ML092940740

Initial Exam 2008-301 Final Administrative Documents

ML092940740
Person / Time
Site:	Catawba
Issue date:	10/20/2009
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/08-301, 50-414/08-301
Download: ML092940740 (83)

Text

{{#Wiki_filter:ES-201 Examination Preparation Checklist Form ES-201-1 Facility: C~Jffi,* Date of Examination: 121117D(~ Developed by: Written - Facility lXl NRcD II Operating - Facility)in NRcD Target Chief Date* Task Description (Reference) Examiner's Initials -180

1.

Examination administration date confirmed (C.1.a; C.2.a and b) -120

2.

NRC examiners and facility contact assigned (C.1.d; C.2.e) 8/} -120

3.

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

4.

Corporate notification letter sent (C.2.d) q'l'7, [-90] [5. Reference material due (C.1.e; C.3.c; Attachment 3)] 179/Z j-"-,,;;: {-75}

6.

Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, r/17 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) {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility C;!22-licensee (C.2.h; C.3.e)} {-45}

8.

Proposed examinations (including written, walk-through JPMs, and 10/17 scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d) -30

9.

Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.g; /0/3/ ES-202) -14

10. Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; If/I 7 ES-202)

-14

11. Examination approved by NRC supervisor for facility licensee review 11//7 (C.2.h; C.3.f)

-14

12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

II/;7 -7

13. Written examinations and operating tests approved by NRC supervisor I#/Z1 (C.2.i; C.3.h)

-7

14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm H(?cj 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

/1/ zi with facility licensee (C.3.k) -7

16. Approved scenarios, job performance measures, and questions (f/~f distributed to NRC examiners (C.3.i)

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

[Applies only] {Does not apply} to examinations prepared by the NRC. ES-201, Page 25 of 28 ES-201 Examination Preparation Checklist Form ES-201-1 Facility: C~Jffi,* Date of Examination: 121117D(~ Developed by: Written - Facility lXl NRcD II Operating - Facili~)tl NRcD Target Chief Date* Task Description (Reference) Examiner's Initials -180

1.

Examination administration date confirmed (C.1.a; C.2.a and b) -120

2.

NRC examiners and facility contact assigned (C.1.d; C.2.e) 8/£ -120

3.

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

4.

Corporate notification letter sent (C.2.d) q'/"7, [-90] [5. Reference material due (C.1.e; C.3.c; Attachment 3)] 79/Z j.o. F- {-75}

6.

Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, r/17 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) {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility C;!22-licensee (C.2.h; C.3.e)} {-45}

8.

Proposed examinations (including written, walk-through JPMs, and 10/17 scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d) -30

9.

Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.g; /0/3/ ES-202) -14

10. Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; If/I 7 ES-202)

-14

11. Examination approved by NRC supervisor for facility licensee review 11//7 (C.2.h; C.3.f)

-14

12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

II/;7 -7

13. Written examinations and operating tests approved by NRC supervisor I#/Z1 (C.2.i; C.3.h)

-7

14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm H(?cj 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

/1/ zi with facility licensee (C.3.k) -7

16. Approved scenarios, job performance measures, and questions (f/~f distributed to NRC examiners (C.3.i)

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

[Applies only] {Does not apply} to examinations prepared by the NRC. ES-201, Page 25 of 28

ES-201, Rev. 9 Examination Security Agreement Form ES-201-3 1.Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of l:Jec..laof 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 not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of"b-e<:. *=08:. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAMEJOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE ./7 d /

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• ES-201, Rev. 9 Examination Security Agreement Form ES-201-3 1.Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of l:Jec..laof 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 not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of"b-e<:. *=08:. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

'... / ES-201 Examination Security Agreement Form ES-201-3

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes) of !I...O/.O¥' 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 not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes) of . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. JOB TITLE / RESPONSIBILITY DATE DATE NOTE /Jeo O.lo~ ,.t/).. 6 E'-L- "'>AeL.J b. r/t;1:.elJI/t:r )JED 'l ~ NeO ~........R.... 61':;) '....:.. <<'"-."'~" 1.2£0 12~6tf-tP l2-o"'.(}~Q. R ~ (oJ N~ NfD I.:2..,..... (?... br.'~ ~s.r...... 't. ~,'toe\\- \\\\\\~\\;) m't':.2.. ~/t'>~s KIf,Ab L;"UlIJ-2iqQ(tn...V-t.. ~P.L3 J?erhrYh.f tI.f./'1VI fj tt'.-1'\\-. ~ ~ 'iO )2.)3/ 01 ,p...7~ tJ?,t.,~'tf hr(,fi'rJ") &" 12JLI)Or 0... " 5IZjfJ{J tint-hy J.J"d:,-(v+ O(1)**,t-v--,. Vdi 't?-rntr;-/ c>/t-.-.h-/I'l1t\\fTv'l "."'1'ffle.-1(vt ES-201, Page 27 of 28 ES-201 Examination Security Agreement Form ES-201-3

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes) of !I...O/.O¥' 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 not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes) of . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. JOB TITLE / RESPONSIBILITY DATE DATE NOTE

1. """"9'-'F-...!.>.t:.."71-~L...I....='-:"'::"-

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9. _____________________________________________________ _

10. ___________________________________________________ _

11. ___________________________________________________ _

12. ___________________________________________________ _

13. ___________________________________________________ _

14. ___________________________________________________ _

15. ___________________________________________________ _

NOTEStJ;.j J?erhrYh.f tI.f./'1(.d fj tt'.-1..... ~ ~ 'iO )2.)3/ 01 ,p...7~

1. Z-tJ?,t.,~'tf hr(,fi'rJ") &"

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

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of bE.C. Z~ 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 ~d not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Pe(:.Ze4::). From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE i.Ar:-"'~/ ~z:~;,.,. IV.... 'W- ".. v sitv"/o'l £flic-&£ ~EMr~

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1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of bE.C. Z~ 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 ~d not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Pe(:.Ze4::). From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE ES-201, Page 26 of 27

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

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of (2., ( l b<t 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 not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 0.. /-0 '". From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. JOB TITLE / RESPONSIBILITY DATE DATE NOTE 5£0 /Z..-.n >~ V':_.- A I~ ~/"l¥O~ \\J<'"\\J~ 2 (-r<O ~ctcliiC /:tJb fflffaeR--01j _2,c> -rl .:5 " h '71. 'f ~l J zlitJ, W!~~,.~ 5KO .5'!<.~ /Je'ty] ",/5 p,fI"'Na, 9'~c ';90 --== ~~ J p, ~

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1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of (2., ( l b<t 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 not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 0.. /-0 '". From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

4.

5.

6.

7.

JOB TITLE / RESPONSIBILITY 5£0 NOTE

Dameron, Hubert C From: Lyall, Kevin S Sent: To:

Subject:

Wednesday, February 04, 2009 11:48 AM Dameron, Hubert C; Wilkins, Teresa A Re: HLP exam security I attest that I did not divulge any exam material to anyone and that the statements below are true. I turned my badge back into Sam Brooks when I left. Kevin Kevin From: Dameron, Hubert C To: Lyall, Kevin S; Wilkins, Teresa A Sent: Wed Feb 04 10:53:14 2009

Subject:

HLP exam security Both of you signed the exam security agreement for the 08 HLP exam. I need both of you to sign back out. While it's best for you to physically sign out of the document I can deal with via e-mail. When you sign out you attest to the follOWing: To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Dec. 2008. From the date that I entered into this security agreement until the completion ofthe 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. A reply to this email stating that you attest that the statement is correct is sufficient. Please mail the badge to me at CN01A. 1 Dameron, Hubert C From: Lyall, Kevin S Sent: To:

Subject:

Wednesday, February 04, 2009 11:48 AM Dameron, Hubert C; Wilkins, Teresa A Re: HLP exam security I attest that I did not divulge any exam material to anyone and that the statements below are true. I turned my badge back into Sam Brooks when I left. Kevin Kevin From: Dameron, Hubert C To: Lyall, Kevin S; Wilkins, Teresa A Sent: Wed Feb 04 10:53:14 2009

Subject:

HLP exam security Both of you signed the exam security agreement for the 08 HLP exam. I need both of you to sign back out. While it's best for you to physically sign out of the document I can deal with via e-mail. When you sign out you attest to the follOWing: To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Dec. 2008. From the date that I entered into this security agreement until the completion ofthe 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. A reply to this email stating that you attest that the statement is correct is sufficient. Please mail the badge to me at CN01A. 1

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: ~~p.. Date of Examination: l'Llod t:)~ Initials Item Task Description a b* cft-

1.

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

(JJ; ~~ I~ w J R

b.

Assess whether the outline was systematically and randomly prepared in accordance with ~ ~~ I Section D.1 of ES-401 and whether all KIA categories are appropriately sampled. T cPt {)#"' ~ f)..; T

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

E ~S be'" ~ ~ N

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

2.

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number j6 ~{ Jf 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 cb ~( J L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. 0 To the extent possible, assess whether the outline(s) conform(s) with the qualitative 4f R

c.

dt? \\J~ 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 J W distributed among the safety functions as specified on the form JJr 1 (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 on the form.

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

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

c.

Determine if there are enough different outlines to test the projected number and mix dV1 ~( 1# 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

~ bif' IJ y in the appropriate exam sections. ~ G ~ bW ~ E

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

n N Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. M W ;A () E

c.

R

d. Check for duplication and overlap among exam sections.

d0 (\\'" ~ A dV1 ~ J r; L

e. Check the entire exam for balance of coverage.

f.

Assess whether the exam fits the appropriate job level (RO or SRO). cPt W ~ I~

a. Author

...A J( ~I.. ~/Na.,~e/Signature ()j,frJ Vt' ~ J. D~ 1/11 {o'S"

b. Facility Reviewer (*)

~12-{1f-0 j). f'7jLL~/Y 4\\&-~(~I-c.... //jtf"iDt' GE:epr~C) LLl, lAsOl hL11le-1' W:-=-~ II/Nip??£'

c. NRC Chief Examiner (#)

d. NRC Supervisor MAUlJtJf.A... 'T' WlOIl1)dJN /

'If( /1124(4: AI.~

B(

~"-It-VJr Note:

1. Independent NRC reviewer initial items in Column "c n

chief examiner concurrence required.

• Not applicable for NRC-prepared examination outlines ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

~~p.. Date of Examination: l'Llod t:)~ Initials Item Task Description a b* cft-

1.

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

I~ I~~ ~ w J R

b.

Assess whether the outline was systematically and randomly prepared in accordance with ~ ~~ I Section D.1 of ES-401 and whether all KIA categories are appropriately sampled. T ~- ~ar ~ {Y T

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

E N

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

~S be'" ~ 'Jk

2.

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number j6 ~{ Jf 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 cb ~( J L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. 0 To the extent possible, assess whether the outline(s) conform(s) with the qualitative

f R

c.

dt? \\J~ 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 J W distributed among the safety functions as specified on the form JJr 1 (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 on the form.

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

I (1 ) the tasks are distributed among the topics as specified on the form <¥1 ~, (2) at least one task is new or Significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations dV1 ~( ; II

c.

Determine if there are enough different outlines to test the projected number and mix 1-- 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

~ bif' J in the appropriate exam sections. n G I~ It¥' -* E

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

n N Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. I¥? W -A VI E

c.

R 1d0 I{\\", ~

d. Check for duplication and overlap among exam sections.

A 1dJ-lt I~ J L

e. Check the entire exam for balance of coverage.

1\\

f.

Assess whether the exam fits the appropriate job level (RO or SRO). cPt W ~ tv

a. Author

...A

~

~~/N~')]e/Signature ()/frJ Vt'~

j D~

1111 {o'S"

b. Facility Reviewer (*)

D£f/f-0 il biLL&4tJ!' 40->J/Y/---C I/JJ"/Dt' NRC Chief Examiner (#) GE:(Z.pf<f..) LLl, lAsOl hL:t1\\.e)! W:--~ II/NIp??£'

c.

d. NRC Supervisor MAuow..... 'T' WlO/IJ.)dJN /

~ -{. /1124(4: AtI.~ ~ , ~'-ltcPr Note:

1. Independent NRC reviewer initial items in Column "c n

chief examiner concurrence required.

• Not applicable for NRC-prepared examination outlines

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ~RO DSRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R N USing Data Book Figure 9 (Pennissible Successive Attempts to Start Motors) detennine the allowed starting time for NCP. Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjA/6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Calculate Unit Vent flow manually per PTjljAj4450j017 (Unit Vent Flow Manual Calculation). Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Umits Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes) (N)ew or (M)odified from bank ~ 1) (P)revious 2 exams (~ 1; randomly selected) ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ~RO DSRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R N USing Data Book Figure 9 (Pennissible Successive Attempts to Start Motors) detennine the allowed starting time for NCP. Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjA/6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Calculate Unit Vent flow manually per PTjljAj4450j017 (Unit Vent Flow Manual Calculation). Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Umits Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes) (N)ew or (M)odified from bank ~ 1) (P)revious 2 exams (~ 1; randomly selected)

ES-301, Rev. 9 . Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO ~SRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R M Determine if a work hours extension is required and if so, which limits are exceeded. Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOj Aj6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Determine SLC requirements and complete a Unit Vent Flow Manual Calculation per PTjljAj4450j017 Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Umits Emergency Plan R D Upgrade an Emergency Classification and Complete an Emergency Notification Form NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes) (N)ew or (M)odified from bank ~ 1) (P)revious 2 exams (~ 1; randomly selected) ES-301, Rev. 9 . Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO ~SRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R M Determine if a work hours extension is required and if so, which limits are exceeded. Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOj Aj6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Determine SLC requirements and complete a Unit Vent Flow Manual Calculation per PTjljAj4450j017 Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Umits Emergency Plan R D Upgrade an Emergency Classification and Complete an Emergency Notification Form NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes) (N)ew or (M)odified from bank ~ 1) (P)revious 2 exams (~ 1; randomly selected)

ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ~RO o SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function

a.

Perform a Manual Makeup to the vcr (SNAP 191) D S 1

b.

Respond to NC System Leakage (SNAP 192) ADS 2

c.

Depressurize the NC System to Minimize Primary to Secondary Leakage during A D L S 3 a SGTR (SNAP 193)

d.

Cooldown the PRT Using NCDT Heat Exchanger (SNAP 194) D S 5

e.

Restore Offsite Power to 6.9 kV Busses per AP/07 (Loss of Normal Power) A L N S 6 1 (Black Restart Procedure) (SNAP 195)

f.

Perform the Immediate Actions of AP/1/N5500/16, (Malfunction of Nuclear D S 7 Instrumentation System), Case 4, (P/R Malfunction) (SNAP 196)

g.

Shirt Operating RC Pumps (SNAP 197) A N S 8

h.

Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Locally Break Vacuum on a Loss of Feedwater D E 4S

j.

Align Seal Injection to the Unit 2 NC Pumps D E 2

k.

Alternate Cooling to 1A NV Pump D E R 8 Ali RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; ali 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (O)irect from bank

.:5.9/.:5.8/.:5.4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 - 1 ~ 1 (control room system) (L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams .:5. 3 1.:5. 3 I.:5. 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ~RO o SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function

a.

Perform a Manual Makeup to the vcr (SNAP 191) D S 1

b.

Respond to NC System Leakage (SNAP 192) ADS 2

c.

Depressurize the NC System to Minimize Primary to Secondary Leakage during A D L S 3 a SGTR (SNAP 193)

d.

Cooldown the PRT Using NCDT Heat Exchanger (SNAP 194) D S 5

e.

Restore Offsite Power to 6.9 kV Busses per AP/07 (Loss of Normal Power) A L N S 6 1 (Black Restart Procedure) (SNAP 195)

f.

Perform the Immediate Actions of AP/1/N5500/16, (Malfunction of Nuclear D S 7 Instrumentation System), Case 4, (P/R Malfunction) (SNAP 196)

g.

Shirt Operating RC Pumps (SNAP 197) A N S 8

h.

Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Locally Break Vacuum on a Loss of Feedwater D E 4S

j.

Align Seal Injection to the Unit 2 NC Pumps D E 2

k.

Alternate Cooling to 1A NV Pump D E R 8 Ali RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; ali 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (O)irect from bank

.:5.9/.:5.8/.:5.4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 - 1 ~ 1 (control room system) (L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams .:5. 3 1.:5. 3 I.:5. 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator

ES-301, Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO ~ SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System j JPM Title Type Code* Safety Function

a.

b.

Respond to NC System Leakage (SNAP 192) ADS 2

c.

Depressurize the NC System to Minimize Primary to Secondary Leakage during A D L S 3 a SGTR (SNAP 193)

d.

Cooldown the PRT Using NCDT Heat Exchanger (SNAP 194) D S 5

e.

Restore Offsite Power to 6.9 kV Busses per APj07 (Loss of Normal Power) A L N S 6 1 (Black Restart Procedure) (SNAP 195)

f.

Perform the Immediate Actions of APj1jAj5500j16, (Malfunction of Nuclear D S 7 Instrumentation System), case 4, (PjR Malfunction) (SNAP 196)

g.

Shirt Operating RC Pumps (SNAP 197) A N S 8

h.

Perform the Immediate Actions of APj1jAj5500j004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Locally Break Vacuum on a Loss of Feedwater D E 4S

j.

Align Seal Injection to the Unit 2 NC Pumps D E 2

k.

Altemate Cooling to 1A NV Pump D E R 8 All RO and SRO-I control room (and in-plant) systems must be different and selVe different safety functions; all 5 SRO-U systems must selVe different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)ltemate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank

~9/~8/~4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature / - / ~ 1 (control room system) (L)ow-Power / Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams ~ 3 / ~ 3 / ~ 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator ES-301, Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO ~ SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System j JPM Title Type Code* Safety Function

a.

b.

Respond to NC System Leakage (SNAP 192) ADS 2

c.

Depressurize the NC System to Minimize Primary to Secondary Leakage during A D L S 3 a SGTR (SNAP 193)

d.

Cooldown the PRT Using NCDT Heat Exchanger (SNAP 194) D S 5

e.

Restore Offsite Power to 6.9 kV Busses per APj07 (Loss of Normal Power) A L N S 6 1 (Black Restart Procedure) (SNAP 195)

f.

Perform the Immediate Actions of APj1jAj5500j16, (Malfunction of Nuclear D S 7 Instrumentation System), case 4, (PjR Malfunction) (SNAP 196)

g.

Shirt Operating RC Pumps (SNAP 197) A N S 8

h.

Perform the Immediate Actions of APj1jAj5500j004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Locally Break Vacuum on a Loss of Feedwater D E 4S

j.

Align Seal Injection to the Unit 2 NC Pumps D E 2

k.

Altemate Cooling to 1A NV Pump D E R 8 All RO and SRO-I control room (and in-plant) systems must be different and selVe different safety functions; all 5 SRO-U systems must selVe different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)ltemate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank

~9/~8/~4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature / - / ~ 1 (control room system) (L)ow-Power / Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams ~ 3 / ~ 3 / ~ 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator

ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO o SRO-I ~ SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function

a.

b.

c.

d.

e.

Restore Offsite Power to 6.9 kV Busses per AP/07 (Loss of Normal Power) A L N S 6 1 (Black Restart Procedure) (SNAP 195)

f.

g.

Shirt Operating RC Pumps (SNAP 197) A N S 8

h.

Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

j.

Align Seal Injection to the Unit 2 NC Pumps D E 2

k.

Alternate Cooling to 1A NV Pump D E R 8 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank

.::.9/.::.8/.::.4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 - 1 ~ 1 (control room system) (L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams .::. 3 1.::. 3 1.::. 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO o SRO-I ~ SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function

a.

b.

c.

d.

e.

Restore Offsite Power to 6.9 kV Busses per AP/07 (Loss of Normal Power) A L N S 6 1 (Black Restart Procedure) (SNAP 195)

f.

g.

Shirt Operating RC Pumps (SNAP 197) A N S 8

h.

Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

j.

Align Seal Injection to the Unit 2 NC Pumps D E 2

k.

Alternate Cooling to 1A NV Pump D E R 8 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank

.::.9/.::.8/.::.4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 - 1 ~ 1 (control room system) (L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams .::. 3 1.::. 3 1.::. 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: C,pc-"'tAl.cJi5A Date of Examination: IZ,( odo f Operating Test Number:

a.

b.

c.

d.

e.

1. General Criteria The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).

There is no day-to-day repetition between this and other operating tests to be administered during this examination. The operating test shall not duplicate items from the applicants' audit test(s). (see Section D.1.a.) Overlap with the written examination and between different parts of the operating test is within acceptable limits. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.

2. Walk-Through Criteria

a.

Each JPM includes the following, as applicable: initial conditions initiating cues references and tools, including associated procedures reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include: detailed expected actions with exact criteria and nomenclature Initials a b* (JJ ~ system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b.

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

~ ~~ Date

a.

Author

b.

Facility Reviewer(*)

c.

NRC Chief Examiner (#) Printed Nam.i~ignature d o,frv rL Su 1I1l:;\\)r / ~ /0Lllft0 D. /'-'l//leW:! / (J-/4?*~-' £t;M-'lJ) (,J, It-\\S\\~VLY~.fi It f,tf/of (f II? jut" / ;IF!! C?1-¥t8

d.

NRC Supervisor r/~/v~ f lY NOTE: The facility signature is not applicable for NRC-developed tests. Independent NRC reviewer initial items in Column "cn; chief examiner concurrence required. c# J l~ I ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: CA-""fAl.c) i5A Date of Examination: IZ,{ 0,[0 f Operatinq Test Number: Initials

1. General Criteria a

b* c#

a.

The operating test conforms with the previously approved outline; changes are consistent with ()..Lj ~¥' A sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution). I ~

b.

There is no day-to-day repetition between this and other operating tests to be administered ~ bl during this examination.

c.

The operating test shall not duplicate items from the applicants' audit test(s). (see Section D.1.a.) ~ ~~ r ~i

d.

Overlap with the written examination and between different parts of the operating test is within ~ ,f ~ acceptable limits. It appears that the operating test will differentiate between competent and less-than-competent tJ>i I~

e.

~ J~' applicants at the desiqnated license level.

2. Walk-Through Criteria

a.

Each JPM includes the following, as applicable: (JJ initial conditions initiating cues references and tools, including associated procedures j 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 system response and other examiner cues ~ statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b.

Ensure that any changes from the previously approved systems and administrative walk-through ~ ¥ J 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 on those forms and Form ES-201-2.

3. Simulator Criteria The associated simulator operating tests (scenario sets) have been reviewed in accordance with tJJJ.\\J~ ~

Form ES-301-4 and a copy is attached. Printed Nai<s~nature Date dOl +rv rL S u 1I1l:;\\)r .j..A.A.- - It !J,; LoY

a.

Author I0LII{t0 D. ~/I;e(j/fJ-f~/--/ L f II ~ii)t"

b.

Facility Reviewer(*) ~t;fM.'1J) hi, It-Y>'vkH vVLJ4! /,,'.£.' IIZF1/ t~'if8

c.

NRC Chief Examiner (#) ~l'( 1JAW.ow -r: W~ /1Cliut:rffw:r---

d.

NRC Supervisor r/~/v~ lY NOTE: The facility signature is not applicable for NRC-developed tests. Independent NRC reviewer initial items in Column "cn; chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: ~AVJ("3A Date of Exam:l2lDII~~enario Numbers: 'ZI 11'l Operating Test No.: QUALITATIVE ATTRIBUTES Initials a b* c#

1.

The initial conditions are realistic, in that some equipment andlor instrumentation may be out (jt/l ~~ g of service, but it does not cue the operators into expected events.

2.

The scenarios consist mostly of related events. IJI{ '{':Jif" 1:\\

3.

Each event description consists of dt-7 the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event I~f t the symptomslcues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

4.

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

5.

The events are valid with regard to physics and thermodynamics. d0 1\\1~, \\

6.

Sequencing and timing of events is reasonable, and allows the examination team to obtain lfJJ. ~~ 'f complete evaluation results commensurate with the scenario objectives. v

7.

If time compression techniques are used, the scenario summary clearly so indicates. J1~ ~~ f Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

8.

The simulator modeling is not altered. M ~ ~

9.

The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator pb ~( J performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

10.

Every operator will be evaluated using at least one new or significantly modified scenario. ~ I~ [) All other scenarios have been altered in accordance with Section 0.5 of ES-301. (,

11.

All individual operator competencies can be evaluated, as verified using Form ES-301-6 dJ1 \\jif T( (submit the form along with the simulator scenarios).

12.

Each applicant will be significantly involved in the minimum number of transients and events ~ ~~( 0 specified on Form ES-301-5 (submit the form with the simulator scenarios). The level of difficulty is appropriate to support licensing decisions for each crew position. M t¥ )

13.

f Target Quantitative Attributes (Per Scenario; See Section D.5.d) 'i~~~~u~l*, TJ

1.

Total malfunctions (5-8) 715/7 PI IbP-' (

2.

Malfunctions after EOP entry (1-2) 5 12-/~ tJti lb~ -1 trn

3.

Abnormal events (2-4) G, I..., I & {JA.. I~~ cf:

4.

Major transients (1-2) Z I (/2 cf1.-v I~~ rI-'

5.

EOPs enteredlrequiring substantive actions (1-2)

2. I Z I If

~ ~ J

6.

EOP contingencies requiring substantive actions (0-2) 2-lOla M \\:)~ ~

7.

Critical tasks (2-3) '2.- 12. I Z- ~ ~~ ~ ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: ~AVJ("3A Date of Exam:l2lDII~~enario Numbers: 'ZI 11'l Operating Test No.: QUALITATIVE ATTRIBUTES Initials a b* c#

1.

The initial conditions are realistic, in that some equipment andlor instrumentation may be out (jt/l ~~ g of service, but it does not cue the operators into expected events.

2.

The scenarios consist mostly of related events. .{JJf '{':Jif" I~ ~

3.

Each event description consists of dt-7 the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event ~f t the symptomslcues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

4.

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

5.

The events are valid with regard to physics and thermodynamics. d0 \\1~, \\

6.

Sequencing and timing of events is reasonable, and allows the examination team to obtain lfJJ. tJ~ 'f complete evaluation results commensurate with the scenario objectives. v

7.

If time compression techniques are used, the scenario summary clearly so indicates. J10 ~~ R Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

8.

The simulator modeling is not altered. M ~ Y

9.

The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator pb ~( Ii performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

10.

Every operator will be evaluated using at least one new or significantly modified scenario. ~ V [) All other scenarios have been altered in accordance with Section 0.5 of ES-301. (,

11.

All individual operator competencies can be evaluated, as verified using Form ES-301-6 dJ1 \\jif ~ (submit the form along with the simulator scenarios).

12.

Each applicant will be significantly involved in the minimum number of transients and events ~ ~~( 0 specified on Form ES-301-5 (submit the form with the simulator scenarios). (JJ W )

13.

The level of difficulty is appropriate to support licensing decisions for each crew position. ( Target Quantitative Attributes (Per Scenario; See Section D.5.d) 'i~~~~u~l*, TJ

1.

Total malfunctions (5-8) 715/7 PI bP-' Ie

2.

Malfunctions after EOP entry (1-2) 5 12-/~ tJij b~ -1 lin

3.

Abnormal events (2-4) G, I..., I & 'IP.. t-..~ CF--

4.

Major transients (1-2) Z I (/2 ~ ~~ rr

5.

EOPs enteredlrequiring substantive actions (1-2)

2. I Z I If

~ ~ J

6.

EOP contingencies requiring substantive actions (0-2) 2-lOla M \\:)~ ~

7.

Critical tasks (2-3) '2.- 12. I Z- ~ ~~ 1

ES-301 Transient and Event Checklist Form ES-301-5 Facility: CATAWBA NUCLEAR STATION Date of Exam: 12/01/2008 Operating Test No.: A E Scenarios P V 1 2 3 4 T M P E 0 I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I C M S A B S A B S A B S A B L U A T R T 0 R T 0 R T 0 R T 0 M(*) N Y 0 C P 0 C P 0 C P 0 C P R I U T P E RO RX 1 4 1 1/2 1 1 0 ~ SRO-I NOR 2 0/1 1 1 1 0 I/C 46 235 16 235 35 46 126 345 4/5 4 4 2 SRO-U MAJ 7 7 7 7 7 7 7 7 2 2 2 1 0 TS 0 2 2 RO RX 1 4 1 1/2 1 1 0 0 NOR 2 0/1 1 1 1 SRO-I I/C 23456 12356 3456 12345 4/5 4 4 2 0 6 SRO-U MAJ 7 7 7 7 2 2 2 1 ~ TS 356 123 46 34 4-6 0 2 2 RO RX 1 1 4 4 1 1 1/2 1 1 0 0 SRO-I NOR 2 0/1 1 1 1 ~ I/C 23456 46 12356 16 3456 35 12345 126 4/5 4 4 2 SRO-U 6 0 MAJ 7 7 7 7 7 7 7 7 2 2 2 1 TS 356 123 46 34 2/3 0 2 2 RO RX 1 1 0 0 SRO-I NOR 1 1 1 0 IIC 4 4 2 SRO-U MAJ 2 2 1 0 TS 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 IIC malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-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 Facility: CATAWBA NUCLEAR STATION Date of Exam: 12/01/2008 Operating Test No.: A E Scenarios P V 1 2 3 4 T M P E 0 I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I C M S A B S A B S A B S A B L U A T R T 0 R T 0 R T 0 R T 0 M(*) N Y 0 C P 0 C P 0 C P 0 C P R I U T P E RO RX 1 4 1 1/2 1 1 0 ~ SRO-I NOR 2 0/1 1 1 1 0 I/C 46 235 16 235 35 46 126 345 4/5 4 4 2 SRO-U MAJ 7 7 7 7 7 7 7 7 2 2 2 1 0 TS 0 2 2 RO RX 1 4 1 1/2 1 1 0 0 NOR 2 0/1 1 1 1 SRO-I I/C 23456 12356 3456 12345 4/5 4 4 2 0 6 SRO-U MAJ 7 7 7 7 2 2 2 1 ~ TS 356 123 46 34 4-6 0 2 2 RO RX 1 1 4 4 1 1 1/2 1 1 0 0 SRO-I NOR 2 0/1 1 1 1 ~ I/C 23456 46 12356 16 3456 35 12345 126 4/5 4 4 2 SRO-U 6 0 MAJ 7 7 7 7 7 7 7 7 2 2 2 1 TS 356 123 46 34 2/3 0 2 2 RO RX 1 1 0 0 SRO-I NOR 1 1 1 0 IIC 4 4 2 SRO-U MAJ 2 2 1 0 TS 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 IIC malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-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, Rev. 9 Competencies Checklist Form ES-301-6 Facility: Catawba Nuclear Station Date of Examination: 12/01/2008 Operating Test No.: APPLICANTS RO BOP SRO-U/I N/A Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 467 146 357 126 235 235 467 345 2-7 1-7 3-7 1-7 and Conditions 7 7 7 7 7 Comply With and 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 Use Procedures (1) 7 7 7 7 7 7 7 7 Operate Control 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 Boards (2) 7 7 7 7 7 7 7 7 Communicate 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 and Interact 7 7 7 7 7 7 7 7 Demonstrate Supervisory n/a n/a n/a n/a n/a n/a n/a n/a 1-7 1-7 1-7 1-7 Ability (3) Comply With and n/a n/a n/a n/a n/a n/a n/a n/a 356 123 46 34 Use Tech. Specs. (3) Notes: (1 )Includes Technical Specification compliance for an RO. (2)Optional for an SRO-U. (3)Only applicable to SROs. Instructions: Check the applicants'license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. ES-301, Rev. 9 Competencies Checklist Form ES-301-6 Facility: Catawba Nuclear Station Date of Examination: 12/01/2008 Operating Test No.: APPLICANTS RO BOP SRO-U/I N/A Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 467 146 357 126 235 235 467 345 2-7 1-7 3-7 1-7 and Conditions 7 7 7 7 7 Comply With and 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 Use Procedures (1) 7 7 7 7 7 7 7 7 Operate Control 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 Boards (2) 7 7 7 7 7 7 7 7 Communicate 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 and Interact 7 7 7 7 7 7 7 7 Demonstrate Supervisory n/a n/a n/a n/a n/a n/a n/a n/a 1-7 1-7 1-7 1-7 Ability (3) Comply With and n/a n/a n/a n/a n/a n/a n/a n/a 356 123 46 34 Use Tech. Specs. (3) Notes: (1 )Includes Technical Specification compliance for an RO. (2)Optional for an SRO-U. (3)Only applicable to SROs. Instructions: Check the applicants'license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-401 Written Examination Quality Checklist Form ES-401-6 Date of Exam:'z.lOt \\o, Exam Level: RO [2( <:Rn n

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

a. Author Item Description Questions and answers are technically accurate and applicable to the facility.

a.

NRC KlAs are referenced for all questions.

b.

Facility learning objectives are referenced as available. SRO questions are appropriate in accordance with Section D.2.d of ES-401 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). 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 _ tJJe examinations were developed independently; or -0he licensee certifies that there is no duplication; or _ other (explain) Bank use meets limits (no more than 75 percent 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. Bank Modified New 9/- yg/- Memory CIA Between 50 and 60 percent of the questions on the RO exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected KlAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s} at right. 35' / - '-fO / - References/handouts provided do not give away answers or aid in the elimination of distractors. Question content conforms with specific KIA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified. Question psychometric quality and format meet the guidelines in ES Appendix B. 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 / Si~ature Jo~ IL.SulraA /o,AhAJ-

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor JIIJII'N-lL'/. \\JJlhLlA-AIA.I /

7l\\ I '"' Note:

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

1. Independent NRC reviewer initial items in Column "c n

chief examiner concurrence required.

Initial a b* I Date a {tt/or =.~ (~ht1//tg ES-401 Written Examination Quality Checklist Form ES-401-6 IbCA\\~M Date of Exam:,z.I Ot \\ 0' Exam Level: RO[2( SRoD Initial Item Description a b* G~

1.

Questions and answers are technically accurate and applicable to the facility. ~ b~ Jt

2.

a.

NRC KlAs are referenced for all questions. l-' ~~ V

b.

Facility learning objectives are referenced as available. ~l

3.

SRO questions are appropriate in accordance with Section D.2.d of ES-401 ~?-' ~\\tg

4.

The sampling process was random and systematic (If more than 4 RO or 2 SRO questions J v 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: r--- _ the audit exam was systematically and randomly developed; or _ the audit exam was completed before the license exam was started; or l ~e examinations were developed independently; or ~~ he 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 '6/- 9 yg/- btf 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; (V' the SRO exam may exceed 60 percent if the randomly 35""'/ '-fO / ~~ selected KlAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right. .J,

8.

References/handouts provided do not give away answers I-" b~ ~ or aid in the elimination of distractors. ~ -,

9.

Question content conforms with specific KIA statements in the previously approved t""'" Wrt' ~ 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. r ~~ Mk /~

11.

The exam contains the required number of one-point, multiple choice items; ~ tJ~

1\\-

the total is correct and agrees with the value on the cover sheet. '-.J Printed Name / 7cature Date

a. Author Jo~ IL.~rQA

~(}}.hAf-n{diar

b. Facility Reviewer (*)

B{(!.IA-v 1l. A '{fer /L. l/;J. J!;;. ') ---2l './h--.J.J =.~

c. NRC Chief Examiner (#)

.~ c((A '1.,1) \\,.) U\\5 f4{ A-A1P/'V'--f({..'~.d"'f-;

d. NRC Regional Supervisor J/~IIN~l (. 'W/bIliANAU /7\\

I " (~ht1//tg ~~ Note:

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

1. Independent NRC reviewer initial items in Column "c n

chief examiner concurrence required.

ES 401, Rev 9 Question 1 507 2 508 3 509 4 510 5 511 6 512 7 513 f)}JAL-2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description EPE007 EK2.03 KIA System Reactor Trip Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7/45.7) EPE009 EA2.10 Small Break LOCA Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5/45.13) EPE011 2.4.30 Large Break LOCA EPE011 GENERIC Tier/Group Importance RO/SRO T/G 1 /1 RO 3.5 SRO 3.6 Reactor trip status panel T/G 1 / 1 RO 3.1 SRO 3.7 Airborne activity T/G 1 / 1 RO 2.7 SRO 4.1 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 143.5 145.11 ) APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1 / 1 RO 2.7 SRO 3.1 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8/41.10 145.3) Relationship of charging flow to pressure differential between charging and RCS................................. APE025 2.4.30 Loss of Residual Heat Removal System (RHRS) T/G 1 / 1 RO 2.7 SRO 4.1 APE025 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE026 AA2.03 Loss of Component Cooling Water (CCW) T/G 1 / 1 RO 2.6 SRO 2.9 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5/45.13) The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition APE027 AA1.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 /1 RO 3.9* SRO 3.6* Ability to operate and 1 or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 145.5/45.6) Pressure recovery, using emergency-only heaters Page 1 of 12 ES 401, Rev 9 Question 1 507 2 508 3 509 4 510 5 511 6 512 7 513 f)}JAL-2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description EPE007 EK2.03 KIA System Reactor Trip Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7/45.7) EPE009 EA2.10 Small Break LOCA Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5/45.13) EPE011 2.4.30 Large Break LOCA EPE011 GENERIC Tier/Group Importance RO/SRO T/G 1 /1 RO 3.5 SRO 3.6 Reactor trip status panel T/G 1 / 1 RO 3.1 SRO 3.7 Airborne activity................................................. T/G 1 / 1 RO 2.7 SRO 4.1 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 143.5 145.11 ) APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1 / 1 RO 2.7 SRO 3.1 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8/41.10 145.3) Relationship of charging flow to pressure differential between charging and RCS................................. APE025 2.4.30 Loss of Residual Heat Removal System (RHRS) T/G 1 / 1 RO 2.7 SRO 4.1 APE025 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE026 AA2.03 Loss of Component Cooling Water (CCW) T/G 1 / 1 RO 2.6 SRO 2.9 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5/45.13) The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition.................. APE027 AA1.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 /1 RO 3.9* SRO 3.6* Ability to operate and 1 or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 145.5/45.6) Pressure recovery, using emergency-only heaters..................... Page 1 of 12

ES401, Rev 9 Question 8 514 9 515 10 516 11 517 12 518 13 519 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO EPE029 2.4.34 Anticipated Transient Without Scram (ATWS) T/G 1 / 1 RO 4.2 SRO 4.1 EPE029 GENERIC Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13) EPE038 EK1.02 Steam Generator Tube Rupture (SGTR) T/G 1 / 1 RO 3.2 SRO 3.5 Knowledge of the operational implications of the following concepts as they apply to the SGTR: (CFR 41.8 / 41.10 / 45.3) Leak rate vs. pressure drop APE057 AA2.13 Loss of Vital AC Electrical Instrument Bus T/G 1 / 1 RO 3.0 SRO 3.4 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5/ 45.13) APE058 AA1.02 Loss of DC Power Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7/45.5/45.6) APE062 AK3.03 Loss of Nuclear Service Water Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 /45.7) APE065 AK3.03 Loss of Instrument Air Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: (CFR 41.5,41.10 /45.6/45.13) VCT level and pressure indicators and recorders T/G 1/1 RO 3.1* SRO 3.1 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector T/G 1 / 1 RO 4.0 SRO 4.2 Guidance actions contained in EOP for Loss of nuclear service water.... T/G 1 / 1 RO 2.9 SRO 3.4 Knowing effects on plant operation of isolating certain equipment from instrument air Page 2 of 12 ES401, Rev 9 Question 8 514 9 515 10 516 11 517 12 518 13 519 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO EPE029 2.4.34 Anticipated Transient Without Scram (ATWS) T/G 1 / 1 RO 4.2 SRO 4.1 EPE029 GENERIC Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13) EPE038 EK1.02 Steam Generator Tube Rupture (SGTR) T/G 1 / 1 RO 3.2 SRO 3.5 Knowledge of the operational implications of the following concepts as they apply to the SGTR: (CFR 41.8 / 41.10 / 45.3) Leak rate vs. pressure drop........................................ APE057 AA2.13 Loss of Vital AC Electrical Instrument Bus T/G 1 / 1 RO 3.0 SRO 3.4 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5/ 45.13) APE058 AA1.02 Loss of DC Power Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7/45.5/45.6) APE062 AK3.03 Loss of Nuclear Service Water Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 /45.7) APE065 AK3.03 Loss of Instrument Air Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: (CFR 41.5,41.10 /45.6/45.13) VCT level and pressure indicators and recorders...................... T/G 1/1 RO 3.1* SRO 3.1 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector............................. T/G 1 / 1 RO 4.0 SRO 4.2 Guidance actions contained in EOP for Loss of nuclear service water.... T/G 1 / 1 RO 2.9 SRO 3.4 Knowing effects on plant operation of isolating certain equipment from instrument air..................................... Page 2 of 12

ES401, Rev 9 Question 14 520 15 521 16 522 17 523 18 524 19 525 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KiA Number KiA Description KiA System Tier/Group Importance RO/SRO APE077 AA1.01 Generator Voltage and Electric Grid Disturbances T/G 110 RO 3.6 SRO 3.7 Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10 1 45.5,45.7, and 45.8 ) WE04 EK2.2 LOCA Outside Containment Knowledge of the interrelations between the (LOCA Outside Containment) and the following: (CFR: 41.7/45.7) WE05 EK3.1 Loss of Secondary Heat Sink Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) (CFR: 41.5/41.10, 45.6,45.13) Grid frequency and voltage......................................................... T/G 1 1 1 RO 3.8 SRO 4.0 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. T/G 1 1 1 RO 3.4 SRO 3.8 Facility operating characteristics during transient conditions, includingDcoolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics. WE11 EK2.1 Loss of Emergency Coolant Recirculation T/G 1 1 1 RO 3.6 SRO 3.9 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. WE12 EK1.3 Uncontrolled Depressurization of all Steam Generators T/G 1 1 1 RO 3.4 SRO 3.7 Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators) (CFR: 41.8/41.10/45.3) Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators). APE001 AA1.06 Continuous Rod Withdrawal T/G 1 12 RO 3.0* SRO 2.9* Ability to operate and 1 or monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.71 45.5/45.6) Rod transfer switches Page 3 of 12 ES401, Rev 9 Question 14 520 15 521 16 522 17 523 18 524 19 525 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KiA Number KiA Description KiA System Tier/Group Importance RO/SRO APE077 AA1.01 Generator Voltage and Electric Grid Disturbances T/G 110 RO 3.6 SRO 3.7 Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10 1 45.5,45.7, and 45.8 ) WE04 EK2.2 LOCA Outside Containment Knowledge of the interrelations between the (LOCA Outside Containment) and the following: (CFR: 41.7/45.7) WE05 EK3.1 Loss of Secondary Heat Sink Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) (CFR: 41.5/41.10, 45.6,45.13) Grid frequency and voltage......................................................... T/G 1 1 1 RO 3.8 SRO 4.0 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. T/G 1 1 1 RO 3.4 SRO 3.8 Facility operating characteristics during transient conditions, includingDcoolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics. WE11 EK2.1 Loss of Emergency Coolant Recirculation T/G 1 1 1 RO 3.6 SRO 3.9 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. WE12 EK1.3 Uncontrolled Depressurization of all Steam Generators T/G 1 1 1 RO 3.4 SRO 3.7 Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators) (CFR: 41.8/41.10/45.3) Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators). APE001 AA1.06 Continuous Rod Withdrawal T/G 1 12 RO 3.0* SRO 2.9* Ability to operate and 1 or monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.71 45.5/45.6) Rod transfer switches............................................. Page 3 of 12

ES401, Rev 9 Question 20 526 21 527 22 528 23 529 24 530 25 531 26 532 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description APE005 2.4.6 APE005 GENERIC APE024 AK1.04 KIA System Inoperable/Stuck Control Rod Emergency Boration Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8/41.10/45.3) Tier/Group Importance RO/SRO T/G 1 12 RO 3.7 SRO 4.7 Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) T/G 1 12 RO 2.8 SRO 3.6 Low temperature limits for born concentration.................... APE033 AK1.01 Loss of Intermediate Range Nuclear Instrumentation T/G 1 12 RO 2.7 SRO 3.0 Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: CFR 41.8 1 41.10 1 45.3) Effects of voltage changes on performance APE037 AA2.03 Steam Generator (S/G) Tube Leak T/G 1 12 RO 3.4 SRO 3.9 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 1 45.13) EPE074 EA1.01 Inadequate Core Cooling Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41.7/45.5/45.6) APE036 AK3.03 Fuel Handling Incidents Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10/45.6/45.13) That the expected indication on main steam lines from the S/Gs should show increasing radiation levels T/G 1 12 RO 4.2 SRO 4.4 RCS water inventory T/G 1 12 RO 3.7 SRO 4.1 Guidance contained in EOP for fuel handling inciqent WE03 EK2.1 LOCA Cooldown and Depressurization T/G 1 12 RO 3.6 SRO 4.0 Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. Page 4 of 12 ES401, Rev 9 Question 20 526 21 527 22 528 23 529 24 530 25 531 26 532 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description APE005 2.4.6 APE005 GENERIC APE024 AK1.04 KIA System Inoperable/Stuck Control Rod Emergency Boration Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8/41.10/45.3) Tier/Group Importance RO/SRO T/G 1 12 RO 3.7 SRO 4.7 Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) T/G 1 12 RO 2.8 SRO 3.6 Low temperature limits for born concentration.................... APE033 AK1.01 Loss of Intermediate Range Nuclear Instrumentation T/G 1 12 RO 2.7 SRO 3.0 Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: CFR 41.8 1 41.10 1 45.3) Effects of voltage changes on performance........................... APE037 AA2.03 Steam Generator (S/G) Tube Leak T/G 1 12 RO 3.4 SRO 3.9 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 1 45.13) EPE074 EA1.01 Inadequate Core Cooling Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41.7/45.5/45.6) APE036 AK3.03 Fuel Handling Incidents Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10/45.6/45.13) That the expected indication on main steam lines from the S/Gs should show increasing radiation levels...................... T/G 1 12 RO 4.2 SRO 4.4 RCS water inventory.............................................. T/G 1 12 RO 3.7 SRO 4.1 Guidance contained in EOP for fuel handling inciqent.................. WE03 EK2.1 LOCA Cooldown and Depressurization T/G 1 12 RO 3.6 SRO 4.0 Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. Page 4 of 12

ES 401, Rev 9 Question 27 533 28 534 29 535 30 536 31 537 32 538 KIA Number KIA Description WE09 EK3.3 2008 RO NRC Examination Combined PWR Written Examination Outline KIA System Natural Circulation Operations Form ES-401-2/3 TierlGroup Importance RO/SRO T/G 1 12 RO 3.5 SRO 3.6 Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations) Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations. (CFR: 41.5/41.10, 45.6,45.13) SYS003 A2.02 Reactor Coolant Pump System (RCPS) T/G 2 I 1 RO 3.7 SRO 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP SYS004 A1.01 Chemical and Volume Control System Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5/45.5) Activity levels in primary system SYS004 K1.34 Chemical and Volume Control System T/G 2 I 1 RO 2.9 SRO 3.8 T/G 2 I 1 RO 2.7 SRO 2.9 Knowledge of the physical connections andlor cause-effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9/45.7 to 45.8) Interface between CVCS and reactor coolant drain tank; and PZR PCS.... SYS005 K4.11 Residual Heat Removal System (RHRS) T/G 2 I 1 RO 3.5* SRO 3.9* Knowledge of RHRS design feature(s) andlor interlock(s) which provide or the following: (CFR: 41.7) Lineup for low head recirculation mode (external and internal) SYS006 A1.05 Emergency Core Cooling System (ECCS) T/G 2 I 1 RO 2.9 SRO 3.3 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5/45.5) CCW flow (establish flow to RHR heat exchanger prior to placing in service Page 5 of 12 ES 401, Rev 9 Question 27 533 28 534 29 535 30 536 31 537 32 538 KIA Number KIA Description WE09 EK3.3 2008 RO NRC Examination Combined PWR Written Examination Outline KIA System Natural Circulation Operations Form ES-401-2/3 TierlGroup Importance RO/SRO T/G 1 12 RO 3.5 SRO 3.6 Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations) Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations. (CFR: 41.5/41.10, 45.6,45.13) SYS003 A2.02 Reactor Coolant Pump System (RCPS) T/G 2 I 1 RO 3.7 SRO 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP................... SYS004 A1.01 Chemical and Volume Control System Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5/45.5) Activity levels in primary system SYS004 K1.34 Chemical and Volume Control System T/G 2 I 1 RO 2.9 T/G 2 I 1 RO 2.7 SRO 3.8 SRO 2.9 Knowledge of the physical connections andlor cause-effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9/45.7 to 45.8) Interface between CVCS and reactor coolant drain tank; and PZR PCS.... SYS005 K4.11 Residual Heat Removal System (RHRS) T/G 2 I 1 RO 3.5* SRO 3.9* Knowledge of RHRS design feature(s) andlor interlock(s) which provide or the following: (CFR: 41.7) Lineup for low head recirculation mode (external and internal) SYS006 A1.05 Emergency Core Cooling System (ECCS) T/G 2 I 1 RO 2.9 SRO 3.3 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5/45.5) CCW flow (establish flow to RHR heat exchanger prior to placing in service Page 5 of 12

ES 401, Rev 9 Question 33 539 34 540 35 541 36 542 37 543 38 544 39 545 KIA Number KIA Description SYS007 2.4.6 2008 RO NRC Examination Combined PWR Written Examination Outline KIA System Pressurizer Relief Tank/Quench Tank System (PRTS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2 1 1 RO 3.7 SRO 4.7 SYS007 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) SYSOOB K3.03 Component Cooling Water System (CCWS) Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: RCP SYSOOB K4.09 Component Cooling Water System (CCWS) T/G 2 1 1 RO 4.1 SRO 4.2 T/G 2 11 RO 2.7 SRO 2.9 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) The "standby" feature for the CCW pumps SYS010 2.1.25 Pressurizer Pressure Control System (PZR PCS) T/G 2 1 1 RO 3.9 SRO 4.2 SYS010 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) SYS012 A2.02 Reactor Protection System (RPS) Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 1 43.5 1 45.3 145.5) Loss of instrument power SYS012 K5.01 Reactor Protection System (RPS) Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5/45.7) DNB SYS013 K6.01 Engineered Safety Features Actuation System (ESFAS) Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8) Sensors and detectors Page 6 of 12 T/G 2 1 1 RO 3.6 SRO 3.9 T/G 211 RO 3.3* SRO 3.B T/G 2/1 RO 2.7* SRO 3.1* ES 401, Rev 9 Question 33 539 34 540 35 541 36 542 37 543 38 544 39 545 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS007 2.4.6 Pressurizer Relief Tank/Quench Tank System (PRTS) T/G 2 1 1 RO 3.7 SRO 4.7 SYS007 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) SYSOOB K3.03 Component Cooling Water System (CCWS) T/G 2 1 1 RO 4.1 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: RCP........................................................... SYSOOB K4.09 Component Cooling Water System (CCWS) T/G 2 11 RO 2.7 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) The "standby" feature for the CCW pumps............................ SYS010 2.1.25 Pressurizer Pressure Control System (PZR PCS) T/G 2 1 1 RO 3.9 SRO 4.2 SRO 2.9 SRO 4.2 SYS010 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) SYS012 A2.02 Reactor Protection System (RPS) T/G 2 1 1 RO 3.6 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 1 43.5 1 45.3 145.5) Loss of instrument power......................................... SRO 3.9 SYS012 K5.01 Reactor Protection System (RPS) T/G 211 RO 3.3* SRO 3.B Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5/45.7) DNB........................................................... SYS013 K6.01 Engineered Safety Features Actuation System (ESFAS) T/G 2/1 RO 2.7* SRO 3.1* Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8) Sensors and detectors............................................ Page 6 of 12

ES 401, Rev 9 Question 40 546 41 547 42 548 43 549 44 550 45 551 46 552 2008 RO NRC Examination Combined PWR Written Examination Outline KIA Number KIA Description KIA System SYS022 K2.02 Containment Cooling System (CCS) Knowledge of power supplies to the following: (CFR: 41.7) SYS025 A4.01 Ice Condenser System Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /45.5 to 45.8) Chillers Ice condenser isolation valves SYS026 A1.03 Containment Spray System (CSS) Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5/45.5) Containment sump level SYS026 K1.01 Containment Spray System (CSS) Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) ECCS SYS039 K5.01 Main and Reheat Steam System (MRSS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 211 RO 2.5* SRO 2.4* T/G 2 11 RO 3.0* SRO 2.7* T/G 2 I 1 RO 3.5 SRO 3.5 T/G 2 I 1 RO 4.2 SRO 4.2 T/G 2 11 RO 2.9 SRO 3.1 Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5/45.7) Definition and causes of steam/water hammer SYS059 A4.11 Main Feedwater (MFW) System Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8) T/G 2 11 RO 3.1 Recovery from automatic feedwater isolation SYS061 A3.03 Auxiliary I Emergency Feedwater (AFW) System T/G 2 I 1 RO 3.9 Ability to monitor automatic operation of the AFW, including: (CFR: 41.7/45.5) AFW S/G level control on automatic start Page 7 of 12 SRO 3.3 SRO 3.9 ES 401, Rev 9 Question 40 546 41 547 42 548 43 549 44 550 45 551 46 552 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS022 K2.02 Containment Cooling System (CCS) T/G 211 RO 2.5* SRO 2.4* Knowledge of power supplies to the following: (CFR: 41.7) Chillers SYS025 A4.01 Ice Condenser System T/G 2 11 RO 3.0* SRO 2.7* Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /45.5 to 45.8) Ice condenser isolation valves...................................... SYS026 A1.03 Containment Spray System (CSS) T/G 2 I 1 RO 3.5 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5/45.5) Containment sump level........................................... SYS026 K1.01 Containment Spray System (CSS) T/G 2 I 1 RO 4.2 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) ECCS.......................................................... SYS039 K5.01 Main and Reheat Steam System (MRSS) T/G 2 11 RO 2.9 Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5/45.7) SYS059 A4.11 Main Feedwater (MFW) System Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8) Definition and causes of steam/water hammer........................ T/G 2 11 RO 3.1 Recovery from automatic feedwater isolation........................ SYS061 A3.03 Auxiliary I Emergency Feedwater (AFW) System T/G 2 I 1 RO 3.9 Ability to monitor automatic operation of the AFW, including: (CFR: 41.7/45.5) AFW S/G level control on automatic start............................ Page 7 of 12 SRO 3.5 SRO 4.2 SRO 3.1 SRO 3.3 SRO 3.9

ES 401, Rev 9 Question 47 553 48 554 49 555 50 556 51 557 52 558 2008 RO NRC Examination Combined PWR Written Examination Outline KJA Number KJA Description KJA System SYSOS2 A3.01 AC Electrical Distribution System Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7/45.5) Vital ac bus amperage SYSOS3 K2.01 DC Electrical Distribution System Knowledge of bus power supplies to the following: (CFR: 41.7) Major DC loads SYSOS3 K3.01 DC Electrical Distribution System Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7/45.6) ED/G SYSOS4 A3.07 Emergency Diesel Generator (ED/G) System Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/45.5) Load sequencing SYSOS4 KS.07 Emergency Diesel Generator (ED/G) System Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.71 45.7) Air receivers SYS073 A2.02 Process Radiation Monitoring (PRM) System Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5 145.3 1 45.13) Detector failure Page 8 of 12 Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2 / 1 RO 3.0 SRO 3.1 T/G 2/1 RO 2.9* SRO 3.1* T/G 2 / 1 RO 3.7* SRO 4.1 T/G 2/1 RO 3.S* SRO 3.7* T/G 2 / 1 RO 2.7 SRO 2.9 T/G 2 / 1 RO 2.7 SRO 3.2 ES 401, Rev 9 Question 47 553 48 554 49 555 50 556 51 557 52 558 KJA Number KJA Description SYSOS2 A3.01 2008 RO NRC Examination Combined PWR Written Examination Outline KJA System AC Electrical Distribution System Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2 / 1 RO 3.0 SRO 3.1 Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7/45.5) Vital ac bus amperage............................................. SYSOS3 K2.01 DC Electrical Distribution System Knowledge of bus power supplies to the following: (CFR: 41.7) Major DC loads SYSOS3 K3.01 DC Electrical Distribution System Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7/45.6) ED/G SYSOS4 A3.07 Emergency Diesel Generator (ED/G) System T/G 2/1 RO 2.9* SRO 3.1* T/G 2 / 1 RO 3.7* SRO 4.1 T/G 2/1 RO 3.S* SRO 3.7* Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/45.5) Load sequencing................................................. SYSOS4 KS.07 Emergency Diesel Generator (ED/G) System T/G 2 / 1 RO 2.7 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.71 45.7) Air receivers.................................................... SYS073 A2.02 Process Radiation Monitoring (PRM) System T/G 2 / 1 RO 2.7 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45.13) Detector failure................................................. Page 8 of 12 SRO 2.9 SRO 3.2

ES401, Rev 9 Question 53 559 54 560 55 561 56 562 57 563 58 564 59 565 KIA Number KIA Description SYS076 K2.01 2008 RO NRC Examination Combined PWR Written EXamination Outline KIA System Service Water System (SWS) Knowledge of bus power supplies to the following: (CFR: 41.7) Service water SYS078 K3.02 Instrument Air System (lAS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2/1 RO 2.7* SRO 2.7 T/G 2 1 1 RO 3.4 SRO 3.6 Knowledge of the effect that a loss or malfunction of the lAS will have on the following: (CFR: 41.7 / 45.6) Systems having pneumatic valves and controls SYS103 K1.07 Containment System Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) SYS001 K2.02 Control Rod Drive System T/G 2 1 1 RO 3.5* SRO 3.7* Containment vacuum system T/G 2 1 2 RO 3.6 SRO 3.7 Knowledge of bus power supplies to the following: (CFR: 41.7) One-line diagram of power supply to trip breakers SYS011 A1.02 Pressurizer Level Control System (PZR LCS) Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5/ 45.5) Charging and letdown flows SYS016 K1.12 Non-Nuclear Instrumentation System (NNIS) Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) S/G SYS017 K3.01 In-Core Temperature Monitor (ITM) System Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7/45.6) Natural circulation indications Page 9 of 12 T/G 2 1 2 RO 3.3 SRO 3.5 T/G 2 1 2 RO 3.5* SRO 3.5* T/G 2 1 2 RO 3.5* SRO 3.7* ES401, Rev 9 Question 53 559 54 560 55 561 56 562 57 563 58 564 59 565 2008 RO NRC Examination Combined PWR Written EXamination Outline Form ES-401-2/3 KIA Number KIA Description SYS076 K2.01 KIA System Service Water System (SWS) Knowledge of bus power supplies to the following: (CFR: 41.7) SYS078 K3.02 Instrument Air System (lAS) Knowledge of the effect that a loss or malfunction of the lAS will have on the following: (CFR: 41.7 / 45.6) SYS103 K1.07 Containment System Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) SYS001 K2.02 Control Rod Drive System Knowledge of bus power supplies to the following: (CFR: 41.7) Tier/Group Importance RO/SRO T/G 2/1 RO 2.7* SRO 2.7 Service water.................................................... T/G 2 1 1 RO 3.4 SRO 3.6 Systems having pneumatic valves and controls........................ T/G 2 1 1 RO 3.5* SRO 3.7* Containment vacuum system....................................... T/G 2 1 2 RO 3.6 SRO 3.7 One-line diagram of power supply to trip breakers..................... SYS011 A1.02 Pressurizer Level Control System (PZR LCS) T/G 2 1 2 RO 3.3 SRO 3.5 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5/ 45.5) Charging and letdown flows........................................ SYS016 K1.12 Non-Nuclear Instrumentation System (NNIS) T/G 2 1 2 RO 3.5* SRO 3.5* Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) S/G............................................................ SYS017 K3.01 In-Core Temperature Monitor (ITM) System T/G 2 1 2 RO 3.5* SRO 3.7* Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7/45.6) Natural circulation indications..................................... Page 9 of 12

ES401, Rev 9 Question 60 566 61 567 62 568 63 569 64 570 65 571 66 572 KIA Number KIA Description SYS027 K5.01 2008 RO NRC Examination Combined PWR Written Examination Outline KIA System Containment Iodine Removal System (CIRS) Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7 /45.7) Purpose of charcoal filters SYS035 2.2.40 Steam Generator System (S/GS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2/2 RO 3.1* SRO 3.4* T/G 2 12 RO 3.4 SRO 4.7 SYS035 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 /45.3) SYS045 A3.05 Main Turbine Generator (MT/G) System Ability to monitor automatic operation of the MT /G system, including: (CFR: 41/7/45.5) Electrohydraulic control SYS071 K4.01 Waste Gas Disposal System (WGDS) T/G 2 1 2 RO 2.6 T/G 2 1 2 RO 2.6 Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) Pressure capability of the waste gas decay tank SYS079 A4.01 Station Air System (SAS) Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) SYS086 K6.04 Fire Protection System (FPS) Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7/45.7) Cross-tie valves with lAS Fire, smoke, and heat detectors GEN2.1 2.1.45 GENERIC - Conduct of Operations T/G 2 1 2 RO 2.7 T/G 2 1 2 RO 2.6 T/G 3 1 0 RO 4.3 SRO 2.9 SRO 3.0 SRO 2.7 SRO 2.9 SRO 4.3 Conduct of Operations Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 / 43.5 / 45.4) Page 10 of 12 ES401, Rev 9 Question 60 566 61 567 62 568 63 569 64 570 65 571 66 572 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS027 K5.01 Containment Iodine Removal System (CIRS) T/G 2/2 RO 3.1* SRO 3.4* Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7 /45.7) Purpose of charcoal filters........................................ SYS035 2.2.40 Steam Generator System (S/GS) T/G 2 12 RO 3.4 SRO 4.7 SYS035 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 /45.3) SYS045 A3.05 Main Turbine Generator (MT/G) System T/G 2 1 2 RO 2.6 Ability to monitor automatic operation of the MT /G system, including: (CFR: 41/7/45.5) Electrohydraulic control SYS071 K4.01 Waste Gas Disposal System (WGDS) T/G 2 1 2 RO 2.6 Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) SYS079 A4.01 Station Air System (SAS) Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) SYS086 K6.04 Fire Protection System (FPS) Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7/45.7) Pressure capability of the waste gas decay tank T/G 2 1 2 RO 2.7 Cross-tie valves with lAS.......................................... T/G 2 1 2 RO 2.6 Fire, smoke, and heat detectors..................................... GEN2.1 2.1.45 GENERIC - Conduct of Operations T/G 3 1 0 RO 4.3 SRO 2.9 SRO 3.0 SRO 2.7 SRO 2.9 SRO 4.3 Conduct of Operations Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 / 43.5 / 45.4) Page 10 of 12

ES 401, Rev 9 Question 67 573 68 574 69 575 70 576 71 577 72 578 73 579 74 580 KIA Number KIA Description GEN2.1 2.1.8 Conduct of Operations GEN2.2 2.2.2 Equipment Control GEN2.2 2.2.39 Equipment Control GEN2.3 2.3.11 Radiation Control GEN2.3 2.3.4 Radiation Control GEN2.3 2.3.7 Radiation Control GEN2.4 2.4.13 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System TierlGroup Importance ROISRO GENERIC - Conduct of Operations T/G 3 I 0 RO 3.4 SRO 4.1 GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control GENERIC - Radiation Control GENERIC - Radiation Control Ability to coordinate personnel activities outside the control room. (CFR: 41.10 145.5/45.12/45.13) T/G 3 I 0 RO 4.6 SRO 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2) T/G 3 I 0 RO 3.9 SRO 4.5 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) T/G 3 I 0 RO 3.8 SRO 4.3 Ability to control radiation releases. (CFR: 41.11 143.4/45.10) T/G 3 I 0 RO 3.2 SRO 3.7 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4/45.10) T/G 3 I 0 RO 3.5 SRO 3.6 Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10) GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 4.0 SRO 4.6 Emergency Procedures 1 Plan Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 1 45.12) GEN2.4 2.4.22 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.6 SRO 4.4 Emergency Procedures 1 Plan Knowledge of the bases for prioritizing safety functions during abnormal/emergencyoperations. (CFR: 41.7 141.10 143.5/45.12) Page 11 of 12 ES 401, Rev 9 Question 67 573 68 574 69 575 70 576 71 577 72 578 73 579 KIA Number KIA Description GEN2.1 2.1.8 Conduct of Operations GEN2.2 2.2.2 Equipment Control GEN2.2 2.2.39 Equipment Control GEN2.3 2.3.11 Radiation Control GEN2.3 2.3.4 Radiation Control GEN2.3 2.3.7 Radiation Control GEN2.4 2.4.13 2008 RO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System TierlGroup Importance ROISRO GENERIC - Conduct of Operations T/G 3 I 0 RO 3.4 SRO 4.1 GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control GENERIC - Radiation Control GENERIC - Radiation Control Ability to coordinate personnel activities outside the control room. (CFR: 41.10 145.5/45.12/45.13) T/G 3 I 0 RO 4.6 SRO 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2) T/G 3 I 0 RO 3.9 SRO 4.5 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) T/G 3 I 0 RO 3.8 SRO 4.3 Ability to control radiation releases. (CFR: 41.11 143.4/45.10) T/G 3 I 0 RO 3.2 SRO 3.7 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4/45.10) T/G 3 I 0 RO 3.5 SRO 3.6 Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10) GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 4.0 SRO 4.6 Emergency Procedures 1 Plan Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 1 45.12) 74 580 GEN2.4 2.4.22 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.6 SRO 4.4 Emergency Procedures 1 Plan Knowledge of the bases for prioritizing safety functions during abnormal/emergencyoperations. (CFR: 41.7 141.10 143.5/45.12) Page 11 of 12

ES 401, Rev 9 Question 75 581 KIA Number KIA Description GEN2.4 2.4.42 2008 RO NRC Examination Combined PWR Written Examination Outline KIA System GENERIC - Emergency Procedures I Plan Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 3/0 RO 2.6 SRO 3.8 Emergency Procedures / Plan Knowledge of emergency response facilities. (CFR: 41.10 /45.11) Page 12 of 12 ES 401, Rev 9 Question 75 581 KIA Number KIA Description GEN2.4 2.4.42 2008 RO NRC Examination Combined PWR Written Examination Outline KIA System GENERIC - Emergency Procedures I Plan Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 3/0 RO 2.6 SRO 3.8 Emergency Procedures / Plan Knowledge of emergency response facilities. (CFR: 41.10 /45.11) Page 12 of 12

ES 401, Rev 9 Question 1 507 2 508 3 509 4 510 5 511 6 512 7 513 rltJkG 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description EPE007 EK2.03 KIA System Reactor Trip Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7 1 45.7) EPE009 EA2.10 Small Break LOCA Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5/45.13) EPE011 2.4.30 Large Break LOCA EPE011 GENERIC Tier/Group Importance RO/SRO T/G 1 1 1 RO 3.5 SRO 3.6 Reactor trip status panel T/G 1 11 RO 3.1 SRO 3.7 Airborne activity T/G 1 11 RO 2.7 SRO 4.1 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1 1 1 RO 2.7 SRO 3.1 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.81 41.10/45.3) Relationship of charging flow to pressure differential between charging and RCS................................. APE025 2.4.30 Loss of Residual Heat Removal System (RHRS) T/G 1 1 1 RO 2.7 SRO 4.1 APE025 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE026 AA2.03 Loss of Component Cooling Water (CCW) T/G 1 1 1 RO 2.6 SRO 2.9 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5/45.13) The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition APE027 AA1.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 11 RO 3.9* SRO 3.6* Ability to operate and 1 or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 1 45.5 1 45.6) Pressure recovery, using emergency-only heaters Page 1 of 16 ES 401, Rev 9 Question 1 507 2 508 3 509 4 510 5 511 6 512 7 513 rltJkG 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description EPE007 EK2.03 KIA System Reactor Trip Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7 1 45.7) EPE009 EA2.10 Small Break LOCA Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5/45.13) EPE011 2.4.30 Large Break LOCA EPE011 GENERIC Tier/Group Importance RO/SRO T/G 1 1 1 RO 3.5 SRO 3.6 Reactor trip status panel T/G 1 11 RO 3.1 SRO 3.7 Airborne activity................................................. T/G 1 11 RO 2.7 SRO 4.1 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1 1 1 RO 2.7 SRO 3.1 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.81 41.10/45.3) Relationship of charging flow to pressure differential between charging and RCS................................. APE025 2.4.30 Loss of Residual Heat Removal System (RHRS) T/G 1 1 1 RO 2.7 SRO 4.1 APE025 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE026 AA2.03 Loss of Component Cooling Water (CCW) T/G 1 1 1 RO 2.6 SRO 2.9 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5/45.13) The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition.................. APE027 AA1.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 11 RO 3.9* SRO 3.6* Ability to operate and 1 or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 1 45.5 1 45.6) Pressure recovery, using emergency-only heaters..................... Page 1 of 16

ES401, Rev 9 Question 8 514 9 515 10 516 11 517 12 518 13 519 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO EPE029 2.4.34 Anticipated Transient Without Scram (ATWS) T/G 1 1 1 RO 4.2 SRO 4.1 EPE029 GENERIC Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13) EPE038 EK1.02 Steam Generator Tube Rupture (SGTR) T/G 1 1 1 RO 3.2 SRO 3.5 Knowledge of the operational implications of the following concepts as they apply to the SGTR: (CFR 41.8 / 41.10 / 45.3) Leak rate vs. pressure drop APE057 AA2.13 Loss of Vital AC Electrical Instrument Bus T/G 1 11 RO 3.0 SRO 3.4 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5/ 45.13) APE058 AA1.02 Loss of DC Power Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7 / 45.5 / 45.6) APE062 AK3.03 Loss of Nuclear Service Water Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 /45.7) APE065 AK3.03 Loss of Instrument Air Knowledge of the rea~ons for the following responses as they apply to the Loss of Instrument Air: (CFR 41.5,41.10 /45.6/45.13) VCT level and pressure indicators and recorders T/G 1/1 RO 3.1* SRO 3.1 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector T/G 1 11 RO 4.0 SRO 4.2 Guidance actions contained in EOP for Loss of nuclear service water.... T/G 1 1 1 RO 2.9 SRO 3.4 Knowing effects on plant operation of isolating certain equipment from instrument air Page 2 of 16 ES401, Rev 9 Question 8 514 9 515 10 516 11 517 12 518 13 519 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO EPE029 2.4.34 Anticipated Transient Without Scram (ATWS) T/G 1 1 1 RO 4.2 SRO 4.1 EPE029 GENERIC Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13) EPE038 EK1.02 Steam Generator Tube Rupture (SGTR) T/G 1 1 1 RO 3.2 SRO 3.5 Knowledge of the operational implications of the following concepts as they apply to the SGTR: (CFR 41.8 / 41.10 / 45.3) Leak rate vs. pressure drop APE057 AA2.13 Loss of Vital AC Electrical Instrument Bus T/G 1 11 RO 3.0 SRO 3.4 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5/ 45.13) APE058 AA1.02 Loss of DC Power Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7 / 45.5 / 45.6) APE062 AK3.03 Loss of Nuclear Service Water Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 /45.7) APE065 AK3.03 Loss of Instrument Air Knowledge of the rea~ons for the following responses as they apply to the Loss of Instrument Air: (CFR 41.5,41.10 /45.6/45.13) VCT level and pressure indicators and recorders...................... T/G 1/1 RO 3.1* SRO 3.1 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector............................. T/G 1 11 RO 4.0 SRO 4.2 Guidance actions contained in EOP for Loss of nuclear service water.... T/G 1 1 1 RO 2.9 SRO 3.4 Knowing effects on plant operation of isolating certain equipment from instrument air..................................... Page 2 of 16

ES 401, Rev 9 Question 14 520 15 521 16 522 17 523 18 524 19 525 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO APE077 AA1.01 Generator Voltage and Electric Grid Disturbances T/G 1 1 0 RO 3.6 SRO 3.7 Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10/45.5,45.7, and 45.8 ) WE04 EK2.2 LOCA Outside Containment Knowledge of the interrelations between the (LOCA Outside Containment) and the following: (CFR: 41.7/45.7) WEOS EK3.1 Loss of Secondary Heat Sink Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) (CFR: 41.5/41.10, 45.6,45.13) Grid frequency and voltage......................................................... T/G 1 1 1 RO 3.8 SRO 4.0 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. T/G 1 11 RO 3.4 SRO 3.8 Facility operating characteristics during transient conditions, inciudingDcoolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics. WE11 EK2.1 Loss of Emergency Coolant Recirculation T/G 1 11 RO 3.6 SRO 3.9 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. WE12 EK1.3 Uncontrolled Depressurization of all Steam Generators T/G 1 1 1 RO 3.4 SRO 3.7 Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators) (CFR: 41.8/41.10/45.3) Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators). APE001 AA1.06 Continuous Rod Withdrawal T/G 1 12 RO 3.0* SRO 2.9* Ability to operate and / or monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.7 / 45.5/45.6) Rod transfer switches Page 3 of 16 ES 401, Rev 9 Question 14 520 15 521 16 522 17 523 18 524 19 525 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO APE077 AA1.01 Generator Voltage and Electric Grid Disturbances T/G 1 1 0 RO 3.6 SRO 3.7 Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10/45.5,45.7, and 45.8 ) WE04 EK2.2 LOCA Outside Containment Knowledge of the interrelations between the (LOCA Outside Containment) and the following: (CFR: 41.7/45.7) WEOS EK3.1 Loss of Secondary Heat Sink Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) (CFR: 41.5/41.10, 45.6,45.13) Grid frequency and voltage......................................................... T/G 1 1 1 RO 3.8 SRO 4.0 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. T/G 1 11 RO 3.4 SRO 3.8 Facility operating characteristics during transient conditions, inciudingDcoolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics. WE11 EK2.1 Loss of Emergency Coolant Recirculation T/G 1 11 RO 3.6 SRO 3.9 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. WE12 EK1.3 Uncontrolled Depressurization of all Steam Generators T/G 1 1 1 RO 3.4 SRO 3.7 Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators) (CFR: 41.8/41.10/45.3) Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators). APE001 AA1.06 Continuous Rod Withdrawal T/G 1 12 RO 3.0* SRO 2.9* Ability to operate and / or monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.7 / 45.5/45.6) Rod transfer switches............................................. Page 3 of 16

ES401, Rev 9 Question 20 526 21 527 22 528 23 529 24 530 25 531 26 532 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KiA Number KiA Description APE005 2.4.6 APE005 GENERIC APE024 AK1.04 KiA System Inoperable/Stuck Control Rod Emergency Boration Knowledge of the operational implications of the following concepts as they apply to Emergency Soration: (CFR 41.8/41.10/45.3) Tier/Group Importance RO/SRO T/G 1 12 RO 3.7 SRO 4.7 Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) T/G 1 12 RO 2.8 SRO 3.6 Low temperature limits for born concentration.................... APE033 AK1.01 Loss of Intermediate Range Nuclear Instrumentation T/G 1 12 RO 2.7 SRO 3.0 Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: CFR 41.8 / 41.10 / 45.3) Effects of voltage changes on performance APE037 AA2.03 Steam Generator (S/G) Tube Leak T/G 1 12 RO 3.4 SRO 3.9 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5/ 45.13) EPE074 EA1.01 Inadequate Core Cooling Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41.7/45.5/45.6) APE036 AK3.03 Fuel Handling Incidents Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10/45.6/45.13) That the expected indication on main steam lines from the S/Gs should show increasing radiation levels T/G 1 I 2 RO 4.2 SRO 4.4 RCS water inventory T/G 1 12 RO 3.7 SRO 4.1 Guidance contained in EOP for fuel handling incident WE03 EK2.1 LOCA Cool down and Depressurization T/G 1 12 RO 3.6 SRO 4.0 Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. Page 4 of 16 ES401, Rev 9 Question 20 526 21 527 22 528 23 529 24 530 25 531 26 532 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KiA Number KiA Description APE005 2.4.6 APE005 GENERIC APE024 AK1.04 KiA System Inoperable/Stuck Control Rod Emergency Boration Knowledge of the operational implications of the following concepts as they apply to Emergency Soration: (CFR 41.8/41.10/45.3) Tier/Group Importance RO/SRO T/G 1 12 RO 3.7 SRO 4.7 Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) T/G 1 12 RO 2.8 SRO 3.6 Low temperature limits for born concentration.................... APE033 AK1.01 Loss of Intermediate Range Nuclear Instrumentation T/G 1 12 RO 2.7 SRO 3.0 Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: CFR 41.8 / 41.10 / 45.3) Effects of voltage changes on performance........................... APE037 AA2.03 Steam Generator (S/G) Tube Leak T/G 1 12 RO 3.4 SRO 3.9 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5/ 45.13) EPE074 EA1.01 Inadequate Core Cooling Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41.7/45.5/45.6) APE036 AK3.03 Fuel Handling Incidents Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10/45.6/45.13) That the expected indication on main steam lines from the S/Gs should show increasing radiation levels...................... T/G 1 I 2 RO 4.2 SRO 4.4 RCS water inventory.............................................. T/G 1 12 RO 3.7 SRO 4.1 Guidance contained in EOP for fuel handling incident.................. WE03 EK2.1 LOCA Cool down and Depressurization T/G 1 12 RO 3.6 SRO 4.0 Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: (CFR: 41.7/45.7) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. Page 4 of 16

ES 401, Rev 9 Question 27 533 28 534 29 535 30 536 31 537 32 538 KIA Number KIA Description WE09 EK3.3 2008 SRO NRC Examination Combined PWR Written Examination Outline KIA System Natural Circulation Operations Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 1 12 RO 3.5 SRO 3.6 Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations) Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations. (CFR: 41.5/41.10, 45.6,45.13) SYS003 A2.02 Reactor Coolant Pump System (RCPS) T/G 2 1 1 RO 3.7 SRO 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP SYSOO4 A1.01 Chemical and Volume Control System T/G 2/1 RO 2.9 SRO 3.8 Ability to predict and/or monitor changes in parameters Activity levels in primary system (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5 145.5) SYSOO4 K1.34 Chemical and Volume Control System T/G 2/1 RO 2.7 SRO 2.9 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) Interface between CVCS and reactor coolant drain tank; and PZR PCS SYS005 K4.11 Residual Heat Removal System (RHRS) T/G 2 1 1 RO 3.5* SRO 3.9* Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following: (CFR: 41.7) Lineup for low head recirculation mode (external and internal) SYS006 A1.05 Emergency Core Cooling System (ECCS) T/G 2 11 RO 2.9 SRO 3.3 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5/45.5) CCW flow (establish flow to RHR heat exchanger prior to placing in service Page 5 of 16 ES 401, Rev 9 Question 27 533 28 534 29 535 30 536 31 537 32 538 KIA Number KIA Description WE09 EK3.3 2008 SRO NRC Examination Combined PWR Written Examination Outline KIA System Natural Circulation Operations Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 1 12 RO 3.5 SRO 3.6 Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations) Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations. (CFR: 41.5/41.10, 45.6,45.13) SYS003 A2.02 Reactor Coolant Pump System (RCPS) T/G 2 1 1 RO 3.7 SRO 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP................... SYS004 A1.01 Chemical and Volume Control System Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5 145.5) Activity levels in primary system SYS004 K1.34 Chemical and Volume Control System T/G 2 11 RO 2.9 T/G 2 11 RO 2.7 SRO 3.8 SRO 2.9 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) Interface between CVCS and reactor coolant drain tank; and PZR PCS SYS005 K4.11 Residual Heat Removal System (RHRS) T/G 2 1 1 RO 3.5* SRO 3.9* Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following: (CFR: 41.7) Lineup for low head recirculation mode (external and internal) SYS006 A1.05 Emergency Core Cooling System (ECCS) T/G 2 11 RO 2.9 SRO 3.3 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5/45.5) CCW flow (establish flow to RHR heat exchanger prior to placing in service Page 5 of 16

ES401, Rev 9 Question 33 539 34 540 35 541 36 542 37 543 38 544 39 545 KIA Number KIA Description SYS007 2.4.6 2008 SRO NRC Examination Combined PWR Written Examination Outline KIA System Pressurizer Relief Tank/Quench Tank System (PRTS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 211 RO 3.7 SRO 4.7 SYS007 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) SYSOOB K3.03 Component Cooling Water System (CCWS) Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: RCP SYSOOB K4.09 Component Cooling Water System (CCWS) T/G 211 RO 4.1 SRO 4.2 T/G 211 RO 2.7 SRO 2.9 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) The "standby" feature for the CCW pumps... SYS010 2.1.25 Pressurizer Pressure Control System (PZR PCS) T/G 2 I 1 RO 3.9 SRO 4.2 SYS010 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) SYS012 A2.02 Reactor Protection System (RPS) Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.5) Loss of instrument power SYS012 K5.01 Reactor Protection System (RPS) Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5/45.7) DNB SYS013 K6.01 Engineered Safety Features Actuation System (ESFAS) Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8) Sensors and detectors Page 6 of 16 T/G 2 I 1 RO 3.6 SRO 3.9 T/G 2 I 1 RO 3.3* SRO 3.B T/G 2/1 RO 2.7* SRO 3.1* ES401, Rev 9 Question 33 539 34 540 35 541 36 542 37 543 38 544 39 545 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS007 2.4.6 Pressurizer Relief Tank/Quench Tank System (PRTS) T/G 211 RO 3.7 SRO 4.7 SYS007 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) SYSOOB K3.03 Component Cooling Water System (CCWS) T/G 211 RO 4.1 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: RCP........................................................... SYSOOB K4.09 Component Cooling Water System (CCWS) T/G 211 RO 2.7 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) The "standby" feature for the CCW pumps............................ SYS010 2.1.25 Pressurizer Pressure Control System (PZR PCS) T/G 2 I 1 RO 3.9 SRO 4.2 SRO 2.9 SRO 4.2 SYS010 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) SYS012 A2.02 Reactor Protection System (RPS) T/G 2 I 1 RO 3.6 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.5) Loss of instrument power......................................... SRO 3.9 SYS012 K5.01 Reactor Protection System (RPS) T/G 2 I 1 RO 3.3* SRO 3.B Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5/45.7) DNB........................................................... SYS013 K6.01 Engineered Safety Features Actuation System (ESFAS) T/G 2/1 RO 2.7* SRO 3.1* Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8) Sensors and detectors............................................ Page 6 of 16

ES401, Rev 9 Question 40 546 41 547 42 548 43 549 ' 44 550 45 551 46 552 2008 SRO NRC Examination Combined PWR Written Examination Outline KIA Number KIA Description KIA System SYS022 K2.02 Containment Cooling System (CCS) Knowledge of power supplies to the following: (CFR: 41.7) SYS025 A4.01 Ice Condenser System Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) Chillers Ice condenser isolation valves SYS026 A1.03 Containment Spray System (CSS) Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5 1 45.5) Containment sump level..... SYS026 K1.01 Containment Spray System (CSS) Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) ECCS SYS039 K5.01 Main and Reheat Steam System (MRSS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 211 RO 2.5* SRO 2.4* T/G 2 11 RO 3.0* SRO 2.7* T/G 2 I 1 RO 3.5 SRO 3.5 T/G 2 11 RO 4.2 SRO 4.2 T/G 2 I 1 RO 2.9 SRO 3.1 Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5/45.7) Definition and causes of steam/water hammer SYS059 A4.11 Main Feedwater (MFW) System Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8) T/G 2 11 RO 3.1 Recovery from automatic feedwater isolation SYS061 A3.03 Auxiliary I Emergency Feedwater (AFW) System T/G 2 I 1 RO 3.9 Ability to monitor automatic operation of the AFW, including: (CFR: 41.7/45.5) AFW S/G level control on automatic start Page 7 of 16 SRO 3.3 SRO 3.9 ES401, Rev 9 Question 40 546 41 547 42 548 43 549 ' 44 550 45 551 46 552 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS022 K2.02 Containment Cooling System (CCS) T/G 211 RO 2.5* SRO 2.4* Knowledge of power supplies to the following: (CFR: 41.7) Chillers........................................................ SYS025 A4.01 Ice Condenser System T/G 2 11 RO 3.0* SRO 2.7* Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) Ice condenser isolation valves...................................... SYS026 A1.03 Containment Spray System (CSS) T/G 2 I 1 RO 3.5 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5 1 45.5) Containment sump level........................................... SYS026 K1.01 Containment Spray System (CSS) T/G 2 11 RO 4.2 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) ECCS SYS039 K5.01 Main and Reheat Steam System (MRSS) T/G 2 I 1 RO 2.9 Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5/45.7) SYS059 A4.11 Main Feedwater (MFW) System Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8) Definition and causes of steam/water hammer........................ T/G 2 11 RO 3.1 Recovery from automatic feedwater isolation........................ SYS061 A3.03 Auxiliary I Emergency Feedwater (AFW) System T/G 2 I 1 RO 3.9 Ability to monitor automatic operation of the AFW, including: (CFR: 41.7/45.5) AFW S/G level control on automatic start............................ Page 7 of 16 SRO 3.5 SRO 4.2 SRO 3.1 SRO 3.3 SRO 3.9

ES401, Rev 9 Question 47 553 48 554 49 555 50 556 51 557 52 558 2008 SRO NRC Examination Combined PWR Written Examination Outline KIA Number KIA Description KIA System SYS062 A3.01 AC Electrical Distribution System Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7/45.5) Vital ac bus amperage SYS063 K2.01 DC Electrical Distribution System Knowledge of bus power supplies to the following: (CFR: 41.7) Major DC loads SYS063 K3.01 DC Electrical Distribution System Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7/45.6) ED/G SYS064 A3.07 Emergency Diesel Generator (ED/G) System Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/45.5) Load sequencing SYS064 K6.07 Emergency Diesel Generator (ED/G) System Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.71 45.7) Air receivers SYS073 A2.02 Process Radiation Monitoring (PRM) System Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45.13) Detector failure Page 8 of 16 Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2 1 1 RO 3.0 SRO 3.1 T/G 2/1 RO 2.9* SRO 3.1* T/G 2 1 1 RO 3.7* SRO 4.1 T/G 2 1 1 RO 3.6* SRO 3.7* T/G 211 RO 2.7 SRO 2.9 T/G 211 RO 2.7 SRO 3.2 ES401, Rev 9 Question 47 553 48 554 49 555 50 556 51 557 52 558 KIA Number KIA Description SYS062 A3.01 2008 SRO NRC Examination Combined PWR Written Examination Outline KIA System AC Electrical Distribution System Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2 1 1 RO 3.0 SRO 3.1 Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7/45.5) Vital ac bus amperage............................................. SYS063 K2.01 DC Electrical Distribution System Knowledge of bus power supplies to the following: (CFR: 41.7) Major DC loads SYS063 K3.01 DC Electrical Distribution System Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7/45.6) ED/G SYS064 A3.07 Emergency Diesel Generator (ED/G) System T/G 2/1 RO 2.9* SRO 3.1* T/G 2 1 1 RO 3.7* SRO 4.1 T/G 2 1 1 RO 3.6* SRO 3.7* Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/45.5) Load sequencing................................................. SYS064 K6.07 Emergency Diesel Generator (ED/G) System T/G 211 RO 2.7 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.71 45.7) Air receivers.................................................... SYS073 A2.02 Process Radiation Monitoring (PRM) System T/G 211 RO 2.7 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45.13) Detector failure................................................. Page 8 of 16 SRO 2.9 SRO 3.2

ES 401, Rev 9 Question 53 559 54 560 55 561 56 562 57 563 58 564 59 565 KIA Number KIA Description SYS076 K2.01 2008 SRO NRC Examination Combined PWR Written Examination Outline KIA System Service Water System (SWS) Knowledge of bus power supplies to the following: (CFR: 41.7) Service water SYS078 K3.02 Instrument Air System (lAS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2/1 RO 2.7* SRO 2.7 T/G 2 / 1 RO 3.4 SRO 3.6 Knowledge of the effect that a loss or malfunction of the lAS will have on the following: (CFR: 41.7/45.6) Systems having pneumatic valves and controls SYS103 K1.07 Containment System Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) SYS001 K2.02 Control Rod Drive System T/G 2/ 1 RO 3.5* SRO 3.7* Containment vacuum system T/G 2 / 2 RO 3.6 SRO 3.7 Knowledge of bus power supplies to the following: (CFR: 41.7) One-line diagram of power supply to trip breakers SYS011 A1.02 Pressurizer Level Control System (PZR LCS) Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5/ 45.5) Charging and letdown flows SYS016 K1.12 Non-Nuclear Instrumentation System (NNIS) Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) S/G SYS017 K3.01 In-Core Temperature Monitor (ITM) System Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7/45.6) Natural circulation indications Page 9 of 16 T/G 2 / 2 RO 3.3 SRO 3.5 T/G 2/2 RO 3.5* SRO 3.5* T/G 2 / 2 RO 3.5* SRO 3.7* ES 401, Rev 9 Question 53 559 54 560 55 561 56 562 57 563 58 564 59 565 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description SYS076 K2.01 KIA System Service Water System (SWS) Knowledge of bus power supplies to the following: (CFR: 41.7) SYS078 K3.02 Instrument Air System (lAS) Knowledge of the effect that a loss or malfunction of the lAS will have on the following: (CFR: 41.7/45.6) SYS103 K1.07 Containment System Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) SYS001 K2.02 Control Rod Drive System Knowledge of bus power supplies to the following: (CFR: 41.7) Tier/Group Importance RO/SRO T/G 2/1 RO 2.7* SRO 2.7 Service water.................................................... T/G 2 / 1 RO 3.4 SRO 3.6 Systems having pneumatic valves and controls........................ T/G 2/ 1 RO 3.5* SRO 3.7* Containment vacuum system....................................... T/G 2 / 2 RO 3.6 SRO 3.7 One-line diagram of power supply to trip breakers..................... SYS011 A1.02 Pressurizer Level Control System (PZR LCS) T/G 2 / 2 RO 3.3 SRO 3.5 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5/ 45.5) Charging and letdown flows........................................ SYS016 K1.12 Non-Nuclear Instrumentation System (NNIS) T/G 2/2 RO 3.5* SRO 3.5* Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) S/G............................................................ SYS017 K3.01 In-Core Temperature Monitor (ITM) System T/G 2 / 2 RO 3.5* SRO 3.7* Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7/45.6) Natural circulation indications..................................... Page 9 of 16

ES 401, Rev 9 Question 60 566 61 567 62 568 63 569 64 570 65 571 66 572 KiA Number KiA Description SYS027 K5.01 2008 SRO NRC Examination Combined PWR Written Examination Outline KiA System Containment Iodine Removal System (CIRS) Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7/45.7) Purpose of charcoal filters SYS035 2.2.40 Steam Generator System (S/GS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2/2 RO 3.1* SRO 3.4* T/G 2 / 2 RO 3.4 SRO 4.7 SYS035 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10/43.2/43.5 145.3) SYS045 A3.05 Main Turbine Generator (MT/G) System Ability to monitor automatic operation of the MT/G system, including: (CFR: 41/7/45.5) Electrohydraulic control SYS071 K4.01 Waste Gas Disposal System (WGDS) T/G 2 / 2 RO 2.6 T/G 2 / 2 RO 2.6 Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) Pressure capability of the waste gas decay tank SYS079 A4.01 Station Air System (SAS) Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) SYS086 K6.04 Fire Protection System (FPS) Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7/45.7) Cross-tie valves with lAS Fire, smoke, and heat detectors GEN2.1 2.1.45 GENERIC - Conduct of Operations T/G 2 / 2 RO 2.7 T/G 2 / 2 RO 2.6 T/G 3 / 0 RO 4.3 SRO 2.9 SRO 3.0 SRO 2.7 SRO 2.9 SRO 4.3 Conduct of Operations Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 1 43.5 145.4) Page 10 of 16 ES 401, Rev 9 Question 60 566 61 567 62 568 63 569 64 570 65 571 66 572 KiA Number KiA Description SYS027 K5.01 2008 SRO NRC Examination Combined PWR Written Examination Outline KiA System Containment Iodine Removal System (CIRS) Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7/45.7) Purpose of charcoal filters SYS035 2.2.40 Steam Generator System (S/GS) Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2/2 RO 3.1* SRO 3.4* T/G 2 / 2 RO 3.4 SRO 4.7 SYS035 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10/43.2/43.5 145.3) SYS045 A3.05 Main Turbine Generator (MT/G) System T/G 2 / 2 RO 2.6 Ability to monitor automatic operation of the MT/G system, including: (CFR: 41/7/45.5) Electrohydraulic control SYS071 K4.01 Waste Gas Disposal System (WGDS) T/G 2 / 2 RO 2.6 Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7) SYS079 A4.01 Station Air System (SAS) Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) SYS086 K6.04 Fire Protection System (FPS) Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7/45.7) Pressure capability of the waste gas decay tank T/G 2 / 2 RO 2.7 Cross-tie valves with lAS.......................................... T/G 2 / 2 RO 2.6 Fire, smoke, and heat detectors..................................... GEN2.1 2.1.45 GENERIC - Conduct of Operations T/G 3 / 0 RO 4.3 SRO 2.9 SRO 3.0 SRO 2.7 SRO 2.9 SRO 4.3 Conduct of Operations Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 1 43.5 145.4) Page 10 of 16

ES 401, Rev 9 Question 67 573 68 574 69 575 70 576 71 577 72 578 73 579 74 580 KIA Number KIA Description GEN2.1 2.1.8 Conduct of Operations GEN2.2 2.2.2 Equipment Control GEN2.2 2.2.39 Equipment Control GEN2.3 2.3.11 Radiation Control GEN2.3 2.3.4 Radiation Control GEN2.3 2.3.7 Radiation Control GEN2.4 2.4.13 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System Tier/Group Importance RO/SRO GENERIC - Conduct of Operations T/G 3 I 0 RO 3.4 SRO 4.1 GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control GENERIC - Radiation Control GENERIC - Radiation Control Ability to coordinate personnel activities outside the control room. (CFR: 41.10 /45.5/45.12/45.13) T/G 3 I 0 RO 4.6 SRO 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2) T/G 3 I 0 RO 3.9 SRO 4.5 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) T/G 3 I 0 RO 3.8 SRO 4.3 Ability to control radiation releases. (CFR: 41.11 /43.4 / 45.10) T/G 3 I 0 RO 3.2 SRO 3.7 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10) T/G 3 I 0 RO 3.5 SRO 3.6 Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10) GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 4.0 SRO 4.6 Emergency Procedures / Plan Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 / 45.12) GEN2.4 2.4.22 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.6 SRO 4.4 Emergency Procedures / Plan Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CFR: 41.7 /41.10 /43.5 /45.12) Page 11 of 16 ES 401, Rev 9 Question 67 573 68 574 69 575 70 576 71 577 72 578 73 579 74 580 KIA Number KIA Description GEN2.1 2.1.8 Conduct of Operations GEN2.2 2.2.2 Equipment Control GEN2.2 2.2.39 Equipment Control GEN2.3 2.3.11 Radiation Control GEN2.3 2.3.4 Radiation Control GEN2.3 2.3.7 Radiation Control GEN2.4 2.4.13 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System Tier/Group Importance RO/SRO GENERIC - Conduct of Operations T/G 3 I 0 RO 3.4 SRO 4.1 GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control GENERIC - Radiation Control GENERIC - Radiation Control Ability to coordinate personnel activities outside the control room. (CFR: 41.10 /45.5/45.12/45.13) T/G 3 I 0 RO 4.6 SRO 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2) T/G 3 I 0 RO 3.9 SRO 4.5 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) T/G 3 I 0 RO 3.8 SRO 4.3 Ability to control radiation releases. (CFR: 41.11 /43.4 / 45.10) T/G 3 I 0 RO 3.2 SRO 3.7 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10) T/G 3 I 0 RO 3.5 SRO 3.6 Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10) GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 4.0 SRO 4.6 Emergency Procedures / Plan Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 / 45.12) GEN2.4 2.4.22 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.6 SRO 4.4 Emergency Procedures / Plan Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CFR: 41.7 /41.10 /43.5 /45.12) Page 11 of 16

ES401, Rev 9 Question 75 581 76 582 77 583 78 584 79 585 80 586 81 587 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO GEN2.4 2.4.42 GENERIC - Emergency Procedures I Plan T/G 310 RO 2.6 SRO 3.8 Emergency Procedures / Plan EPE009 2.2.25 Small Break LOCA EPE009 GENERIC EPE011 2.2.36 Large Break LOCA EPE011 GENERIC Knowledge of emergency response facilities. (CFR: 41.10 / 45.11) T/G 1 11 RO 3.2 SRO 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5/41.7/43.2) T/G 1 1 1 RO 3.1 SRO 4.2 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 /43.2 / 45.13) APE026 AA2.05 Loss of Component Cooling Water (CCW) T/G 1 11 RO 2.4* SRO 2.5* Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5/45.13) The normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS APE057 2.4.21 Loss of Vital AC Electrical Instrument Bus T/G 1 1 1 RO 4.0 SRO 4.6 APE057 GENERIC APE058 AA2.03 Loss of DC Power Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5/45.13) Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12) T/G 1 1 1 RO 3.5 SRO 3.9 DC loads lost; impact on ability to operate and monitor plant systems.... APE077 AA2.09 Generator Voltage and Electric Grid Disturbances T/G 1 1 0 RO 3.9 SRO 4.3 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 /45.5,45.7, and 45.8) Operational status of emergency diesel generators........................ Page 12 of 16 ES401, Rev 9 Question 75 581 76 582 77 583 78 584 79 585 80 586 81 587 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO GEN2.4 2.4.42 GENERIC - Emergency Procedures I Plan T/G 310 RO 2.6 SRO 3.8 Emergency Procedures / Plan EPE009 2.2.25 Small Break LOCA EPE009 GENERIC EPE011 2.2.36 Large Break LOCA EPE011 GENERIC Knowledge of emergency response facilities. (CFR: 41.10 / 45.11) T/G 1 11 RO 3.2 SRO 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5/41.7/43.2) T/G 1 1 1 RO 3.1 SRO 4.2 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 /43.2 / 45.13) APE026 AA2.05 Loss of Component Cooling Water (CCW) T/G 1 11 RO 2.4* SRO 2.5* Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5/45.13) The normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS........................ APE057 2.4.21 Loss of Vital AC Electrical Instrument Bus T/G 1 1 1 RO 4.0 SRO 4.6 APE057 GENERIC APE058 AA2.03 Loss of DC Power Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5/45.13) Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12) T/G 1 1 1 RO 3.5 SRO 3.9 DC loads lost; impact on ability to operate and monitor plant systems.... APE077 AA2.09 Generator Voltage and Electric Grid Disturbances T/G 1 1 0 RO 3.9 SRO 4.3 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 /45.5,45.7, and 45.8) Operational status of emergency diesel generators........................ Page 12 of 16

ES 401, Rev 9 Question 82 588 83 589 84 590 85 591 86 592 87 593 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description APE024 2.2.39 APE024 GENERIC APE068 2.4.21 APE068 GENERIC APE069 AA2.01 KIA System Emergency Boration Control Room Evacuation Loss of Containment Integrity Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: (CFR: 43.5/ 45.13) WE16 EA2.1 High Containment Radiation Ability to determine and interpret the following as they apply to the (High Containment Radiation) (CFR: 43.5/45.13) Tier/Group Importance RO/SRO T/G 1 12 RO 3.9 SRO 4.5 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) T/G 1 I 2 RO 4.0 SRO 4.6 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12) T/G 1 12 RO 3.7 SRO 4.3 Loss of containment integrity T/G 1 12 RO 2.9 SRO 3.3 Facility conditions and selection of appropriate procedures during abnormal and emergency operations. SYS003 A2.01 Reactor Coolant Pump System (RCPS) T/G 211 RO 3.5 SRO .39 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) Problems with RCP seals, especially rates of seal leak-off SYS026 2.4.47 Containment Spray System (CSS) T/G 2 I 1 RO 4.2 SRO 4.2 SYS026 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/ 45.12) Page 13 of 16 ES 401, Rev 9 Question 82 588 83 589 84 590 85 591 86 592 87 593 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description APE024 2.2.39 APE024 GENERIC APE068 2.4.21 APE068 GENERIC APE069 AA2.01 KIA System Emergency Boration Control Room Evacuation Loss of Containment Integrity Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: (CFR: 43.5/ 45.13) WE16 EA2.1 High Containment Radiation Ability to determine and interpret the following as they apply to the (High Containment Radiation) (CFR: 43.5/45.13) Tier/Group Importance RO/SRO T/G 1 12 RO 3.9 SRO 4.5 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) T/G 1 I 2 RO 4.0 SRO 4.6 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12) T/G 1 12 RO 3.7 SRO 4.3 Loss of containment integrity...................................... T/G 1 12 RO 2.9 SRO 3.3 Facility conditions and selection of appropriate procedures during abnormal and emergency operations. SYS003 A2.01 Reactor Coolant Pump System (RCPS) T/G 211 RO 3.5 SRO .39 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) Problems with RCP seals, especially rates of seal leak-off.............. SYS026 2.4.47 Containment Spray System (CSS) T/G 2 I 1 RO 4.2 SRO 4.2 SYS026 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/ 45.12) Page 13 of 16

2008 SRO NRC Examination ES 401, Rev 9. Combined PWR Written Examination Outline Form ES-401-2/3 Question 88 594 89 595 90 596 91 597 92 598 KIA Number KIA Description SYS039 A2.02 KIA System Main and Reheat Steam System (MRSS) TierlGroup Importance RO/SRO T/G 2 1 1 RO 2.4 SRO 2.7* Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.13) Decrease in turbine load as it relates to steam escaping from relief valves. SYS062 2.1.20 AC Electrical Distribution System T/G 211 RO 4.6 SRO 4.6 SYS062 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10/43.5/45.12) SYS076 A2.02 Service Water System (SWS) Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or. operations: (CFR: 41.5/43.5/45/3/45/13) Service water header pressure SYS033 2.2.22 Spent Fuel Pool Cooling System (SFPCS) T/G 2 1 1 RO 2.7 SRO 3.1 T/G 2 1 2 RO 4.0 SRO 4.7 SYS033 GENERIC Knowledge of limiting conditions for operations and safety limits. (CFR: 41.51 43.2/45.2) SYS072 A2.02 Area Radiation Monitoring (ARM) System Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/43.31 45.13) Detector failure Page 14 of 16 T/G 2 12 RO 2.8 SRO 2.9 2008 SRO NRC Examination ES 401, Rev 9. Combined PWR Written Examination Outline Form ES-401-2/3 Question 88 594 89 595 90 596 91 597 92 598 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS039 A2.02 Main and Reheat Steam System (MRSS) T/G 2 1 1 RO 2.4 SRO 2.7* Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or Decrease in turbine load as it relates to steam escaping from relief valves. mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.13) ~------------------------- SYS062 2.1.20 AC Electrical Distribution System T/G 211 RO 4.6 SRO 4.6 SYS062 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10/43.5/45.12) SYS076 A2.02 Service Water System (SWS) Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or. operations: (CFR: 41.5/43.5/45/3/45/13) T/G 2 1 1 RO 2.7 Service water header pressure...................................... SYS033 2.2.22 Spent Fuel Pool Cooling System (SFPCS) T/G 2 1 2 RO 4.0 SRO 3.1 SRO 4.7 SYS033 GENERIC Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5/ 43.2/45.2) SYS072 A2.02 Area Radiation Monitoring (ARM) System T/G 2 12 RO 2.8 Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/43.3/ 45.13) Detector failure................................................. Page 14 of 16 SRO 2.9

ES 401, Rev 9 Question 93 599 94 600 95 601 96 602 97 603 98 604 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description SYS086 A2.01 KIA System Fire Protection System (FPS) Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13) Tier/Group Importance RO/SRO T/G 2 I 2 RO 2.9 SRO 3.1 Manual shutdown of the FPS GEN2.1 2.1.14 GENERIC - Conduct of Operations T/G 3 I 0 RO 3.1 SRO 3.1 Conduct of Operations GEN2.1 2.1.36 Conduct of Operations GEN2.2 2.2.15 Equipment Control GEN2.2 2.2.3 Equipment Control GEN2.3 2.3.13 Radiation Control Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CFR: 41.10/43.5/ 45.12) GENERIC - Conduct of Operations T/G 3 I 0 RO 3.0 SRO 4.1 GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10/43.6/45.7) T/G 3 I 0 RO 3.9 SRO 4.3 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.10 / 43.3 / 45.13) T/G 3 I 0 RO 3.8 SRO 3.9 (multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5/41.6/41.7/41.10/45.12) T/G 3 I 0 RO 3.4 SRO 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12/43.4 / 45.9 / 45.10) Page 15 of 16 ES 401, Rev 9 Question 93 599 94 600 95 601 96 602 97 603 98 604 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description SYS086 A2.01 KIA System Fire Protection System (FPS) Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13) Tier/Group Importance RO/SRO T/G 2 I 2 RO 2.9 SRO 3.1 Manual shutdown of the FPS....................................... GEN2.1 2.1.14 GENERIC - Conduct of Operations T/G 3 I 0 RO 3.1 SRO 3.1 Conduct of Operations GEN2.1 2.1.36 Conduct of Operations GEN2.2 2.2.15 Equipment Control GEN2.2 2.2.3 Equipment Control GEN2.3 2.3.13 Radiation Control Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CFR: 41.10/43.5/ 45.12) GENERIC - Conduct of Operations T/G 3 I 0 RO 3.0 SRO 4.1 GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10/43.6/45.7) T/G 3 I 0 RO 3.9 SRO 4.3 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.10 / 43.3 / 45.13) T/G 3 I 0 RO 3.8 SRO 3.9 (multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5/41.6/41.7/41.10/45.12) T/G 3 I 0 RO 3.4 SRO 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12/43.4 / 45.9 / 45.10) Page 15 of 16

ES 401, Rev 9 Question 99 605 100 606 KIA Number KIA Description GEN2.3 2.3.14 Radiation Control GEN2.4 2.4.3 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System Tier/Group Importance RO/SRO GENERIC - Radiation Control T/G 3 I 0 RO 3.4 SRO 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 /43.4 /45.10) GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.7 SRO 3.9 Emergency Procedures / Plan Ability to identify post-accident instrumentation. (CFR: 41.6 /45.4) Page 16 of 16 ES 401, Rev 9 Question 99 605 100 606 KIA Number KIA Description GEN2.3 2.3.14 Radiation Control GEN2.4 2.4.3 2008 SRO NRC Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System Tier/Group Importance RO/SRO GENERIC - Radiation Control T/G 3 I 0 RO 3.4 SRO 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 /43.4 /45.10) GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.7 SRO 3.9 Emergency Procedures / Plan Ability to identify post-accident instrumentation. (CFR: 41.6 /45.4) Page 16 of 16

ES-401, Rev. 9 Record of Rejected KJAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KA 1/2 APE076 AK3.06 (Q25) There is a question that was used on the 2006R (exam bank #148) which would meet this but within 2 years. It deals with demineralizers which is the only real action in AP/18. Replaced with KIA APE036 AK3.03 2/1 SYS008 K4.07 Q(35) No such component at eNS. KIA replacements originally provided 4.04 and 4.08 are not high enough value (2.1 and 2.3) Replaced with KIA SYS008 K4.09 1/0 APEO?? AA2.04 Q(81) Duplicate KA of RO exam #14. Replaced with KIA APEO?? AA2.09 1/1 APE025 2.2.39 Q(82) Cannot write an SRO question. Replaced with KIA APE024 G2.2.22 1/2 APE069 AA2.02 Q(84) Cannot write an SRO question. Replaced with KIA APE069 AA2.01 2/2 SYS086 A2.01 Q(93) Cannot write an SRO question. Replaced with KIA SYS086 A2.04 ES-401, Rev. 9 Record of Rejected KJAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KA 1/2 APE076 AK3.06 (Q25) There is a question that was used on the 2006R (exam bank #148) which would meet this but within 2 years. It deals with demineralizers which is the only real action in AP/18. Replaced with KIA APE036 AK3.03 2/1 SYS008 K4.07 Q(35) No such component at eNS. KIA replacements originally provided 4.04 and 4.08 are not high enough value (2.1 and 2.3) Replaced with KIA SYS008 K4.09 1/0 APEO?? AA2.04 Q(81) Duplicate KA of RO exam #14. Replaced with KIA APEO?? AA2.09 1/1 APE025 2.2.39 Q(82) Cannot write an SRO question. Replaced with KIA APE024 G2.2.22 1/2 APE069 AA2.02 Q(84) Cannot write an SRO question. Replaced with KIA APE069 AA2.01 2/2 SYS086 A2.01 Q(93) Cannot write an SRO question. Replaced with KIA SYS086 A2.04

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: ~~A Date of Exam: '1-/t>,f II r Exam Level: ROO SRO~ Initial Item Description a b* q#

1.

Questions and answers are technically accurate and applicable to the facility. Y l{f II

2.

a.

NRC KJAs are referenced for all questions. tv" ~IJ

b.

Facility learning obLectives are referenced as available.

3.

SRO questions are appropriate in accordance with Section D.2.d of ES-401 IV IfJ.s!' 1-<1 ~

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: <f1A cI _ the audit exam was systematically and randomly developed; or _ the audit exam was completed before the license exam was started; or ~e examinations were developed independently; or _ the licensee certifies that there is no duplication; or _ other (explain) I~~

6.

Bank use meets limits (no more than 75 percent Bank Modified New J from the bank, at least 10 percent new, and the rest I~ / <1 41/23 JI? ~rJ( new or modified); enter the actual RO / SRO-only I / r 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; h j~ the SRO exam may exceed 60 percent if the randomly ~S- / S- 't6 / ~r( selected KJAs support the higher cognitive levels; enter 2-D the actual RO / SRO question distribution(s) at right.

8.

References/handouts provided do not give away answers i1 1t'1~.~ or aid in the elimination of distractors. f .>~

9.

Question content conforms with specific KJA statements in the previously approved b~ 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. i1 w j)# \\

11.

The exam contains the required number of one-point, multiple choice items; 4'( bif ,I the total is correct and agrees with the value on the cover sheet. Printed Name / Signature Date jo~ k'...~ I~L II/M/Ol

a. Author

b. Facility Reviewer (*)

"BielAN D.Mil...lfl2 ZI/bo-~ ~ /;/If'I,!)~

c. NRC Chief Examiner (#)

(~~ ~r L..45~A~l\\.,~ 11!141&u

d. NRC Regional Supervisor t1.JAtcdu.;.-r: 1l/!J),{jAAIA.1 r 12\\

J.., IliZ"h$l' .J/J/fJ:Li7(J //f L Note:

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

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

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: ~~A Date of Exam: '1-/t>,f II r Exam Level: ROO SRO~ Initial Item Description a b* q#

1.

Questions and answers are technically accurate and applicable to the facility. Y {f..1:

2.

a.

NRC KJAs are referenced for all questions. tv" ~ '1

b.

Facility learning objectives are referenced as available. D

3.

SRO questions are appropriate in accordance with Section D.2.d of ES-401 IV {'J-.st" -< ~

4.

The sampling process was random and systematic (If more than 4 RO or 2 SRO questions j 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: <f1A cI _ the audit exam was systematically and randomly developed; or _ the audit exam was completed before the license exam was started; or ~e examinations were developed independently; or _ the licensee certifies that there is no duplication; or _ other (explain) ~~

6.

Bank use meets limits (no more than 75 percent Bank Modified New J from the bank, at least 10 percent new, and the rest I~ / <1 41/23 JI? ~rJ( new or modified); enter the actual RO / SRO-only I / r 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; h j~ the SRO exam may exceed 60 percent if the randomly ~S- / S- 't6 / ~r( selected KJAs support the higher cognitive levels; enter 2-D the actual RO / SRO question distribution(s) at right.

8.

References/handouts provided do not give away answers h It'l~.~ or aid in the elimination of distractors. f .. ~

9.

Question content conforms with specific KJA statements in the previously approved b~ 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. i1 ~ ~\\

11.

The exam contains the required number of one-point, multiple choice items; 4'( bif V the total is correct and agrees with the value on the cover sheet. ) Printed Name /,~ Date _~jo~ ~. ~ -;j..J. II/M/Ol

a. Author

b. Facility Reviewer (*)

I5~JAN D. M i I...L f 12 '-v/k<- ~ --h. t;Ih /di{'/l>~

c. NRC Chief Examiner (#)

(~i3i2Af2D ~r Lk5C61Y/..lV.,;,.,1/ li..t::::,kd! 11/14/&i.£

d. NRC Regional Supervisor t1.JAtcdu.;.-r: lI/f[)'uA.f '" J T /J\\

.J." !~/t.f( J////i" 7"(TN I L 7' ~ ~ Note:

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

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

F1}/{tL ES-401, Rev. 9 Catawba 2008-301 RO Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (FIH)

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

LOD (1-5) Stem Icuesl T/F I cred'lpartiall JOb-I Minutia I #1 I Back-I Q= I SRO I utE! Focus Dist. Link units ward KIA Only S Instructions

7.

Explanation [Refer to Section 0 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.

12.

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

b.

Check the appropriate box if a psychometric flaw is identified: The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements. The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem). k Check the appropriate box if a job content error is identified: The question is not linked to the job requirements (i.e., the question has a valid 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 (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements. Is. Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable). I ,6. Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory? At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met). OQ71,~Ii~2;!O~I;Bo[m~rilin~'Kli/.f;.;\\m~i ES-401, Rev. 9 Catawba 2008-301 RO Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (FIH)

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

LOD ~--~~~--r---.---~--.----.---r---; (1-5) Stem Cues T/F Credo Partial Job-Minutia

1. 1 Back-Q=

SRO utE! Explanation Focus Dist. Link units ward KIA Only S Instructions [Refer to Section 0 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 (LaD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).

13.

Check the appropriate box if a psychometric flaw is identified: The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements. The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

14.

Check the appropriate box if a job content error is identified: The question is not linked to the job requirements (i.e., the question has a valid 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 (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements.

15.

Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable). !6. 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?

7.

At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met). I::;r,~.,d{~.n~;t::~t~l;*'lit;]t;~!:;l; ii:;

2'1~~"li;fll

~

Q#

1. I 2.

LOK LOD ~I ---.---r--~----r---4---~--~--~---4 (F/H) (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Explanation Q#

1.

2.

3. Psychometric Flaws LOK LOD ~--,-~.---~--~--~---.----~--~--~

4. Job Content Flaws

5. Other

6.

7.

(F/H) (1-5) Explanation

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Sack-0=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 2 H 2 X E 009EA2.1 Question appears to match KiA. Distractors A and B may not be plausible. Is there any time that Safety Injection Actuated light is lit that the operators would not go to E-O besides a loss of aIlAC? NEW Licensee stated that there are times that the SI S light would be lit, and the operators would go to another procedure besides E-O. (accumulators isolated) The licensee added an RCS Pressure, and temperature to allow the applicant to decide which procedure was applicable. SAT 11/03/2008. 3 F 2 011 EG2.4.30 SAT BANK - 2005 NRC exam. S 4 H 2 022AK1.02 Question kind of matches KiA. "SAT. S This question could be easily modified. BANK - 2005 NRC exam. 5 H 2 X E 025AG2.4.30 Question appears to match KiA. I think this was also on the 2007 exam will check to ensure. OMP 1-7 states two are required without a procedure. This action will be outside the procedure, therefore someone could argue 0 is also correct (more conservative. NEW? S Licensee changed stem to have the question deal in accordance with the sites procedure OMP-1-7. (Changed all distractors) SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Sack-0=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 2 H 2 X E 009EA2.1 Question appears to match KiA. Distractors A and B may not be plausible. Is there any time that Safety Injection Actuated light is lit that the operators would not go to E-O besides a loss of aIlAC? NEW Licensee stated that there are times that the SI S light would be lit, and the operators would go to another procedure besides E-O. (accumulators isolated) The licensee added an RCS Pressure, and temperature to allow the applicant to decide which procedure was applicable. SAT 11/03/2008. 3 F 2 011 EG2.4.30 SAT BANK - 2005 NRC exam. S 4 H 2 022AK1.02 Question kind of matches KiA. "SAT. S This question could be easily modified. BANK - 2005 NRC exam. 5 H 2 X E 025AG2.4.30 Question appears to match KiA. I think this was also on the 2007 exam will check to ensure. OMP 1-7 states two are required without a procedure. This action will be outside the procedure, therefore someone could argue 0 is also correct (more conservative. NEW? S Licensee changed stem to have the question deal in accordance with the sites procedure OMP-1-7. (Changed all distractors) SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 6 H 2 026AA2.03 Question appears to match KIA. SAT S NEW 7 F 2 S 027AA1.04 Question appears to match KIA. SAT NEW 8 F 2 E 029EG2.4.34 Question appears to match the KIA. Question needs some enhancements. The operator need only know that the motor generator out put breaker needs to be opened and D is the answer. Change the distractors to be 1 and 2 only, 1, 2, and 3 only 1, 2, and 4 only and 1, 2, 3, and 4. NEW S Licensee made changes as requested. SAT 11/03/2008. 9 H 2 S 038EK1.02 Question kind of matches KIA. BANK - 2005 NRC exam Please change the answers so that the Correct answer is different than C. 10 F 2 S OS7AA2.13 Question appears to match KIA. SAT NEW

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 6 H 2 026AA2.03 Question appears to match KIA. SAT S NEW 7 F 2 S 027AA1.04 Question appears to match KIA. SAT NEW 8 F 2 E 029EG2.4.34 Question appears to match the KIA. Question needs some enhancements. The operator need only know that the motor generator out put breaker needs to be opened and D is the answer. Change the distractors to be 1 and 2 only, 1, 2, and 3 only 1, 2, and 4 only and 1, 2, 3, and 4. NEW S Licensee made changes as requested. SAT 11/03/2008. 9 H 2 S 038EK1.02 Question kind of matches KIA. BANK - 2005 NRC exam Please change the answers so that the Correct answer is different than C. 10 F 2 S OS7AA2.13 Question appears to match KIA. SAT NEW

1. I 2.

3. Psychometric Flaws Q#

LOK LOD (F/H) (1-5) Stem Cues T/F Focus 11 F I 2 13 H 2

4. Job Content Flaws

5. Other I 6.

U/EI S

7.

Explanation 058AA1.02 Question appears to match KIA. SAT (Is the time limit in accordance with a procedure? If so, this should be stated). NEW S ILicensee added lAW OP/lIAl6350/008. SAT 11/03/2008. S I065AK3.03 Question appears to match KIA. I assume the crew entered AP/O/A/5500/022 due to air leak? You might need to say this. NEW Licensee Made NO changes. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws Q#

LOK LOD (F/H) (1-5) Stem T/F Credo Partial Job-Minutia

1. /

Back-Focus Dist. Link units ward 11 F 2 13 2

5. Other Q=

SRO KIA Only

6.

U/EI S E

7.

Explanation 058AA1.02 Question appears to match KIA. SAT (Is the time limit in accordance with a procedure? If so, this should be stated). NEW S Licensee added lAW OP/lIAl6350/008. SAT 11/03/2008. 065AK3.03 Question appears to match KIA. I S assume the crew entered AP/O/A/5500/022 due to air leak? You might need to say this. NEW Licensee Made NO changes. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

8ack-0= SAO utEi Explanation Focus Dist. Link units ward KIA Only S 14 H 2 E 077 AA 1.01 Question appears to match KIA. This may be considered a direct look up. I will have another examiner review and comment. NEW Licensee has blacked out the information on the S referenced graph that would make the question a direct lookup. SAT 11/03/2008. 15 H 2 S W/E04EK2.2 Question appears to match KIA. Modified from 2004 NRC exam. SAT Modified. SAT 11/03/2008. 16 F 2 S W/E05EK3.1 Question matches KIA. SAT I I NEW SAT 11/03/2008. 17 F 2 S W/E11EK2.1 Question appears to match KIA. Are the defeat buttons in distractor C labeled correctly? Otherwise question appears to be SAT. NEW Added FWST to C distractor now labeled correctly. SAT 11/03/2008. 18 F 2 E W/E12EK1.3 Question Kind of matches KIA. Is an annunciator received when the MSIVs are closed or a MSLI is received? Using one of these indications would match the KIA better. NEW S Changes made as requested. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

8ack-0= SAO utEi Explanation Focus Dist. Link units ward KIA Only S 14 H 2 E 077 AA 1.01 Question appears to match KIA. This may be considered a direct look up. I will have another examiner review and comment. NEW Licensee has blacked out the information on the S referenced graph that would make the question a direct lookup. SAT 11/03/2008. 15 H 2 S W/E04EK2.2 Question appears to match KIA. Modified from 2004 NRC exam. SAT Modified. SAT 11/03/2008. 16 F 2 S W/E05EK3.1 Question matches KIA. SAT NEW SAT 11/03/2008. 17 F 2 S W/E11EK2.1 Question appears to match KIA. Are the defeat buttons in distractor C labeled correctly? Otherwise question appears to be SAT. NEW Added FWST to C distractor now labeled correctly. SAT 11/03/2008. 18 F 2 E W/E12EK1.3 Question Kind of matches KIA. Is an annunciator received when the MSIVs are closed or a MSLI is received? Using one of these indications would match the KIA better. NEW S Changes made as requested. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q# LOK LaD (FIH) (1-5) Stem Cues T/F Credo Partial Job-Minutia

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 19 H 2 E 001 AA 1.06 Question does not really meet the KIA, however it is a good attempt, and the switch involved does transfer some control of the rods. The stem should state lAW whatever procedure is applicable for example lAW AP-15. S NEW Licensee added lAW AP-15. SAT 11/03/2008. 20 F 2 S 005AG2.4.6 Based on a previous discussion AP actions were determined to be acceptable to satisfy this KIA. Is there any occurrence of Mode 2 with Ketti 2': 1.0? If not this may not be acceptable. Will Discuss. NEW I Licensee stated that TS3.1.6 does have actions that refer to the above. No other changes made. SAT 11/03/2008. 21 H 2 S 024AK1.04 Question appears to match KIA. SAT NEW SAT 11/03/2008. I 22 F 2 S 033AK1.01 Question appears to match KIA. SAT NEW SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q# LOK LaD (FIH) (1-5) Stem Cues T/F Credo Partial Job-Minutia

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 19 H 2 E 001 AA 1.06 Question does not really meet the KIA, however it is a good attempt, and the switch involved does transfer some control of the rods. The stem should state lAW whatever procedure is applicable for example lAW AP-15. S NEW Licensee added lAW AP-15. SAT 11/03/2008. 20 F 2 S 005AG2.4.6 Based on a previous discussion AP actions were determined to be acceptable to satisfy this KIA. Is there any occurrence of Mode 2 with Keff 2': 1.0? If not this may not be acceptable. Will Discuss. NEW Licensee stated that TS3.1.6 does have actions that refer to the above. No other changes made. SAT 11/03/2008. 21 H 2 S 024AK1.04 Question appears to match KIA. SAT NEW SAT 11/03/2008. 22 F 2 S 033AK1.01 Question appears to match KIA. SAT NEW SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO utEl Explanation Focus Dist. Link units ward KIA Only S 23 H 2 E 037AA2.03 Question appears to match KIA. Need to add a specific power level for the Unit. 60% or so, some one could make the assumption that power had been reduced to a level where the N-16 monitors may not be the first indication. Otherwise SAT. Modified from a 2003 NRC exam. S Added the crew has stabilized the plant at the runback target per Al1/5500/003 (Load Rejection) SAT 11/03/2008. 24 H 4 S 074EA1.01 Question kind of matches KIA. Change

1. 2. to read: Why are these conditions more restrictive than earlier transition conditions Otherwise SAT. (Is this RO knowledge?)

NEW Licensee made changes as requested. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO utEl Explanation Focus Dist. Link units ward KIA Only S 23 H 2 E 037AA2.03 Question appears to match KIA. Need to add a specific power level for the Unit. 60% or so, some one could make the assumption that power had been reduced to a level where the N-16 monitors may not be the first indication. Otherwise SAT. Modified from a 2003 NRC exam. S Added the crew has stabilized the plant at the runback target per Al1/5500/003 (Load Rejection) SAT 11/03/2008. 24 H 4 S 074EA1.01 Question kind of matches KIA. Change

1. 2. to read: Why are these conditions more restrictive than earlier transition conditions Otherwise SAT. (Is this RO knowledge?)

NEW Licensee made changes as requested. SAT 11/03/2008.

Q#

4. Job Content Flaws

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5) 26 H 2

5. Other

6.

7.

Explanation WE03EK2.1 Question appears to match KIA. Need add ReS temperature. Used on the 2004 NRC exam under KIA 005K4.02 BANK Made changes as requested. SAT 11/03/2008. Q#

1.

2.

3. Psychometric Flaws LOK LOD I--.-----=-....--,----.---i----.-----"T----r--l

4. Job Content Flaws (F/H)

(1-5) 26 H 2

5. Other

6.

7.

Explanation E03EK2.1 Question appears to match KIA. Need add ReS temperature. Used on the 2004 NRC under KIA 005K4.02 BANK Made changes as requested. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-0=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S H 2 X U WE09EK3.3 Question does not meet KIA. The KIA 27 asks for reasons. Why do they stop depressurization when RVLlS is less than 73%? From 2006 NRC exam. Modified S Added a basis for stopping the depressurization. SAT 11/03/2008. H 2 X 003A2.02 Question appears to match KIA. Very 28 similar to question # 86 (SRO). The only difference is the initiating event. What procedure directs these actions? It seems to me that there is not a correct answer. AP-4 does direct the actions listed in choice C, but you would have to go to the procedure to S perform them. Question symmetry does not look right. One of these needs to be changed. 2004 NRC exam BANK Discussed with Licensee. Determined based on discussion that question as written is SAT. Shuffled distractors. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-0=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S H 2 X U WE09EK3.3 Question does not meet KIA. The KIA 27 asks for reasons. Why do they stop depressurization when RVLlS is less than 73%? From 2006 NRC exam. Modified S Added a basis for stopping the depressurization. SAT 11/03/2008. H 2 X 003A2.02 Question appears to match KIA. Very 28 similar to question # 86 (SRO). The only difference is the initiating event. What procedure directs these actions? It seems to me that there is not a correct answer. AP-4 does direct the actions listed in choice C, but you would have to go to the procedure to S perform them. Question symmetry does not look right. One of these needs to be changed. 2004 NRC exam BANK Discussed with Licensee. Determined based on discussion that question as written is SAT. Shuffled distractors. SAT 11/03/2008.

5. Other

6.

7.

4. Job Content Flaws

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5) Q# Explanation 30 I H I 2 I X I I I~~..... 34 Question appears to match KIA. Need to E place in the stem Excess letdown is in service and aligned to the VCT, or someone could make the assumption that excess letdown was aligned to the NCDT to begin with. Otherwise okay. SINEW Licensee made changes as requested. SAT 11103/2008. 31 I F I 2 I I S 1005K4.11 Question appears to match KIA. SAT this is a fundamental level question. NEW SAT 11/03/2008.

5. Other

6.

7.

4. Job Content Flaws

1.

2.

3. Psychometric Flaws LOK LODI----r--....;..,.----,-____,r__-~__r--_r_____,r____I (F/H)

(1-5) Q# Explanation H 2 X 004K1.34 Question appears to match KIA. Need to 30 in the stem Excess letdown is in service and gned to the VCT, or someone could make the assumption that excess letdown was aligned to the NCDT to begin with. Otherwise okay. S NEW Licensee made changes as requested. SAT 11103/2008. F 2 S K4.11 Question appears to match KIA. SAT this 31 is a fundamental level question. NEW T 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 006A 1.05Question appears to match KIA. Please 32 H 2 E add automatically to the stem. 'What is the earliest time that KC flow is automatically aligned to the NO heat exchanger?" NEW S Licensee made changes as requested. SAT 11/03/2008. 007G2.4.6 Question Does not match KIA. The KIA 33 H 2 X U system is Pressurizer Relief Tank and how EOP mitigating strategies relate. This question is an H.1 question describing what constitutes a bleed and feed. NEW S Licensee replaced question. Chief Examiner allowed AOP actions to satisfy the KIA. (Normally EOPs do not address this). Otherwise the KIA appears to match. SAT 11/03/2008. 008K3.03 Question appears to match the KIA. 34 H 2 E Change Distractor C to read... Open the #1 seal bypass valve to restore seal cooling. Change distractor 0 to read All seal cooling to NCP1 C is lost. Secure NCP 1C to prevent further seal damage. SAT 2004 NRC exam. BANK S Made changes as requested. Shuffled distractors. SAT 11/03/2008. --I....--

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 006A 1.05Question appears to match KIA. Please 32 H 2 E add automatically to the stem. 'What is the earliest time that KC flow is automatically aligned to the NO heat exchanger?" NEW S Licensee made changes as requested. SAT 11/03/2008. 007G2.4.6 Question Does not match KIA. The KIA 33 H 2 X U system is Pressurizer Relief Tank and how EOP mitigating strategies relate. This question is an H.1 question describing what constitutes a bleed and feed. NEW S Licensee replaced question. Chief Examiner allowed AOP actions to satisfy the KIA. (Normally EOPs do not address this). Otherwise the KIA appears to match. SAT 11/03/2008. 008K3.03 Question appears to match the KIA. 34 H 2 E Change Distractor C to read... Open the #1 seal bypass valve to restore seal cooling. Change distractor 0 to read All seal cooling to NCP1 C is lost. Secure NCP 1C to prevent further seal damage. SAT 2004 NRC exam. BANK S Made changes as requested. Shuffled distractors. SAT 11/03/2008.

1. I 2.

Q# I LOK LOD (F/H) (1-5) 35 I H I 2 I I I I I I 36 I H I 2 I I I I I I 37 I H I 2 I X I I X I I

5. Other I

I I I I I I 6. I

7.

U/Eil Explanation S 008K4.09 Question appears to match the KIA. SAT S 12007 NRC Exam Modified. SAT 11/03/2008. 01 OG2.1.25 Question appears to match the KIA. IS ISATNEW SAT 11103/2008. 2A2.02 Question appears to match KIA. NEW I E IWili the OTOT bistables be in if just the lower etector on N-42 failed low? If not, and the bistables have not been placed in a tripped condition, the reactor may not trip, and C would be correct. Please explain. NEW Ran on simulator at BOL and EOL conditions rmed that with only the lower detector failing low the OTDT bistable would still come in. SAT 11103/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws Q#

LOK LOD (F/H) (1-5) Stem T/F Credo Partial Job-Minutia

1. 1 Back-Focus Dist.

Link units ward 35 H 2 36 H 2 37 H 2 X X

5. Other Q=

SRO KIA Only

6.

7.

U/EI Explanation S 008K4.09 Question appears to match the KIA. SAT S NRC Exam Modified. SAT 11/03/2008. 01 OG2.1.25 Question appears to match the KIA. S SAT NEW SAT 11103/2008. 012A2.02 Question appears to match KIA. NEW E Will the OTOT bistables be in if just the lower detector on N-42 failed low? If not, and the bistables have not been placed in a tripped condition, the reactor may not trip, and C would be correct. Please explain. NEW Ran on simulator at BOL and EOL conditions and S confirmed that with only the lower detector low the OTDT bistable would still come in. SAT 11103/2008.

Q# 39 41 I 42 I

1.

LOK (F/H) H 2 F 121 F 121

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Stem Icuesl T/F I cred*1 Partial I JOb-I Minutia I #1 I Back-I Q= I SRO I u/EI Focus Dist. Link units ward KIA Only S Explanation 013K6.01 Question appears to match KIA. SAT. S 12005 NRC Exam. BANK SAT 11/03/2008. 025A4.01 Question appears to match KIA. Appears I S Ito be SAT. NEW SAT 11/03/2008. 026A1.03 Question appears to match KIA. SAT 1 SiNEW SAT 11/03/2008. Q# 39 41 42

1.

LOK (F/H) H F F

4. Job Content Flaws

2.

3. Psychometric Flaws LOD ~--~~--~----~--~~----~~~~

5. Other

6.

(1-5) Stem Cues T/F Credo Partial Job-Minutia

1. 1 8ack-Q=

SRO u/EI Focus Dist. Link units ward KIA Only S 2 S 2 S 2 S

7.

Explanation 3K6.01 Question appears to match KIA. SAT. 005 NRC Exam. BANK SAT 11/03/2008. 025A4.01 Question appears to match KIA. Appears to be SAT. NEW SAT 11/03/2008. 026A1.03 Question appears to match KIA. SAT NEW SAT 11/03/2008.

Q# 43 45 I 46 I

1.

LOK (F/H) H F F

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

LOD (1-5) 2 I 2 I I 2 I Stem Icuesl T/F I Cred.IPartiallJOb-IMinutial #1 I Back-I Q= I SRO IUlEI Focus Dist. Link units ward KIA Only S Explanation x I I I I I I I I 026K1.01 Question appears to match KIA. Very E IwordY. Attempt to get rid of most of the BOP reports. Actual stem needs some modification Which one of following describes the status of the 1 A NS pump 1245, and the earliest time that NO Aux spray can be placed in service? NEW S ILicensee made changes as requested. SAT 11/03/2008. . 11 Question appears to meets KIA. I S 12003 NRC exam question. BANK Licensee shuffled distractors as requested. SAT 11/03/2008. 1A3.03 Question appears to meets KIA. SAT. IS INEW SAT 11/03/2008.

1.

2.

3. Psychometric Flaws Q#

LOK LOD (F/H) (1-5) Stem T/F Credo Partial Focus Dist. 43 H 2 X 45 F 2 46 F 2

4. Job Content Flaws

5. Other Job-Minutia

1. 1 Back-Q=

SRO Link units ward KIA Only

6.

UlEi S E

7.

Explanation 026K1.01 Question appears to match KIA. Very wordy. Attempt to get rid of most of the BOP reports. Actual stem needs some modification Which one of the following describes the status of the 1 A NS pu at 1245, and the earliest time that NO Aux spray can be placed in service? NEW S Licensee made changes as requested. SAT 11/03/2008. 059A4.11 Question appears to meets KIA. NRC exam question. BANK Licensee shuffled distractors as requested. SAT 11/03/2008. 061A3.03 Question appears to meets KIA. SAT. S NEW SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 062A3.01 Question appears to meet KIA. Change 47 H 2 E 2B Amps to 2B output amps. (field amps will decrease as voltage is lowered. NEW S Added output to 2B amps. SAT 11/03/2008. 063K2.01 Question appears to meets KIA. There 48 F 1 X U are no plausible distractors. Only one power supply is DC @ 125 volts, and the correct answer (250V). Almost all emergency lube oil pumps in the industry are DC. Need to have more plausible distractors. As written very little discriminatory value. NEW S Replaced question. Very simple. Appears to match KIA. SAT 11/03/2008. 063K3.01 Question appears to match KIA. 49 F 2 X E Distractor B does not appear to be plausible. 2004 NRC exam. BANK S Licensee changed distractor B to be more plausible. SAT 11/03/2008. 064A3.07 Question appears to match KlA.SAT 50 H 2 S NEW SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 062A3.01 Question appears to meet KIA. Change 47 H 2 E 2B Amps to 2B output amps. (field amps will decrease as voltage is lowered. NEW S Added output to 2B amps. SAT 11/03/2008. 063K2.01 Question appears to meets KIA. There 48 F 1 X U are no plausible distractors. Only one power supply is DC @ 125 volts, and the correct answer (250V). Almost all emergency lube oil pumps in the industry are DC. Need to have more plausible distractors. As written very little discriminatory value. NEW S Replaced question. Very simple. Appears to match KIA. SAT 11/03/2008. 063K3.01 Question appears to match KIA. 49 F 2 X E Distractor B does not appear to be plausible. 2004 NRC exam. BANK S Licensee changed distractor B to be more plausible. SAT 11/03/2008. 064A3.07 Question appears to match KlA.SAT 50 H 2 S NEW SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 064K6.07 Question appears to match KIA. SAT 51 F 2 E 2003 NRC exam question. Add automatically and manually started to D. BANK S Licensee made changes as requested. SAT 11/03/2008. 073A2.02 Question kind of matches KIA. What 52 H 2 X ? E procedure is used to mitigate the failure? The actions should be lAW a procedure. It appears that Ctmt. ventilation is isolated and must be restored. NEW S Licensee made changes, SAT 11/03/2008. underlined not 076K2.01 Question appears to match KIA. Do any 53 F 1 S of these busses supply 1 ETA? If so it is also a correct answer. NEW SAT 11/03/2008. i 078K3.02 Question appears to match KIA. Some of 54 F 2 S the information in the stem is window dressing. SAT NEW SAT 11/03/2008. 1 03K1.07 Question kind of matches KIA. What is 55 F 2 E the significance of the second part of the question? Do you have a containment vacuum system? Which one of the foliowinQ describes a condition that

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 064K6.07 Question appears to match KIA. SAT 51 F 2 E 2003 NRC exam question. Add automatically and manually started to D. BANK S Licensee made changes as requested. SAT 11/03/2008. 073A2.02 Question kind of matches KIA. What 52 H 2 X ? E procedure is used to mitigate the failure? The actions should be lAW a procedure. It appears that Ctmt. ventilation is isolated and must be restored. NEW S Licensee made changes, SAT 11/03/2008. underlined not 076K2.01 Question appears to match KIA. Do any 53 F 1 S of these busses supply 1 ETA? If so it is also a correct answer. NEW SAT 11/03/2008. 078K3.02 Question appears to match KIA. Some of 54 F 2 S the information in the stem is window dressing. SAT NEW SAT 11/03/2008. 1 03K1.07 Question kind of matches KIA. What is 55 F 2 E the significance of the second part of the question? Do you have a containment vacuum system? Which one of the following describes a condition that

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S would automatically close 1 VQ-1 0, and what would the consequence be if the valve failed to close? NEW S Licensee changed all distractors and stem. SAT 11/03/2008. 001 K2.02 Does not match the KIA. This question 56 F 2 X U really asks what happens if both bypass breaker are closed, not power supplies. NEW S Replaced Question with a new question. Appears to match the KIA. SAT 11/03/2008. 011 A 1.02 Question kind of matches KIA. The 57 H 2 E question should be at approximately what time does charging/letdown have to be returned to service to prevent exceeding a T/S limit. 2005 NRC exam Modified. S After discussion with licensee, OK leave as is. SAT 11/03/2008. 016K1.12 Question appears to match KIA. Not sure 58 H 1.5 E if all of these are plausible. Will discuss. BANK Licensee shuffled all distractors, discussed question and distractor plausibility. SAT S 11/03/2008. 017K3.01 Question appears to match KIA. SAT. 59 H 2 S 2003 NRC exam.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 8ack-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S would automatically close 1 VQ-1 0, and what would the consequence be if the valve failed to close? NEW S Licensee changed all distractors and stem. SAT 11/03/2008. 001 K2.02 Does not match the KIA. This question 56 F 2 X U really asks what happens if both bypass breaker are closed, not power supplies. NEW S Replaced Question with a new question. Appears to match the KIA. SAT 11/03/2008. 011 A 1.02 Question kind of matches KIA. The 57 H 2 E question should be at approximately what time does charging/letdown have to be returned to service to prevent exceeding a T/S limit. 2005 NRC exam Modified. S After discussion with licensee, OK leave as is. SAT 11/03/2008. 016K1.12 Question appears to match KIA. Not sure 58 H 1.5 E if all of these are plausible. Will discuss. BANK Licensee shuffled all distractors, discussed question and distractor plausibility. SAT S 11/03/2008. 017K3.01 Question appears to match KIA. SAT. 59 H 2 S 2003 NRC exam.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

Back-Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S BANK Shuffled distractors. SAT 11/03/2008. 027K5.01 Question appears to match KIA. Stem 60 F 2 E Focus - Radiation monitoring teams would measure actual dose not projected dose. Could we change distractor 0 to read heaters are de-energized? 2003 NRC exam. BANK Licensee changed distractor D. Shuffled distractors, removed projected from stem. SAT 11/03/2008. 035G2.2.40 Questions appears to match KIA. 2005 61 F 2 S NRC exam. SAT BANK Shuffled distractors as requested. SAT 11/03/2008. 045A3.05 Question appears to match KIA. 62 H 2 X X S Distractors C and 0 are not plausible. Is there such a thing as a manual runback? Are you talking about manually ramping load off of the turbine? This question needs some work. NEW Stem was changed by eliminating the concerns of the chief examiner. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

Back-Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S BANK Shuffled distractors. SAT 11/03/2008. 027K5.01 Question appears to match KIA. Stem 60 F 2 E Focus - Radiation monitoring teams would measure actual dose not projected dose. Could we change distractor 0 to read heaters are de-energized? 2003 NRC exam. BANK Licensee changed distractor D. Shuffled distractors, removed projected from stem. SAT 11/03/2008. 035G2.2.40 Questions appears to match KIA. 2005 61 F 2 S NRC exam. SAT BANK Shuffled distractors as requested. SAT 11/03/2008. 045A3.05 Question appears to match KIA. 62 H 2 X X S Distractors C and 0 are not plausible. Is there such a thing as a manual runback? Are you talking about manually ramping load off of the turbine? This question needs some work. NEW Stem was changed by eliminating the concerns of the chief examiner. SAT 11/03/2008.

4_ Job Content Flaws Q#

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5)

5. Other

6.

7.

Explanation 079A4.01 Question kind of matches KIA. There is 64 I H I 2 I I E Ino sequence in the distractors, they are all in the same order. At what pressure do the valves perform the swap? How can an operator monitor them with out knowing the pressure that should operate? Not very discriminating. 2003 NRC exam question. BANK Made changes as requested. Need to shuffle S Idistractors around. SAT 11/03/2008. 086K6.04 Question appears to match KIA. SAT. 65 I F I 2 I IS INEW SAT 11/03/2008. G2.1.45 Question appears to match KIA. Do you 66 I H I 2 I I E I have a % steam flow indicator? I don't think so? Need another name for #1. Otherwise it is not plausible. NEW S Iucensee informs NRC that they do indeed have % steam flow meter. SAT 11/03/2008. Q#

1.

2.

3. Psychometric Flaws LOK LOD~--'-~---'---'---+--'----'--'---~

(F/H) (1-5) Explanation

4. Job Content Flaws

5. Other

7.

6.

01 Question kind of matches KIA. There is 64 H 2 no sequence in the distractors, they are all in the same order. At what pressure do the valves perform swap? How can an operator monitor them with knowing the pressure that should operate? Not discriminating. 2003 NRC exam question. BANK Made changes as requested. Need to shuffle S distractors around. SAT 11/03/2008. 086K6.04 Question appears to match KIA. SAT. 65 F 2 S NEW SAT 11/03/2008. G2.1.45 Question appears to match KIA. Do you 66 H 2 E have a % steam flow indicator? I don't think so? Need another name for #1. Otherwise it is not plausible. NEW S Licensee informs NRC that they do indeed have % steam flow meter. SAT 11/03/2008.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S G2.1.8 Question appears to match KIA. SAT 67 F 2 S NEW SAT 11/03/2008. G2.2.2 Question appears to match KIA. SAT 68 F 2 S NEW SAT 11/03/2008. G2.2.39 Question appears to match KIA. SAT 69 F 2 S 2003 NRC Exam. Modified SAT 11/03/2008. G2.3.11 Question appears to match KIA. SAT 2003 70 F 2 S NRC Exam BANK SAT 11/03/2008. G2.3.4 Question appears to match KIA. SAT 2004 71 F 3 S NRC exam. BANK SAT 11/03/2008. G2.3.7 Question appears to match KIA. 2003 NRC 72 H 2 E exam. BANK This question can be easily modified to be some what different than the bank question. BANK Licensee shuffled distractors but did not change the basic question. SAT 11/03/2008. -~--

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S G2.1.8 Question appears to match KIA. SAT 67 F 2 S NEW SAT 11/03/2008. G2.2.2 Question appears to match KIA. SAT 68 F 2 S NEW SAT 11/03/2008. G2.2.39 Question appears to match KIA. SAT 69 F 2 S 2003 NRC Exam. Modified SAT 11/03/2008. G2.3.11 Question appears to match KIA. SAT 2003 70 F 2 S NRC Exam BANK SAT 11/03/2008. G2.3.4 Question appears to match KIA. SAT 2004 71 F 3 S NRC exam. BANK SAT 11/03/2008. G2.3.7 Question appears to match KIA. 2003 NRC 72 H 2 E exam. BANK This question can be easily modified to be some what different than the bank question. BANK Licensee shuffled distractors but did not change the basic question. SAT 11/03/2008.

I

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

Back-er-SRO U/EI Explanation Focus Dist. Link units ward KIA Only S G2.4.13 Question appears to match KIA. Distractors 73 F 2 X Band 0 are not plausible. Everyone with a license is responsible for CSFs. So why would a procedure not allow someone else with a license to be given the task of monitoring CSFs. Need better distractors. NEW S Revised question appears to be acceptable. SAT 11/03/2008. G2.4.22 Question appears to match KIA. SAT 74 H 2 S NEW SAT 11/03/2008. G2.4.42 Question appears to match KIA. SAT 75 F 2 S NEW SAT 11/03/2008. 39 Sats, 10 Unsats, and 26 Enhancements Generic Comments: Need all originals of modified questions. All bank questions should have the answers rotated from original (i.e. if the answer was originally A, swap the correct answer to B, C, or D. I I

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

Back-er-SRO U/EI Explanation Focus Dist. Link units ward KIA Only S G2.4.13 Question appears to match KIA. Distractors 73 F 2 X Band 0 are not plausible. Everyone with a license is responsible for CSFs. So why would a procedure not allow someone else with a license to be given the task of monitoring CSFs. Need better distractors. NEW S Revised question appears to be acceptable. SAT 11/03/2008. G2.4.22 Question appears to match KIA. SAT 74 H 2 S NEW SAT 11/03/2008. G2.4.42 Question appears to match KIA. SAT 75 F 2 S NEW SAT 11/03/2008. 39 Sats, 10 Unsats, and 26 Enhancements Generic Comments: Need all originals of modified questions. All bank questions should have the answers rotated from original (i.e. if the answer was originally A, swap the correct answer to B, C, or D. I

~;JJkU ES-401, Rev. 9 Catawba 2008-301 SRO Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

LOD (1-5) Stem Icuesl T/F ! cred.! partial! JOb-! Minutia! #1 ! Back-! Q= ! SRO I U/EI Focus Dist. Link units ward KIA Only S Instructions

7.

Explanation [Refer to Section 0 of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1.

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

2.

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

3.

Check the appropriate box if a psychometric flaw is identified:* The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements. The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4.

Check the appropriate box if a job content error is identified: The question is not linked to the job requirements (i.e., the question has a valid 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 (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements.

5.

Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable).

6.

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?

7.

At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met). ES-401, Rev. 9 Catawba 2008-301 SRO Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

3. Psychometric Flaws LOD ~----~~~----~----~----~----~----~-----r----~

4. Job Content Flaws

5. Other

6.

7.

(1-5) Stem Cues T/F Credo Partial Job-Minutia

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. Link units ward KIA Only S Instructions [Refer to Section 0 of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1.

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

2.

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

3.

Check the appropriate box if a psychometric flaw is identified:* The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements. The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4.

Check the appropriate box if a job content error is identified: The question is not linked to the job requirements (i.e., the question has a valid 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 (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements.

5.

Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable).

6.

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?

7.

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

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5) Q# 77 H 3 x

4. Job Content Flaws

5. Other

6.

7.

Explanation E,011 EG2.2.36 Question appears to match the KIA. Reference for question 77 could help answer question 76. Appears to be SRO only. Stem Focus is also confusing. Try "assuming that components remain inoperable." Second question discussing ECCS Criteria. Enhancements needed. NEW Licensee made enhancements as requested, anged question 76. SAT 11.05/2008

4. Job Content Flaws

1.

2.

3. Psychometric Flaws LOK LOD I---.,...---.:....,.----.r---.---.j----,.--~-._____I Q#

(F/H) (1-5) 77 H 3 x

5. Other

6.

7.

Explanation E 011 EG2.2.36 Question appears to match the KIA. Reference for question 77 could help answer question 76. Appears to be SRO only. Stem Focus is also confusing. Try "assuming that components remain inoperable." Second question discussing ECCS Criteria. Enhancements needed. NEW Licensee made enhancements as requested, changed question 76. SAT 11.05/2008

1. I 2.

0# LOK LOD (F/H) (1-5) 78 H I 2 I X I

4. Job Content Flaws

5. Other I 6.

SRO I u/EI Only S TE

7.

Explanation 026AA2.05 Question Kind of matches KIA. There is not really a loss of the CCW system, but it is a loss of a control function of the system that effects CCW to the NO system. Stem Focus, second part of stem should read and what system is required to be declared inoperable? NEW Licensee made changes as requested. ,T 11/05/2008

1.

2.

3. Psychometric Flaws 0#

LOK LOD (F/H) (1-5) Stem T/F Credo Partial Focus Dist. 78 H 2 X

4. Job Content Flaws

5. Other Job-Minutia

1. 1 Back-0=

SRO Link units ward KIA Only

6.

u/EI S E

7.

Explanation 026AA2.05 Question Kind of matches KIA. There is not really a loss of the CCW system, but it is a loss of a control function of the system that effects CCW flow to the NO system. Stem Focus, second part of stem should read and what system is required to be declared inoperable? NEW Licensee made changes as requested. SAT 11/05/2008

1. I 2.

Q# LOK LOD (F/H) (1-5) 80 I F? I 2

4. Job Content Flaws

5. Other I 6.

cred.! partial! JOb-! Minutia! #1 ! BaCk-! Q= ! SRO I u/EI Dist. Link units ward KIA Only S I X I Ts

7.

Explanation 058AA2.03 Question does not really meet the KIA. What DC loads were lost? I am sure that if the unit trips that some loads were lost. I also realize that th entering of E-O implies that the loss of dc (impact) caused the reactor to trip. Question was also marked as a memory level question. A reference is also provided. If this is a memory level question then a reference should not be required. NEW Monitoring Voltage is what the licensee considered as the impact on ability to operate and monitor plant systems. OK. (Reference removed) Question is SAT 11/05/2008

1.

2.

3. Psychometric Flaws Q#

LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Focus Dist. 80 F? 2

4. Job Content Flaws

5. Other Job-Minutia

1. 1 Back-Q=

SRO Link units ward KIA Only X

6.

u/EI S S

7.

Explanation 058AA2.03 Question does not really meet the KIA. DC loads were lost? I am sure that if the unit that some loads were lost. I also realize that entering of E-O implies that the loss of dc (impact) caused the reactor to trip. Question was also marked as a memory level question. A reference is also provided. If this is a memory level question then a reference should not be required. NEW Monitoring Voltage is what the licensee considered as the impact on ability to operate and monitor plant systems. OK. (Reference removed) Question is SAT 11/05/2008

Q#

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5)

4. Job Content Flaws

5. Other

6.

7.

Explanation

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q# LOK LOD r---,---.----.----r---;---.-----r--,r-~ (F/H) (1-5) Explanation

4. Job Content Flaws Q#

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5) 85 F 2

5. Other

6.

x x

7.

Explanation E16EA2.1 Question does not totally meet the KIA. is no procedure selection. The applicant is given what procedure is to be implemented in the Stem. However, there is some value in the setpoint requires entry into the procedure, this is RO knowledge. The basis statements are really the function of a charcoal filter. This is also RO (radiation worker knowledge). Therefore the question is not SRO only. NEW Licensee rewrote question, changed setpoints to be more realistic, and added actions to perform that would mitigate the event. Appears to match KIA. Appears to be SRO only. SAT 11/05/2008

4. Job Content Flaws Q#

1.

2.

3. Psychometric Flaws LOK LOD I---.--~----'r---.----I-.....,.--,.--.-----l (F/H)

(1-5) 85 F 2

5. Other

6.

x x

7.

Explanation E16EA2.1 Question does not totally meet the KIA. re is no procedure selection. The applicant is given what procedure is to be implemented in the Stem. However, there is some value in the setpoint requires entry into the procedure, this is RO knowledge. The basis statements are really the nction of a charcoal filter. This is also RO (radiation worker knowledge). Therefore the question is not SRO only. NEW Licensee rewrote question, changed setpoints to be more realistic, and added actions to perform at would mitigate the event. Appears to match KIA. Appears to be SRO only. SAT 11/05/2008

1. I 2.

4. Job Content Flaws Q#

LOK LaD (F/H) (1-5) 86 H I 2 87 H 2

5. Other I 6.

SRO I U/EI Only S TE S

7.

Explanation uu",..*,,:~.01 Question appears to match KIA. Appears be SRO only. What makes the procedure selection in C plausible? NEW Licensee changed distractor C. SAT 11/05/2008 026G2.4.47 Question appears to match KIA. to SRO only. SAT NEW

1.

2.

3. Psychometric Flaws Q#

LOK LaD (F/H) (1-5) Stem Cues T/F Credo Partial Focus Dist. 86 H 2 87 H 2

4. Job Content Flaws

5. Other Job-Minutia

1. /

Back-Q= SRO Link units ward KIA Only

6.

U/EI S

7.

Explanation I\\J\\J.~,..,.... 01 Question appears to match KIA. Appears be SRO only. What makes the procedure lection in C plausible? NEW SAT 11/05/2008 .47 Question appears to match KIA. pears to SRO only. SAT NEW

1. I 2.

Q# LOK LaD (F/H) (1-5) Stem Focus 90 H I 2

3. Psychometric Flaws

4. Job Content Flaws

5. Other Cues T/F I 6.

u/EI S

7.

Explanation 076A2.02 Question appears to match KIA. Appears to be SRO knowledge. SAT. NEW SAT 11/05/2008

1.

2.

3. Psychometric Flaws Q#

LOK LaD (F/H) (1-5) Stem Cues T/F Credo Partial Focus Dist. 90 H 2

4. Job Content Flaws Job-Minutia

1. 1 Back-Link units ward

5. Other Q=

SRO KIA Only

6.

u/EI S

7.

Explanation 076A2.02 Question appears to match KIA. Appears be SRO knowledge. SAT. NEW SAT 11/05/2008

Q#

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5) 94 H 3 x

4. Job Content Flaws

5. Other

6.

7.

Explanation .1.14 Question appears to match KIA. Do not see how this is a general emergency. If a site evacuation is always precluded by a site assembly, why would anyone choose B or D. There is not a release etc. Question needs some work. Modified S I Licensee changed distractors band d (added non-essential personnel) SAT 11/05/2008

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other Q#

LOK LOD i---,-----,r---r---.----t---.------.----.----1 (F/H) (1-5)

6.

7.

Explanation .1.14 Question appears to match KIA. Do not see how this is a general emergency. If a site uation is always precluded by a site assembly, why would anyone choose B or D. There is not a release etc. Question needs some work. Modified S Licensee changed distractors band d (added non-essential personnel) SAT 11/05/2008

Q#

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5) 4.ioh Content Flaws

5. Other

6.

7.

Explanation Q#

1.

2.

3. Psychometric Flaws LOK LOD ~--,-~.---.---~--~---.----.---,---~

4. Job Content Flaws

5. Other

6.

7.

(F/H) (1-5) Explanation

Q# 99

1. I 2. I

3. Psychometric Flaws LOK LOD (F/H)

(1-5) F 2

4. Job Content Flaws

5. Other

6.

7.

Explanation E I G2.3.14 Question appears to match KIA. Appears to be SRO only. Both of the Notifications are required. Need to change to soonest required notification, or something similar. NEW S 'Licensee added first to stem. SAT 11/05/2008

3. Psychometric Flaws

4. Job Content Flaws Q#

1.

2.

LOK LOD ~--T-~r---r---~--~--~--~---r--~ (F/H) (1-5) 99 F 2

5. Other

6.

7.

Explanation E G2.3.14 Question appears to match KIA. Appears to be SRO only. Both of the Notifications are required. Need to change to soonest required notification, or something similar. NEW S Licensee added first to stem. SAT 11/05/2008

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

8ack-Q= SRO UJE/ Explanation Focus Dist. Link units ward KIA Only S 100 F 1 X U G2.4.3 Question appears to match KIA. Not SRO only knowledge. All operators are required to know PAM indicators and the why is obvious. Discussed changing the basis statements for C and D will look at again on prep week. 11/04/2008. 2 Sats, 15 Unsats, and 8 Enhancement = 60 % unsatisfactory. Overall 29% of questions were deemed to be unsatisfactory before discussing with licensee. (SRO and RO combined.)

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. /

8ack-Q= SRO UJE/ Explanation Focus Dist. Link units ward KIA Only S 100 F 1 X U G2.4.3 Question appears to match KIA. Not SRO only knowledge. All operators are required to know PAM indicators and the why is obvious. Discussed changing the basis statements for C and D will look at again on prep week. 11/04/2008. 2 Sats, 15 Unsats, and 8 Enhancement = 60 % unsatisfactory. Overall 29% of questions were deemed to be unsatisfactory before discussing with licensee. (SRO and RO combined.)

ES-403, Rev. 9 Written Examination Grading Quality Checklist Form ES-403-1 Facility: Catawba 2008-301 Date of Exam: 12/10/2008 Exam Level: RO/SRO

1.

2.

3.

4.

5.

6.

Item Description Clean answer sheets copied before grading Answer key changes and question deletions justified and documented Applicants' scores checked for addition errors (reviewers spot check> 25% of examinations) Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail All other failing examinations checked to ensure that grades are justified Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature

a. Grader

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

Initials a b c Date ~ (Jllz~/II' (*) The' facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. ES-403, Rev. 9 Written Examination Grading Quality Checklist Form ES-403-1 Facility: Catawba 2008-301 Date of Exam: 12/10/2008 Exam Level: RO/SRO

1.

2.

3.

4.

5.

6.

Item Description Clean answer sheets copied before grading Answer key changes and question deletions justified and documented Applicants' scores checked for addition errors (reviewers spot check> 25% of examinations) Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail All other failing examinations checked to ensure that grades are justified Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature

a. Grader

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

Initials a b c Date ~ (Jllz~/II' (*) The' facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-403 Written Examination Grading Quality Checklist Form ES-403-1 Facility: {'1}--r/1 v* n j} Date of Exam: /2))&'/0 <[ Exam Level: ROGXj SROW Initials Item Description a b c

1.

Clean answer sheets copied before grading IJ'~v

2.

Answer key changes and question deletions justified l)ltV and documented

3.

Applicants' scores checked for addition errors l)itt? (reviewers spot check> 25% of examinations)

4.

Grading for all borderline cases (80 +/-2% overall and 70 or 80, 7(!!/ as applicable, +/-4% on the SRO-only) reviewed in detail

5.

All other failing examin~tions checked to ensure that grades Xt{J are justified

6.

Performance on missed questions checked for training deficiencies and wording problems; evaluate validity )10 of questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader X$C£&~

) 2-/;ljt2'[

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

(*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. ES-403, Page 6 of 6 ES-403 Written Examination Grading Quality Checklist Form ES-403-1 Facility: {'1}--r/1 l/' n,t} Date of Exam: /2-))&,)0 <J Exam Level: RO[b(.l SROM Initials Item Description a b c

1.

Clean answer sheets copied before grading IJ'~v

2.

Answer key changes and question deletions justified l)ltV and documented

3.

Applicants' scores checked for addition errors

,(t;[)

(reviewers spot check> 25% of examinations)

4.

Grading for all borderline cases (80 +/-2% overall and 70 or 80, 7it:;J as applicable, +/-4% on the SRO-only) reviewed in detail

5.

All other failing examin~tions checked to ensure that grades Xt{J are justified

6.

Performance on missed questions checked for training deficiencies and wording problems; evaluate validity )10 of questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader X$C£&~

) 2-/;ljt2'[

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

(*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. ES-403, Page 6 of 6}}