Revision as of 06:42, 12 March 2020

Text

Initial Exam 2009-302 Final Administrative Documents - Section 7
	ML093430193
Person / Time
Site:	Hatch
Issue date:	12/07/2009
From:	; NRC/RGN-II/DRS/OLB
To:	; Southern Nuclear Operating Co
References
	50-321/09-302, 50-366/09-302, ES-201, ES-201-1
	Download: ML093430193 (107)
	v • d • e

{{#Wiki_filter:FACILITY NAME: _...:..H.;.;..A~T....;:C;..;..H~ _-:..H.:.:..A..;..:T:....;:C;.;.,H.:...-_ _ _ _ _ _ _ _ _ __ Section 7 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 FINAL ADMINISTRATIVE DOCUMENTS CONTENTS: [21 Exam Preparation Checklist [2f (ES-201-1) [21 Final Exam Outline Quality Checklist [2/ (ES-201-2) [2J,Exam [21. Exam Security Agreements (ES-201-3) [if Final Administrative Topics Outline (ES-301-1) Gl Final Control Room & [] & Walk-Through Test Outline (ES-301-2) o o Final Operating Test Quality Check Sheet (ES-301-3) o Final Simulator Scenario Quality Check Sheet [JFinal (ES-301-4) Q Final Transient and Event Check Sheet G1 (ES-301-5) (ES-301-S) G Final Competencies Check Sheet (ES-301-6) o D Final Written Exam Sample Plan (ES-401-1/2/3) - - [t Final Record of Rejected KAs c;(Final (ES-401-4) Gf Final Written Exam Quality Check Sheet [J (ES-401-6) Q/;Final Written Exam Review Work Sheet Q:'Final (ES-401-9) -- d [1 Written Exam Grading Quality Check Sheet (ES-403-1) __ Location of Electronic Files: O:\Hatch Examinations\lnitial Exam 2009-302 Submitted By: Bruno Caballero

srl 02Qr9-s\l:p Sf] 1- filJi'll- fonns-IDs,doe 020f2-sypl-fiual-founs-ms doc ES-201 Examination Preparation Checklist Form ES-201-1

                   ~  ATCrt ATC.H                                                                 Date of Examination: 1IOI2.IoLO~  /2.10[01 Facility:                                                                                                             0 Developed by: Written - Facility             ~ NRC D GI'                II Operating - Facility         Gr NRC D Target                                                                                                                  Chief Date*                                      Task Description (Reference)                                          Examiner's Initials
        -180         1.       Examination administration date confirmed (C.1.a; C.2.a and b)                                 13K
                                                                                                                             $K
        -120         2.       NRC examiners and facility contact assigned (C.1.d; C.2.e)                                    "PU 1JU
        -120         3.       Facility contact briefed on security and other requirements (C.2.c)                          17;J1.

17fi1

        -120         4.       Corporate notification letter sent (C.2.d)       J "'"",-e.

L-L\'\e 41 2.00 2.0b5 5 Jl;U. Jl;J{ [-90] [5. Reference material due (C.1.e; C.3.c; Attachment 3)] Sept Sepf 4, 4 I 20C>~ 2{>()~ "'$)l

                                                                                                                           "$){

{-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-1's, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d) ~ a~ 141 a.~ 2-0b~ 14, 2-0D~ {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility

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licensee (C.2.h; C.3.e)} :r

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( JPM~~~~d4, 200~ Proposed examinations (including written, walk-through JPM~~~~d.:h zoo') {-45} 8. scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form 7tJX 7tJlL ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

         -30         9.                                                                      (C.1.ilo.2.

Preliminary license applications (NRC Form 398's) due (c.1.lilo.2.g; g; "17fK "11:fK ES-202) ~f 24 "24 ocr

         -14         10.      Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; ES-202)                                                  OC+ ]]2/2-2 / kilO'}

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         -14         11.       Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) tJ/A tl/A
         -14         12.       Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)                      -;:tJJL
                                                                                                                             -f}fJL
          -7         13.       Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)                                             oc.t 'Z.-o, Qct     t..-o, z-oot:(

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          -7         14.       Final applications reviewed; 1 or 2 (if >1 0) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent               ~

(C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

          -7         15.       Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)
                                                                                                                            ~
          -7         16.       Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)                                                       /'/IJL 1)A...-

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

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

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Date of Examination: /o/;;J 6/;J&?tJ,{ Initials Item Task Description a b* c#

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

W R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether ali all KiA cateqories cate ories are appropriately a pro riatel sampled. T

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

T E

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

N

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

I M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T test s), and that scenarios will not be repeated from the applicants' audit testis), repealed on subsequent days. da s. o0 c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks ( W 1/ 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 T test{s) (3) no tasks are duplicated from the applicants' audit testis) (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

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

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

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

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

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

G b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. E N N c. Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5. E

d. Check for duplication and overlap among exam sections.

R A e. Check the entire exam for balance of coverage. L

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

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Supervisor Note: # Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines ES-201, Page 26 of 28 r;

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: HATCH Date of Examination: Oct/Nov 2009 Initials Item Task Description a b* C#

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

k'i'1; ,v~ v~ 1Jj{. ~[ W R b. Assess whether the outline was systematically and randomly prepared in accordance with ~ r;':'li I Section D.1 of ES-401 and whether all KIA categories are appropriately sampled. $I~ bt~ T T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. ~fi:'! oft! tJ1L f't.*U~ E N d. Assess whether the justifications for deselected or rejected KIA statements are appropriate. C:~'(

                                                                                                                       '?-f/f 1_    "j                   }{1}~/

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,I'

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number 4+ VIA S

of normal evolutions, instrument and component failures, technical specifications, and major transients. "'~~ Ii/A M~ ,VIA I \ M U

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule \ iIt, without compromising exam integrity, and ensure that each applicant can be tested using L

at least one new or Significantly significantly modified scenario, that no scenarios are duplicated

                                                                                                                                       ,III A

T from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. II 0 1\1

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

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

(1 ) the outline(s) contain(s) the required number of control room and in-plant tasks ! ( W 1 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 , i T (3) no tasks are duplicated from the applicants' audit test(s) , (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria , i on the form. i

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

                                                                                                                                    ~ ;~~~
                                                                                                                        ;.~jq IJJ!~" I~
                                                                                                                        ~

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

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

d..t< cJ!.6i-G E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. (!i~ (:'i.i) '8'1,- 1J' 1.... N E

c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. vM

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                                                                                                                                                    -[:</...

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d. Check for duplication and overlap among exam sections. 1Y1L L e. Check the entire exam for balance of coverage. #-"

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f. Assess whether the exam fits the appropriate job level (RO or SRO).SRO).* tI-f( ~ 11ht p;~~.

Date

a. Author CI'-'tii /)Owt? 5~/"7/;;1Z

                                                                                                                                    $/'7/t;'l

b. Facility Reviewer (*)

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c. NRC Chief Examiner (#)

d. NRC NRC Supervisor j..(A t.ux..M.-

J..cA WtD~ AluM /I f.f/...

                                                           --C. WII::>IM.I.NA.I t.c..ec...M-"'t'.                             .
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{ ..,.,. Viv'r ( \ Note: II

                           # Independent NRC reviewer initial items in Column "c";

Not applicable for NRC-prepared examination outlines fU*

                                                                                    "~hief
                                                                                               =tw.lf' chief examiner concurrence required.

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

1. Pre-Examination .

                                                                                                                                                      ... II I\
                                                                                                                                                             } )

oct I" Joe; 11 1.1 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 112/;)("/IJ l lot)'/!) 1 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 licensee's 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 I),ot Q,ot divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Inl?ilr- i41K9- iV~z.r=fom il/~'~'fom 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 DATE ~OT" 1 Plnthonl}Sq \I Pb.rl- Ops ~dr"cJ..r 1./~6/9

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NOTES: ES-201, Page 27 of 28

ES-201 Examination Security Agreement Form ES-201-3 1 J

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of ti).t./o9.

                                                                                                                                               "/)1.;/09"
                                                                                                                                                             /1
                                                                                                                                                                )

0' jI I~ 0'

                                                                                                                                                          ~ 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 licensee's 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 did. Q,ot divulge to any unauthorized persons any information concerning the NRC licensing examinations administered c

during the week(s) of/c/:16lf- If / J~/Ffom of/CI:U/f-lf ~/F10m 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. If!/11.-J C4 r2l2D '--'L 555 (2~1 2*111:;;,

3. ..

                     ])uyven
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4. 0",,'11 WNEF IS 55

5. ;J""t: 'fI M(.WY'r :':h~..J;c f

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8. L'fAco._""l 2;4&-1!O Z.u.j'rA. t.L c...I'"i>~

0PoS .5.... ,;>-;-,." zf"...,k~-r. s~ I~s~(l,u.d J i"I S hI<<. f-vv T jPttt.-r /MJ'IU/~ (JPS rlblG $o{Jv. I" s*.:rC\I(...t\\{ 1=s:::T 'lv" '-.L"""ll'1I , / ,VI..,OlUl 'QVLy ,/VQVX

oJ ES-201, Page 27 of 28

ES-201 Examination Security Agreement Form ES-201-3 1.

1. Pre-Examination , . I' J,.t. }a,

                                                                                                                                                               '"~ II J,.z..Jo~

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of /IJ.(f!6!tJ 9 ft)/c:lt/tl9 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 ~enOOthorized nbt 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 licensee's 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 of /{;/;;6H*~/I/I¥Prom during the week(s) of/4:;f!f- 11jI¥Prom 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.

:::~t4~Q~i1::A-w::::p..-/~=====

2. IID~

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3. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ ____

4. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ ____

5. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ ____

6. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ ____

7. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ ____

8. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ ____

9. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ ____

10., _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

10. _____ ___

11.,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

11. ___ __ ___

12.,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

12. __ _ ____

13.,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

13. __ _ ____

14.,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

14. ____ _ _ __

15._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ ___ NOTES: ES-201, Page 27 of 28

NRC Final ES-301 Administrative Topics Outline Form ES-301-1 Facility: HATCH Date of Examination: Oct 26 2 2009 Examination Level: RO X SRO X Operating Test Number: 2009-302 Administrative Topic Type Describe activity to be performed (see Note) Code* Admin 1 N,R Diesel Fuel Oil and Confined Space ALL Conduct of Operations 2.1.26 (3.4/3.6) Admin 2 D,R Determine Minimum Crew Staffing SRO Only Conduct of Operations 2.1.5 (3.9/4.2) Admin 3 M,R Determine Drywell Floor Drain Leak Rate 2.2.12 Equipment Control (3.7) RO Only Admin 4 M,R Review/Approve Equipment Danger Tagout 2.2.13 Equipment Control (4.3) SRO Only Admin 5 N,R Evaluate a Radiation Work Permit (RWP) and Radiation Control Survey Map 2.3.7 (3.5/3.6) ALL Admin 6 D,R Perform a Prompt Offsite Dose Assessment Emergency ProcedureslPlan 2.4.39 (3.9) RO Only Admin 7 D,R Determine a Protective Action Recommendation Emergency ProcedureslPlan (PAR) 2.4.9 (4.0) SRO Only NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

(:s 3 for ROs; ::;:s 4 for SROs & RO retakes) (D)irect from bank (::; (N)ew or (M)odified from bank (2: 1) (:s 1; randomly selected) (P)revious 2 exams (::;

(

( FINAL ES-301 Control RoomlIn-Plant Systems Outline Form ES-301-2 Facility: HATCH Date of Examination: Oct26,2009 Oct 26,2009 Exam Level: RO X SRO-I X SRO-U Operating Test No.: 2009-302 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* TypeCode* Safety Function Normal Start of Recirc ASD A,L,M,S SF-l SF-1 202001 Recirc System K6.02 (3.1/3.2) Restore RWL With RHRSW D,S SF-2 295031 Reactor Low Water Level Al.08 (3.8/3.9) A1.08 ED Using Head Vents M,S SF-3 295025 High Reactor Pressure A1.01 (2.9/3.0) Roll the Main Turbine A,L,M,S SF-4 ( 245000 Main Turbine Gen. (2.712.6) A4.06 (2.7/2.6) Lower Torus Water Level N,S SF-5 223001A2.11 Primary Containment System and Auxiliaries A2.11 (3.6/3.8) Re-Energize Bus with Diesel Generator A,M,S SF-6 295003 Partial or Complete Loss of AC A1.02 (4.2/4.3) Rod Worth Minimizer Functional Test (RO ONLy) ONLY) A,M,L,S SF-7 201006 Rod Worth Minimizer System A3.02 (3.5/3.4) Loss of Air Actions for Rx Bldg Ventilation A,N,S SF-8 295019 Partial or Total Loss of Inst. Air (2.812.9) K2.08 (2.8/2.9) 1 \

FINAL ES-301 Control RoomlIn-Plant Systems Outline Form ES-301-2 Facility: HATCH Date of Examination: Oct 26, 2009 26,2009 Exam Level: RO X SRO-I X SRO-U Operating Test No.: 2009-302 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) System / JPM Title Type Code* Safety Function SF-l Vent the Scram Air Header M,E,R 295015 Incomplete SCRAM K2.11 (3.5/3.7) SF-6 Locally Start 1B PSW Pump Breaker Without Control Power A,E,M 295004 Partial or Total Loss of DC A1.07 (3.3/3.3) SF-7 Start RPS MG Set D,R 212000 Reactor Protection ( System A1.01 (2.812.9)

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

Type Codes Cdteda Criteria for RO 1 SRO-I 1 SRO-U (A)ltemate path 4-6/4-6/2-3 (C)ontrol room (D)irect (D )irect from bank ::;9/::;8/::;4

                                                                                          -:::.91-:::.8/-:::.4 (E)mergency or abnormal in-plant                                                        ~1/~1/~1
                                                                                          ~1/~l/~l (EN)gineered safety feature                                                                  1           ~l
                                                                                                                ~1    (control room system)

(L)ow-Power 1 Shutdown ~1/~1/~l

                                                                                          ~1I~1I~1 (N)ew or (M)odified from bank including leA)l(A)                                        ~2/~2/~l
                                                                                          ~2/~2/~1 (P)revious 2 exams                                                                      -:::. 3 1 ::;

-: ::. 3 1I::;

                                                                                                               -:::. 2 (randomly selected)

(R)CA ~1I~1I~1

                                                                                          ~l/~lI~l (S)irnulator

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ES-301 Operating Test Quality auality Checklist Form ES-301-3 Facility: ~. 1:. -:c. HA77t/ HA7iJ.l Date of Examination: JO/6)~hO()1 lo/tJJ' Operating Test N~~~(-302 JxOD1 Operatinq N~~~-302 Initials

1. General Criteria a b* c#

a. The operating test conforms with the previously approved outline; changes are consistent with sampling samplino requirements (e.o., (e.g., 10 CFR 55.45, operational importance, safety function distribution). M Ai> 11'I~l. 1iJt 1J;t

b. There is no day-to-day repetition between this and other operating tests to be administered during this examination. ~ (L JI; It !1U-IfU.

c. test(s~(see operating test shall not duplicate items from the applicants' audit testis).

The operatino (see Section D.1.a.) I~ t& 1Cl'l~_ $( J!fX-

d. Overlap with the written examination and between different parts of the operating test is within acceptable limits. # ct. %l1. f}fU.

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

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2. Walk-Through Criteria -- ---- --

a. Each JPM includes the following, as applicable:

                 ***        initial conditions initiating cues
                  ****      references and tools, including associated procedures reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee

operationally important specific performance criteria that include:

                            - detailed expected actions with exact criteria and nomenclature

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                            - system response and other examiner cues
                            - statements describing important observations to be made by the applicant                                  f      C{ 1lJH-  11J1.-
                            -      criteria for successful completion of the task
                           - identification of critical steps and their associated performance standards
                           - restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified j C£ ~

fo11-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. ~ ct-r~ C(, 1NA-Prim'~'~ Pri"mdg~ Date

a. Author ~()+l.O(l'l- 8g" tJlJ.+l.QII't BQ II 71t.It. * '()bdufJ~

JDhdu.,'i r,

b. Facility Reviewer(*) Cjllf/L/f".~ rc-dm C~vftL/~dj ~dm JYldi

                                                                     ~rlti/cfaAbL2--
                                                                             ~.ltA.                U. JJ UA                                '    I
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c. NRC Chief Examiner (#) CJItf>-kL~f3(U) ~N.

gP,UpJ{) CJPr.13*IlL&8flO (3,{2.UpJl) I ~ /~ jp/1Mo loh~/2t;o1

                                                                                                                                /Oa~/2001

d. NRC Supervisor /JJUDULr.W~!

I.J)JJAULT-W~~~J A--rittli.tv .- 1d,

                                                                                                                                  ;. IJ 7.'

l~!ZOt6' l!J/Z NOTE: . -

                                                                                     / l\.

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

                                                                                         ~--
                                                                                             )

tests . 1\

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

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ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility:: E.I. E. I. HATCH Date of Exam: 10/26/2009 10,,,,,/,,nnQ ,... Scenario Numbers: 1 12/4 Operating Test No.: .200 T. ,,', '" ............ QUALITATIVE ATTRIBUTES Initials a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. .A'3 et ct >>U ~

2. The scenarios consist mostly of related events. ~ ~ l1JfJ1 %M..

3. Each event description consists of

the point in the scenario when it is to be initiated
the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

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f£ f?ti

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. pi; C£ 1IX $X

5. The events are valid with regard to physics and thennodynamics.

thermodynamics. :cz ~

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Sequencing and timing of events is reasonable, and allows the examination team to obtain 6. complete evaluation results commensurate with the scenario objectives. fo ct-C(., ~ 11K

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

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

                                                                                                                              /;
                                                                                                                              )/;     CC ~

( 8. The simulator modeling is not altered. JI; ct.-ct- 1#i 1!K

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator perfonnance performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios. rj; C£ 1/fJ(

1/fJ{

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 0.5 of ES-301. pI3 fA C& ~ Ct- ilfJt.

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

Fonn ES-301-6

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

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

A!5 ct ~ 1$t Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1. Total malfunctions (5-8) (p 1r.J 7 ? M M C{, Ct- i?fj{ JlJ1.

2. Malfunctions after EOP entry (1-2) ~.

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0< I a~ I~ !A-6 tt tt- ~ iJJ{ 3. 4. Abnormal events (2-4) Abnonnal Major transients (1-2)

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5. EOPs entered/requiring substantive actions (1-2) ~ ~ ri-

01. A-!> ct rio .A-6 u ~ 1tt1-

6. EOP contingencies requiring substantive actions (0-2) IJ 0 0 ~ C(, ct- ~

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7. Critical tasks (2-3) ~ a ~ #

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ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility:. E.I. E. I. HATCH Date of Exam: 10/2612009 10/26/2009 Scenario Numbers: 5 Operating Test No.: 2009-302 QUALITATIVE ATTRIBUTES Initials a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. ;J6 ct 1iK 1tK

2. The scenarios consist mostly of related events. ,A(3 Af3 UC ~

11ft{

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)

                                                                                                                         )6 fi6 4!- 4!.- 1JKtJK

the event termination point (if applicable)

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4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. 4: 11K 1hf-

5. The events are valid with regard to physics and thermodynamics. ~ Gt.-

M C£ 1!K

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives. # q '$H.. $H..

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

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

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fib t:c 1Jt1-( 8. The simulator modeling is not altered. M

                                                                                                                            )IJ cL 1/fIt   f!JIt

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.

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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. W;

                                                                                                                         ~ C{     cr.. 1Ht-
                                                                                                                                          ~

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

                                                                                                                            )6 fiI; ct: ~
                                                                                                                            ~ ct Each applicant will be significantly involved in the minimum number of transients and events 12.

specified on Form ES-301-5 (submit the form with the simulator scenarios). Lt 1ft, Wt-

13. The level of difficulty is appropriate to support licensing decisions for each crew position. ~ U ~ 1J1t 1J1[

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

1. Total malfunctions (5-8) '7 u A8 U 1fJd( 1Mf-

2. Malfunctions after EOP entry (1-2) J.- AB u ~

3. Abnormal events (2-4) ;:;.,.

                                                                                                 .l                         AB Cl Ci'., ll!k J!k

4. Major transients (1-2) J A13 u lAS ct 1}ff '!J;It

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

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6. EOP contingencies requiring substantive actions (0-2) I/ M ct 't4l ~

7. Critical tasks (2-3) 3 ~ ct ~u i!Jft,

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ES-301 Transient and Event Checklist Form ES-301-5 Facility: Plant E. I. Hatch Date of Exam: October 26th th , 2009 Operating Test No.:2009-302 A E Scenarios p V 1 2 4 5 (Spare) T M P E I L N 0 CREW CREW CREW CREW N I T T POSITION POSITION POSITION POSITION A I C M A T S A B S A B S A B S A B L U N Y R T 0 R T 0 R T 0 R T 0 M(*) 0 C P 0 C P 0 C P 0 C P T P R I U E RO RX 2 2 2 1 1 0 D SRO-I NOR 1 1 2 1 1 1 Neel (11) I/C 3,4, 2,5 4,5 8 4 4 2 I Tharp (16) X X SRO-U 5,6 MAJ 7 8 7 3 2 2 1 D TS 3,5,6 3 0 2 2 RO RX 2 7 2 1 1 0 D NOR 1 1 2 1 1 1 I Purdon (12) Whitson (17) SRO-I X X I/C 4,6 2,4, 5,6 3,6 8 4 4 2 SRO-U ( D MAJ 7 8 7 3 2 2 1 TS 2,3 2 0 2 2 RO RX 7 2 2 1 1 0 D NOR 1 1 2 1 1 1 I Mitchel (13) Wiggins (18) SRO-I X X I/C 3,5 4,6 3,4, 8 4 4 2 SRO-U 5,6 D MAJ 7 8 7 3 2 2 1 TS 4,6 2 0 2 2 RO RX 2 2 1 1 1 0 D SRO-I NOR 1 1 1 1 1 1 I/C 3,4, 3,6 4,5 4 4 4 D SRO-U 5,6 2 D MAJ 7 7 7 1 2 2 1 TS 3,5 2 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, (IIC) malfunctions and one major transient, in the ATC including at least two instrument or component (I/C) position. If an Instant SRO additionally serves in the BOP position, one IIC I/C malfunction can be credited toward the two IIC malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

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

ES-301 Transient and Event Checklist Form ES-301-5 I Facility:

           'yo     ...... E. I. Hatch Plant th Date of Exam: October 26th , 2009          Operating Test No.:2009-302 A

A E Scenarios p V 1 2 4 5 (Spare) T M P E I 0 L N CREW CREW CREW CREW N T I T POSITION POSITION POSITION POSITION I C A M A A T S A B S A B S A B S A B L U N Y R T 0 R T 0 R T 0 R T 0 M(*) 0 C P 0 C P 0 C P 0 C P T P R I U E RO RX 2 7 2 3 1 1 0 D NOR 1 1 2 1 1 1 I Sanford (14) SRO-I X I/C 3,4, 5,6 4,6 3,4, 5,6 10 4 4 2 SRO-U MAJ 7 8 7 3 2 2 1 D TS 3,5,6 4,6 5 0 2 2 RO RX 2 7 2 1 1 0 D SRO-I NOR 1 1 2 1 1 1 II Lyon lyon (15) X SRO-U IIC 4,6 2,4, 5,6 3,6 8 4 4 2 ( D MAJ 7 8 7 3 2 2 1 TS 2,3 2 0 2 2 RO RX 2 1 1 1 0 X NOR 1 1 2 1 1 1 I Costa (Rl) SRO-I I/C 3,5 2,5 4,5 6 4 4 2 D SRO-U MAJ 7 8 7 3 2 2 1 D TS N/A 0 2 2 RO RX 2 2 1 1 1 0 D SRO-I NOR 1 1 1 1 1 1 IIC 3,4, 3,6 4,5 4 4 4 2 D SRO-U 5,6 D MAJ 7 7 7 1 2 2 1 TS 3,5 2 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one IICI/C malfunction can be credited toward the two IIC malfunctions required for the ATC position.

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

( evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

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

ES-301 Competencies Checklist Form ES-301-6 Facility: Plant E. I. Hatch Date of Examination: 10/26/2009 Operating Test No.: 2009-302 APPLICANTS RO X X RO D RO D RO D SRO-I D SRO-I D SRO-I X X SRO-I D D SRO-U D SRO-U D SRO-U D SRO-U D Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 4 5 1 2 4 5 InterpreVDiagnose Interpret/Diagnose All All All All All All All All Events and Conditions Comply With and All All All All All All All All Use Procedures (1) Operate Control All All All All All All All All Boards (2) Communicate All All All All All All All All ( and Interact Demonstrate N/A N/A N/A N/A All All All All Supervisory Ability (3) Comply With and N/A N/A N/A N/A 3,5 2,3 4,6 3,5 Use Tech. Specs. (3) (3) 6 Notes: (1 ) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U. (3) Only applicable to SROs. Instructions: Check the applicants' license type and enter one or more event numbers that will allow the examiners to evaluate evety applicable competency for evety applicant.

ES-401 1 Rev. 9 ES-401.Rev.9 BWR Examination Outline Form ES-401-1 Facility: HATCH Date of Exam: OCT/NOV 2009 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total 1 4 3 3 4 3 3 20 4 3 7 1.

Emergency & & 1 1 1 2 1 1 7 2 1 3 2 N/A N/A Abnormal Plant Evolutions 5 4 4 6 4 4 6 4 10 Tier Totals 27 .- 1 3 2 3 2 2 3 3 3 2 1 2 26 3 2 5

2. 1 1 1 1 1 1 2 1 1 1 1 12 0 2 1 3 2

Plant 4 3 4 3 4 5 4 3 2 3 38 5 3 Systems Tier Totals 3

                                                                                              --                                     -8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 2 2 1 2

1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO

            ../    and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

          /        The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do I v not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.

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

5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of2.5of 2.5 or higher shall be v*/ selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

V 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7. *The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics V/

          'V        must be relevant to the applicable evolution or system.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance

            ../
            /'      ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if   fuel handling equipment is sampled in other iffuel than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
                    # 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs,

              /
              ./     and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
                                                                                                            ---~

ES-401 2 Form ES-401-1 ES-401, REV 9 (RD) (ro) T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 295003AK1.04 Partial or Complete Loss of AC /6 3.1 3.2 ~ 0 0 0 0 0 0 0 0 0 0 Electrical bus divisional separation ................. . 295004G2.4.9 Partial or Total Loss of DC Pwr /6/6 3.8 4.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies. 295005AK3.07 Main Turbine Generator Trip / 3 3.8 3.8 0 0 ~ 0 0 0 0 0 0 0 0 0 0 0 0 ............................. ... Bypass valve operation .............................. I c-==-=--==---==--- Reactor

                                                                                                                 .-_.---.-                                                                  i 295006AA1.02 295006AA  1.02 SCRAM /1                                  3.9    3.8  0 0 0 0 0 0           ~
                                                                                           ~   0 0 0 0                    water level control system ................... .

Reactor water level control system ................... . 295018..\1<3.06 295018AK3.06 Partial or Total Loss of CCW /8 Partla'IOrTotiiliossof /8 3.3 3.3 0 0 ~

                                                                            ~ 0 DOD0 0 0 0 0 0 0                Increasing cooling water flow to heat exchangers......

I I" i 295019AA2.02 Partial or Total Loss of Inst. Air /8

                                                  /8     3.6   3.7   0 0 0 0 0 0 0             ~  0 0 0        Status of safety-related instrument air system loads (see                  II AK2.1-AK2.19)

AK2.1 - AK2.19) ................................ .. i 295021G2.2.40 Loss of Shutdown Cooling /4 /4 3.4 3.4 4.7 4.7 0 0 0 0 0 0 0 0 0 0 ~ DDDDDDDDDD~ Ability to apply technical specifications for a system. 295023AA1.04 Refueling Acc Cooling Mode / 88 3.4 3.7 0 0 0 0 0 0 ~ 0 0 0 0 Radiation monitoring equipment... .................... 295025G2.1.23 High Reactor Pressure / 3 0 0 0 0 0 0 tJ 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~

                                                                                                       ~       Ability to perform specific system and integrated plant procedures during all modes of plant operation.

295026EK3.01 Suppression Pool-Highwaier Pool High Water Temp./ Temp. / 3.8 4.1 0 ~ 0 0 0 0 0 0 0 0 0DD~DDDDDDDD Emergency/normal depressurization................... 5 295028EA1.03 High Drywell Temperature /5 3.9 3.9 0 0 0 0 0 0 ~

                                                                                           ~  0 0 0 0          Drywell cooling system ...............................

Page 1 of 2 4/29/2009 1:47 PM

ES-401, REV 9 (Ro) T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 295030EK1.02 Low Suppression Pool Wtr Lvi LviI15 5 3.5 3.8 ~ 0 0 0 0 0 0 0 0 0 0

                                                                               ~DDDDDDDDDD                                           ........................................... ...

Pump NPSH............................................ 12 295031EA1.05 Reactor Low Water Level Level/2 4.3 4.3 0 0 0 0 0 0 ~ 0 0 0 0 DDDDDD~DDDD Reactor core isolation system: Plant-Specific ........ SCRAM Condition Present and Power 4.0 4.0 0 ~ 0 0 0 0 0 0 0 0 0 . ------~ ---- 295037EK2.07 Neutron monitoring system ........................... .. Above APRM Downscale or Unknown 11 --... -.-... ---.~-- .. --~--------..- ---------- .. _ - - - - - - - - - - --_._-- 700000AK2.07 Generator Voltage and Electric Grid 3.6 3.7 0 ~ 0 0 0 0 0 0 0 0 0 Turbine 1I Generator control Distrurbancecs

~-- .. ----- -- -- -- -- - -- -- -- ------- -- ---- - ----------- -- -- -- -- -

295001AK2.07 Partial or Complete Loss of Forced 3.4 3.4 3.4 3.4 0 ~

                                                                                  ~  0 0 0 0 0 DOD    0 0 0 U 0       Core flow indication................................. .

Core Flow Circulation 11 & 4 -._._---_. __Control 295016AA2.06 Abandonmentl7 Room Abandonment 17 3.3 3.5 0 0 0 0 0 0 0 ~ 0 0 0 Cooldown rate ........................................ . 295024EA2.02 High Drywell Pressure 1 15 5 4.0 0 0 0 0 0 0 0 ~ 3.9 4.0 ~ 0 0 0 Drywell temperature.................................. . 295038EK1.03 High Off-site Release Rate 1 9 19 2.8 3.8 ~ 0 0 0 0 0 0 0 0 0 0 Meteorological effects on off-site release .......... ..

                                  .-.---... - . .- - - - - - - - - - - - - - - - - - - - - - - - - - - - - = c - - - c - -

6OOO00AK1.02 600000AK1.02 Plant Fire On Site 1 8 18 2.9 3.1 2.9 ~

                                                                               ~ 0 0 0 0 0 0 0 0 0 0                  Fire Fighting Page 2 of 2                                                                   4/29/2009 1:47 PM 4129/2009

ES-401 ES*401 3 Form ES-401-1

ES-401, REV 9 ~C>> CRD) T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A A11 A2 A3 A4 G TOPIC: RO AO SRO 29501 OAA 1.05 295010AA1.05 High Drywell Pressure IIS5 3.1 3.4 0 0 0 0 0 0 blJ ~ 0 [J II 0 0 DrywelVsuppression vent and purge.................. ...................... 29501302.4.1 295013G2.4.1 High Suppression Pool Temp./S Temp. 1 5 4.6 4.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of EOP entry conditions and immediate im mediate action steps.

-=:-=--=-=-=-=--=-....

295015AA1.02 Incomplete SCRAM I111 4.0 4.2 0 0 0 0 0 0 ~ [] 0 0 0 ..................................................... RPS ................................................. 295020AA2.03 Inadvertent Cont. Isolation I1 S 5&&7 3.7 3.7 0 0 0 0 0 0 0 ~ 0 0 0 Reactor Aeactorpower power......................................... 295032EK1.02 Secondary Containment Area High SecondaryConiainment 3.6 4.0 ~

                                                                             ~  0 0 0 0 0 0 0 0"         0 0 0                                       ...................................

Radiation releases ................................. '" . Temperature 1 IS5 Cej'/ T~ (e'3'> T~J~"'l..e. ~j ~ j S~c.. flcWcL1~ s<:C- fb.,()chtv"rt- 1~lMih

""Iih

_ . - ...... \\Vf\c._~&i*~

                                                                                                             .___ --::-'-'\\~V~r\~C.  . ~~O'v\ If                    \f   rc ..... _~~

fj ~£V'\M\S prt-es.ewt \Y1.l.~ ) 295035EK3.02 Secondary Containment High 3.3 3.5 3.S 0 0 ~ 0 0 0 0 0 0 0 0 Secondary containment ventilation response .......... .............. Differential Pressure I S 5

                                    ...........     -------------                      - - - - - - - - - - - - - - - - - c......----.

500000EK2.06 High CTMT Hydrogen Cone. I1 S 5 3.0 3.4 3.0 3.4 0 ~

                                                                                ~ 0 0 0 0 0 0 0 0 0                  Wetwell Spray system Page 1 of 1                                                                              4129/2009 4/29/2009 1        :47 PM 1:47

ES-401 ES*401 4 Form ES-401-1

ES-401, REV 9 (I<D) (1<0) T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 203000G2.1.31 203000G2.1.31 RHRlLPCI: Injection Mode 4.6 4.3 D 0 D 0 D0 D 0 D0 D 0 D 0 D 0 D0 D 0 ~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

 - - - .. --- -'--"-' ----.--.----.-.-----------.---                                         -==-==c--=---==-==--==---:-:---:-----.----..

205000KS:OS-----StilitdownCooli-ng 205000K5.03 Shutdown Cooling 2.8 3.1 D 0 D 0 D0 D 0 ~

                                                                                        ~    D 0 D   0 D 0 D0 D 0 D 0       Heat removal mechanisms
                                                                                   --_.-_.=-=:=-=--=--=::-::=---=
                                                                                   ---.-~.                                     .... _-_._------

. 206000K5.05 HPCI 3.3 3.3 DOD 0 0 0 D 0 ~ D 0 D 0 D 0 D0 D 0 D 0 Turbine speed control: BWR-2,3,4

     -                                                                                                      =-==-=--~-:-:--          ...-----

209001K1.09 209001K1.09 LPCS 3.2 3.4 ~ D 0 D0 D 0 D0 D 0 D 0 D 0 D0 D 0 D 0 Nuclear boiler instrumentation

                                                                                                          .---=------:-:--:---:--:---------

209001K1.13 LPCS 2.8 3.0 ~ 0 D D 0 D 0 D0 D 0 D 0 D 0 D0 D 0 D 0 Leak detection 211000K4.03 SLC 3.8 3.9 D 0 D 0 D0 ~ D 0 D 0 D 0 D 0 D0 D 0 D 0 Keeping sodium pentaborate in solution 212000A2.16 RPS 4.0 4.1 D 0 D 0 D 0 D 0 D0 D 0 D 0 ~ D 0 D 0 D 0 Changing mode switch position poSition 212000A2,19 212000A2.19 RPS RPS 3.8 3.9 D 0 D 0 D 0 D 0 D0 D 0 D 0 ~ D 0 D 0 D 0 Partial system activation (half-SCRAM) 0 ~

                                                                                                      ------~-

215003A1.04 --IRM IRM 3.4 3.4 D 0 D0 D0 D 0 D 0 D ~ D0 D 0 D 0 D 0 Control rod block status

                                                                                                    . _ - - - - - - - = - : .. _ . _ - - - - - - - - - - - - -

215004K6.01 Source Range Monitor 3.2 3.3 D0 D0 D0 D 0 D 0 ~ D0 D0 D 0 D 0 D 0 RPS RPS 215005A1.04 215005A1.04 APRM 1j LPRM 4.1 4.1 4.1 4.1 0DDDDDD~DDDD 0 ODD 0 Iill 0 0 0 0 SCRAM and and rod rod block block trip trip setpoints Page 11 of Page of 33 4/29/2009 11:47:47 PMPM

ES-401, REV 9 (ko) (RO) T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 21S00SA1.0S 215005A1.05 APRM 1 / LPRM 3.3 3.2 0 0 0 0 0 0 ~ 0 0 0 0 Lights and alarms 217000K2.03 RCIC 2.7 2.8 0 ~ 0 0 0 [] 0 0 0 0 0 0 RCIC flow controller 218000K1.06 ADS 3.9 3.9 ~ 0 0 0 0 0 0 0 0 0 0 Safety/relief valves 223002K3.21 PCIS/Nuclear Steam Supply Shutoff 2.6 2.7 0 0 ~ 0 0 0 0 0 0 0 0 Traversing in-core probe system 239002A3.05 239002A3.0S SRVs 4.1 4.2 0 0 0 0 0 0 0 0 ~ 0 0 Suppression pool temperature 259002A4.03 2S9002A4.03 Reactor Water Level Control 3.8 3.6 0 0 0 0 0 0 0 0 0 ~ 0 All individual component controllers when transferring from manual to automatic modes 259002K6.04 Reactor Water Level Control 3.1 3.1 0 0 0 0 0 ~ 0 0 0 0 0 Reactor feedwater flow input 261000K3.01 261000K3.01 SGTS 3.3 3.6 0 0 ~ 0 0 0 0 0 0 0 0 Secondary containment and environment differential pressure 261000K3.06 SGTS 3.0 3.3 0 0 ~ 0 0 0 0 0 0 0 0 Primary containment oxygen content: Mark-I&II 262001G2.2.44 AC Electrical Distribution 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 262002A3.01 UPS (AC/DC) 2.8 3.1 0 0 0 0 0 0 0 0 ~ 0 0 Transfer from preferred to alternate source Page 2 of 3 4/29/2009 1:47 1:47 PM

ES-401, REV 9 eRO) (RO) T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: AO SAO 263000A2.01 DC Electrical Distribution 2.8 3.2 D DDODD D D D D 0 ~ D D D Grounds 264000K4.04 EDGs 2.6 2.7 D D D ~ D D D D D D D Field flashing 300000K6.07 Instrument Air 2.5 2.6 D D D DODD D ~ DOD D D D D DOD Valves 400000K2.02 Component Cooling Water 2.9 2.9 D ~ D DOD DOD 0 DOD0 D D D 0D CCWvalves Page 3 of 3 4/29/2009 1:47 PM

ES*401 5 Form ES*401*1 i I ES-401, REV 9 (RO) T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 I I KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC; TOPIC: I RO SRO I! 201001K5.02 CRD HydrauliC Hydraulic 2.6 2.6 0 0 0 0 ~ 0 0 0 0 0 0 Flow indication i 202001A3.04 202001A3.04 Recirculation 3.2 3.1 __ .-___ ._.-=--=---,-=--- 0 0 0 0 0 0 0 0 ~

                                                                                                                 ~   0 0         Lights and alarms IIt I!

202002K2.02 Recirculation Flow Control 2.6 2.6 2.6 2.6 0 ~ 0 0 0 0 0 0 0 0 0 D~DDDDDDDDD - Hydraulic power unit: Plant-Specific .~

                                                                                                                               -Hydraulic                                          wrl'te qveS~
                                                                                                                                                                           ,;::;;p 'vV<0te   C(\J estih"l +.,
                                                                                                                                  -tcvtqt.--{ p~ >-vtfrj
                                                                                                                                  --\-oAqe..-{            >vt.fr ~ tZ.'VLu,'>U()&!-.1t\.d ct'1/Lo~/.\.>je.Mt\.J*vt.t    ~ It-
                                                                                                                                                                                              ...v{- k    AS.!)        SD
-.--            "._-,,-----_.. - --=---------------:~--------~
                                                                                                             .c=--=~=-==--------:-:----:::c-_:_--.----

Ii 204000G2.4.46 RWCU 4.2 4.2 4.2 4.2 0 0 0 0 0 0 (J 0 0 0 ~ DDDDDD[JDDD~ Ability to verify that the alarms are consistent with the I I plant conditions. ii Ii 214000K1.04 RPIS 3.2 3.2 3.2 3.2 ~ 0 0 0 0 0 0 0 0 0 0

                                                                                      ~DDDDDDDDDD                               RMCS: Plant-Specific II 216000A2.10                   Nuclear Boiler Inst.                        3.3 3.3   3.S 3.S  0 0 0 0 0 0 0 ~ 0 0 0 DDDDDDD~DDD                               Rapid vessel depressurizations                                                   i I

I I I I II 233000K4.06 Fuel Pool Cooling/Cleanup 2.9 2.9 3.2 3.2 0 0 0 ~ 0 0 0 0 0 0 0 DDD~DDDDDDD Maintenance of adequate pool level i I _ . _ - - _ _ _ _ 0 _ _ _ _ _ _- - - - - _ _ _ _ _ _ 0 _ _ _ _ . _ - - - - - - - - - - - - - - - - -

                                                                                                                      ._-----::-:-:---:----:-:-----:---_._------                                                I 234000K3.04                    Fuel Handling Equipment                     2.9 3.8 2.9   3.8  0  0  ~  0 0 0 0 0 0 0 0 DD~DDDDDDDD                                core modifications/alterations                                                  I I

II 241 OOOA 1.24 241000A1.24 Reactorffurbine Pressure Regulator ReactoriTurbine 2.6 2,6 2.7 2.7 0 0 0 0 0 0 ~

                                                                                                           ~ 0 0 0 0            Main turbine eccentricity                                                      I Ii:!

286000A4.02 Fire Protection 2.5 2.5 0 0 0 0 0 0 0 0 0 ~ 0 system~piant~-- Applicable component cooling water system: Plant- i, Specific (t.g') Dte.,~ b'rt... ?(}Mf (e..g.) D!e.,sd- R'ft.. F'[)Mf ~ ,~~ ,Mc#

                                                                                                                                               ~Sv~ ~~          ~'v'aWt0~        wtu~1L Wf~)  ~),

290002K6.08 Reactor Vessel Internals 2.9 3.2 0 0 0 0 0 ~

                                                                                                     ~     0 0 0 0 0            Nuclear boiler instrumentation                                             I I
                                                                                                                                                                                                          !ii I

Page 1 of 2 4/29/2009 1:47 PM I

ES-401, REV 9 (Rt>> ( Rc>> T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Kl K2 K1 K2 K3 K3 K4 K4 K5 K5 K6K6 A1 Al A2 A3 A3 A4 G G TOPIC: RO AD SRO SAO 290003A1.04 Control Room Aoom HVAC 2.5 2.8 D 0D 0D 0D D 0 0 D 0 ~ D 0D 0D 0D 0 Control room pressure Page 2 of 2 4/29/2009 1:47 PM

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 t. Conduct ofOperation$. 2~ .

.Equipment
 .Control 3,

3" Radlatl<<)o Radlaticm ContrOl* Control 4, E~ergerlCY Procedures I Plan 3 PointTotal

ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO G2.1.17 Conduct of operations 3.9 3.9 4.0 4.0 0DODDDDDDDD~ 0 0 0 0 0 0 0 0 0 ~ Ability to make accurate. accurate, clear and concise verbal reports. G2.1.6 Conduct of operations 3.8 3.8 4.8 4.8 DOD 0 DOD DOD ~ DODODOODOD~ Ability to manage the control room crew during plant transients. G2.1.8 Conduct of operations 3.4 3.4 4.1 4.1 D D D D D D D D D D ~ OOOOOOOOOO~ Ability to coordinate personnel activities outside the control room. G2.2.1 Equipment Control 4.5 4.5 4.4 4.4 D D D D D D D D D 0 ~ OOOOOOOOOO~ Ability to perform pre-startup procedures for the faCility. facility, including operating those controls associated with plant equipment that could affect reactivity. G2.2.37 Equipment Control 3.6 3.6 4.6 4.6 D D D D D D D D D D ~ OOOOOOOOOO~ Ability to determine operability and/or availability of safety related equipment G2.2.44 Equipment Control 4.2 4.2 4.4 4.4 D D D D D D D D D D ~ OOOOOOOOOO~ Ability to interpret control room indications to verify the status and operation of a system. system, and understand how operator actions and directives affect plant and system conditions G2.3.13 Radiation Control 3.4 3.4 3.8 3.8 D D D D D D D D D D ~ OOOOOOOOOO~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.5 Radiation Control 2.9 2.9 2.9 2.9 D D D D D D D D D D ~ OOOOOOOOOO~ Ability to use radiation monitoring systems - - . - - - - - - - - .-------:::------:--:::.,.------c-------:--------==-=----==------=::--c-:=-----,-:----:----:--:--c:-:c::-----,-----:--- G2.4.26 Emergency Procedures/Plans D D D D D D D D D D 3.1 3.6 OOOOOOOOOO~ ~ Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage. G2A.49 G2.4.49 Emergency Procedures/Plans 4.6 4.6 4.4 4.4 D D D D D D D D D D ~ OOOOOOOOOO~ Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. Page 1 of 1 5/6/2009 6:20 AM 5/612009

ES-401 2 Form ES-401-1 KlA.Toplc(s)

ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 295001AA2.04 Partial or Complete Loss of Forced 3.0 3.1 0 D D0 0 DOD0 0 0 0 ~ 0 0 0 DOD Individual jet pump flows: Not-BWR-1&2 Not-8WR-1 &2.............. . Core Flow Circulation / 1 & 4 -::-::c:--::-:--.:-::--:-::-.-----------------..... ------- .--- ....- .. - ..- - -.- .. -- ... -..- ....- .. - .....-.--.- ........ ---- .................. - .... -.. ... - ... -.----. -.--- 295004G2.1.23 Partial or TOlal Total Loss of DC PwrTS*----4.3 Pwr / 6 4.3 4.4 0 D D0 0 0 0 0 0 0 DODD D D [fD*-~-*- 0 ~ AbiliiY-toperlo;m Ability to pertorm specific system and integrated plant

                                                                             -                               -                                  procedures during all modes of plant operation.                          operation .

295005AA2.02 Main Turbine Generator Trip I/ 3 2.4 2.7 0 0 0 0 DOD D DOD li2l ~ 0 D 0 D 0 Turbine vibration .................................... . 295019AA2.02 Partial or Total Loss of Inst. Air //8 8 3.6 3.6 3.7 3.7 0 DOD0 0 0 DOD 0 0 0 li2l ~ 0 0 0 Status of safety-related instrument air system loads (see AK2.1 - AK2.19) ................................. . -_._---_._---- ..... __._---_.. _-...,--:-...,--::--=--==--==--=---==-=- ---------_._---..

                                      --. ----------                                                                   - -----~-------.-----        __._--

295030G2.1.20 Low Suppression Pool Wtr Lvi / S 5 4.6 4.6 DOD DODD 0 0 D 0 0 DOD 0 0 0 ~ Ability to execute procedure steps. 295031G2.2.44 Level / 2 Reactor Low Water Level/2 4.2 4.4 0 0 0 DOD 0 0 0 DOD 0 0 0 0 D ~ Ability to interpret control room indications to verify the status and operation of a system. system, and understand how operator actions and directives affect plant and system conditions 700000AA2.03 Generator Voltage and Electric Grid 3.S 3.5 3.6 0 DOD0 0 0 DOD 0 0 0 D ~ 0 0 0 Generator current outside the generator capability curve Distrurbancecs Page 1 of 1 4/29/2009 1:47 PM

ES-401 3 Form ES-401-1 ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 295007AA2.01 High Reactor Pressure 13 13 4.1 4.1 0 0 0 0 0 0 0 ~ 0 0 0 Reactor pressure ..................................... 295012G2.4.11 High Drywell Temperature 1/5 5 4.0 4.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of abnormal condition procedures.

~----------

295013AA2.01 High Suppression Pool Temp. 1 5 3.8 4.0 4.0 0 0 0 0 0 0 0 bll b{] 0 0 0 Suppression pool temperature ........................ Page 1 of 1 4/29/2009 1:47 PM

ES-401 4 ES-401-1 Form ES-4.01-1

ES-401, AEV REV 9 SAO T2G1 BWA SRO BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: AO RO SAO SRO 211000G2.2.44 SLC 4.2 4.4 0 0 0 0 ODD 0 0 0 0D 0D 0D ~ Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 21 SOO3G2. 1.27 21S003G2.1.27 lAM IRM 3.9 4 DDDDDDDDDD~ DDDDDDDDDO~ Knowledge of system purpose and or function.

                                                            ----------~------------------                                                                       -----.------
                                                                                             - - - - - - - - - : - = - - - - - - - : - - : - : - : - - : - '....-----'----:c----:----,.,-..,.-'

261000A2.12 SGTS 3.2 3.2 3.4 3.4 0D 0D 0D DOD 0 0 0 0D ~

                                                                                                                 ~     0D 0D 0D                 High fuel pool ventilation radiation: Plant-Specific.
                                                                                                                                               !iigh 264000A2.09                                 EDGs                     3.7    4.1  0D D 0 0D 0D D0 0D D       0     ~    0D D  0 0D               Loss of A.C. power

_ _ * * * " ** _ _ " . . . ,, _ _ _ m _ _ _ _ _ _ 400000A2.02 Component Cooling Water 2.8 3.0 0D D 0 0D D0 0D D 0 0D ~ DOD 0 0 0 High/low surge tank level Page 1 of 1 1011 4/29/2009 1:47 PM 1:47

ES-401 5 Form ES~01-1 ES-401-1

ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 216000A2.14 Nuclear Boiler Inst. 2.9 2.9 0D 0D 0D D0 0D 0D 0D ~ 0D 0D 0D Recirculation flow: Design-Specific 234000G2.2.25 Fuel Handling Equipment 3.2 4.2 0D 0D 0D 0D 0D 0D D 0 0D D0 0D ~ Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. 272000A2.11 Radiation Monitoring 3.4 3.7 3,7 0D 0D D 0 0D 0D D 0 0D ~ 0D D0 0D Leakage and/or breaks from contaminated systems to atmosphere or to other process systems Page 1 of 1 4/29/2009 11:47

47 PM

ES*401 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 L Conduct of OpE:)rations 2. Equipment Control 3, Radiation Control** 4. Plan

ES-401, REV 9 ES401, SRO T3 BWR EXAMINATION OUTLINE' OUTLINE FORM ES-401-1 KA NAME I/ SAFETY' FUNCTION; FUNCTION: IR K1 K2 K3 K4 K5 KS K6 A A11 A2 A3 A4 G TOPIC: RO AO SRO SAO G2.1.26 G2.1.28 Conduct of operations 4.1 4.1 0 0D 0D 0D 0D 0D 0DOD 0 0 0D ~ Knowledge of the purpose and function of major system components and controls. _.. ~---.---- G2.1.37 Conduct of operations 4.3 4,6 4.6 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Knowledge of procedures, guidelines or limitations associated with reactivity management G2.2.1 Equipment Control 4.S 4.5 4.4 0 4.4 D D 0 0D D 0 0D 0D 0D 0D 0D 0D ~

facility, Ability to perform pre-startup procedures for the faCility. including operating those controls associated with plant reactivity. equipment that could affect reactivity_

                                                                                                                     - - - - - _.. _----._----                         ..          ---.~  ..-

G2.2.23 Equipment Control 3.1 3.1 4.6 4.6 0D 0D 0D 0D 0D 0D 0D 0D 0D 0 bll ~ Ability to track Technical Specification limiting conditions for operations. 02.3.13----'-- G2.3.13 --Radiation Radiation Control Control 3.4 3.8 0 D 0D 0D 0D D 0 D 0 0D 0D 0D 0D ~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.4.37 Em ergency ProceduresJPlans Emergency Procedures/Plans 3.0 4.-1 4.1 0D 0D 0" D 0 D 0D 0 D 0 D 0D 0D 0D ~

                                                                                                                 ~       Knowledge of the lines of authority during implamentation of an emergency plan.
                                                                                                                    ----:c=--~-.

G2.4.41 Emergency Procedures/Plans 2.9 4.6 0D D 0 0D 0D D 0 0D 0D 0D 0D 0D ~ Knowledge of the emergency action level thresholds and classifications. Page 1 of 1 4/29/2009 1 :47 PM 1:47

ES-401 Record of Rejected K/As Form ES-401-4 Hatch Oct/Nov 2009 Initial Exam Tier / Randomly Reason for Rejection Group Selected KIA 111 (RO) 295001 295001AK2.05 AK2. 05 Hatch does not have loop-select feature; replaced wi 295001 AK2.07 (Core Flow Indication) III (RO) 111 295016 AA2.07 Torus pressure is not utilized in the shutdown-from-outside-the-control room procedure. Replaced wi 295016 AA2.06 (cooldown (cool down rate) 111 (RO) EA2.1 0 295024 EA2.10 Hatch is a Mark I containment; replace wi 295024 EA2.02 (Drywell Temp) III (RO) 111 EKl.0l 295038 EKl.01 Unable to write a discriminating question at the RO level; replaced wi 295038 EKl.03 (Meterological effects on off-site release) EK1.03 111 (RO) 600000 AK1.01 AKl.01 Unable to write a discriminating question at the RO level; replaced with 600000 AK1.02 (Fire fighting) AKl.02 211 (RO) 206000 K5.04 Asterisk indicates high variability; steam driven pump precludes writing good NPSH question. Replaced wi 206000 K5.05 (Turbine speed control) 211 (RO) 215005 A1.03 AI.04 (same tier and group; i.e., scram & Overlapped 215005 A1.04 & rod block trip setpoints). Replaced wi 215005 A1.05 (lights and alarms) 211 (RO) 218000 K1.05 Hatch remote shutdown panel only has non-ADS valves; i.e., SRVs "B" & & "F" (U2) and SRVs "c" & (U1). Replaced wi 218000 K1.06 (safetylreliefvalves)

                                                     & "G" (UI).

211 (RO) 261000 K3.04 At Hatch, the HPCI barometric condenser vacuum pump discharges to the HPCI room HVAC system (not SBGT). Replaced wi 261000 K3.01 (Secondary Cnmt & & environment differential pressure) ( 211 (RO) 263000 A2.02 At Hatch, chargers do not trip on hi temp; therefore, no effect to DC electrical distribution other than H2 production. Same KIA was used on April 2009 exam but licensee had much difficulty writing question. Replaced wi 263000 A2.01 (Grounds) 211 (RO) 300000 K6.04 Overlap wi 300000 K6.07 (Valves) in tier 2/group 1. Replaced with 259002 Reactor Water Level Control, K6.04 (Reactor FW flow input) 2/2 (RO) 214000 K1.02 Hatch does not have RSCS any longer. Replaced wi 214000 KI.04 K1.04 (RMCS: Plant specific) 2/2 (RO) 233000 K4.08 Hatch is a BWR 4. Replaced wi 233000 K4.06 (maintenance of adequate pool level) 2/2 (SRO) 234000 G2.2.39 Less than or equal to 1I hour Tech Specs are RO knowledge and this is not generally applicable to fuel handling equipment; replaced wi 234000 G2.2.25 (Knowledge ofthe bases in Tech Specs for LCOs & & Safety Limits) 212 (SRO) 2/2 272000 A2.09 Overlap wi 233000 K4.06 (Tier 2 Gp 2 RO exam) and also difficult to quantifylpredict rad monitor response to low fuel pool level. Replaced wi 272000 A2.11 (leakage and/or breaks from contaminated systems to atmosphere or to other process systems) 2/2 (RO) 286000 A4.02 06/26/09: Licensee stated that at Hatch, the Diesel Fire Pump component cooling water system has no instrumentation available in the control room. Chief Examiner randomly re-selected 286000 A4.05 211 (RO) 215004 K6.01 06/26/09: Licensee stated that the loss or malfunction ofRPS has no effect on the SRMs. (converse could be true but not this KIA KlAas as stated) Chief Chief Examiner randomly re-selected 215004 K6.04 (

ES-401 Written Examination Quality Checklist Form ES-401-6 1~=H=a=tC=h======D=a=te=o=f=E=x=am=: Facility: Plant E. I. Hatch Date of Exam: 11/1212009 Exam Level: RO CRl

                                                                           =11='=121=20=O=9=======E=xa=m=Le=v=e=I:=R=;=O=CRl==S=R=O=[RJ=><'==:I SRO [RI Initial Item Description

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

2. a. NRC KlAs KJAs are referenced for all questions.

b. Facility leaming learning objectives are referenced as available.

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

4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office). .~

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

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

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

!\ 7. Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly 44 / 19 selected KlAs KJAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right. t1 j() I 'Ih

                                                                                                               .{ CJ /0          /e-eo
                                                                                                                              '/6/

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

9. Question content conforms with specific KIA KJA 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.

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

(\ \ \ Printed Name / Sign~lre Sign~re *. IIfi /J /J /I

/J

a. Author H-rr+ho t\ V '"B'lll f-trr+hot\y ~'lll (I )J,~~

A;;l1JAth- n""i!j/ f)~j/t/ !')

/1

b. Facility Reviewer (*) CJ,ihtj6:~

C-h;hr, rtdrvlvnA 1",,--:::' di"VIl/;t,,[ t-.A I'.A v6_j p / P

                                                                                                                  /      ~

fA/-, .Jt/

                                                                                                                                        .J;/

c. NRC Chief Examiner (#) -gR.\)

j&R.VNQ No ~J\L..L£/l.O / '76. J( !Jflf~f1f/J;t..O

                                                                          ~1\1A.£/l.O L'18..,                    hlf/.iMJ

d. NRC Regional Supervisor lJAJL/JUJ..T. '!ltf)l1~lAJT 1f ~I' I (rlilJllJl.I~.--r

                                                                                                     ~
                                                                                                     '-'                   )I Note:

The facility reviewer's initials/signature are not applicable for NRC-developed examinations.

                # Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
                                                                                                                                                             \,
                                                                                                                                                          ,,  "\

ES-401 Written Examination Review Worksheet Form ES-401-9

  ~---~~  ---~-
                 - _.. -    -~     ----     --_._-  -        ---    - - - _... _ - - - - -

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

Q# 0# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- 0= SRO B/M/N Q= B/MiN U/E/S U/EtS Explanation Focus Dist. Link units ward KIA Only Gen The following 5 questions were EXACT repeats from the Hatch April 2009 Exam. [Refer to NUREG 1021, ES-401, Section D.2.f (pg 8)] RO-4 items: 0#1 (Q#1 Q#1 0#19 (Q#18 (0#1 April 2009); Q#19 (0#18 April 2009); Q#50 0#50 (Q#50 (0#50 April 0#73 (April 2009 Q#73); 2009); Q#73 0#73); SRO-1 item: 0#98 (Q#98 Q#98 (0#98 April 2009) Gen The following questions were submitted as MODIFIED from the Hatch April 2009 Exam: 0#10 (Q#10 Q#10 (0#10 April 2009) ;0#54

                                                                                                                                         ;Q#54 (mod April 2009 Q#54);

0#54); Q#55 0#55 (mod April 2009 Q#55); 0#55); Gen The following RO questions were preliminarily determined to be outside the acceptability ranges of NUREG 1021: 0#22, Q#34, Q#22, 0#34, Q#48, 0#48, Q#59, 0#59, Q#65, 0#65, Q#66, 0#66, Q#75 0#75 = 7 After discussions w/ licensee, the following RO questions were determined to be outside the acceptability ranges of NUREG 1021: Q#48, 0#48, Q#59, 0#59, Q#65, 0#65, Q#66 0#66 = 4 Gen 20% The following SRO questions were preliminarily determined to be outside the acceptability ranges of NUREG 1021: Q#77, 0#78, Q#81 0#77, Q#78, 0#81,, Q#82, 0#82, Q#85, 0#85, Q#89, 0#89, Q#92 0#92 = 7 After discussions w/ licensee, the following SRO questions were determined to be outside the acceptability ranges of NUREG 1021: 0#77, Q#81 Q#77, 0#81,, Q#82, 0#82, Q#89, 0#89, Q#92 0#92 = 5 Gen The following questions need to be assessed for knowledge overlap and throughout the exam review process: 0#18/51; Q#19/39/84; Q#18/51; 0#19/39/84; Q#24/43; 0#24/43; Q#57/80/28; 0#57/80/28; Q#440#44 && inplant JPM; Q#50/36; 0#50/36; Q#65/93; 0#65/93; and Q#89/61 0#89/61 Gen The phrase "the Shift Supervisor will direct. .." is not a requirement direct... for SRO only questions, and its use may unnecessarily raise the reading burden.

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

B. Q# LOK LOD LOO (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO B/MIN B/MiN UlEtS U/E/S Explanation Focus Dist. Oist. Link units ward KIA Only I I I I I I I I I I I I I I I I I Instructions I [Refer to Section D0 of ES-401 and Appendix B for additional information regarding each of the following concepts.]

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

2. Enter the level of difficulty (LOD)

(LOO) 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., (Le., 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 Itlilt~ri~1ilieiieptab!' 'ml 4.

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

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

           ***            The question is not linked to the job requirements (Le., the question has a valid KIA 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 (Le., 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 KIA and those that are designated SRO-only ( KP..""."., '1IIiiIIt*

(K(&ilr;l!:tjiQ~p~l?l~vlill.mi§m~~EiiY!)8QQeptapl,?).

6. Enter question source: (B)ank.

(B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.1. 0.2.f.

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

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

ES-401 2 Form ES-401-9

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

8. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 8ack-Back- Q= SRO 8/M1N B/M/N U/EtS U/E/S Explanation Focus Dist. Link units ward KIA Only 1 H 2 8 B e 201001 K5.02 S 1 .Exact REPEAT from 2009-301 April exam, Q#1. The question 1.Exact should be randomly selected from the bank. Discuss wi licensee.

2. Licensee agreed to remove the diagram and test applicants' knowledge of flow with respect to flow setpoint following a manual scram. QUESTION IS SAT.

2 H 2 x x x N e 202001 A3.04 S 1. Cue: Ask the licensee why 69% power was chosen. [speed limiter #2 steam flow setpoint is 65%.] Ask the licensee why the stem needs to state that both feed pumps are operating? (will 1 pump suffice at this power?) Ask the licensee why the word "RED" is capitalized?

2. Partial: Since the question stem does not specify the lowest "c" is also reactor water level, an applicant could argue that "C" correct IF the steam flow setpoint was not exceeded, i.e.,

Le., 69% power is too close to the 65% steam flow setpoint. Suggest adding a statement to the stem that the lowest reactor water level achieved was 36" and was subsequently recovered by the 28 2B RFPT. Will the unit response be the same at 100% power? If so, then pick a higher initial power. Discuss wi licensee: licensee.

3. #/units: Provide exact label name and Panel 2H11-P602 Pane12H11-P602 identification to the ASD runback run back lites. 34S0-831-001-2 34S0-B31-001-2 uses the terminology as follows: "red Recife Recirc ASD A Runbaek Runback light at panel 2H11-P602': Ask the licensee if this is the exaet exact wording on the light as labeled on the control board.

4. Concern was: Since #2 limiter depends on RWL < 32" (or SF >

65%), this question may not have enough information, i.e.,Le., would be a simulator "prediction." Fixed by changing power to 90%. QUESTION IS SAT

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N U/EIS Explanation Focus Dist. Link units ward KIA Only 3 H 2 x x x N e IS 202002 K2.02 S 1. Cues: The fill-in-the-blank statement is a cue because it pOints points the applicant to the fact that both pumps operate in the same fashion, i.e., Le., they'll either both trip or both continue to run even though the power supply is only 4KV Bus 2C. The fill-in-the-blank statement does not allow for the applicant to demonstrate a knowledge of the common cooling pump power supply for both ASDs. Suggest re-working the question to test the applicants knowledge that both ASDs will trip [following a loss of Bus 2C] instead of just one ASD tripping.

2. Cred Dist: The second part of the choices is not symmetrical, i.e.,

Le., "0" is the only choice that states that the pumps will not trip.

3. Q=KlA: Suggest limiting the question to test the power supply to the Adjustable Speed Drive (ASD) and auxiliaries.

4. Changed 2nd 2 nd part of "A" to match ~ 2nd part of "D." Question requires knowledge of reactor feed pump oil pump power supplies. QUESTION IS SAT.

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

B. Q# LOK LOO (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO B/MiN U/EtS UlEtS Explanation Focus Oist. Link units ward KIA Only 4 H 2 x M e 203000 G2.1.31 S 1. Stem Focus: Why does the stem state that the unit is in Mode 3?

2. Stem Focus: Were the "A" and "0" pumps overridden off?

Suggest re-wording as follows:

                                                                                               "Unit 2 was operating at 100% when a LOCA occurred and the following conditions currently exist:

Orywell pressure at 3 psig Drywell
RPV pressure at 500 psig

                                                                                                     *                  [normal level}

RPV level at [normallevell

RHR"A" RHR "A" and "D""0" pumps overridden off
RHR"C" pump running in LPCI mode
RHR "B" pump running in Torus Cooling mode WOOTF identifies the control room panel that provides flow indicators for BOTH RHR loops and the expected flow indication on these flow indicators?

A. 2H11-P601; Both loops flow indicators will have flow B. 2H11-P601; ONLY one loop's flow indicator will have flow C. 2H11-P602; Both loops flow indicators will have flow o. O. 2H11-P602; ONLY one loop's flow indicator will have flow

3. Stem Focus: The fill-in-the-blank statement is grammatically incorrect; Le.,

i.e., "when the operator looks at flow will determine ... "

4. Partial: Is there any flow indication [or anything that can be indication) at all on Panel construed as flow indication] PaneI2H11-P602?

2H11-P602? Verify with licensee

5. Suggested changes incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SROSAO B/MIN U/E/S U/EIS Explanation Focus Dist. Link units ward KIA Only 5 F 2 x x N e 204000 G2.4.46 S 1. Partial: An applicant can successfully argue any of the choices as correct in an appeal. The word "valid" and "DIRECTLY" "DIAECTLY" in the stem make all choices potentially correct.

2. Cue: The stem statement "Assume each annunciator has been in alarm for 60 seconds" can be a cue to the applicant because the correct answer ("A") is the only alarm with an associated time delay.

Suggest re-working the question to the following: Unit 1 was operating at 100% power with the following RWCU indications:

RWCU Inlet Flow Indicator R609: 245 gpm
RWCU Demin "A" '~" &

                                                                                                                          & "B" "8" Flow Ind R605A1B:       gpm each 115gpm R605A18: 115 The following alarm is subsequently received, RWCU SYS LEAK (602-421)

Which ONE of the following is the expected flow indication at the 1G31-R615 Cleanup Leak Detection Indicator on Pane11H11-P613, at the time when the annunciator began alarming? A. Ogpm B. 60gpm I C. 15gpm D. 45gpm

3. Changes incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 6 F 2 x x e 205000 K5.03 S 1. Job-Link: It appears that the crew is violating procedure with reactor level as stated at 30." Suggest removing the level provided in the stem and asking applicant for the required minimum level lAW 34S0-E11-010-1.

2. Stem Focus: RHR flow does not specify whether this is one loop (or two).

3. Job-Link: Ask the licensee how is the "corrected level' is determined or calculated. Suggest asking the applicants to determine the required 1C32-R606A, B, 8, & C level indications [let them determine what the level indicators should ind.icate indicate to ensure natural circulation path has been established.]

4. Licensee re-worked question to address items 1 & 2.

QUESTION IS SAT. 7 H 2 x x B e 206000 K6.05 S 1. Cred Dist: "C" and "0" "D" may not be plausible since the second part (trip on overspeed) can never occur on HPCI because the stop and control valves are both "oil-to-open" (Le., held closed by spring pressure). Discuss this wI wi the licensee. Suggest the following fill-in-the-blank statement:

                                                                                               "When the HPCI High Water Reset pushbutton is depressed, the              will open and the ramp generator                 limit the control valve position. "

A. FOOt; will B. FOOt; will not

c. Stop Valve; will D. Stop Valve will not

2. Stem Focus: some terms in the stem can be improved such as th bacl<' vs. lowered) and 5tfi bullet 3rd bullet ("decreased bac/('

("pushed' ("pushed'vs vs depressed).

3. Plausibility is that RCIC operates opposite than HPCI.

Licensee incorporated suggestion. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1#/ Back- Q= SRO B/MIN B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 8 H 2 x M e Ii 209001 K1.09 S 1. Q=KlA: The proposed question targets 209001 A3.01 ["Ability to monitor automatic operations of LPCS, LPeS, including valve operation. '1 The required KIA is knowledge of physical operation."] connections and/or cause effect relationships between LPCS and nuclear boiler instrumentation. Although the proposed question deals with the parameter of reactor pressure [and its impact on the LPCS valve operation], it does not test the applicants' knowledge of the relationship between tile the valves and the transmitters. Suggest writing a question testing the applicants' knowledge of which level transmitters are used to initiate LPCS [N091A, B, C,

                                                                                                   & OJ 0] and/or which reference legs these instruments instruments utilize

[D003A provides N091 B & 0; D003B provides N091A Cl. N091 A & C). Another possibility is to write a question testing the applicants' knowledge of how the reactor pressure instrument pennit permit opening of the injection valves, i.e., < 425 psig (U2), i.e., do the pressure instruments take into account the static head of the coolant in the recirc loops or do they simply measure the steam dome pressure. [pressure instrument tap point: steam dome or recirc loops].

2. Licensee fixed question by testing applicants' knowledge of where pressure instrument taps off of. QUESTION IS SAT.

9 F f: S 209001 K1.13 H 1. Licensee classified this question as Higher Order. Discuss whether this question is Fundamental knowledge wI w/ licensee. Question is SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= U/EIS SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 10 F 2 M E 211000 K4.03 S 1. This question was previously used on the April 2009 exam Q#10 with slightly modified tank levels. [The[ The choices are identical; however, the Figure "A" tank levels has been changed.] Discuss wi licensee how the question was randomly selected and criteria to classify as "modified.". Discuss changing the 1st st portion of the question wi licensee. Alternatives include: Suggest writing a question to test the applicants' knowledge of how many immersion heaters [2] and the power supply to the immersion heaters [R24-S012 and -S011, A&B, respectively] or strip heaters (heat tracing) on the pump suction line piping. Alternate possibility is to test applicants' knowledge of temperatures at which immersion and strip heaters cycle. Suction line heat tracing can also cause an alarm in the control room at 55 degrees.

2. Question was already modified to ask for COLD shutdown [B] vs HOT shutdown [B]. QUESTION IS SAT.

11 H 2 x x x B E 212000 A2.16 st S 1. Cred Dist: "A" is not plausible because if the 1st part is correct, nd then the 2 nd part can never be correct.

2. Stem Focus: In order to ensure that "0" remains plausible and avoid potential cues, the fill-in-the-blank statement should be split into two separate sentences as follows:

                                                                                                  "Placing the Reactor Mode Switch to the START & HOT STBY position ___ cause an automatic scram signal.

After the mode switch has been placed to the START & HOT STBY position, all source range monitors (SRMs) ___ required to be immediately fully inserted.

3. #/units: The 34GO-OPS-13-1 lists the mode switch position as "START & HOT STBY" [not Start/Hot Stby]

4. Licensee re-wrote question to test applicants' knowledge of if a scram will [or will not] occur and what required procedure action afterwards. QUESTION IS SAT.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws s.

5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-S) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- U/EiS Q= SRO B/MiN U/EtS Explanation Focus Dist. Link units ward KIA Only 12 H 2 x x M e 212000 A2.19 S 1. Partial: "B" can also be argued as correct by an applicant because bypassing IRM "G" is an action required by the applicable annunciator response procedure. [even though it can't be done ... it's still listed in the ARP.]

                                                                                                                 .. .it's

2. Stem Focus: the stem refers (twice) to "the applicable annunciator procedure..". This is sufficiently vaguetovague to allow several correct answers or no correct answer. On the other hand, if the name of the "applicable annunciator procedure' is listed, [REACTOR AUTO-SCRAM SYSTEM A TRIP] then the 51 answer to the 1st part of the question is given away.

Since question deals with similar situation as previous Q#11 and Q#14 [IRM range during a plant shutdown or startup], suggest re-working the question to power operations and note the following allowance for A2 KIA statements in NUREG-1 NUREG-1021021,, Rev 9, Supp 1, ES-401, Section 2.a (page 6 of 33):

                                                                                                 "When selecting or writing questions for KlAs that test coupled knowledge or abilities (e.g., the A.2 KIA statements in Tiers 1 and 2 and a number of generic KIA statements, such as 2.4.            1, in 2.4.1, Tier 3), try to test both aspects of the KIA statement. If that Is    is not possible without expending an Inordinate   inordinate amount of resources, limit the scope of the question to that       th~t aspect of the KIA statement requiring the highest cognitive level (e.g.,

the (b) portion of the A.2 KIA statements) or substitute another randomly selected KIA. KIA."n Suggestion: Write question at 100% 100% power with RPS MG set trip and ask applicant to predict some alarms that will be received and then test specific required actions out of the procedure used to recover from the MG set trip, i.e., Le., how to place on alternate power supply, etc.

3. Licensee proposed using a Brunswick 2008 exam item involving a half scram test and testing applicants' knowledge of how many scram lites are on/off and the minimum way to reset scram switch (one direction or both). ThiS This proposal still did not hit the 2nd portion of the A2 KIA and could be vague with respect to Ops expectations for resetting a scram. Licensee re-wrote another question to ask for RPS MG Set trip impact on RWCU F001 valve and the preferred source of altemate alternate power alignment lAW 34S0-C71 procedure.

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-S) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 13 F 2 x x B e E 214000 K1.04 S 1. Stem Focus: The RMCSlRWM RMCS/RWM Rod Block or Sys. Trouble (603-239) annunciator will also be in alarm but is not included in the stem.

2. Cue: The 1st sl and 2nd bullets are not necessary to elicit the correct response.

Suggest the following re-worded question: Unit 1 is at 5% power and the following alarms are received:

RMCSIRWM Rod Block or Sys. Trouble (603-239)

RMCSJRWM

INOPERA T/VE Process computer alarm typer: RPIS INOPERATIVE Which ONE of the following identifies how the Reactor Manual Control System (RMCS) is affected?

A. No control rod can be selected; Full-in and Full-out lights on the full core display are still available B. No control rod can be selected; Full-in and Full-out lights on the full core display are NOT available C. Any control rod can still be selected; Full-in and Full-out lights on the full core display are still available D. Any control rod can still be selected; ; Full-in and Full-out lights on the full core display are NOT available

3. Licensee incorporated suggestion in the form of a fill-in-the-blank item. QUESTION IS SAT.

14 H 2 x e E 215003A1.04 21S003A1.04 th S 1. (annunciator') in Sth Stem Focus: Misspelled word (annunciatot) 5 bullet; also, 2nd bullet has SRMSs. s1

2. Stem Focus: 1st bullet should be START & & HOT STBY

3. Stem Focus: Change IRM "H" to failed downscale and bypassed

4. Stem Focus: Make the fill-in-the-blank statement current tense as follows: "The ROD OUT BLOCK annunciator will clear if the operator ranges or if the operator ___ . (Change 2nd part of each choice to be present tense.)

5. S. Changes incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- B/M/N U/E/S Q= SRO B/MIN Explanation Focus Dist. Link units ward KIA Only 15 F 2 x x x B e 215004 K6.04 S 1. Job Link: The TRM refers to the shorting links as RPS shorting links; Re-word the 1stsl bullet as "Reactor Protection System (RPS) Shorting Links have been REMOVED"

2. Stem Focus: Re-word the 2nd bullet as "Due to a detector malfunction, the SRM "A* "A" count rate begins to rise"

3. Stem Focus: Convert the fill-in-the-blank statement as follows:

                                                                                                  "The
                                                                                                  'The SRM Upscale Trip (High High Scram) set point is and when SRM "A*   "A" reaches this setpoint a will occur.

nd

4. #/units: Change the 2nd part of each choice to either half scram or full scram

5. Comments incorporated. QUESTION IS SAT.

16 F 2 x N e 215005 A 1.04 S 1. Job-link: U2 Hatch Tech Spec 3.3.1, Function 2.b, Simulated Thermal Power - High lists the set point as s:s; 0.57w + 56.8%. The LXR plausibility analysis lists the scram set point as 0.57w

                                                                                                  + 53%. The applicants' need to know that the question is testing their knowledge of the Tech Specs setpoint (not actual).

Discuss wIwi the licensee to ensure that this question cannot be appealed (deleted) after the exam due to no correct answer.

2. Licensee modified the proposed question to ask for the ACTUAL set point in accordance with the annunciator procedure.

QUESTION IS SAT.

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

Q# LOK LOD LOO (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1#/ Back- Q= SRO B/MIN B/MiN U/E/S UlEtS Explanation Focus Oist. Dist. Link units ward KIA Only 17 H 3 x x M t; 215005A1.05 215005 A 1.05 S 1. Q=KlA: KIA requires applicants to predict changes or monitor changes in lights and alarms that are associated with the APRMs. As proposed, the question asks the applicants to predict the current status, i.e., Le., no changes are involved. Suggest modifying the question to test the applicants' knowledge of the current status of ROD OUT BLOCK alarm and then to predict the status of the alarm if an LPRM detector is subsequently bypassed. In other words, provide a list of LPRMs that are bypassed and then ask the applicant what will happen if an additional detector is bypassed. The answer could be no alarm (due to currently bypassed detectors) and no alarm (even when the additional detector is bypassed), etc. This will convert the question to a two-part question and will eliminate asymmetry of "0" being the only choice with a "not."

2. Oist: "0" is not plausible because it is the only one without Cred Dist:

an accompanying "reason" in the choice.

3. Job-link: What is the Ops management expectation for continuing a startup with this many LPRMs inoperable? Would the startup have commenced with this many LPRMs inoperable?

4. Licensee modified question to incorporate having to declare LPRM inoperable and predicting the impact (rod block alarm).

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/EtS U/E/S Explanation Focus Dist. Link units ward KIA Only 18 H 3 x x N e 216000 A2.1 0 S 1. Cred Dist: "CO "C" is not plausible because the stem already states that level swelled to +40"; therefore, eliminating the narrow range is not plausible. fd

2. Stem Focus: Is the 3rd bullet referring to the peak bulk average OW DW temperature or simply one point in the drywell peaks at 155 deg?

th th

3. Stem Focus: The 5th and 6th bullets are redundant and can be combined.

4. Stem Focus: Could not find anything in 34AB-B21-002-2 that prohibits using the wide range instruments when reactor pressure is less than 500 psig. Is this caution embedded in the EOPs? If so, then modify the lAW statement in the stem to reflect exact reference.

5. Job-link: Question poses scenario with a hot drywell and subsequent ED required due to low torus level. KIA requires indications and applicants to predict impact of ED on water level inqications use of mitigating procedures. Usually, the crew will begin ED and not worry about level indications until the ED is'almost is almost complete or until flashing is observed. Not sure if testing the applicants' knowledge of level monitoring immediately when ADS valves are opened is linked to actual job performance.

wi licensee to gain understanding. Could be minutia. Discuss wI Question could be slightly modified to ask applicants when flashing is expected [what OW DW temp & vessel pressure] and the corresponding required procedure [vessel flooding or 34AB-B21-002-2 RPV water level corrections].

6. wi Q#51 knowledge: when WR level instruments Overlap wI can/cannot be used

7. Licensee explained that no overlap issues [w Q#51] blc OW DW spray and vessel flooding are concepts in Q#51. All other items above incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back-Creel. B/M/N U/EIS Q= SRO B/MIN Explanation Focus Dist. Link units ward KIA Only 19 F 2 x B e 217000 K2.03 S . 1. EXACT Repeat from April 2009 exam. [Q# 18]. The question should be randomly selected from the bank (discuss wI wi licensee) or or,, at a minimum, modified in some way.

2. Cues/Cred CuesiCred Dist: The only DC power source is the correct answer. Suggest changing "0" to DC Cabinet 2B ( ) .

3. Discuss how this question does not overlap Q#39 and Q#84.

4. No overlap with Q#39 blc b/c RCIC not listed. No overlap w Q#84 blc b/c of a different power supply board. Licensee incorporated changing "0" to 2R25-S002 (no longer exact repeat).

QUESTION IS SAT. 20 H 3 M S 218000 K1.06

1. Modified from April 2009 exam [0#19].

[Q#19].

2. Stem focus: Re-word the stem question as follows: "Given these trends, WOOTF predicts the EARLIEST time that the ADS valves will automatically open?"

3. Licensee incorporated change. QUESTION IS SAT.

21 H 4 x x N e 223002 K3.21 S 1. Minutia: The proposed question is testing the applicants' knowledge of which 2R25-S103 breaker supplies each TIP machine. Discuss wi Ops and Training management to ensure approval. LOD may be too high. Otherwise, question is SAT. st

2. Stem Focus: Suggest combining the 1st sentence and the first 3 bullets into two sentences.

3. Licensee eliminated the breaker # from the stem. All other TIP machines have their detectors at the PARKED position.

QUESTION IS SAT.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws s. Other

5. 6. 7. 8.

Q# LOK LOO (F/H) (1-S) (1-5) Stem Cues TIF Credo Partial Job- Minutia #1 Back-8ack- 8/M1N U/EIS Q= SRO B/MIN Explanation Focus Oist. Link units ward KIA Only 22 F 2 x B 8 yIJ 233000 K4.06 e 1. Cred Oist: "CO "C" is not plausible because the other choices all provide conservative auto-actions, i.e., re-position, trip, isolate. S "C" is the only choice wlo an auto-action.

"CO

2. Cred Oist: "0" is not plausible because 1) the demins bypassing on low level will not ever terminate a level loss, 2) there is no feature on any demin that causes a low level isolation, and 3) the filter demin bypass valve has no auto-open features at Hatch.

Suggest testing applicants' knowledge of features that ensure fuel pool level is safe, i.e., pumps taking suction from bottom of the skimmer surge tanks [vs discharging to the bottom of the fuel pool] and no piping connections below the level of the transfer gate [vs Unit 1 and Unit 2 cross connect capability via transfer canal].

3. Discussed grading this question as "enhancemenf' item wi licensee blc the submersion depth of the diffusers is plausibility basis blc the decay heat removal (G71) system has diffusers at some mid-position. "B""8" and "0" are partially correct (still). Licensee modified to 8 psig suction pressure trip vs 18 psig [basis is CRO pump suction pressure trip]. QUESTION IS SAT.

23 F 2 x N e 234000 K3.04 st S 1. Stem Focus: Modify the 1sl bullet to specify that the bundle is still seated in the core.

2. Stem Focus: Split up the fill-in-the-blank statement into two separate sentences to eliminate the "and/but' connector.

3. Stem Focus: Modify the 1stst part of "A" and "C" to include the nd word can "still" [be unlatched.] Modify the 2nd 2 part of "A" to include the word can "still" [be raised.] Similarly with the 2nd part of "C."

4. Stem Focus: Modify the stem question to ask "WOOTF identifies how this malfunction will affect the main grapple?"

s.

5. Changes incorporated. QUESTION IS SAT.

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

Q# LOK LOD (FIH) (F/H) (1-5) Stem Cues TIF Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 24 H 2 x x M e 239002 A3.05 nd S 1. Job-link: The 2nd 2 part of the question is directly targeted towards the KIA [monitor torus temperature]; however, however. the 34AB-T23-003-2 is an abnormal operating procedure and the question involves the EOPs. Ask the licensee if the 34AB procedure is still enforceable during an A TWS in the EOP ATWS network. Alternatively, Alternatively. test the applicants' knowledge of one of the EOP requirements related to torus temperature during during an ATWS.

2. Cred Dist: Discuss wI wi licensee how "An "A" and "C" [only placing one loop in torus cooling] are plausible given an A TWS exists wI ATWS wi torus temp at 105 deg and rising. An applicant can,potentially can potentially elim inate "A" and "CD eliminate "C" because prudent to place two two loops in torus cooling anytime an ATWS exists.

3. Ensure no overlap exists wI wi Q#43.

4. No overlap exists blc Q#43 tests applicants' knowledge of PC flowchart entry condition and when scram is required. Licensee incorporated changes listed above. QUESTION IS'SAT. IS SAT.

25 F 3 N S 241000 A1.24

1. Stem Focus: Ask licensee if applicants need to have HMI spelled out. Licensee spelled out. QUESTION IS SAT.

26 F 2 B S 259002 A4.03

1. Stem Focus: Suggest embedding a picture of the controller in the stem.

2. Licensee embedded em bedded picture. QUESTION IS SAT.

27 F 2 x B E 259002 K6.04

1. Partial: Modify the 3rd 3 rd bullet to capitalize the first word (the) and to state that the "A" FW flow signal to the FWCS suddenly fails downscale." This will preclude an

                                                                                                         ......"suddenly applicant assuming a slow gradual failure making "A" also correct.

2. Licensee incorporated changes. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/FTIF Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 28 H 2 x x N eE 261000 K3.01 Stem Focus/Cues: 4th and 5th th bullets are not necessary to elicit S 1. the correct response since both of these items are normal 100% power configuration. [Verify wI wi licensee.]

2. Stem Focus: Split out the fill-in-the-blank statement into two sentences as follows: [the "and/bur "and/buf' connector is confusing]

                                                                                                'The Unit 2 SBGT system "The                                      . The Unit 2 Rx Bldg differential pressure (/1p)

(fJ.p) A. responded correctly; will remain the same. B. failed to start; will remain the same C. responded correctly; will approach O' 0" D. failed to start; will approach 0"

3. Combine the 2nd 2nd and 3rd bullets for conciseness.

4. This question m may a fw.~y " with Q#57 and/or Q#80.

5. Question does not overlap wI wi Q#57 blc that question tests applicants' knowledge of procedural guidance to stop one SBGt following a high rad start. Question does not overlap Q#80 blc that question tests applicants' knowledge of how many trains will be running and procedure selection. Other recommended changes incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ #1 Back- Q= SRO B/MiN U/EIS B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 29 H 3 x N e 261000 K3.06 S 1. Q=KlA: Difficult KIA to hit. The proposed question is testing the applicants' knowledge of the loads provided by 600 V Bus 2C [SBGT 2A, DW OW vent valve 2T48-F319, and Normal DW OW N2 makeup Vlv]. The KIA requires testing the applicants' knowledge of how a loss of the SBGT will affect 02 concentration. Suggest the following enhancement: Unit 2 is inerting the primary containment in accordance with Containment Atmospheric Control & Dilution, 3480-T 34S0-T48-002-2, Section 7. 11, Primary Containment Inerting. The following 7.11, conditions currently exist:

SBGT 2A running
DW 02 concentration is 4.2%, slowly lowering WOOTF predicts how the oxygen concentration and DW venting are affected if the 2A SBGT trips?

A. DW 02 concentration will continue to lower; OW OW DW is not allowed to be vented B. DW 02 concentration will continue to lower, DW is still allowed to be vented with no SBGT in service C. DW 02 concentration will remain at 4.2%; DW is not allowed to be vented D. DW 02 concentration will remain at 4.2%; DW is still allowed to be vented with no SBGT in service

2. Licensee incorporated changes. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EtS U/E/S Explanation Focus Dist. Link units ward KIA Only 30 F +

          .:t.          x                                                 x        B    e E   262001 G2.2.44 st 2                                                                             S   1. Cue: The 1st sentence cues the operator that a power supply caused the 3 alarms. The applicant should be able to interpret/deduce that a DC power supply has been lost wlo interpreVdeduce                                           w/o providing this information.

2. Q=KlA: Test the applicants' ability to interpret control room indications by asking which power supply has been lost [2R25-S004 or another 125VDC cabinet]. Test the applicant's ability to understand how operator actions are affected by asking whether a 4KV breaker can still be remotely opened from the control [or cannot].

nd

3. LOD=1: Loss of DC (provided by 2nd bullet) prevents breaker operation (borderline GFES knowledge).

4. Licensee incorporated Item# 1 & #2 suggestions. QUESTION IS SAT.

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

B. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- B/MIN U/E/S Q= SRO B/M/N Explanation Focus Dist. Link units ward KIA Only 31 H 2 x B e 262002 A3.01 S 1. Stem Focus: The timeline is confusing with respect to the two st fill-in-the-blank statements. The 1st statement is asking for "currenf' status of what's powering the Vital AC Bus. The 2nd statement is asking the status of what's powering the Vital AC [34AB-R23-001-2 ??] have Bus after some procedure actions [34AB-R23-001-2 been completed and, then, after a low voltage alarm is received. Suggest the following: [Caution! May not be technically correct; verify wi licensee] Unit 2 is at 100% power when a loss of offsite power occurs and the "2C" "2C' EOG fails to start. WOOTF identifies how the Vital AC Bus is currently receiving its power and also identifies when the Vital AC Bus will transfer to a different source? A. Vital AC batteries; ONL Y after power has been restored to the non-essentialloads supplied from 600 V Bus 2C B. 600 V Bus 2C; ONL Y after power has been restored to the non-essential loads supplied from 600 V Bus 20 C. Vital AC batteries; ONLY ONL Y after power has been restored to the non-essential loads supplied from 600 V Bus 20 D. 600 V Bus 20; ONL Y after power has been restored to the non-essential loads supplied from 600 V Bus 2C

2. Licensee incorporated suggestion and verified technical accuracy.

QUESTION IS SAT. 32 H 2 x B e 263000 A2.01 nd S 1. Stem Focus: Consider streamlining the 2nd 2 fill-in-the-blank statement as follows: "The readings from meter 1R42-613B mean that the ground 19,000 ohms. [greater than or less than]

2. Discuss use of reference wi licensee. May be acceptable.

3. Use of reference is not direct lookup and is required to answer the question. Does not compromise other questions.

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 33 F 2 x B e 264000 K4.04 S 1. Partial: "A" can be argued as correct. Consider asking for WOOTF per missives is required to flash the permissives field [At engine vs Remotej Remote] and another knowledge item to convert to 2-part question.

2. Licensee modified question to test applicants' knowledge of switch position to start diesel and to flash the field (2 (2 different positions). QUESTION IS SAT.

34 H 2 x x x N lJ V 286000 A4.05 e 1. Cred Dist: "B" and "D""0" are not plausible because a LOOP exists; i.e., an unknowledgable un knowledgable applicant can eliminate these S two choices sim ply because electricity is not available. simply

2. Stem Focus: The 3rd 3rU bullet duplicates the 4th bullet and is not necessary to elicit the correct response.

3. Stem Focus: Modify the 1SIsl fill-in-the-blank statement to incorporate "is required to _ _ in accordance with

[procedurej. [procedure].

4. Partial: The 2nd fill-in-the-blank statement suggests that a "manual" start of the engine driven pump is required even though these engines auto-start at 100/90 (AlB, respectively).

An applicant can potentially argue that there is NO correct answer since the 2nd fill-in-the-blank statement suggests that a "manual" start is absolutely required.

5. Partial: After the 1E EDG output breaker is opened [to de-bus], the EDG will at some point be manually energize the 1E busj,

                                                                                                  tripped.
                                                                                                  "tripped." An applicant can also argue that "B" is correct.

6. Licensee classified as Fundamental; however, may be Higher order question. Discuss wi licensee.

7. Discussed wi licensee and changed grade to "enhancement" "enhancemenf' blc b/c "B" and "D" "0" are plausible since 1E Emerg Bus provides only power to the electric fire pump, i.e., LOOP doesn't mean station blackout. All other changes incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back-Creel. Q= SRO B/MIN U/E/S U/EtS Explanation Focus Dist. Unk Link units ward KIA Only 35 H 2 X X N S 290002 K6.08 Need more information from the licensee to evaluate this test item. This KIA [the effect of losing nuclear boiler instrumentation on vessel internals] is difficult to hit. Does a slowly drifting single level transmitter cause actual level to change and stabilize? Discussed wI wi licensee and accepted question since carryover/carryunder are associated with the nuclear boiler. QUESTION IS SAT. 36 F 2 x x B Ie 290003 A 1.04 S 1. Partial: If refuel floor vent rad K611 monitors "see" 18 mr/hr m r/hr won't the K601A K601 A also "see" same radiation? An applicant could potentially argue as correct? Discuss wI wi licensee.

2. Stem Focus: The stem asks for WOOTF "Signals" "signals" cause MCREC ... aren't these really "plant conditions?" WOOTF Unit 2 plant conditions will cause Control Room pressure to automatically be higher relative to Turbine Buildingpressure?

Building pressure?

3. Stem Focus: The word "relative" may cause confusion. Does Turbine Building pressure mean atmospheric pressure?

4. Cue: Add the instrument numbers for the MSL rad monitors to "C"

                                                                                                 "C" to make symmetrical with choice "A"

5. Ucensee Licensee modified the proposed question to address all items listed above. QUESTION IS SAT.

37 H 2 x S 295001 K2.07

1. Stem Focus: The 4th bullet can be shortened to "2B21-R613, "Core Plate dpl dp/ Rx Core Flow" Flow" recorder...................

                                                                                                                                              .. ................. 19%

2. Stem Focus: The fill-in-the-blank statement can be re-worded as "The 2B21-R613 recorder ___ accurate and actual core flowis ___

flow is - -- .

3. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 Back- U/EIS Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 38 H 2 x x x N e 295003 K1.04 S 1. Job-link: Given a LOOP, HPCI/RCIC inservice, and a Group 1 isolation, it is not realistic that the EOPs haven't already been 111 entered. [The 9th bullet was intended to test applicants' additional knowledge that the 2CD transformer is only allowed if in Mode 4 or 5; however, the premise that the EOPs haven't been entered may make this question unrealistic.] Discuss wI wi licensee. 111

2. Cues: The 8th bullet [" It is desired to power 2C from the 2CD xfrmr'7 and the first phrase in the fill-in-the-blank fill-in-the--blank statement ["to power 2C Bus from 2CD xfrmr'7 are cues to the applicant that 2C is de-energized. The applicant should be able to deduce this information from the provided information in the stem. Suggest asking the applicant the following:

Test the applicants' knowledge of whether or not the 2CD transformer bus link must first be re-Iocated (false) and whether there is an electrical [or administrative only] interlock to prevent supplying both 2C and 2D 20 at the same time. I st

3. Stem Focus: The 1at bullet can be consolidated with the first sentence in the question.

4. Licensee modified question to make EOPs not being entered more realistic (initial conditions are plant is shutdown). Licensee eliminated the cue. QUESTION IS SAT.

39 H 2 x N e 295004 G2.4.09 S 1. Stem Focus: The 1at sl bullet states that 1R22-S016 "trips." The

                                                                                                     trips' may cause confusion; suggest changing to "de-word "trips' energizeS' energizes' to eliminate the possibility of batteries continuing to power the bus.

2. Stem Focus: Spell out the choice "CO "C" and "D" "0" , Reactor Feed pump and Condensate Booster Pump.

3. Discuss how this question does not overlap Q#84 and Q#19

4. Question does not overlap Q#84 blc b/c 1 R22-S022 is power supply for HPCI discharge valve and Q#39 asks about 1R22-S016 which is RCIC valves. Question does not overlap wI wi Q#19 blc b/c 2R25-S001 is power supply to RCIC flow controller and Q#39 asks about 1R22-S016 which is power supply to rcic VALVES.

Licensee incorporated suggestions. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 40 F ~

          -+                                                                        B     e  295005 K3.07 2                                                                                 S 1. LOD = 1; Question is exact repeat from Brunswick 2008 Exam.

Discuss LOD wI wi the licensee and negotiate different question. Suggest testing applicants' knowledge of bypass valve capacity [21%] and when bypass valves are required to be operable [0:: [~ 24% RTP].

2. Licensee modified into a 2-part question which tests applicants' knowledge of the pressure xmitters (for bypass valve control).

QUESTION IS SAT. 41 H 2 x x x M e 295006 A 1.02 S 1. Stem Focus: The stem states that RWL is -1" and rising, however, it does not state from what level indicator this indication is obtained. Is this actual level from the wide range indicators? Incorporate exact level indicator numbers/lD #s. #So [same comment for steam flow indication]

2. Cue: The 2nd 2 nd and 3rd 3rd bullets are cues to an applicant. Combine the 1st51 bullet with the first sentence.

3. Cred Dist: Why are the wide range instruments plausible since FWLC only uses the narrow range? Discuss wI wi licensee.

4. Stem Focus: Suggest re-wording the fill-in-the-blank statement as follows:

                                                                                                   "IF level continues to rise, THEN a FWLC set point setdown will first occur at - __  -. This set down will cause the FW master controller (C32-R600) set       pOint to be automatically changed to setpoint

5. Licensee incorporated suggestions. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 #/ Back- Q= SRO BIMIN B/M/N U/EIS U/EiS Explanation Focus Dist. Link units ward KIA Only 42 H 2 x B e 1. Q=KlA: The proposed question tests the applicants' knowledge of the auto-isolation at 1.85 psig. However, the proposed S question does not test the applicants' ability to operate or monitor the drywelVtorus drywell/torus vent system during a high drywell pressure condition. Since all choices provide an auto-isolation time, then the applicant does not need to know whether or not the high pressure isolation has been bypassed [in the 34S0-T 34S0-T4848 procedure network.] Suggest re-working the question to test the applicants' knowledge of procedure and/or override interlocks. An alternative is to test the applicants' knowledge of whether an auto-isolation will occur at 1.85 psig [using normal 34S0-T48 allowances] and applicable release rates during the drywell leak dryweilleak scenario.

2. Licensee incorporated an additional element to test applicants' knowledge of the additional flowpath available via the fast vent valves. QUESTION IS SAT.

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

Q# LOK LOD LOO (F/H) (1-5) Stem Cues TIF Credo Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EIS U/EtS Explanation Focus Dist. Oist. Link units ward KIA Only 43 F 2 x x M E 295013 G2.4.01 S 1. Partial: An applicant can argue "0" as correct if a prudent decision making call is made with respect to drywell pressure at 1.2 psig and continuing to rise. The stem question asks "WOOTF actions would the crew be "expected" to take? wi Ops management regarding conservative decision to Oiscuss wI Discuss scram the reactor with OW pressure approaching the auto-scram setpoint. One entry condition for RC flowchart is "scram required and> 5% power."

2. Stem Focus: Which indicator is the 2nd bullet referring to?

Provide indicator 10 # and name.

3. Stem Focus: Suggest making drywell pressure 1.2 psig and steady and then re-wording the stem question as follows:

                                                                                               " ___ loop(s) of RHR Suppression Pool Cooling are currently required to be in service. Entry to the Primary Containment Control Flowchart _   ____ _ required. "

4. Ensure no overlap exists wI wi Q#24.

5. wi Q#24 blc Q#43 was modified to test No overlap exists wI applicants' knowledge of whether PC flowchart entry is required and the min torus temp that requires a manual scram. QUESTION IS SAT.

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

B. Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 Back- U/EIS Q= SRO B/MIN U/EtS Explanation Focus Dist. Link units ward KIA Only 44 H I1 x x B E 295015 A 1.02 295015A1.02 st nd rd S 1. Stem Focus: The 1st , 2nd 2 ,and 3rd 3 bullets can be combined with the first sentence for streamlining. Use "past tense" in the initial wording, to convey a sequence of events that have transpired. Unit 2 was at 100% when an auto-scram signal was received. The reactor operator inserted a manual scram signal and all immediate operator actions were taken and the following conditions currently exist:

The 8 white RPS lights on 2H11-P603 are illuminated
Full core display blue lights are all extinguished

2. LOD=1 and/or Cred Dist: "C" "c" and "D""0" offer no discriminatory value and the plausibility is border line.

Suggest the following question: WOOTF identifies the current status of the APRM downscale indications (at panel ?) and the required operator action lAW IA W 31ED-EOP-103-2, 31EO-EOP-103-2, EOP Control Rod Insertion Methods? A. Illuminated; Individually scram control rods B. Illuminated; Place RPS Test Trip Logic Switches to TRIP C. Extinguished; ditto "A" ':.4" D. Extinguished; ditto "8" "S"

3. Discuss whether proposed question was higher order (vs Fundamental) wI wi licensee.

4. Ensure n no §fl!:!~p o " wI wi in-plant JPM [initial RPS assessment actions prior to venting scram air header].

5. No overlap wI wi in-plant JPM because in-plant JPM dealt with venting the scram air header. Licensee incorporated suggestions. QUESTION IS SAT.

45 H 2 x M E 295016 A2.06 nd S 1. Cue: The 2nd bullet is not necessary to elicit the correct response.

2. Licensee corrected and eliminated the 2nd nd "c" and parts of "C" "D." QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ #1 Back- Q= SRO B/MIN U/EIS U/E/S Explanation Focus Dist. Link units ward KIA Only 46 F 2 x x B e 295018 K3.06 S 1. Partial: The 2nd bullet refers to the RBCCW heat exchangers "fouling."

                                                                                                fouling. This bullet is vague and can potentially render none of the choices correct [depends on the extent of the fouling]

Delete 2nd bullet and see suggested revision below:

2. Stem Focus: The alarm alann procedure [RBCCW SYS HEAT EXCH OUTLET TEMP HIGH 650-349] does not provide a "reason" for st throttling open the PSW flow thru the heat exchanger. The 1st fill-in-the-blank statement implies that the ["only"] reason for throttling open the PSW flow thru the heat exchange is to prevent RWCU from isolating.

Suggest testing the applicants' knowledge of RWCU use for RWL control [i.e., blow down operation causes the RWCU system to place a large heat load on the Non-Regen Hx; therefore, this would suffice as a "partial" loss of RBCCW for Q=KlA] as follows: WOOTF identifies a reason why raising PSW flow is required and how this will affect the differential pressure (dEflta (delta P) between RBCCWand PSW? A. Lowers the RWCU return temperature to the vessel in the Regenerative Heat Exchanger; less delta P B. Lowers the RWCU return temperature to the vessel in the Regenerative Heat Exchanger; more delta P C. Lowers the RWCU non-regenerative heat exchanger outlet temperature; less delta P D. Lowers the RWCU non-regenerative heat exchanger outlet temperature; more delta P

3. Licensee incorporated suggestions. QUESTION IS SAT.

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

8. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1#/ Back- B/MIN U/E/S Q= SRO B/M/N Explanation Focus Dist. Link units ward KIA Only 47 H 2 x x N e 295019 A2.02 S 1. Partial: "A" is also correct because Rx Bldg dP will "remain negative' which an applicant can argue is the same as negativd' "remaining as is."

2. Cred Dist: "A" and "B" are not plausible because an un-knowledgable applicant could "reasonably guess" that the dP indication will change in some way even if he/she does not know how the instrument air loss affects the dampers. Suggest the following:

The Reactor Building differential pressure (delta P) will become more and the SBGT Inlet Dampers from from the Reactor Building will fail ___ . A. positive; open B. positive; closed c. C. negative; open D. negative; closed

3. Licensee incorporated suggestions. QUESTION IS SAT.

I

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

Q# LOK LOO LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO B/MIN B/M/N U/EIS U/E/S Explanation Focus Oist. Dist. Link units ward KIA Only 48 H 2 x tJ V 295020 A2.03 S 1. Cred Oist: Dist: "CO "C" and "0" are not plausible an un knowledgable applicant can "reasonably guess" that when an MSIV closes that power will change in some way [fluctuate either up or down].; down).; therefore, power won't remain the same, .. .if .it'llII change somehow.

2. Dist: "A" and "C" Cred Oist: "C" are not plausible because the fill-in-the-blank statement combines "half" and "full" full scram together; I

therefore, the 2nd half of these choices ["will be generated"]generated") is not plausible. Suggest writing a question testing applicants' knowledge of expected reactor power, heat balance power indications following an inadvertent RWCU isolation, including colors of heat balance numbers and/or validity of heat balance information. Refer to 34S0-G31-003-2, Section 7.4, Step #1 Evaluate the impact of removing the RWCU system from service on the computer heat balance. The RO applicant should have knowledge how RWCU isolation affects actual reactor power and reactor power heat balance indications.

3. Licensee did not incorporate suggestion regarding how heat

[power) is affected when RWCU isolates. Licensee balance [power] contended that 1stsl part of question was plausible [if applicant reasoned that bypass valves compensated for pressure transient] transient) and that the test was written at the novice operator level. Licensee modified question to address comment #2 by removing the full scram" and adding an additional MSIV closure to the stem. QUESTION IS SAT. 49 H 2 x x N e 295021 G2.2.40 S 1. Cue: The 1stsl sentence states that Unit 2 is in Hot Shutdown. The applicant should be able to deduce this information based on the 1stsl bullet, i.e., reactor pressure at 134 psig. nd

2. Stem Focus: Suggest re-wording the 2nd fill-in-the-blank statement to state "is required' (vs MUSnMUST)

3. Stem Focus: For the 1stsl fill-in-the-blank statement, enclose the words "without entry to a Required Action Statement'Statemenf' in parenthesis.

4. Licensee incorporated changes. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N UlElS U/EIS Explanation Focus Dist. Link units ward KIA Only 50 H 2 B 295023 A 1.04 S 1. EXACT repeat from 2009-301 April exam, Q#50 Discuss wI wi licensee how question was randomly selected.

2. Overlap wIwi knowledge of proposed Q#36, i.e., refuel rad monitors of 15 mrlhr m rlhr on K601 A 1M cause MCREC to go to pressurization mode.

st

3. Suggest keeping 1st part of the question [related to how low level will drain to] and incorporating a new 2nd part that tests applicant knowledge of how to operate or monitor the different rad monitor (Le., K611 A thru 0 refuel floor vent ex/:laust exhaust))

4. Licensee resolved overlap concem by revising 2nd part of the question to ask for how the local horn hom alarm must be silenced.

QUESTION IS SAT. 51 H 2 N 295024 A2.02

1. Overlap wIwi knowledge from Q#18; Le., i.e., when WR level instruments can! cannot be used> during ED.

Suggest keeping the 1stst part of the question [related to whether OW spray can be initiated or not] and incorporating knowledge item related to interpreting drywell reference leg temperatures (provided) and Caution 1 information.

2. Does not overlap wI wi Q#18 blc that question pertains to when SRVs initially opened at high reactor pressure. Licensee proposed to provide applicant wIwi reference and test knowledge of whether level can be determined. QUESTION IS SAT.

52 H 2 N S 295025 G2.1.23

1. Stem Focus: Add a question to the stem as follows:

                                                                                                         "WOOTF completes the following foJ/owing statement in accordance with 31ED-EOP-107-2?'

31EO-EOP-107-2?'

2. Changes incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFTlF Credo Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EtS U/EIS Explanation Focus Dist. Link units ward KIA Only 53 F 2 x x B e 295026 K3.01 S 1. We (NRC) need a basis document (vs a lesson plan) listed in the question as "in accordance with" to ensure only one correct answer. Need to get a copy of the Hatch Plant Specific Technical Guideline document which was based on the generic BWROG guidelines. Which document is this at Hatch?

2. Stem Focus: Re-word the stem as follows (to avoid duplication wi Q# 43 and eliminate ... (see item 3 below) wI

3. Cue: the 2nd bullet ["Shift Supervisor directs entry into EOP PC Primary Containment Contro/,]

Contro/1 is a cue for Q#43

                                                                                                .. WOOTF identifies the reason that emergency depressurization "WOOTF is required when torus temperature exceeds the safe area of the Heat Capacity Temperature Limit Curve in accordance with the Hatch EOP Basis Document xxx-xxx1237' xxx-xxx 123?'

A. Ensures that the Primary Containment Pressure Limit will not be exceeded. B. Ensures that the Net Positive Suction Head (NPSH) Limits for the ECCS and RCIC will not be exceeded C. Ensures that ..... D. Ensures that.. ...

4. Licensee provided basis and incorporated suggested changes.

QUESTION IS SAT. 54 H 2 x e 295028 A 1.03 1.03 S 1. Modified from April 2009 exam Q#54. Discuss wI wi licensee how this question was randomly selected. April 2009 exam had same answer "c" as correct even though the April exam involved a LOCA. Discuss wI wi licensee.

2. Job Link: Primary Containment Control flowchart in DW/T leg directs the crew to operate drywell cooling fans lAW 34S0-T47-001-1 and to spray the drywell before temperature tem perature reaches 280 degrees. What directs the crew to operate the OW Chiller?

Discuss wI wi licensee.

3. First step in DW/T leg also states to operate drywell chillers lAW

                                                          -                                     34S0-P64. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back-Creel. 8ack- Q= SRO B/MIN 8/M1N U/E/S UlEiS Explanation Focus Dist. Link units ward KIA Only 55 H 2 x x x M eE 295030 K1.02 S 1. Modified from Q#55 on the April 2009 exam to test HPCI (vs RHR pump on previous exam). nd

2. Cred Dist: "B" "8" is not plausible because of the 2nd 2 part, i.e., if RWL is currently rising, then why is flow required to be increased?

3. Cue: The fill-in-the-blank statement cues the applicant to look at a graph. Re-word to state: "HPCI pump operation is NPSH and vortex limits and nd

4. Stem Focus: Make the 2nd part of "CO "C" the same as the 2nd part of "0" gpni' to "C". [These "D" by adding "to 3000 gprrf' rrhese choices will still remain different because of the word "NOr]

5. Licensee incorporated suggestions. QUESTION IS SAT.

56 H 2 x x x B 8 eE A 1.05 295031 A1.05 S 1. Cred Dist: "A" is not plausible because the stem states that RWL is still lowering.

2. Cred Dist: "A" and "B" "8" [leave in AUTO] are not plausible because the last bullet states that the RCIC Flow Controller has failed downscale.

3. Partial: Does the RCIC Flow Indication at 500 gpm mean that a pipe break has occurred?

4. Job-Link: Does the minimum flow value show up on the flow controller? Is flow sensor downstream or upstream of min flow path?

5. Licensee revised question to target all of the items above.

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN BIMIN UlEiS UlEtS Explanation Focus Dist. Link units ward KIA Only 57 H 2 x x x x N e 295032 K1.02 S 1-

1. Job-Link: The stem states that the HPCI Pump Room Area Temp is 2E31-N011. According to the Secondary Containment Flowchart, there are no such prefixes of "E31." The Table 4 on the flowchart [Ambient Temps] lists three temperature elements in the pump room, 2E41-N024, -N030A, and N030B.

2. Partial: "C" "C" can also be argued as correct. On Unit 2: the SBGTs will auto-start at18 mremlhr mrem/hr on 2D11-K609 A-D [Reactor Zone HVAC exhaust] and the Rx Bldg HVAC will also isolate.

This value is also above the Max Normal Operating Value for the SC Flowchart. The 34AB-T22-003-2 procedure is required to be entered [from the override at the top of the SC Flowchart.] 34AB-T22-003-2, Step 4.4.2.2 directs the operator to confirm initiation OR manually initiate SBGT as per 34S0-T46-001-2. 34S0-T46-001-2. In accordance with the 34S0-T46-001-2 NOTE preceding Step 7.2.1.4, the operator is directed to operate both trains of SBGT only WHEN required per another procedure OR IF required to maintain adequate negative pressure. Since the Rx Bldg HVAC is isolated, an applicant can also argue that both trains of SBGT are needed to maintain the negative pressure.

3. Stem Focus: The 1st51 fill-in-the-blank statement has a typo, "Standy."

4. Stem Focus: There is an extra space in the 1st 51 sentence after the word "power."

5. Cue: The 1st51 bullet states that a HPCI steam line break occurs in the HPCI pump room. Is this necessary to elicit the correct response? Discuss wi wI licensee.

nd

6. Stem Focus: The 2nd part of the question can be better aligned with the KIA [operational implication of rad releases] if it tested the SC Flowchart SCIT leg and SC/R leg knowledges associated with not jumpering and running the HVAC fans during a radiation situation [vs testing the HPCI room cooler logic].

7. This question may overlap with Q# 28 and/or Q#80.

8. No overlap wiwI Q# 28 and #80 blc b/c this question implies that more than 1 train is running ... but doesn't tell if 2 or 4 trains running.

Licensee provided new proposed question to target the items listed above; however, the proposal had a cue that Rx Bldg HVAC isolated and SBGT auto-started and both on hi rad. Negotiated removing cue on Rx Bldg HVAC isolation on high rad and left in the SBGT auto-start on hi rad. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SAO B/MIN SRO U/E/S B/M/N U/EIS Explanation Focus Dist. Link units ward KIA Only 58 F 2 x x N e 295035 K3.02 S 1. Job-Link: What is the status of the C007A and C007B exhaust fans? Discuss RB AB HVAC arrangement wI wi licensee.

2. Partial: Because of the wording of "C",

                                                                                                                                         "CO, an applicant can argue there is not correct answer or that "0" is the correct answer. "C" (correct answer) states that reason the C004A continues to run is to "prevent a high Reactor Building DP." The term "high DP" is confusing and can be seen both ways by an applicant. High differential pressure can mean the building is excessively negative [with respect to atmospheric pressure] ... OR OA high differential pressure can be interpreted to mean that the building has a large "positive" pressure with respect to atmospheric pressure. Discuss wI wi licensee.

3. Licensee added status of all fans and fixed wording.

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO B/MIN B/M/N U/EIS U/E/S Explanation Focus Dist. Link units ward KIA Only 59 H 2 B Y

                                                                                          \J  295037 K2.07 S   1. Q=KlA: The Emergency/Abnormal required KIA topic is the interrelationship between an A    TWS and the neutron monitoring ATWS system. The Section 295037 of the BWR KIA catalog is associated only with the ATWS event.

The question, as proposed by the licensee, tests the applicants' knowledge of the P-T-F map following a recirc pump trip when the OPRMs are inoperable, i.e., a scram is required. Apparently, the intent was to meet the KIA topic statement called "SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknowr/'; Unknowri'; however, the required ATWS topic is not being tested. Suggest testing the applicants' knowledge of when boron injection is required (25% peak-to-peak oscillations occurring), including how to determine these oscillations given the APRMlOPRM display screens.

2. Cue: The fill-in-the-blank statement cues the applicant which P-T-F map to use (OPRMs inoperable). This initial plant condition rd should be listed in the first sentence in the stem vs the 3rrl bullet.

3. Reference Provided: Discuss which regions of the P-T-F map are required to be memorized by the applicants and consider not providing a P-T-F map.

4. Licensee provided replacement question; however, it was disjointed b/c of less than 5% and greater than 50% fill-in-the-blank statements. Licensee incorporated suggestion for 25%

peak-to-peak oscillations. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/EtS U/EIS Explanation Focus Dist. Link units ward KIA Only 60 F 2 x x N e 295038 K1.03 S 1. Tough KIA to hit: Since the ROs are responsible for acquiring data for Table TRN-0052, MIDAS Data Input Acquisition, then this KIA can be met by testing applicants' knowledge of data collected, including which elevation to use for an elevated release.

2. Cue: The stem states that the release is elevated. Suggest providing the release point and requiring the applicants' to decide whether a ground or elevated release is occurring. For example, if the release is occurring from the top of the Turbine Building, then the release is considered a GROUND release.

Suggest modifying the 2nd sentence to provide information as to which building Iplant location is causing the release.

3. Cred Dist: "CO "C" and "D" are not plausible because an un knowledgable applicant will choose the 100 meter choices unknowledgable since the word "ELEVATED" is capitalized in the 1st fill-in-the-blank statement (cue) and provided in the stem.

Alternatively, test the applicants' knowledge that wind speed, direction values MUST be the 15 minute averages (not instantaneous values).

4. Licensee incorporated changes, 15 minute average and definition of which way the wind is blowing at 90 degrees. QUESTION IS SAT.

61 F 2 x B e 300000 K6.07 S 1. Stem Focus: The phrase "it is expected that' in both of the fill-in-the-blank statements is not required to elicit the correct response. nd

2. Stem Focus: In the 2nd fill-in-the-blank statement, the "and' "or", i.e., If F017 fails to isolate OR pressure should be an "01",

continues to decrease ...."

3. Licensee incorporated comments. QUESTION IS SAT.

62 F 3 S 400000 K2.02 QUESTION IS SAT.

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

B. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 8ack- Q= SRO 8/M1N U/E/S U/EIS Explanation Focus Dist. Link units ward KIA Only 63 H 2 x N e 500000 K2.06 S 1. Stem Focus: The oxygen and hydrogen concentrations do not specify which space is affected, i.e., drywell and/or torus. Consequently, the PCG flowchart override cannot be used for the oxygen action determinations.

2. For regional consistency, provide reference (PCG Override step) at the end of the exam with the other references. Add bracketed [reference provided] to the stem.

3. Stem Focus: The 1st5t sentence includes power level, etc ....can be streamlined as "A LOGA LOCA occurred on Unit 2 which resulted in the following primary containment oxygen and hydrogen concentrations!'

concentrations;'

4. Licensee incorporated comments. QUESTION IS SAT.

64 F 2 x N e 600000 K1.02 S 1. Stem focus: Consolidate the entire stem by re-wording as follows:

                                                                                               "WOOTF plant fire locations requires a manual reactor scram In accordance with the 34AB-X43-001-2, Fire Procedure, when a major fire exists?'

2. Stem Focus: Re-word "C" exactly like the procedure terminology, i.e., OIL STORAGE TANK ROOM.

3. Stem Focus: Revise "A" and "8" to become a plant location, i.e., "A" is Main Transformer Yard and "8" is some room in the turbine building near cables?

4. Licensee incorporated comments. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/FTIF Credo Partial Job- Minutia #1 Back- U/EIS Q= SRO B/MIN UlEtS Explanation Focus Dist. Link units ward KIA Only 65 H +

          -+                       x                                              N    Y.

U 700000 K2.07 2 S 1. LOD=1: The proposed question tests the applicants' knowledge of which way to position the voltage regulator to increase VARS [raise or lower]. This is borderline GFES knowledge and does not hit the required KIA "Knowledge of interrelationship between grid disturbances and the turbine/generator control" at the RO level.

2. Cred Dist: "A" and "B" are not plausible to an unknowledgable 111 applicant because the 4th 4 bullet states that reactive load is negative and the fill-in-the-blank statement states positive is wanted. An un knowledgable applicant can eliminate LOWER as unknowledgable a credible possibility.

Suggest the following test item: Both units are operating at 100% power and the 2H"-P659 2H11-P659 voltmeter 2S40-R615 indicates 230 KV voltage at [some abnormally low value here}here] and is fluctuating by + 5kV. The NCC has notified the control room crews that 230KV Bus voltage cannot be maintained above normal minimum voltage. Voltage. WOOTF identifies how reactive load can be raised and also identifies a required operator action in accordance with 34AB-S11-001, Operation With Degraded System Voltage? A. Use the REGULA TOR ADJUST control switch; Operator Is is required to initiate a 1 hour required action statement B. Use the HMI Screen and select Load Raise [or terminology]; Operator is required to appropriate Hatch terminology}; initiate a 1 hour required action statement C. Use the REGULA TOR ADJUST control switch; Transfer Station Service Busses to their alternate supply D. Use the HMI Screen and select Load Raise [or terminology]; Transfer Station Service appropriate Hatch terminology}; Busses to their alternate supply

3. Verify no overlap wi Q#93.

4. No overlap wi Q#93 blc b/c Q#93 tests applicants' knowledge of capability curve (provided) and EDG operability.

Licensee incorporated proposed question. QUESTION IS SAT.

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

Q# LOK LOO (FIH) (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back-8ack- 8/M1N U/EIS Q= SRO B/MIN Explanation Focus Oist. Link units ward KIA Only 66 F 2 x N y G2.1.06 nd S 1. Oist "B" Cred Oist: "8" and "0" are not plausible because the 2nd part [ONLY Nuclear Plant Operators] is overly restrictive with respect to communications protocol. Suggest the following: WOOTF identifies the required transient communication protocol in accordance with DI-OPS-59-896, Operations Management Expectations, Attachment 5, Strategies For Successful Transient Mitigation? A. A crew update is required to be preceded by an annunciator check. A crew update is a tool used primarily by the Shift Supervisor. B. A crew update is required to be preceded by an annunciator check. A crew update is a short transfer of information from anyone on the crew to the rest of the crew. C. A crew brief is required to be preceded by an annunciator check. A crew brief is a tool used primarily by the Shift Supervisor. O. A crew brief is required to be preceded by an annunciator check. A crew brief is a short transfer of information from anyone on the crew to the rest of the crew.

2. Licensee incorporated suggestion. QUESTION IS SAT.

67 F 2 x N S G2.1.08

1. Stem focus: Replace the word "should" with "is required to" in the 1st fill-in-the-blank statement.

2. Stem focus: spell out "SO"

3. Licensee incorporated suggestions. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- U/EIS Q= SRO B/MIN U/EtS Explanation Focus Dist. Link units ward KIA Only 68 F 2 x N E G2.1.17 st S 1. Stem Focus: Re-word the 1at fill-in-the-blank statement as follows: "When reporting the HPCI failure to start to the Shift Supervisor, the operator required to use the Shift Supervisor's name or title. "

2. Stem Focus: Re-word the 2nd 2 nd fill-in-the-blank statement as follows: "If the operator provides the exact value of RWL to the Shift Supervisor, then he/she required to provide the trend direction."

Modify the 2nd2 nd part of "A" and "C" to include the words "is still required."

3. Licensee incorporated suggestions. QUESTION IS SAT.

69 F 2 N S G2.2.01 70 F 2 x x x N E G2.2.37 S 1. Cred Dist: "A" is not plausible because an unknowledgable un knowledgable applicant could reasonably infer that the EDG was INOP if the emergency stop pushbutton was depressed.

2. Partial: "B" can be argued as correct by an applicant because the word "degraded" can be loosely interpreted as "inoperable."

3. Stem focus: The term "available" is undefined in 34SV-R43-001-2. Since no other procedure is referenced in the stem, this term can be "loosely" interpreted.

Suggest testing the applicants' knowledge of whether 1) the EDG is required to be declared INOPERABLE in accordance with Tech Specs [the 34SV procedure states to "Notify the Shift Supervisor to ensure Tech Specs are complied with PRIOR to performing the following step'] step'j and 2) whether the EDG can still auto-start. a uto-sta rt.

4. Licensee incorporated suggestions. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S U/EIS Explanation Focus Dist. Link units ward KIA Only 71 H 2 x x N eE G2.2.44 S 1. Partial: "0" "D" can be argued as correct by an applicant because 5t the 1st portion (is NOT adequate to manually insert control rods) could be interpreted to as linked to the separate condition that RWM has not been bypassed.

2. Stem Focus: Avoid the use of the connector "and/but" "and/but" in the fill-in-the-blank statement.

3. Suggest the following revisions.

Delete 2nd bullet [250 psid has been established] Add new bullet stating RxAx power is 19% (between LPAP and LPSP Add new bullet stating that the scram has NOT been reset Test the applicants' knowledge of 1) whether the RWM will (or will not) allow rod insertion and 2) what action is required to drive rods lAW 31 EO-EOP-1 03-1 [choose between close the EO-EOP-103-1 1C11-F034 (correct) OR place the reactor mode switch to the 1C11-F034 Shutdown position.

4. Licensee incorporated suggestions. QUESTION IS SAT.

1..

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 72 H 2 x B e G2.3.05 S 1. Partial: "C" can be argued as correct by an applicant because he/she could argue that he/she didn't "expecf "expecf' the alarm (even though it's an "expected" alarm). Suggest re-wording the stem as follows: WOOTF completes the following statements? The MAIN STEAM LINE RADIA TlON HIGH (601-425) RADIATION annunciator alarming. If radiation levels continued to rise, the LOWEST rad level at which the MAIN STEAM LINE RADIATION RADIA TlON HIGH-HIGH (603-125) annunciator will alarm is _ _ . A. is; 3,000 mrlmr/ hr B. is; 990990Rlhr Rlhr C. is NOT; 3,000 mrlhrmr/hr D. is NOT; 990 Rlhr

2. Licensee recommended NOT having different units blc b/c instrument reads out in mrlhr.

mr/hr. Licensee incorporated suggestion otherwise. QUESTION IS SAT. 73 F 2 B e G2.3.13 S 1. Exact REPEAT from 2009-301 April exam, Q#73. The question should be randomly selected from the bank (discuss w/ wi licensee). Discuss w/ wi licensee.

2. Licensee did not incorporate suggested change; however, the correct answer was changed from "a" to "b." QUESTION IS SAT.

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

B. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Crecl. #1 Back- U/EIS Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 74 F 2 x x N e G2.4.26 st S 1. Cue: The 1st fill-in-the-blank statement teaches

                                                                                                                                            "teaches" the applicant that the Cable Spread Room fire suppression system is CO2.

This has the potential to compromise other exam questions.

2. Stem focus: The 1stst fill-in-the-blank sentence is cumbersome.

Suggest re-wording as follows: The Cable Spreading room fire suppression system ___ initiate without operator action.

3. Licensee incorporated suggestions. QUESTION IS SAT.

75 F 2 x x N tJ 1J G2.4.49 S 1. Cred Dist: "B" and "0" are not plausible because an unknowledgable un knowledgable applicant can infer from the word "immediate" that "medium" is not the desired choice. st

2. Cue: The 1st sentence contains a cue, i.e., ".. and reactor power starts rising."

Suggestion: Eliminate the fill-in-the-blank statement and provide 4 choices of immediate operation actions. Use individual recirc controllers, vs use rods [to some incorrect power level - provided that the stem contains the qualifier minimum required immediate operator action]. Etc.

3. License classified as Higher order. Discuss w/ wi licensee.

4. Licensee stated that plausibility [for medium rate] was that power reduction was only 1%. Re-graded question as "enhancement." Suggestions incorporated. QUESTION IS SAT.

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

B. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/EIS Explanation Focus Dist. Link units ward KIA Only 76 H 3 x N e Ii 211000 G2.2.44 S 1. SRO-only because of detailed knowledge of diagnostic steps and decision pOints points in the emergency operating procedures (EOP) that involve transitions to event specific sub-procedures or emergency contingency procedures st

2. Stem Focus: Modify the 1st sentence to state: "Unit 2 was operating at 100% power when an A TWS occurred. The following conditions now currently exist:" [use of the word

                                                                                                transienf "transient" is not necessary to hide the name of the event.]

3. Stem focus: Modify the stem question to read: "WOOTF completes the following statements in accordance with CP-3, A TWS Level Control and RCA RPV Control (A TWS)?, TWS)?'

4. Stem focus: Modify the fill-in-the-blank statement as follows:

                                                                                                "Reactor water level is required to be              and a reactor cooldownis cooldown is A. maintained in the present band; NOT allowed B. maintained in the present band; required to be commenced, but NOT to exceed 100 deg/hr  deglhr C. raised to between +3" to +50"; NOT allowed D. raised to between +3" to +50"; required to be commenced, but NOT to exceed 100 deg/hr deglhr

5. Licensee incorporated changes. QUESTION IS SAT.

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

B. Q# LOK LOD LOO (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- B/MIN U/E/S Q= SRO B/M/N UlEiS Explanation Focus Dist. Oist. Link units ward KIA Only 77 H 2 x x x N Y tJ 215003 G2.1.27 S 1. Cred Dist: "0" are not plausible because the Oscillation Oist: "A" and "D" Power Range Monitors do not have a "lower range."

2. SRO-only: The 2nd portion of the question is not SRO only because RO's are required to know the Modes when a piece of equipment is required to be operable; i.e.,

eqUipment Le., RO knowledge that IRMs are not required in Mode 1. Therefore, the SRO applicant does not need to demonstrate knowledge of LCO 3.0.4.

3. Cue: The 4th sentence is not necessary to elicit the correct response.

Suggestion: If the KIA seems difficult to hit, consider asking a question related to the tech spec action associatediwith associated with the number of required channels pet per trip system that are required to be operable and also test the applicants' knowledge of when RPS Trip capability has been lost with respect to the IRMs.

4. Licensee changed "A" and "D" "0" to include a different distractor related to RWM low power setpoint (vs OPRM). QUESTION IS SAT.

78 7B H 2 x N y tJ 216000 A2.14 S 1. Cred Dist: Oist: "CO "0" are not plausible because when a recirc "C" and "D" pump trips, the vessel level cannot ever decrease, (unless some other leak was already in progress). st For the 1st portion of the question, suggest testing the applicants' knowledge of which thermal limits are required to be adjusted [RO knowledge>> all 3: MCPR; APLHGR; LHGR] and the 2nd portion of the question can remain as is, i.e., Le., how long to complete these actions [24 hours].

2. The DRAFT ORAFT exam submittal package included a blue tab with intented "handouts" (Le., applicant references) and this package included TS 3.4.1 and 3.4.2 (without SRs). Verify wI wi licensee that TS will NOT be provided for Reactor Coolant System.

3. Oiscussed plausibility wI Discussed wi licensee. Licensee stated that level changes associated wI wi a recirc pump trip [Le., level decrease]

was plausible based on applicant misunderstanding where the level was sensed. Re-graded question as "enhancement." No reference required for this question. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N UlElS UlEtS Explanation Focus Dist. Link units ward KIA Only 79 H 2 x x x x B e 234000 G2.2.25 S 1. Job-link: There needs to be more definition in the stem as to exactly what the unit status is with respect to current procedures (refueling) in effect and TS mode. What operating mode is the unit in? The stem states that fuel movement is in progress and also says that control rod removal is in progress. Is there also a governing refueling procedure in effect? What specific section of 34GO-OPS-66-0 is in effect? (single rod withdrawal or multiple rod withdrawal?) Which procedure provides guidance for bypassing the full-in reed switch such that refueling can continue?

2. Stem Focus: Re-word the question such that the applicants' are required to PREDICT how the refueling equipment will perform

[platform will stop prior to reaching cavity or not. not....... grapple will not lower, etc.] etc.)

3. SRO-only: The information provided with this question states the basis for SRO-only is knowledge of the bases of Tech spec 3.9. Assuming that the author is referring to LCO 3.9.1

[because the refueling equipment interlock is defective], defective), then the Action A is RO knowledge. The basis for Action A states that the bundle can be placed in a "safe" location. The meaning of the word "safe" can be potentially argued. This question needs work from the SRO-only perspective and for Item #1 listed above.

4. ;;

lo-~~~tmi~¢iVEld e I"T!...,l" T N~i!cementqlJestioll from IiGlm~ T

5. Job-Link: The question (as proposed) has initial conditions that the rod is only electrically isolated due to friction.

                                                                                                                                               "friction." According to TS 3.1.3, if a control rod is "stuck" then the rod is required to be hydraulically isolated (Bases for Action A.1). Consequently, the initial conditions may not be operationally valid. Research wI       wi licensee to verify which action statement exists when the unit was operating at full power (before the shutdown occurred).

6. Stem Focus: Stem does not specify 1) that the vessel head is removed (or that the Unit is in Mode 5); 2) exactly what the refueling bridge is doing over the core (Stem-(Stem* says that refueling is "about to begin." Is grapple unloaded? Is grapple down?).

Consequently, the applicant could successfully argue that the stem of the question didn't specify plant conditions and that the question is not operationally valid or he/she could potentially argue more than one correct answer. (COMMENTS CONTD)

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

Q# LOK LOO (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1#/ Back- Q= SRO B/MIN B/M/N U/EtS U/EIS Explanation Focus Oist. Link units ward KIA Only 79 H 2 x x x x B E 234000 G2.2.25 (COMMENTS CONTO) S 7. #/units: The first fill-in-the-blank statement requires choosing either "full-in" or "00". Reed switch number "S52" is the reed switch that provides the green full-in indication and refueling interlocks. Licensee found Hatch modification what allows three different reed switches to provide the refueling full-in

                                                                                                                               "full-in" permissive. These three switches are referred to as one "channel" in the TS bases.

8. Licensee subsequently modified question to test refueling grapple logic and TS Bases knowledge of 3.9.4 on bypassing inoperable "full-in" channel allowance.

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/EtS U/E/S Explanation Focus Dist. Link units ward KIA Only 80 H 3 x M e Ii 261000A2.12 261000 A2.12 S 1. This question may overlap with Q# 28 and Q#57, pertaining to how many SBGT will auto-start. Discuss in detail wi licensee.

2. Stem Focus: The phrase "the Shift Supervisor will direct..."

direct..." is not a requirement for SRO only questions, and its use may unnecessarily raise the reading burden.

3. Stem Focus: The stem states that the area rad levels also rose mr/hr>>

to 70 mr/hr >> Which detectors is the stem referring to (by number)? Suggest re-wording the stem to: Unit 2 was operating at 100% power while fuel movement was in progress to load a cask when minor damage to a fuel bundle resulted in the following conditions:

Refuel Floor Area Rad Monitors 2D21-K601 M .... 70 mrlhr 2D21-K601M mr/hr 2D21-K601 K ..... ... 65 mmr/hr rlhr 2D21 -K601 L ........ 70 mr/hr
Refuel Floor Vent Exhaust Monitors 2D11-K634A ..... 15 mr/hr 2D11-K634B ...... 14 mrl hr 18 mr/hr 2D11-k634C ....... 18mrlhr mr/hr 2D11-K634D ....... 19 mrlhr

4. Stem Focus: Eliminate both of the fill-in-the-blank statements and re-word the stem question as follows:

                                                                                                  "WOOTF identifies the total number of SBGTs that will wiJ/

automatically start and the minimum required procedures in accordance with 31EO-EOP-014-2, Secondary Containment Control Flowchart?

5. The plausibility of "B" and "D" [34GO-OPS-013-2, Normal Plant Shutdown] comes from the SC/R leg of the SC Flowchart where applicant needs to know Max Safe Operating Value requires shutdown (vs ED) when rad is not related to primary system discharging.

6. Question does not overlap wi Q# 28 (see comments in Q#28 writeup). Question does not overlap wi Q# 57 (see comments in Q#57 writeup). Suggested providing Table 6 (only) of SC Flowchart; i.e.,

Le., only the bottom ARM portion. Removed prompt off site dose element. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 8ack-

                                                               #/ Back-   Q= SRO B/MIN 8/MIN U/E/S                               Explanation Focus              Dist.         Link          units ward   KIA Only 81               x                        x                                       x    N     Y lJ  264000 A2.09 S   1. SRO-only: The question can be answered using RO systems knowledge because when concurrent LOSP and LOCAs exist on both units, then the 1 B EDG system operation is 18 unpredictable. [see caution on page 3 of 52 in 34AB-R43-001-34A8-R43-001-2).       [systems) knowledge can be used to determine that the 2]. This [systems]

1B EDG is required to be tripped. [vs continue monitoring as 18 stated in "B" "8" and "D"]

                                                                                                                       "D")

2. Stem Focus: The phrase "the Shift Supervisor will direct. .." is not a requirement for SRO only questions, and its use may unnecessarily raise the reading burden.

3. Partial: An applicant can potentially argue that "D" is also correct since monitoring the EDG is never a wrong thing to do.

Discuss wiw/ licensee.

4. Licensee's justification for SRO-only was that the conduct-of-operations perspective on "overriding an automatic function" was being tested, and this was SRO-only. Question remains outside NUREG 1021 acceptability.

5. Licensee re-worked question to test applicants' knowledge of TS 3.8.1 Bases 8ases related to number of feeders required for operable offsite power sources AND the impact on EDG. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N U/E/S U/EIS Explanation Focus Dist. Link units ward KIA Only 82 H 2 x x N Y IJ 272000 A2.11 S 1. In the DRAFT submittal package, only the top portion of SC Flowchart Table 4 was provided. Does licensee intend on also providing the lower portion of the Table 4 (differential temperatures). It will be difficult to answer without both portions of Table 4. Discuss wi licensee.

2. SRO-only: The overall mitigative strategy for SC EOP is that when two areas exceed Max Safe (temperature, water level, or rad) due to a primary system discharging, then ED is required.

This is overall mitigative strategy knowledge [i.e., [Le., RO knowledge of procedures, see KIA G.2.4.6 "Knowledge of EOP mitigation strategies RO importance rating of 3.7] and can be used to eliminate "CO "C" and "0."

                                                                                                                       "D." The applicant is then left with choices "A" and "B", which he/she can then eliminate "A" based on Ax   Rx Bldg HVAC isolation setpoint.

3. Cue: The 2nd fill-in-the-blank statement contains a cue that reactor pressure will be lowered.

Suggest re-working the same question, but ask the SRO applicant to select a procedure without including follow-on action phrases such as ...."maintaining "maintaining <100 deg/hr" or "emergency deg/hr"or depressurize." Use of follow-on action phrases may allow RO knowledge to be used to deduce the correct answer, as is the case in this proposed test item.

4. Licensee re-worked question to test procedure selection knowledge. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/FTIF Credo Partial Job- Minutia #1 Back- Q= SROSAO B/MIN B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only 83 H 3 x x x N e 295001 A2.04 st S 1. Job-link: The documentation of why the 1st fill-in-the-blank is technically accurate could not be found in the draft submittal. The question analysis section states that the tech spec bases states that the recirc system is operating in 1-loop. The only item that could be located in the TS bases was on Page B3.4.1 , which states:

                                                                                                   "Each external loop contains one variable speed motor driven recirculation pump, an adjustable speed drive (ASD) to control pump speed and associated piping, jet pumps, valves, and instrumentation."

However, this statement may not be the one referenced in the question analysis. If this is the statement being referred to in the question analysis, then it is not definitive with respect to officially stating that the plant is in Hoop 1-loop operation with an inoperable jet pump. Discuss wi the licensee where this guidance is documented.

2. Cred Dist: Ask the licensee why "A" and "C" are plausible.

Verify wi licensee that jet pumps 11 thru 20 supply "A" Recirc Aecirc Loop in order to establish credibility of raising "B" loop flow in "A" and "Co.

                                                                                                        "C". If not, then "A" and "C" are not plausible.

3. Stem Focus: The phrase "the Shift Supervisor will direct direct....

                                                                                                                                                                   .." is not a requirement for SRO SAO only questions, and its use may unnecessarily raise the reading burden.

4. Stem Focus: Re-word 3rd sentence in the stem as follows:

Ae-word the 3rd "The diffuser-to-Iower-plenum differential pressure for Jet Pumps 5& & 6 differs by 50% from established patterns."

5. Licensee demonstrated that surveillance requirement not being met for matched flows constituted declaring loop inoperable.

Licensee modified question to include comments. QUESTION IS SAT.

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

Q# 0# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- 0= U/EIS Q= SRO B/MIN U/EtS Explanation Focus Dist. Link units ward KIA Only 84 H 2 x N Ii

                                                                                       ~   295004 G2.1.23 G2.1 .23 S   1. Discuss how this question does n not o  t " 0#39 overlap Q#39 and 19.

2. Stem Focus: The phrase "the Shift Supervisor will direct..." is not a requirement for SRO only questions, and its use may 2 nd fill-in-unnecessarily raise the reading burden. Modify the 2nd the-blank statement to test the applicants' knowledge of the required procedure.

3. Stem Focus: Does the word "FEEDER" in the 1st sentence mean that a load breaker off of S022 has tripped? Or does it mean that the supply breaker off of S022 has tripped. Suggest enhancing the DC loss by stating what is de-energized.

4. No overlap wi 0#

Q# 39 and 0# Q# 19 (see items for explanation). Comments incorporated. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EtS U/EIS Explanation Focus Dist. Link units ward KIA Only 85 F 2 x x x N Y. 1J 295005 A2.02 e Ie 1. Cred Dist: "B" and 'D" are not plausible because the stem states that "The main turbine is operating' and also states that S "if continued operation is desired.."

2. Partial: "A" can also be argued correct because the alarm

                                                                                              . procedure states that the vibe vi be trips may be disabled with the Ops Manager (or designee) and System Engineer approval.

The Shift Supervisor can be the Ops Manager designee.

3. SRO-only: This does not appear to be procedure selection.

Perhaps the basis for SRO-only is detailed recall of the contents of the annunciator procedure w.r.t. whose approvals are required? Discuss wI wi licensee. Suggest testing the applicants' knowledge of the administrative procedures required to document the decision to bypass the high vibe vi be turb trip. Alternatively, test the applicants' knowledge of the turbine vibration setpoint and also the startup procedures' administrative requirements for the vibration instrumentation monitoring. Can you roll the turbine with it bypassed? If so, when or when not?

4. Licensee classified as higher order question. Discuss whether this is fundamental question wI wi licensee.

st

5. Discussed wI wi licensee and their intent (for 1st fill-in-the-blank) statement was to test applicants' knowledge of a failure to auto-trip the turbine on high vibration. The grammar may have been mis-leading; however, the intent was correct. Re-graded to "enhancement." Modified question to test applicants' knowledge of turbine trip setpoint and lowest level of authority required (per procedure) to bypass this turbine trip feature. QUESTION IS SAT.

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

Q# LOK LCD LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- U/EIS Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 86 H 2 x x N J;; Ii 295007 A2.01 S 1. Stem Focus: The 1stst sentence should be past tense since the alarm means that the unit subsequently scrammed. In other words ... "Unit 2 was at 100% 100% power when the following alarm was received"

2. Job-Link: How does the high pressure transient cause torus water level to decrease? Suggest simply stating that torus level and pressure are x and y, respectively.

3. Stem Focus: The phrase "the Shift Supervisor will direct. . ."" is direct...

not a requirement for SRO only questions, and its use may unnecessarily raise the reading burden.

4. Licensee incorporated comments. QUESTION IS SAT.

87 F 2 x N J;; Ii 295012 G2.4.11 S 1. Stem focus: Minimize the use of reference material by re-working the question as follows: WOOTF completes the following statement in accordance with 34AB-T47-001-2, Complete Loss of Drywell Cooling? The crew is required to enter if any peak temperature listed in Attachment 1 is exceeded for A. 34AB-C71-001-2, Reactor Scram Procedure; 1 hour B. 34AB-C71-001-2, Reactor Scram Procedure; 30 minutes C. 34GO-OPS-014-2, Fast Reactor Shutdown; 1 hour D. 34GO-oPS-D14-2, 34GO-OPS-014-2, Fast Reactor Shutdown; 30 minutes

2. SRO-Only justification is that this is detailed knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps

3. Comments incorporated; no need for reference to be distributed to applicants. QUESTION IS SAT.

i

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN B/M/N U/EtS UlE/S Explanation Focus Dist. Link units ward KIA Only 88 F 2 x x M e 295013 A2.01 S 1. SRO-only: The information listed "above the line" in Tech Spec 3.6.2.1 is RO Tech Spec knowledge, including the "Iess-than-or-

                                                                                                                                                        "less-than-or-equal-to" 1 hour action statements in Tech Specs. Additionally, plant parameters that require entry to the major EOPs are also RO knowledge. Licensee stated this test item linked to 10CFR55.43 (5) [procedure selection] because the applicant must recall the action in the procedure and when to take the action.

The following knowledges are required to determine the correct answer "C":

Testing req'd suspended at 105: (Immediate action statement C.1)
Logging req'd every 5 minutes: Step 4.4 in 34AB Because this is borderline SRO-only knowledge with respect to procedure selection, suggest re-working the question to require the applicant to select a procedure or , alternatively, test the applicants' knowledge of the TS Bases for TS 3.6.2.1. The 2nd part of the question [whether or not HPCI HPCl testing can continue]

is a good starting point to retain. st st

2. Stem Focus: Combine the 1st sentence and the 1st bullet for consolidation purposes.

3. Stem focus: misspelled word "stablizes"

4. Stem Focus: The phrase "the Shift Supervisor will direct..." is not a requirement for SRO only questions, and its use may unnecessarily raise the reading burden.

5. Licensee provided replacement question; however, question was not accurate b/c it prescribed action statement even though none was required. Suggested asking for maximum torus temperature wi HPCI HPCl testing in progress AND bases for this number. Licensee incorporated suggestion. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Credo Partial Job- Minutia #1 Back- Q= SRO U/EIS SAO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 89 F 2 x N Y. Y 295019 A2.02 S 1. Cred Dist: "A" and "B" are not plausible because an unknowledable applicant would assume that the Shift Supervisor is not going to stop and sign a work order prior to authorizing repair efforts when control air header pressure is 20 psig and lowering. (not practical)

2. Question may overlap wI wi Q#61. Discuss wI wi licensee

3. Q=KlA: Ask the licensee whether safety related loads are supplied via the non-intr air header by the N2 system.

4. Licensee classified this question as Higher order.. Discuss wI wi licensee.

5. Question no longer overlaps wI wi Q#61 blc it was significantly re-worked. Licensee re-worked question to test applicants' knowledge of lowest required pneumatic supply header pressure to the ADS valve accumulators AND the basis for this value lAW TS Bases. QUESTION IS SAT.

90 H 3 x N e 295030 G2.1.20 G2.1 .20 S 1. Stem Focus: The phrase "the Shift Supervisor SupeNisor will direct..." is not a requirement for SROSAO only questions, and its use may unnecessarily raise the reading burden.

2. Stem Focus: Re-word Ae-word the choices as follows:

A. is; 31 EO-EOP-015-1, Emergency Depressurization B. is NOT; 31 EO-EOP-015-1, Emergency Depressurization c. C. is; 31 EO-EOP-113-2, Terminating AndlOr And/Or Preventing Injection Into The RPV D. is NOT: 31 EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV APV Td

3. Stem Focus: the CP-3 portion in the 3m bullet is not necessary to elicit the correct response.

st

4. Ae-word the 1st sentence as follows: "Unit 2 was Stem focus: Re-word operating at 100% power when an A TWS occurred and the following conditions currently exist;'

exise'

5. Licensee incorporated suggestions. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- U/EIS Q= SRO B/M/N U/EtS Explanation Focus Dist. Link units ward KIA Only 91 H 2 N S 295031 G2.2.44 92 H 3 x x x N Y IJ 400000 A2.02 S 1. SRO-only: The 2nd portion of the question was intended to 10CFRSS.43 (5) [assessment of facility conditions and target 10CFR55.43 selection of appropriate procedures].

                                                                                                 "A" and "B" can be eliminated by RO systems knowledge associated with how many RBCCW pumps remain running

[systems knowledge]. The correct answer "CO "C" can be determined by knowing that the recirc pumps have lost their cooling medium (RBCCW) and require tripping.

2. Partial: There is a potential for no correct answer because the (Le., enter the scram procedure) is guidance to trip the reactor (i.e.,

directed by 34AB-P42-001-2, Step 4.8 which directs the operator to scram the reactor and enter 34AB-C71-001-2 at the shift supervisor direction. Therefore, the requirement for 34AB-C71-001-2 is a discretionary decision point in the procedure and may not always be required.

3. Stem Focus: The phrase "the Shift Supervisor will direct direct....

                                                                                                                                                                .." is not a requirement for SRO only questions, and its use may unnecessarily raise the reading burden.

4. Licensee provided replacement question; however, still did not work. Chief Examiner suggestion taken and incorporated.

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/EtS U/EIS Explanation Focus Dist. Link units ward KIA Only 93 H 3 x N Ii 700000 A2.03 S 1. Verify no overlap wI wi Q# 65.

2. Stem Focus: Use of the connectors in the fill-in-the-blank statement ["res) (are)'1 is confusing. Modify each of the

["(es) is (are)"} choices to have more words such that these connectors aren't required.

3. Stem focus: The word REFERENCE is misspelled.

4. SRO-only: Justification is that the 3825 volt acceptance criteria is based on TS knowledge.

5. No overlap exists wIwi Q#65 (see that question for explanation).

Licensee modified question to accommodate 34AB-S 11-001-0, 34AB-S11-001-0, Step 4.3.3. QUESTION IS SAT. 94 H 2 M Ii G2.1.28 S 1. Licensee proposes to provide 73EP-EIP-001-0, Attachment 1, Fission Product Barrier Chart to the applicants to define what reactor level constitutes a potential or actual loss of the fuel clad barrier. Because the compensated and uncompensated levels are both less than -155 inches, this question becomes a direct lookup if the proposed reference is distributed. Discuss wI wi licensee.

2. Stem Focus: Re-word the 2nd 2 nd fill-in-the-blank as follows: "The HIGHEST REQUIRED emergency claSSification classification is in accordance with 73EP-EIP-001-0.

3. Stem focus: The S17A switch is listed as "RESET". "RESET'. Is this switch a spring return to Auto? What does it mean when the stem states the switch is "RESET?"

nd

4. Stem Focus: misspelled word in the 2nd 2 bullet (Outoboard).

5. Licensee agreed to exclude the top portion of the Fission Product Barrier Evaluation Chart Attachment 1 from the reference being provided. Comments incorporated.

QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward KIA Only 95 F 2 N G2.1.37 S 1. Job-Link: Step 8.3.2 of 30AC-OPS-003-0 states: "The following staffing requirements shall apply to the manning of the Main Control Room: At least two licensed NPOs shall be present, in the MCR, for each reactor, in the process of startup, scheduled reactor shutdown, rapid power reduction, and during recovery from reactor trips caused by transients or emergencies." Does this requirement mean in addition to the normal number of NPOs assigned to the unit? What defines the "control room?" Is it the combined Unit 1 and Unit 2 control room? Discuss wIwi the licensee.

2. Stem Focus: Why is the Unit 2 Control room information provided in the stem? Do the headings [Unit 1 Unit 2] imply separate control rooms?

3. Licensee explained and no changes required. QUESTION IS SAT.

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIFT/F Credo Partial Job- Minutia #1 8ack-Back- Q= SRO 8/M/N B/M/N U/EtS U/EIS Explanation Focus Dist. Link units ward KIA Only 96 H 2 N E Ii G2.2.01 S 1. SRO-only: This question is borderline because the knowledge of how many SRMs are required in Mode 3 vs Mode 2 is RO Tech Spec knowledge .. [See KIA G2.2.1 RO IR = 4.5; 2.2.12 RO IR = 3.7; G2.2.23 RO IR = 4.0; and G2.2.42 RO IR = 3.91 3.9] Also, the knowledge of SRM minimum count rate is RO Tech Spec knowledge

2. Job-Link: The 1stst sentence states that "Unit 2 is in.in Mode 3.....".

8ecause Because the 2nd sentence states that the mode switch has just been placed in the Startup position, the question has the potential to become mis-leading, i.e., the plant is now in Mode

2. Suggest combining the 1st st and 2nd sentences to state that Unit 2 is preparing to startup and the mode switch is in the startup/hot stby position (ensure exact labeling).

3. Stem focus: The 2nd 2nd fill-in-the-blank statement is confusing because it does not ask the applicants for the REQUIRED position of the mode switch.

Discuss wi licensee: The 24 hour repair time exceeds the 4 hour A.1 action statement time; therefore, in accordance with TS, is the licensee allowed to leave the mode switch in startup for 4 hours knowing that the repair time will not be met? Discuss wi licensee.

4. Licensee modified question to test applicants' knowledge of surveillance requirement 3.0.3 (actions for a missed surveillance).

QUESTION IS SAT. 97 F 2 x x x M Ii E G2.2.23 S 1. Q=KlA: The question does not necessarily have to involve a "tracking" RAS because of the KIA statement wording. The

                                                                                                       tracking

licensee may have interpreted the KIA statement wording too restrictive. Consequently, the "8" "B" and "c" "C" choices are not plausible since an unknowledgeable applicant could "guess" that the name of the sheet was "Tracking" when the equipment was not presently required to be operable.

2. Minutia: Testing the applicants' knowledge of whether the SRO is required to "initial" vs "sign" is minutia

3. Licensee explained protocol for tracking vs active LCOs (signature and initials). Question is not minutia. QUESTION IS SAT.

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

I Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= U/EIS SRO B/M/N U/E/S Explanation Focus Dist. Link units ward KIA Only I 98 F 2 B e E G2.3.13 S 1. Exact REPEAT from 2009-301 April exam, Q#98 The question should be randomly selected from the bank. Discuss wi licensee.

2. Licensee modified question to provide a choice between a plant page announcement OR a notification of unusual event.

QUESTION IS SAT. 99 F 2 N e E G2.4.37

1. Cue: The 1st 51 sentence in the 1st 51 fill-in-the-blank statement S

is not needed to elicit the correct response.

2. Licensee incorporated suggestion. QUESTION IS SAT.

100 H 2 x x M e E G2.4.41 S 1. Cue: The 3'd bullet is not necessary to elicit the correct response. st

2. Stem Focus: The 151 sentence can be consolidated with the 1st 51 bullet as follows: "Unit 1 is at 100% power with the 1B EDG tagged out of service for repairs. "

3. Stem Focus: Split out the fill-in-the-blank statement into two sentences and re-word as follows: The "The highest required emergency classification is . The state and local governments are required to be notified by A. Alert; 11 :45 B. Alert; 12:00 C. Site Area Emergency; 11 :50 D. Site Area Emergency; 12:00

4. Licensee incorporated suggestions. QUESTION IS SAT.

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: H kTC-H Date of Exam: "/1210q t\ IZ oq RO@ Exam Level: RO SRO 0 Initials Item Description a b c

1. Clean answer sheets copied before gradingrading

2. Answer key changes and question deletions justified and documented

3. Applicants' scores checked for addition errors (reviewers examinations) reviewers spot check> 25% of examinations

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail

5. All other failing examinations checked to ensure that grades are justified

                 'ustified

6. Performance on missed questions checked for training

( deficiencies and wording problems; evaluate validity of questions uestions missed b by half or more of the applicants Date

a. Grader

b. Facility Reviewer(*) I

c. NRC Chief Examiner (*) I~A 1~/t 1!1f '1 1/1Jf)1 i

d. NRC Supervisor (*) 'z/&Ih>#/f

(*) The facility reviewer's signature is not applicable for examinations graded by the NRC; independent two inde endent NRC reviews are re required. uired. (}}

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