3 X 008AK2.02 Knowledge of the interrelations 2.7/2.7 between the Pressurizer Vapor Space Accident and the following: Sensors and Detectors.

000009 Small Break LOCA / 3 X 009EA2.02 Ability to determine or interpret the 3.5/3.8 following as they apply to a small break LOCA:

Possible leak paths.

000011 Large Break LOCA/ 3 X OIIEKI.O1 Knowledge of the operational 4.1/4.1 implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.

000015/17 RCP Malfunctions / 4 (SRO) X 015AG2.4.8 Knowledge of how abnormal 3.8/4.5 operating procedures are used in conjunction with EOPs.

000015/17 RCP Malfunctions/4 X 015AK1.04 Knowledge of the operational 2.9/3.1 implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow.

000022 Loss of Rx Coolant Makeup / 2 X 022G2.1.20 Ability to execute procedure steps. 4.6/4.6 000022 Loss of Rx Coolant Makeup / 2 (SRO) X 022G2.4.20 Knowledge of the operational 3.8/4.3 implications of EOP warnings, cautions, and notes.

000025 Loss of RHR System / 4 X 025AK3.02 Knowledge of the reasons for the 3.3/3.7 following responses as they apply to the Loss of Residual Heat Removal System: Isolation of RHR low-pressure piping prior to pressure increase above specified level.

000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System X 027AG2.1.28 Knowledge of the purpose and 4.1/4.1 Malfunction / 3 function of major system components and controls.

000027 Pressurizer Pressure Control System x 027G2.4.11 Knowledge of abnormal condition procedures. 4.0/4.2 Malfunction / 3 (SRO) 000029 ATWS / 1 X 029EK2.06 Knowledge of the interrelations 2.9/3.1 between an ATWS and the following: Breakers, relays, and disconnects.

000038 Steam Gen. Tube Rupture / 3 X 038EK1.02 Knowledge of the operational 3.2/3.5 implications of the following concepts as they apply to the SGTR: Leak rate vs. pressure drop.

038A2.03 Ability to determine or interpret the 000038 Steam Gen. Tube Rupture /3 (SRO) x following as they apply to a SGTR: Which S/G is 4.4/4.6 ruptu red 000040 (BW/E05; CE/E05; W/E1 2) Steam X O4OAAI .19 Ability to operate and I or monitor the 3.8/3.9 Line Rupture Excessive Heat Transfer / 4 following as they apply to the Steam Line Rupture: Post accident monitoring panel indicators.

000054 (CE/E06) Loss of Main Feedwater / 4 X 054AK3.04 Knowledge of the reasons for the 4.4/4.6 following responses as they apply to the Loss of Main Feedwater (MFW): Actions contained in EOPs for loss of MFW.

000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 X 056G2.4.11 Knowledge of abnormal condition 4.0/4.2 procedures.

X 000057 Loss of Vital AC Inst. Bus / 6 057AA1 .04 Ability to operate and I or monitor the following as they apply to the Loss of Vital AC 3.5/3.6 Instrument Bus: RWST and VCT valves.

000058 Loss of DC Power! 6 (SRO) X 058AA2.01 Ability to determine and interpret the 3.7/4.1 following as they apply to the Loss of DC Power:

That a loss of dc power has occurred; verification that substitute power sources have come on line 000062 Loss of Nuclear Svc Water / 4 X 062AA2.06 Ability to determine and interpret the following as they apply to the Loss of Nuclear 2.8/3.1 Service Water: The length of time after the loss of SWS flow to a component before that component may be damaged.

000062 Loss of Nuclear Svc Water / 4 (SRO) X 2.6/2.9 062AA2.03 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition.

000065 Loss of Instrument Air / 8 X 065AK3.03 Knowledge of the reasons for the following responses as they apply to the Loss of 2.9/3.4 Instrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air.

000077 Generator Voltage and Electric Grid Disturbances I6 WEO4EK2.2 Knowledge of the interrelations W/E04 LOCA Outside Containment /3 X between the (LOCA Outside Containment) and 3.8/4.0 the following: Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

BWIEO4; W/E05 Inadequate Heat Transfer -

Loss of Secondary Heat Sink / 4 WEO5EA2.2 Ability to determine and interpret W/E05 Inadequate Heat Transfer- Loss of X the following as they apply to the (Loss of Secondary Heat Sink /

Secondary Heat Sink) Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

WE1 1; Loss of Emergency Coolant Recirculation K/ACategoryTotals: 3 3 3 j 3 3 18 K/A Category Totals: = =

= j = 3 3 Group Point Total: 6

ES-401, Rev. 9 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evutions Tier 1/Group 2 (RO / SRO)

E/APE #1 Name I Safety Function K K K A A G K/A Topic(s) IR 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 X 38,39 003AK3.07 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Tech-Spec limits for T-ave.

000003 Dropped Control Rod! 1 (SRO) X 39/38 oo3G2.1.19 Ability to use plant computers to evaluate system or component status.

000005 Inoperable/Stuck Control Rod / 1 X 36,34 OO5AAI.O1 Ability to operate and! or monitor the following as they apply to the Inoperable! Stuck Control Rod:

CRDS.

000024 Emergency Boration I 1 X 3.8/4.1 024AA2.O1 Ability to determine and interpret the following as they apply to the Emergency Boration: Whether boron flow and/or MOVs are malfunctioning, from plant conditions 000028 Pressurizer Level Malfunction / 2 (SRO) X 2.7/4.1 028G2.4.30 Knowledge of events related to system operationlstatus that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

000032 Loss of Source Range NI / X 2.9/3.2 032AA2.05 Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Nature of abnormality, from rapid survey of control room data.

000033 Loss of Intermediate Range NI / 7 X 3.2/3.6 033AK3.O1 Knowledge of the reasons for the following responses as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Termination of startup following loss of intermediate-range instrumentation.

000036 (BW!A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 (SRO) X 037AA2.07 Ability to determine and 3.1/3.6 interpret the following as they apply to the Steam Generator Tube Leak: Flowpath for dilution of ejector exhaust air 000051 Loss of Condenser Vacuum!4

000059 Accidental Liquid RadWaste Rel. /9 X 3.2/3.5 059AK105 Knowledge of the operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: The calculation of offsite doses due to a release from the power plant 000059 Accidental Liquid RadWaste Rel. / 9 (SRO) X 3.2/3.5 059AA2.Ol Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release:

The failure-indication light arrangement for a radioactive-liquid monitor 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms! 7 X 2.5/2.6 061AK2.Ol Knowledge of the interrelations between the Area Radiation Monitoring (ARM) System Alarms and the following: Detectors at each ARM system location 000067 Plant Fire On-site /8 000068 (BW!A06) Control Room Evac. / 8 000069 (WIE14) Loss of CTMT Integrity / 5 000074 /E06&E07) mad. Core Cooling! 4 000076 High Reactor Coolant Activity / 9 W!EO1 & E02 Rediagnosis & SI Termination / 3 W/E1 3 Steam Generator Over-pressure / 4 W/E15 Containment Flooding/S X WEI5EG2.1.27 Ability to perform specific system and integrated plant procedures 4.3/4.4 during all modes of plant operation.

W!E16 High Containment Radiation / 9 BW/A01 Plant Runback /

BW!A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip /4 BW/A05 Emergency Diesel Actuation /6 BW/A07 Flooding! 8 BW/E03 Inadequate Subcooling Margin /4 WEO3EKI .1 Knowledge of the operational X implications of the following concepts as 3.4/4.0 they apply to the (LOCA Cooldown and Depressurization): Components, capacity, and function of emergency systems.

BW/E08; W!E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/Al 3; W!E09&E10 Natural Circ. /4 BW/E13&E14 EOP Rules and Enclosures CE/All; W!E08 RCS Overcooling - PTS /4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery =

K/A Category Point Totals: 2 1 2jiJ2 I Group Point Total: 9 K/A Category Point Totals: (SRO) = = j2 2 Group Point Total: 4

ES-401, Rev. 9 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -her 2/GrouojRO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR 1234561234 003 Reactor Coolant Pump X 2.8/3.2 0D3K5.02 Knowledge of the operational implications of the following concepts as they apply to the RCPS: Effects of RCP coastdown on RCS parameters.

004 Chemical and Volume Control X 004K5.1 9 Knowledge of the operational implications of the following concepts as they apply to the CVCS: Concept of SDM 005 Residual Heat Removal X 2.5/2.6 005K6.03 Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: RHR heat exchanger.

005 Residual Heat Removal (SRO) X 2.7/2.9 005A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation.

006 Emergency Core Cooling X 006A1.18 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: PZR level and pressure.

007 Pressurizer Relief/Quench Tank X 2.9/3.1 007K1.O1 Knowledge of the physical connections andlor cause-effect relationships between the PRTS and the following systems: Containment system.

007 Pressurizer Relief/Quench Tank X 2.6/2.9 007K4.O1 Knowledge of PRTS design feature(s) andlor interlock(s) which provide for the following: Quench tank cooling.

008 Component Cooling Water X 3.1/3.1 008K1.O1 Knowledge of the physical connections and!or cause-effect relationships between the CCWS and the following systems: SWS.

008 Component Cooling Water (SRO) X 008G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

010 Pressurizer Pressure Control X 2.6/3.0 010K5.02 Knowledge of the operational implications of the following concepts as the apply to the PZR PCS: Constant enthalpy expansion through a valve.

010 Pressurizer Pressure Control X 2.7/3.1 010K6.O1 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: Pressure detection systems.

012 Reactor Protection X 012K2.O1 Knowledge of bus power 3.3/3.7 supplies to the following: RPS channels, components, and interconnections.

012 Reactor Protection (SRO) X 3.1/3.6 012A2.O1 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation.

013 Engineered Safety Features X 3.0/3.4 013K4.19 Knowledge of ESFAS design Actuation feature(s) and/or inter-lock(s) which provide for the following: Reason for opening breaker on high-head injection pump.

013 Engineered Safety Features X 013A3.01 Ability to monitor automatic Actuation operation of the ESFAS including: Input channels and logic 022 Containment Cooling X 3.2/3.1 022A4.02 Ability to manually operate andlor monitor in the control room: CCS pumps.

025 Ice Condenser 026 Containment Spray X 3.9/4.2 026A1 .01 Ability to predict and!or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment pressure 026 Containment Spray X 026G2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

026 Containment Spray (SRO) X 41/43 026G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

039 Main and Reheat Steam X 2.9/2.8 039A4.O1 Ability to manually operate and/or monitor in the control room: Main steam supply. Valves.

059 Main Feedwater X 3.2/3.4 059K4.19 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic feedwater isolation of MFW.

061 Auxiliary/Emergency Feedwater X 061A3.05 Ability to monitor automatic 2.5/2.5 operation of the AFW, including:

Recognition of leakage, using sump level changes.

062 AC Electrical Distribution X 2.5/2.9 062A2.l6Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Degraded system voltages.

062A2.04 Ability to (a) predict the 062 AC Electrical Distribution (SRO) X 3.1/3.4 impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect on plant of de-energizing a bus 063 DC Electrical Distribution X 2.9/3.1 063K2.O1 Knowledge of bus power supplies to the following: Major DC loads 063 DC Electrical Distribution X 3.7/4.1 063K3.O1 Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: ED/G 064 Emergency Diesel Generator X 3.9/4.6 064G2.2.42 Ability to recognize system parameters that are entry4evel conditions for Technical Specifications.

073 Process Radiation Monitoring X 2.5)2.9 073 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

076 Service Water X 2.6/2.6 076A1 .02 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures 076 Service Water X 4.2/4.1 076G2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

078 Instrument Air X 2.7/2.9 078K2.01 Knowledge of bus power supplies to the following: Instrument air compressor 103 Containment X 37/41 103K3.03 Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under refueling operations.

103 Containment X 3.5/3.8 103A2.03 Ability to (a> predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A and B isolation K/A Category Point Totals: 2 1I3 3 J3 3121213 Group Point Total: 28 K/A Category Point Totals: (SRO) 31_I 2 Group Point Total: 5

ES-401, Rev. 9 5 Form ES-401-2 rES-401 PWR Examination Outline Form ES-401-2

[ Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A C KIA Topic(s) IR 1234561234 001 Control Rod Drive X 3.6/3.7 001K6.13 Knowledge of the effect of a loss or malfunction on the following CRDS components: Location and operation of RPIS 002 Reactor Coolant 011 Pressurizer Level Control X 3.1/3.2 011K2.O1 Knowledge of bus power supplies to the following: Charging pumps 014 Rod Position Indication X 2.5/2.7 014K4.O1 Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Upper electrical limit 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor X 3.1/3.9 017K5.01 Knowledge of the operational implications of the following concepts as they apply to the ITM system:

Temperature at which cladding and fuel melt 028 Hydrogen Recombiner and Purge Control 029 Containment Purge X 3.0/3.3 029A1 .03 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the Containment Purge System controls including: Containment pressure, temperature, and humidity 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment X 3.6/4.4 034A2.01 Ability to (a) predict the (SRO) impacts of the following malfunctions or operations on the Fuel Handling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Dropped fuel element 035 Steam Generator

041 Steam Dump/Turbine Bypass X 2.7/2.9 041A4.02 Ability to manually operate Control andlor monitor in the control room:

Cooldown valves 045 Main Turbine Generator X 2.5/2.8 045A2.12 Ability to (a) predict the impacts of the following mal-functions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Control rod insertion limits exceeded (stabilize secondary) 058 Condensate X 05602.1.28 Knowledge of the purpose 4.1/4.1 and function of major system components and controls.

068 Liquid Radwaste 071 Waste Gas Disposal (SRO) X 3.3/3.6 071 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Use of waste gas release monitors, radiation, gas flow rate, and totalizer.

072A3.01 Ability to monitor automatic 072 Area Radiation Monitoring X operation of the ARM sys-tem, 2.9/3.1 including: Changes in ventilation alignment 075K1 .01 Knowledge of the physical 075 Circulating Water X 2.5/2.5 connections and!or cause-effect relationships between the circulating water system and the following systems: SWS 079 Station Air (SRO) X 3.8/4.0 07902.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

086 Fire Protection K/A Category Point Totals: 1 1 Ojii 1 1 1 11111 Group Point Total: 10 K/A Category PointTotals: (SRO) j]

121 3 Group PointTotal:

Facility: Turkey Point Date of Exam: 3/20 13 2013-301 RO SRO-Only Category KIA # Topic JR Q# JR Q#

Knowledge of the process for controlling 2.1.14 3.1 3.1 equipment configuration or status Knowledge of the stations requirements for 2.1.38 verbal communications when implementing 3.7 3.8 Conduct of procedures.

Operations Knowledge of procedures, guidelines, or 2.1.37 limitations associated with reactivity 4.3 4.6 management.

Subtotal 2 1 Knowledge of pre- and post-maintenance 2.2.22 4.0 4.7 operability requirements.

Knowledge of the bases in Technical 2.2.25 Specifications for limiting conditions for 3.2 4.2

2. operations and safety limits.

Knowledge of the process for controlling Equipment Control 2.2.11 3.3 temporary design changes.

Ability to determine Technical Specification 2.2.35 45 Mode of Operation.

Subtotal 2 2 Knowledge of radiation exposure limits under 2.3.4 3.7 normal and emergency conditions.

Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable 2*3 5 2.9 survey instruments, personnel monitoring equipment, etc.

Knowledge of radiological safety procedures 2.3.13 3.4 3.8 pertaining to licensed operator duties

3. Knowledge of radiation or contamination Radiation Control 2.3.14 hazards that may arise during normal, abnormal, 3.4 3.8 or emergency conditions or activities.

Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 3.6 conditions.

Subtotal 3 2 Knowledge of the operational implications of 2.4.20 3.8 4.3 EOP warnings, cautions, and notes.

Knowledge of the emergency action level 2.4.41 2.9 4.6 thresholds and classifications.

4. 2.4.42 Knowledge of emergency response facilities. 2.6 3.8 Emergency Knowledge of RO tasks performed outside the Procedures / Plan 2.4.34 main control room during an emergency and the 4.1 resultant operational effects.

Knowledge of the lines of authority during 2.4.37 4.0 implementation of the emergency plan.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Written Examination Quality Checklist Form ES-401-6 FINAL Facility: Tuilcey Point Units 3 & 4 Date of Exam: Exam Level: RO X SRQ X InitIal Item Description a b

1. Questions and answers are technically accurate and applicable to the facility.
2. a. NRC K/As ar referenced for all questions.
b. Facility learning obiectives are referenced as available. I.5
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 tile last 2 NRC licensing exams, consult NRR 01. program office.)
5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly developed: or the audit exam was completed before the license exam was started; or the examinations were developed independently; or XX_ the license certifies that mere is nc duplication; or other (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified): enter the actual RO I SRO-only question distribution(s) at right. 26 I 3 11 I0 38 I 22
7. Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehensivelanelysis level:

the SRO exam may exceed 50 percent it the randomly selected K/As support the higher cognitive levels; enter 3519 40/ 16 the actual RO 1 3RD question distribution(s) at right.

8. References/handouts provided do not give away answers or aid in the elimination of distractors,
9. Question content conforms with specific K/A statements In the previously approved

/

examination outline and is appropriate for the tier to which they are assigned deviations are justified,

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

1 1. The exam contains the required number of one point multiple choice items. Yf the_total_is_correct_and_agrees_with_the_vieue_on_the_cover sheet.

i$

i_li Printed Name/ Signature Date VIA a.Author

b. Facility Reviewer()

I zI

c. NRC Chief Examiner ($) (c,arrcXL

]

4 . Lk4 /

ri. NRC Regional Supervisor tvRt< t1Jrkfr 5/i /1!

/

Note:

  • The facility reviewers initials/signature are not applicable for NRC-developed examinations.

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

ES-401, Rev. 9 Turkey Point 2013-301 RO Written Examination Review Worksheet FINAL Form ES-401-9

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 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 (LCD) of each question using a 1 - 5 (easy difficult) rating scale (questions in the 2

- 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:
  • The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
  • The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
  • The answer choices are a collection of unrelated true/false statements.
  • The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
  • One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
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 sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6. 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?
7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S Generic comments: If a question had two distractors that were not plausible, but were part of a 2X2 the question was graded as an Enhancement. If the question had two distractors that were totally not plausible, the question was graded as unsatisfactory.

F 2 X E OO7EAI.02 Question appears to match the K/A.

Question is kind of confusing as written. It also does not match the procedures you sent with the reference package. The next procedural check of SIG level (in ES-O.1)? Need to add all to maintain all S/G levels...

NEW 112412013 Made changes as requested 2I27I2013 2 H 2 X E 008AK2.04 Question appears to match the K/A. As written distractors C and D are not plausible. State that the leak is from the pressurizer upper level tap or reference leg. Remove vapor space from the stem (this is a cue). That would make C and D more plausible. When you state it is a vapor space accident, everyone is taught pressurizer level rises.

Modified 1I24I2013 Changed to small break LOCA, and ran on simulator. SAT 2I27I2013 3 H 2 X E 009EA2.02 Question appears to match the K/A. As written distractors B and C are not very plausible.

Suggest change third bullet in stem to containment sump level is rising. And change correct answer to C.

NEW 112412013 Made Changes as Requested SAT 2I27I2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 4 F 2 S OIIEKI.1 Question appears to match the K/A. Not very discriminating but SAT BANK SAT as written 212712013 5 H 1 X X X U OI5AKI.04 Question appears to match the K/A.

Cueing in stem Loss of RCP = Reactor Trip. What is the definition of significant? If delta T was 1 degree higher, would that be significant. Depending os significant, B could be argued correct. Using this word could lead to post exam comments. Distractor A and D are not plausible. Distractor analysis is incorrect, it states D is the correct answer. As written LOD=1 BANK 112412013 Replaced question Ask about setpoints SAT 212712013 Setpoints pre-EPU. SAT 6 H I X E 022G2.1.20 Question appears to match the K/A. Do not believe C and D are plausible. MOV 3-381 is not listed in the procedure reference provided. The noun name does match another valve listed in step

6. Is this another valve in the flow path? Need to have another action for C and D.

BANK 112412013 Discussed distractors C and D, and these valves are similar to valves listed in the procedure but will not stop the loss of inventory. SAT 212712013 7 F 2 X X E 025AK3.02 Question appears to match the K/A. Is RHR maintained in automatic when in cooldown line up? If so, that D is not plausible. The system will maintain the flowrate at setpoint. When is bypassing of the interlocks allowed? Can an

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/E Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S applicant assume the interlock is bypassed, can the interlock be bypassed with the plant in this condition/line-up? If so, B could be considered correct.

BANK 112812013 Interlock is not bypassed in this condition, distractor D changed to make it a little more plausible. SAT 2I27I2013 8 H 2 X X X U 027G2.1.28 Do not believe the question matches the K/A. (if it does it is in a backwards manner, will discuss). Distractor A is not plausible. Fourth Bullet should read: CV-4-31 1 Auxiliary Spray Valve indicates dual (red and green lights lit). Remove the rest, this is a cue.

NEW 1128I2013 Question replaced. Not real keen on distractor D Will discuss. 2127I2013 Still Working Rewrote question, SAT 2I28I2013 9 F 2 E 029EK2.06 Question appears to match the K/A.

Distractor C should read the same as distractor D:

both reactor trip and bypass breakers.

BANK 112812013 Made change as requested SAT 212712013 10 H 2 X E 038EK1.02 Question appears to match K/A. With RCPs secured in the stem it would be better to have distractors A and B begin with open one PORV to... This would test the opposite of the earlier step in E-3 where the preferred method is sprays/PORVs/

then Aux spray.

MODIFIED 1I28l2013 Made change as requested SAT 2I27I2013

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

Q# LOK LOD i (F/H) (1-5) Stem ICues T/F Cred. Partial Job- Minutia #/ Back-Dist. Link units ward Q

K/A I SRO Only U/E/

S Explanation Focus!

11 H 2 X E O4OAAI 09 Question appears to match the K/A. I think 450°F is a little high. Also what RCS temperature is qualified as a post accident monitoring instrument? Some stations have specific channels i. e. RCS wide range etc. Please ensure that the question is specific to the actual post accident monitoring channel, or someone could claim there is not a correct answer.

Licensee submitted a new question to replace the original question submitted during an early question submittal. The new question has two distractors that are not plausible (A and C). The original question would be satisfactory if answers A and B were changed to RCS wide range Tcold approximately 350°F, and RCS wide range Tcold approximately 300° F. Distractor C should be changed to approximately 350°F. Then the question would be SAT.

NEW 112812013 Licensee replaced question with a new question.

New Question is SAT 212712013 12 F 2 X U 054AK3.04 Question appears to match the K/A.

Distractors A and D are not plausible. I realize this is a bank question previously given on an NRC exam, but these two distractors are not plausible. Replace A and D.

BANK 112812013 Changed distractor A and D as requested. SAT 2I27I201 3

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

Q# LOK LOD I (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back-Dist. Link units ward Q=

K/A I SRO Only U/E/

S Explanation Focus 13 F 2 X E O56G2.411 Question appears to match the K/A. The use of the word Preferred should be avoided.

Could first be used and still be correct lAW the ONOP? This question appears to be written at the fundamental level.

BANK 112812013 Made changes as requested. SAT 212712013 14 H 2 S 057AA1.04 Question appears to match the K/A.

Please change the answer order so that A is not the correct answer. The bank question answer is A.

Otherwise SAT BANK 112812013 Made change as requested. SAT 212712013 15 F 2 X E 062AA2.06 Question appears to match the K/A. The initial conditions states that flow is less than that for all three CCW heat exchangers is less than the minimum required. The stem states the minimum ICW flows to each CCW heat exchanger. What are we attempting to ask? This could be confusing to the applicants.

NEW 112812013 After discussion left question as is. SAT 212712013 16 H 2 S 065AK3.03 Question appears to match the K/A. SAl NEW 112812013 Question is sat, need to have verb agreement with disctractor C. 212712013 SAT

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- I SRO U/E/

S Explanation Focus Dist. Link units ward K/A j Only 17 H 2 X E WEO4EK2.2 Question appears to match the K/A.

The applicant is informed of break isolation (RCS pressure going up) therefore, distractor D is not plausible.

BANK 112812013 Changed distractor as requested. SAT 212712013 18 H 2 X U WEO5EA2.2 Question does not appear to match the K/A. What limit are we testing? While you have a limit on flow in several of the distractors, it is not applicable to the situation. Need to reword question/stem so that a limit is tested. With DWDS 3-012 danger tagged closed, distractors C and D are not plausible. (standby feed is not available.)

MODIFIED Licensee changed question but is it is now similar to one of the scenarios. Remove DWDS 3-012 danger tagged closed from the stem and leave the rest of the original question as is.

Made changes as requested. SAT 2/27/2013 19 H 2 X X U 003AK3.07 Question kind of matches the K/A.

Distractor B does not have a reason. Not sure you could achieve these conditions with only one dropped rod. Did you try this on the simulator? With all the RCPs running, I dont think you could get here. Distractor analysis does not match for B, no mention of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the distractor. Distractor C is no plausible, why would I trip the reactor if I was above the minimum temperature for criticality? This question needs some work BANK 112812013 Made several changes to question as requested.

SAT 212712013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back-Link units ward Q=

K/A I SRO Only U/E/

S Explanation Focus Dist.

20 F 2 S OO5AAI .01 Question appears to match K/A. SAT BANK 112812013 (Previous TP NRC exam) 21 H 2 S 024AA2.01 Question appears to match K/A. Change distractor A to read flow indicated is adequate.

Otherwise SAT NEW 1I28I2013 22 H 2 5 032AA2.05 Question appears to match the K/A. SN BANK 112812013 23 H 2 E 033AK3.01 Question appears to match the K/A.

Distractor D is not plausible as written. Why would power have to be maintain below P-6 if only one intermediate range detector was required?

NEW 1I28I2012 Changed distractor D. Need to ensure D is not correct. Then SAT. 212712012 Changed wording on distractor D to clarify. Now SAT 212812013 24 F 2 X X U 059AK1 .05 This is a tough K/A, and I dont really think you hit it. But it was a good try. Distractors A and B are not plausible. There is not mention of calculation (although in the answer you do state that chemistry needs to determine off-site dose rates. I think this question should be asked using the concept of limits (2 X ODCM limits or something similar) Will discuss and determine if a new K/A needs to be given.

No changes were made to the question. Comments still stand.

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

Q# LOK LOD (F/H) (1-5) Stem Cues Focus T/F Cred. Partial Job- Minutia #1 Back-Dist. Link units ward Q=

K/A J SRO Only U/E/

S Explanation NEW 112812013 Changed KIA to AKI.01 or 1.02 02I20I2013 Wrote new question to new KIA. SAT 2I27I2013 25 F 2 S 061AK2.01 Question appears to match the K/A.

SAT NEW 1I28I2013 26 F 2 S WEI5G2.1.27 Question kind of matches the K/A.

SAT NEW 1!28I2013 After further review, change the stem to state:

WOOTF identifies a system Made changes as requested. SAT. 212712013 27 F 2 X X X U WEO3EKI.1 Question does not meet the K/A. This is a diesel load limit question and has nothing to do with ES-I .2. Need a different question that talks about the capacity of systems used to mitigate or ar used in a Cooldown and depressurization. Question also has two distractors that are not plausible, A and C. Why would you not start a charging pump in ES-1.2 this is a major mitigation strategy. Operational Validity?

NEW1I28I201 3 Question re-written, appears to be okay, what reference is to be provided, and why do the applicant require it? 2I27I2013 change stem to read heater breakers, use redacted reference is okay. SAT 2I27I201 3

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 28 F 2 S 003K5.02 Question appears to match the K/A. SAT This is a memory level question not higher cognitive.

BANK 112912013 29 H 2 S 004K5.19 Question appears to match the K/A. SAT MODIFIED 112912013 30 H 2 E 005K6.03 Question appears to match the K/A.

Change stem of question to state the required method that will initially re-establish cooling BANK 1I29I2013 Initially was not inserted as requested. Is there a reason for this? Added Initially SAT 2I27I2013 31 H 2 X X E 006A1.18 Question appears to match the K/A.

Distractor B is not plausible. As stated in your distractor analysis, with an RCP running, there is not bubble in the head. Need to discuss in detail why distractor C is not correct. If the leak was beyond the capability of I HHSI pump, and I charging pump, RCS pressure could decrease to the point of saturation.

BAN K I I29I201 3 Changed distractor B, with the leak limited to 25Ogpm and capacity of the SI pumps, it appears that C is incorrect. SAT 2I27I2013 007K1.01 Question appears to match the K/A. Not ry discriminating. Do not believe distractor B is Dlausible. LOD=1. Question is asked as a undamental level.

NEW 1129/2013

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

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

S Explanation Wrote new question SAT 212712013 33 F 2 S 007K4.01 Question appears to match the K/A.

Question is adequate, please place the only after the valves. The operator must manually close CV 519B, PRT PRIMARY MAKE UP ONLY.

NEW 1I2912013 Made changes as requested SAT 212712013.

34 F 2 X E 008K1.01 Question appears to match the K/A. This question is very similar to RO question 15. Both have numbers for ICW and this will cue the applicant that 11,000 gpm is above the limit. One of the questions must be changed.

NEW 1I29I2013 Made changes as requested SAT 212712013 35 H 2 X E 010K5.02 Question appears to match K/A. The original question that was used on a previous TP exam stated the indications could not be used.

Which one is correct? Not sure 400°F is plausible, will discuss. Question does appear to be MODIFIED. 112912013 After discussion, with the safety valve lifting the indications can be used. SAT 212712013 36 H 2 S 010K&01 Question appears to match K/A. The question appears to be modified. SAT MODIFIEDII29I2OI 3

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 37 H 2 E 012K2.O1 Question appears to match the K/A. Is this the same on Unit 4? If so, or similar we could modify this question.

BANK 112912013 Licensee stated question could not be verified for unit 4. Determined question to be SAT 212712013 38 H 2 S 013K4.19 Question appears to match K/A. SAT NEW 1I29I2013 39 H 2 E 013A301 Question appears to match K/A. You are testing three items again and the applicant need onl know two of them. Suggest the following answer scheme:

A. Active Active Active B. Active Active Blocked C. Blocked Blocked Active D. Blocked Blocked Blocked This way you are really only testing two items.

Will Discuss NEW 1/29I2013 Made changes as requested.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 40 H 2 X U 022A4.02 Question appears to match the K/A. As written the second part of the question is moot, the applicant need only know which fans will start, because the actions are so different. (Only the first part is required to match the K/A.)

Suggest: Which one of the following describes which Emergency Containment Coolers will automatically start as a result of safety injection and the above failure.

A. ONLY 3C B. ONLY 3Aand3C C. ONLY 3B and 3C D. 3A, 3B and 3C With D being the correct answer NEW This question was changed from the first version you asked me to look at. Why the change? Was it technically incorrect? I believe the first version should be tested unless it is wrong. Will discuss. As written I do not believe this is a new question any longer. After the changes to the question A and D are not plausible, 112912013 Did not make all changes as requested. Will discuss 212712013 SAT 41 H 2 S 026A1.01 Question kind of matches the K/A. SAT NEW 112912013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 42 F 2 E 026G2.2.39 Question kind of matches the K/A. You are a little past the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> point with the answer. Not sure if I would expect an RO to know this. Will Discuss. You ask for the maximum time for the unit to be in mode 3, but the statement in Technical Specifications uses the word Hot Standby. To be totally correct the question should use this word also.

NEW 112912013 Made changes as requested. SAT 212712013 43 H 2 X E 039A4.O1 Question appears to match the K/A. The second half of A and D do not appear to be actions.

May need to change the wording in the stem.

NEW 112912013 Replaced Question Distractors C and Dare not plausible. Change to MSIV and MSIV bypass...

Will add something to stem and rewrite using MSIV and bypasses. 212712013 Included an MSIV bypass valve. SAT 2I28I2013 44 H I X E/U 059K4.19 Question kind of matches the K/A.

Although this version is a little easier than the original version. The original version asks what can be used to feed the generators, this version just ask for the position of the valves after a trip. Most plants do not have the bypass valves in automatic at 100%

power, so after the trip of course they should be closed. This may be a level of difficulty LOD= 1.

will have another examiner review. Distractor A is not plausible.

BANK 112912013.

Replaced Question SAT. 2I27I201 3

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 45 H 2 S 061A3.05 Question kind of matches the K/A. SAT NEW 112912013 46 H 2 X X E/U 062A2.16 Question appears to match the K/A.

Cueing in the stem. Remove below the administrative limit. Distractor B is not plausible.

Voltage is low due to total grid voltage being low, which means there is not enough MVARS being shared with other units (or large losses in the lines).

Reducing generator MW would make the problem worse. Distractor C may be correct, if the generator is not at max Mvars out, this is what would be performed.

NEW 112912013 Change to distractor C acceptable, Distractor B is still not plausible.

How about start DGs in anticipation of a loss of offsite power? (Usually this is not acceptable).

Will make changes as requested. Made changes as requested. SAT 2I28I201 3.

47 F 2 S 063K2.01 Question appears to match the K/A. SAT this question is listed as modified but the original was not provided to verify.

MODIFIEDIBANK 112912013 48 H 2 E 063K3.01 Question appears to match the K/A.

Distractors C and D do not need the reasons.

Distractors A and B do not have reasons. Just state 3A EDG auto-started but 3A EDG output breaker did NOT close, and 3A EDG auto-started but has no output voltage.

BANK 1I2912013

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

Q# LOK LOD (F/H) (1-5) Stem Cues Focus T/F I Cred.

Dist.

Partial Job- Minutia #1 Back-Link units ward Q=

K/A SRO Only U/E/

S Explanation 49 F 2 S 064G22A2 Question appears to match the K/A.

SAT NEW 112912013 50 F 2 X E 073A2.02 Question appears to match the K/A.

Distractors A and B are not plausible. Power increases do not depend on process radiation monitors. Need new first part of distractors.

NEW 112912012 Kind of rewrote question, A can also be argued as a correct answer. Will discuss options Rework A and B 212712013 Changed A and B, Okay, but now C and D do not read correctly, change C and D to there are no restriction on power ascension. Made changes as requested SAT 212812013.

51 H 2 X E/U 076At02 Question kind of meets the K/A. The question does not test the temperature of TPCW or Reactor cooling water. The temperature is listed in the stem and you tell them the temperature limits.

Distractors B and C are not plausible. If the throttle valve is shut in B why would the operator place another heat exchanger on service? In distractor C if the valve is opened why would the operator reduce load. These do not make sense. Recommend using a 2X2 with different temperatures; remain less than 1 10°F or another temperature.

BANK 113012013 After a long discussion remove several items from the stem, determined that the question is testing two limits, temperature and flow. SAT 2I2 712013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia I #/ Back- Q I SRO U/E/ Explanation Focus Dist. Link 1hits ward K/A Only S 52 H 2 X E/U 076G2.4.31 Question kind of matches the K/A. Is very similar to the previous question. May be some cueing between questions. This cueing will make distractor D not plausible. One of these K/As may need to be changed if a question cannot be developed that is sufficiently different enough to prevent cueing.

NEW 113012013 Changed KIA to 005G2.4.31 Replaced question New question states ARG reference provided.

The reference will cause more confusion than not having it. Question is SAT without a reference. 212712013 53 F 2 S 078K2.01 Question appears to match the K/A. SAT.

Where are the locations of these Load Centers?

NEW 1I3012013 54 F 2 X E 103K3.03 Question appears to match the K/A.

Distractor D is not plausible.

BANK 113012012 Changed distractor D. SAT 2I27I2013 55 H 2 X E 103A2.03 Question appears to match the K/A. As written distractor D is not plausible. With a loss of TB cooling and Seal Injection RCPs are always secured. (usually within 10 minutes). Change first part of C and D to read, Both seal injection flowpath and thermal barrier cooling have been isolated.

(Less words). In the second part of A and D use something like Check all RCP seal return temperatures are less than 235°F, reset SI, establish Seal injection, then RCP may remain running.(Still do not believe this is very plausible.) With a large break LOCA in progress RCPs are secured for two

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #/ Back-Link units ward Q

K/A I SRO Only U/E/

S Explanation Focus Dist.

reasons, seal/RCP cooling, and loss of subcooling.

So it is very difficult to have distractors that are plausible.

NEW 113012013 Made changes as requested. Need to add s to RCP in distractors A and D. Then SAT 2I27I2013 001 K6.13 Question appears to match the K/A.

56 F 2 Second parts of B and D do not read correctly with the stem above. Should they read: comparing (them) against the Acceptance Criteria contained in 4-OSP-201.1, RO Daily Logs.

Otherwise SAT.

BAN KI I30I201 3 Made changes as requested remove the (Parenthesis ) from them 21271201 3Made changes as requested SAT. 212812013 57 F 2 X E 011 K2.01 Question appears to match the K/A.

Distractors C and D are not plausible with 38 as the normal supply.

NEW 113012013 Completely rewrote question, still need to discuss how the 3C chg pump is supplied by LC 3C. Change D to until the 3C chg pump is stopped. Then SAT. Made changes as requested SAT. 212812013 58 F 2 X U 014K4.06 Question appears to match the K/A.

Distractors C and D are not plausible. The title of the annunciator specifically speaks to shutdown bank rods, not control bank rods.

BANK 1I30I2013 After further discussion concerning the

[

II Q#

1.

LOK 2.

LOD

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

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

annunciator, it was determined question is SAT as written. 212712013 59 F 2 S 017K5.01 Question appears to match the K/A. SAT NEW 1130I2013 60 F 2 X E 029A1 .03 Question appears to match the K/A.

Distractor D is not plausible.

NEW 1130I2013 Changed distractor D. Initial distractor D was more plausible. Please change it back. 212712013 Done 2I27I2013 61 H 2 X E 041 A4.02 Question appears to match the K/A. Do these valves work in pairs? From the information provided with the question it appears they do not.

So why at 40% demand do 4 valves open seem plausible?. According to your figure six, two valves will be full open at 50%, so with the numbers presented it would appear three valves would be more appropriate.

NEW 1I30I2013 Valves do not operate in pairs.

Discuss (Licensee did not change anything).

Change to 3. Then SAT 212712013 Made changes as requested. Now SAT 2I28I201 3

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 62 F 2 X E 045A2.12 Question appears to match the K/A.

Distractor D is not plausible. If the technical specification is not exceeded, why would you commence an emergency boration? Too many words, this would be better for the applicant if you just did a 2X2 with is the T/S exceeded Yes or no, and a second part with immediately commence a...

Emergency boration IAW... and a 16 gpm boration lAW...

NEW 1I30I2013 Made changes as requested SAT 212712013 63 H 2 X E 056G2.1.28 Question appears to match the K/A.

Was 220 psig the old number? If so we should use this number, not the feed pump trip setpoint.

BANK 1130I2013 Made changes as requested.

SAT 2!27I2013 64 F 2 X E/U 072A3.01 Question does not appear to match the K/A. What change in ventilation alignment are we testing? I understand the control room ventilation gets isolated, (and it usually goes to a recirc mode).

What changes needs to be tested, line up etc? I know this was question was used before on an exam but we are not testing line-up changes in ventilation Will discuss.

BANK 113012013 Made requested changes and question now tests ventilation line-up changes. SAT 2I27I2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back-Dist.

Q I SRO U/E/

S Explanation Focus Link units ward K/A Only 65 H 2 X E 075K1.O1 Question appears to match the K/A. The stem in the question states that reactor power is 28%, however distractor A analysis states 8 %, with reactor power at 8% this makes the choices of just tripping the turbine more plausible. Above 10% at your facility tripping just the turbine is not plausible.

Question still appears to be Modified.

MODIFIED 113012013 Will the turbine be online at 8%? If so, then question is SAT. 212712013 66 F 2 X E G2.1 .14 Question appears to match the K/A. If the operator was required to announce entry in to 3-ONOP-071 .2; would he not have to announce entry into 3-GOP-I 00? Just attempting to find plausibility in distractors B and C. Distractor analysis does not match the question.

NEW 1I30I2013 Made changes to all distractors. SAT 212712013 67 F 2 S G2.1.38 Question appears to match the K/A. Not very discriminating.

NEW 113012013 68 F 2 X E G2.2.22 Question appears to match the K/A.

Change times in distractors Band D to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 60 minutes is never used in tech specs. Or you could use 30 minutes.

BANK 113012013 Changed to 30 Minutes SAT 212712013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 69 H 2 S G2.2.25 Question appears to match the K/A. SAT.

BANK 113012013 70 F 2 X U G2.3.13 Question appears to match the K/A.

Distractors C and D are not plausible. How can an area of containment be posted as a Locked High Radiation Area? Unless this term means something different. It would be more plausible if it was posted as a high radiation area and flashing lights or something like that but not locked. Distractor D is the only distractor that lists and elevation, and states nothing else is required. Not plausible.

NEW 113012013 Made changes as discussed. SAT 212712013 71 F 2 X E G2.3.14 Question kind of matches the K/A.

Distractors B and D are not plausible. How with the valve in manual and closed, will is minimize RCS subcooling? If the valve failed open, that would minimize subcooling. With the valve in automatic set at 1060, how would that minimize RCS subcooling? Need to find another reason for these.

BANK 1I30I2013. Not sure if it is really a bank question it is not similar to the attached bank question. Changed B and D SAT 2I27I2013

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

Q# LOK LCD (F/H) (1-5) Stem Cues Focus T/F Cred. Partial Job- Minutia #1 Back-Dist. Link units ward Q

K/A I SRO Only U/E/

S Explanation 72 F 2 X E G2.3.7 Question appears to match the K/A.

Distractors C and D first parts are not plausible, unless an individual can make an entry into containment on a General RWP. You could use a Special RWP or something similar. I dont know all of your terms.

You did not make any changes based on the early review.

NEW 113012013 Replaced question, see if SF pool mapping requires a Specific RWP. Changed to SFP mapping. SAT 2128I2013 73 H 2 X E 32.4.20 Question appears to match KIA.

uestion is kind of confusing as written.

Suggest:

Nhich one of the follow describes RHR pump

)peration based on the above conditions?

\. Manually start 3A and 3B RHR pumps.

3. Start 3B RHR ONLY; since cooling is not available to RHR Heat Exchanger 3A.

. 3A and 3B RHR pumps will auto start when the SI signal is received due to the High Containmen Pressure

). Start 3B RHR only; 3A RHR is not needed under the present plant conditions BANK 1I30I2013 Made changes as requested SAT 212712013

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

Q# LOK LOD I (F/H) (1-5) Stem Cues Focus T/F Cred. Partial Job- Minutia #/ Back-Dist. Link units ward Q=

K/A I SRO Only U/E/

S Explanation 74 F 2 S G2.4.41 Question appears to match K/A. SAT Paperwork states question is modified, however a original question is not included. This question is written at the fundamental level.

BANK 1/3012013 75 F 2 S G2.4.42 Question appears to match the K/A.

Distractor D is the only distractor with a reason, please remove it. D should state: Site assembly area. (You will not evacuate any operations staff) this would be cueing. Otherwise SAT.

NEW 1130/2013 24 Sat, 11 Unsats, and 40 Enhancements

ES-401, Rev. 9 Turkey Point 2013-301 SRO Written Examination Review Worksheet FINAL Form ES-401-9

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 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 (LCD) of each question using a 1 - 5 (easy difficult) rating scale (questions in the 2

- 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:
  • The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
  • The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
  • The answer choices are a collection of unrelated true/false statements.
  • The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
  • One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
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 sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6. 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?
7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S Generic Comment: it appears that you are using the foldout page of procedures as a procedure selection point for SRO only questions. Foldout page transitions are typically RO knowledge, RO have a copy of the page and monitor the control boards to inform others when a transition is required.

76 H 2 X E 015G2.4.8 Question appears to match the K/A.

Appears to have an SRO aspect to it. Is excess seal leakoff and immediate trip criteria in the ONOP or NOP?

Is it required to close the B loop spray valve? If so, there does not appear to be a correct answer. On what indicator can seal D/P been seen lowering.

(Usually in a Westinghouse plant this indicator is 0-200 psig. Would the DIP be this low? If the operators cannot see this in the control room, or on the computer then is should not be an observed condition.

In the stem you ask for the procedure action required, lAW what procedure, the ONOP, EOP, or NOP?

Distractor A should have a procedure listed in the disctractor, lAW some normal shutdown procedure etc.

The end of distractor C should read: . . .while performing actions of 3-EOP-0 The end of distractor D should read:... in parallel with 3-EOP-O.

BANK 0112312013 Made changes as requested 2127I2013 SAT

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 77 H 2 X X X U 022G2.4.20 Not sure the K/A is matched, what note or a caution is being tested? I could not tell from the material you sent.

This question is not SRO only. One only need know the entry conditions for ONOP-47.1, or ONOP-46.4.

Distractor C does not have the procedure name listed and all of the other distractors do.

The material you included with the questions states that ONOP-47.1 is titled Shutdown LOCA Mode 3

(<1000 psig) or Mode 4. The background document states this is loss of charging flow in modes 1-4.

Neither one talks about a caution or a note as described in the K/A.

If you are meaning to test the note in the backgrounc document, then you should be testing weather to shut down or not.

It appears you are attempting to test the note prior to step 9 of ONOP-47. 1, and if so, this is still RO knowledge (system knowledge)

NEW 0112312013 Replaced Question. Appears to be SAT.

212712013

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward KIA Only S 78 H 2 X E 027G24.1 I Question appears to match the K/A.

Appears to have an SRO aspect to it. (due to the note informing the operator to perform a shutdown lAW T/S.

Not sure distractors B and D are totally plausible, Level transmitter 459A is at the appropriate level, why would removing it from the pressurizer level control circuit mitigate the malfunction. Would you not just select another channel to replace 459A? If so, that may be a better response. Unless you have another way to remove 459 from the control circuit.

Distractor analysis is not correct.

NEW Made changes to distractors B and D per discussion in the licensees office. SAT 212712013 79 H 2 X X E/U 038EA2.03 Question appears to match the K/A. The transitions tend to test some SRO knowledge.

Informing the applicants that an RCP has tripped causing the reactor to trip is cueing. For this block just state power is loss to bus XXX (power to the RCP) and the reactor trips. That will add some more plausibility to the 3A S/G. (it will test which pump is powered from which bus). The third bullet is incomplete. Who reports? Just state the following conditions are observed.

With flow throttled to 50 gpm in A S/G, and 300 gpm in B S/G, are you meeting minimum AFW flow numbers? Not sure what your numbers are.

The knowledge to SI the plant and go to EO is foldout page knowledge, and is considered RO knowledge. (ROs are the ones who monitor the foldout page)

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q I SRO U/E/

S Explanation Focus Dist. Link units ward K/A Only Suggest:

Unit 3 is at 100%

The feeder breaker for bus XXX trips open The crew is performing the actions of ES0.1 and the following parameters are observed:

3A SIG level approximately 50% NR with AFW throttled to 50 gpm.

3B SIG level NR off scale low with 300 gpm AFW flow.

3C SIG level approximately 65% level with AFW flow throttled to 50 gpm The rest of the question would be the same. (this still does not fix the foldout page issue)

NEW 0112312013 Rewrote question, still need to reword distractors to state:

3A SIG is ruptured requiring a NOUE to be declared 3C SIG is ruptured requiring a NOUE to be declared 3A SIG is ruptured requiring an Alert to be declared 3CSIG is ruptured requiring an Alert to be declared Made changes as requested. SAT 212812013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q I SRO U/E/ Explanation Focus Dist. Link units ward K/A j Only S 80 H 3 X U 058AA2.O1 Question appears to match the K/A.

Appears to have an SRO aspect to it. On the initial question submittal, the TS reference was not to be distributed to the applicants. Why was this changed?

This was changed from the original question, and distractors A and B are no longer plausible. From the TIS given to the applicants, nothing has 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as a time for getting to cold S/D. In fact giving the applicants the TS aids them in answering the question. All actions in the TS provided state cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, so why would anyone pick 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

NEW 0112312013 Question Is SAT without the TS, this is a 303 call and should be able to answer from memory.

81 H 2 X E 062AA2.03 Question appears to match the K/A, and appears to be SRO only. Distractor D needs only added after Declare the 4A ICW header inoperable ONLY. What makes distractors B and C plausible?

Distractor analysis is not correct.

NEW 0112312013 After discussion with plant staff, the failure of the one valve to open (valve does get a SI signal to operate). However the valve position for SI actuation is (closed). Because it is already in that position, TS entry into 332 is not required.

Borderline SRO will allow because it is testing the operability of the TPCW valves and SI actuation system. SAT 212813013.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 82 H 2 X X X U )03G2.119 Question appears to match the K/A. Do

,ot think the question tests the K/A at the SRO level.

rhe question is flawed in that you are asking for hree items, and the applicant need only know two of hem to answer the question correctly. The applicant ieeds to know where QPTR is measured (or

)btained) and that power should be reduced 12%

rom 100% (rated thermal power) or why power is educed. One of these items should be removed. If I now that we lower power to monitor FQ@Z, and hat power should be lowered to 88%, I would answer B, and I did not need to know where to get

)PTR data from. (then the question does not match he K/A).

JEW 0112312013 Jlade changes as requested SAT 212812013 83 H 2 S 028G2.4.30 Question appears to match the K/A.

Appears to be SRO only. SAT NEW 0112312013 84 H 2 X E 037AA2.07 Question kind of matches the K/A.

Appears to be SRO only. Do not believe distractor B is plausible. I can understand how someone can come up with neither monitor exceeds a tech spec limit, and both exceed, but not one.

NEW 0112312013 Rewrote question to test action levels. Are all the action levels correct for the corresponding numbers? Will discuss. Made changes as requested SAT 2I28I2013.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 85 H 2 S 055AA2.01 Question appears to match the K/A.

Appears to be SRO only knowledge. SAT NEW 0112312013 86 H 2 X X E 005A2.01 Question appears to match the K/A.

Appears to contain some SRO knowledge.

Distractors A and B do not appear to be plausible.

Suggest changing question to read:

Which ONE of the following identifies the action required in accordance with 3-ONOP-050, Loss of RHR?

Isolate containment and:

A. Start an RCP, and feed associated SIG with auxiliary feed water flow.

B. Start an RCP and feed associated SIG with standby feed water flow.

C. Open SIG atmospheric dump valves; feed SIGs with auxiliary feed water flow.

D. Open SIG atmospheric dump valves; feed SIGs with standby feed water flow.

till not sure A and B distractors are plausible.

NEW 01I2312013 Reworded question as requested. Discussed plausibility of A and B, increased RCS pressure to 210 psig to make A and B more plausible.SAT 212812013

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 87 F I X X U 008G2.1.23 Question appears to match the K/A. Do not believe it is SRO only. Had question reviewed by another examiner and he agreed it was not SRO only. By knowing two CCW heat exchangers are required for power operation, and with only 3C out of service, why would an applicant pick A or D. B has the operator perform an OSP that would be performed for a degraded heat exchanger, not for backwashing one, so why would an applciant pick B? That leaves C as the correct answer, and I arrived at this answer without any SRO knowledge.

The OSP also does not have a title. The question needs to be asked at the On line risk level to make it SRO only (how is it determined etc.)

NEW 0112312013 Replaced question with new question. Need to discuss question. Licensee to noodle on question to make it clearer. Made changes as requested SAT. 212812013 88 F 2 X E 012A2.O1 Question appears to match the K/A.

Appears to have an SRO only aspect to it.

Distractors A and C are not plausible. Is there a case where Turkey Point only places one of the channels bistables in trip? I dont think so.

NEW 01123/2013 After further discussion determined that there were times only one bistable is placed in trip.

Items in the stem were changed to make A and C more plausible. SAT 2128/2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 89 H 2 X X E/U 026G2.4.45 Question kind of matches the K/A.

There is only one annunciator in the stem, but the applicant is informed that RWST level is 152,000 gallons. Do not believe the question is SRQ only.

Going to ES-i .3 is on the foldout page and that is RO knowledge. Second part of question is in the ARP. I do not believe it is SRO only either. ES-i .3 has the operator secure one CSP but not both. With containment pressure at 24 psig, CSPs will not be secured until directed. Will have another examiner review the question.

Distractors A and D are not plausible as written. With CTMT pressure at 24 psig, no one is going to secure both CSP.

NEW 112412013 Rewrote question 31 days after a LOCA, Conditions do not appear to be plausible or operationally valid. Need to work on this question. 31 days is part of Up rate analysis, decided to change the question to LOCA occurred 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. SAT 212812013 90 H 2 X U 062A2.04 Question appears to match the K/A. Does not appear to be SRO only. Initial part of question can be answered using RO systems knowledge (did the reactor trip as a result of the loss of 4P08 or not.

That gets the selection down to A or B. The correct answer is a one hour action statement. This is RO knowledge. Therefore, the question can be answered using only RO knowledge.

MODIFIED 112412013 Completely rewrote question. SAT 212812013

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

Q# LOK LOD I (F/H) (1-5) Stem Cues TIF Cred. IPaial Job- Minutia #/ Back- Q= I SRO U/E/

S Explanation Focus Dist. Link units ward K/A Only 91 F 2 X E 034A2.O1 Question appears to match the K/A.

Question does have an SRO aspect to it. Again you are testing three for four items in the question, and the applicant need only know two of these to get the correct answer. (Who needs to be evacuated, or who controls access.)

Who controls access, or who should be evacuated.

The second part of the question is acceptable.

NEW 112412013 Rewrote question what procedure does this come from. The stem should state lAW... Then SAT 212812013 92 H 2 X E 071A2.02 Question appears to match the K/A.

Appears to be SRO only. Is SPING channel 5 in the effluent flow path of the gas tank release? If not then distractors B or D are not plausible. (Typically spent fuel pool storage areas normally are not monitored by instruments in the flow stack) Maybe your plant if different. Not sure if reference is required. Will discuss.

NEW 1I24I2013 After discussion rewrote question. New question appears to be acceptable, need to discuss reference. Also add corrective maintenance to stem for sping channel. Made changes as requested, limited reference to 3-12 to 3-15. SAT 2I28I201 3

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

Q# LOK LOD I (F/H) (1-5) Stem Cues Focus T/F Cred. IPaial Job- Minutia #/ Back-Dist. Link units ward Q

K/A I SRO Only U/E/

S Explanation 93 H 2 S 079G2.4.35 Question appears to match the K/A, and appears to be SRO knowledge. Will get another opinion from another C.E. (good attempt at a tough K/A).

NEW 112412013 Allowed the ONOP to be tested due to service air KIA. Tough KIA to match, but it does test an SRO aspect, and local actions SAT 94 F 2 X E G2i37 Question appears to match the K/A, and appears to be SRO knowledge. What is an AR, and why is this plausible? Do not think the Plant Manager is plausible either. Is his permission required for other items?

NEW 112412013 Replaced Plant Manager with Shift Manager.

Need to state SM may. Then SAT 212812013.

95 F 2 X E G2.2.11 Question appears to match the K/A, and appears to be SRO knowledge. Distractor D is not plausible. Typically operators in the control room do not make changes to drawings. Need to replace D distractor.

NEW 1I24I2013 Changed distractor D, now more plausible. SAT 212812013.

96 H 2 X E G2235 Question appears to match the K/A.

Appears to have an SRO aspect to it. With the reference provided, this would be a direct lookup.

The ** note informing the operator of 380 °F is clearly listed and this would be a cue.

NEW 1I24I2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S Removed reference SAT 212812013 97 F 2 X E G2.3.4 Question appears to match the K/A, and appears to be SRO knowledge. Distractor D is not plausible. Especially the part of the plant manager approval is required to allow volunteers to use emergency dose limits.

BANK 1124I2013 SAT 212812013 98 X E G2.3.5 Question appears to match the K/A, and appears to be SRO knowledge. I realize this was on another exam (TP 2009), but I dont know what validity every 15 minutes provides. Do not think distractors containing every 15 minutes is plausible.

BANK 112412013 SAT 2I28I2013 99 H 2 X E/U G2.4.34 Question does not meet the K/A at the SRO level. Will consider replacing the K/A. (this question could be improved if the basis document was used for performing of the RO tasks during an emergency (why or why not does the RO do something) Just a thought.

NEW 1!2412013 Changed question to a time line to allow the applicant to determine length of time to get to the required conditions. SAT 2I28I2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 100 H 2 S G24.37 Question appears to match the k/A.

Appears to be written at the SRO level.

NEW 112412013 4 Sats, 5 Unsats, and 16 Enhancements

ES403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Turkey Point Nuclear Plant Date of Exam: 03/15/2013 Exam Level: ROISR Initials Item Description a b c 1 Clean answer sheets copied before grading N/A

2. Answer key changes and question deletions justified and NIA documented
3. Applicants scores checked for addition errors c\/J) N/A (reviewers_spot_check>_25%_of_examinations)
4. Grading for all borderline cases (80 V2% overall and 70 or 80, ç.s. N/A as_applicable,_4%_on_the_SRO-only)_reviewed_in_detail
5. All other failing examinations checked to ensure that grades N/A are justified U
6. Performance on missed questions checked for training N/A deficiencies and wording problems; evaluate validity of c) questions_missed_by_half_or more of the_applicants Printed Name/Signature Date
a. Grader /
b. Facility Reviewer(*) .

iV/4

c. NRC Chief Examiner (*) 4IZ3k3
d. NRC Supervisor (*)

(*) /

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

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