ML101520391

Initial Exam 2010-301 Final Administrative Documents

ML101520391
Person / Time
Site:	Oconee
Issue date:	05/04/2010
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-269/10-301, 50-270/10-301, 50-287/10-301, ES-201, Rev 9E
Download: ML101520391 (83)

Text

{{#Wiki_filter:ES-201, Rev. 9E Examination Preparation Checklist Form ES-201-1 Facility: Oconee 2010-301 Date of Examination: 03/29/2010 Facility NRC Examinations Developed by: Written / Operating Test Written / Operating Test T Chief ae Task Description (Reference) Examiners Initials -180 1. Examination administration date confirmed (C.1.a; C.2.a and b) 7/22/2009 -120 2. NRC examiners and facility contact assigned (C. 1.d; C.2.e) 9/29/2009 -120 3. Facility contact briefed on security and other requirements (C.2.c) 9/29/2009 -120 4. Corporate_notification_letter_sent_(C.2.d) [-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] 01/15/2010 {-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES 301-1, ES-301-2, ES-301-5, ES-D-ls, ES-40l-1/2, ES-401-3, and ES-401-4, as 01/08/2010 applicable (C.1.e and f C.3.d) {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility 01/15/2010 licensee (C.2.h; C.3.e)} {-45} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as 2/08/20 10 applicable), supporting documentation (including Forms ES-301-3, ES3014, (Written on ES-30l-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and 2/09/2010) h; C.3.d) -30 9. Preliminary license applications (NRC Fonn 398s) due (C.1.l; C.2.g; ES-202) 02/26/2010 -14

10. Final license applications due and Form ES-201-4 prepared (C.Ll; C.2.i; ES-202) 3/12/2010

-14

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

-14

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

N/A -7

13. Written examinations and operating tests approved by NRC supervisor 03/23/20 10 (C.2.i; C.3.h)

-7

14. Final applications reviewed; 1 or 2 (if>10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent 03/23/2010 (C.2.i;_Attachment_4;_ES-202,_C.2.e;_ES-204)

-7

15. Proctoring/written exam administration guidelines reviewed with facility licensee 03/23/20 10 (C.3.k)

-7

16. Approved scenarios, job performance measures, and questions distributed to 03/23/20 10 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, Rev. 9E Examination Preparation Checklist Form ES-201-1 Facility: Oconee 2010-301 Date of Examination: 03/29/2010 Facility NRC Examinations Developed by: Written 1 Operating Test Written I Operating Test Target Chief Date

• Task Description (Reference)

Examiner's Initials -180

1.

Examination administration date confirmed (C.1.a; C.2.a and b) 7/2212009 -120

2.

NRC examiners and facility contact assigned (C.1.d; C.2.e) 9/29/2009 -120

3.

Facility contact briefed on security and other requirements (C.2.c) 9/29/2009 -120

4.

Corporate notification letter sent (C.2.d) [-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] 01115/2010 {-75}

6.

Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, as 01/08/2010 applicable (C.1.e and f; C.3.d) {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility 01115/2010 licensee (C.2.h; C.3.e)} {-45}

8.

Proposed examinations (including written, walk-through IPMs, and scenarios, as 2/08/2010 applicable), supporting documentation (including Forms ES-301-3, ES-301-4, (Written on ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and 2109/2010) h; C.3.d) -30

9.

Preliminary license applications (NRC Form 398's) due (C.Ll; C.2.g; ES-202) 02/26/2010 -14

10. Final license applications due and Form ES-20 1-4 prepared (C.1.l; C.2.i; ES-202) 3/12/2010

-14

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

-14

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

NIA -7

13. Written examinations and operating tests approved by NRC supervisor 03123/2010 (C.2.i; C.3.h)

-7

14. Final applications reviewed; lor 2 (if>10) applications audited to confirm qualifications I eligibility; and examination approval and waiver letters sent 03/23/2010 (C.2.i; Attachment 4; ES-202, C.2.e; ES-204)

-7

15. Proctoring/written exam administration guidelines reviewed with facility licensee 03/2312010 (C.3.k)

-7

16. Approved scenarios, job performance measures, and questions distributed to 03123/2010 NRC examiners (C.3.i)

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

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: oconee 1010-301 Date of Examination: 3J53J2j? 4 44/ol Item Task Description 1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. w R b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. 2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major S transients. M b. Assess whether there are enough scenario sets (and spares) to test the projected number and U mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T applicants audit test(s), and that scenarios will not be repeated on subsequent days. c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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 distributed W among the safety functions as specified on the form / (2) task repetition from the last two NRC examinations is within the limits specified on the form T (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. Verifythatthe administrative outline meets the criteria specified on Form ES-301-1: (1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. 4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. G E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. d. Check for duplication and overlap among exam sections. L e. Check the entire exam for balance of coverage. f. Assess whether the exam fits the appropriate job level (RO or SRO). Printed Name/Signature Date

a. Author (Q

3 b. Facility Reviewer(*) c. NRC Chief Examiner (#) , -2VO d. NRCSupervisor ,JkJ1J\\fN,{4.J I Note:

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

- Lcr dj &i(i Mo ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: OC.onee 2.010-301 Date of Examination: 3jZ5-3}Zr' q/dl Item Task Description Initials a b* cJi

1.

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

w IJ~ "JA lif< R

b. Assess whether the outline was systematically and randomly prepared in accordance with I~

I Section D.1 of ES-401 and whether all KiA categories are appropriately sampled. T Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. ~ T

c.

~ \\~ E

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

(~ N

2.

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number of Cj11 ~ ~ normal evolutions, instrument and component failures, technical specifications, and major S transients. I M

b.

Assess whether there are enough scenario sets (and spares) to test the projected number and ,v. U mix of applicants in accordance with the expected crew composition and rotation schedule y ~!, L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T 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 and ~ ~\\.ij 'I(~ R

c.

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:

~'\\J (1) the oUtline(s) contain(s) the required number of control room and in-plant tasks distributed 0 W among the safety functions as specified on the form / (2) task repetition from the last two NRC examinations is within the limits specified on the form ~ T (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. I

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

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

c. Determine if there are enough different outlines to test the projected number and mix of

~ ~v-/ I~ applicants and ensure that no items are duplicated on subsequent days.

4.

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

~) ~~ J appropriate exam sections. .q G ~I ~IAJ E

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

i:i N Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5. cJ ~r I E

c.

R

d. Check for duplication and overlap among exam sections.

\\fJ 1U A "1 L

e. Check the entire exam for balance of coverage.

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f.

Assess whether the exam fits the appropriate job level (RO or SRO). () i~tJ Printed Name/Signature Date

a. Author Q..li~/{'J P. W\\~.;,Oavl / C~

3 -d--S-lVl( D

b. Facility Reviewer (*)

(M ~.. ~)2/\\ lJA-~ tf f:J;J~ / l;l{)+:~ ~Jn '3-d-3~/D NRC Chief Examiner (#) ~~ w,LAs.~ ~ V Wffr .3 ~ Zs-20/0

c.

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d. NRC Supervisor

/J/U.f!;UA "[. W [~tJ / ~?1rn "l t>"j(Ztlll() LuJ/YL---_.. ~.J

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

s-D/tl suac J ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: 000NEE Date of Examination: 3/29/10 Initials Item Task Description

a b* c# 1 a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. w R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. T T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. 9 2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S and major transients. 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 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.

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

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2: (1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form / (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants audit test(s) (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form. b. Verify that the administrative outline meets the criteria specified on Form ES-301-1: (1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations 34 f_ c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. $j G E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. R d. Check for duplication and overlap among exam sections. L e. Check the entire exam for balance of coverage.

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

b. Facility Reviewer (*)

GAb rie( (

c. NRCChiefExaminer(#)

(-z4(U 1J-,LA4 /

d. NRC Supervisor Note:

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

Not applicable for NRC-prepared examination outlines C4.% ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: OCONEE Date of Examination: 3/29/10 Initials Item Task Description a b* c#

1.

a.

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

b.

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

I~.~IAJ

2.

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number ~v..) of normal evolutions, instrument and component failures, technical specifications, IcyW S and major transients. I ~!W M

b.

Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule ~ L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T 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 \\~ I~~ R

c.

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:

W ~l'" (1 ) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within the limits specified on the form 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:

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

c.

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

4.

a.

Assess whether plant-specific priorities (including PRA and IPE insights) are covered S~ ~"'" in the appropriate exam sections. G E

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

'Vv. ::z.v-I N Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. ~ IW E

c.

R

d. Check for duplication and overlap among exam sections.

Ie,," ~w A K'~ Ikv L

e. Check the entire exam for balance of coverage.

f.

Assess whether the exam fits the appropriate job level (RO or SRO). U Ik~ 'P. printt 1,.tpeA ignature Date

a. Author tii~J _, l'ntb~,'-'

f. "-I

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b. Facility Reviewer (*)

G~l",q,1 4J;tSr...bv"'~ I ~~~ l~-~ '..()C'I (:.r~ \\J>.~ I I

c. NRC Chief Examiner (#)

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d. NRC Supervisor I

---

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--\\I Note:

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

• Not applicable for NRC-prepared examination outlines

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1.

W R I T T E N

2.

S I M U L A T o R

3.

W / T

4.

G E N E R A L Task Description

a.

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

b.

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

c.

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

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

a.

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

b.

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

c.

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

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 distributed among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s) (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

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

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

c.

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

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

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

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

d. Check for duplication and overlap among exam sections.

e. Check the entire exam for balance of coverage.

f.

Assess whether the exam fits the appropriate job level (RO or SRO). Printed Name/Signature

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Supervisor Form ES-201-2 3/29/2009 Date -

ES-201 Examination Security Agreement Form ES-201-3 1. Pre-Examination acknowledge that have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 3-2.- 10 as of the date of my signature. agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised. 2. Post-Examination To the best of my knoyvledge, did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of4(U . 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 2 h2 S(71( faA r.y4 Z,vAt SIQhA S .) l41lp\\1* 8.5J1 LARK 9. 1O.2h4.L, c 11.J )Afr///r& NOTES: JOB TITLE / RESPONSIBILITY ,4c:-r* 1 tmzg

/ Jy9-q t cS 1l1/I2 5 -fC7l (\\IuLy P,S 2. 3. 4. 5. 6, 7. SIGNATU (1) 12 1 3-i r,J.mL2-r J14-9 £b Vde rp4 ,fi, il 7, cht.- .2 .J ?4/LL DATE SIGNATURE(2) DATE NOTE 1$fL Wzi -/-) C-,---- 94i 3-2.-7 ///,t2 _34ZJo /. _M-4v/*o i z... c ,t, )1-Mo &3-3 &--h) j4 /Z-3-3f- /

I ES-201, Page 27 of 28 MAY 20 2010 ES-201 Examination Security Agreement Form ES-201-3

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 3 r z"'-1 Q 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'J.J."i....(D . 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 DATE SIGNATURE (2) ES-201, Page 27 of 28 MAY 2 0 2010

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 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility, licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee, I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised. 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of i-t--i . 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 1. M2fs1/f,

2. /)i 1

.u,L /-1,I 2 -1,4(,r S4-NOTES: 51L0 0P5 jtAT -C) I-Ui? b 0 /2-. F...

• JOB TITLE / RESPONSIBILITY

7. L

/._ SIGNATURE 1)

3. ii c.c.1,qi1J 4.

5. 1i P L*NO

7.,c-*- 5. Gck 8.

I-.- r. fL7fr7 .5 izcj DATE SIGNATURE(2) DATE NOTE ,.- -lO Z-.-lfl JilLil Ii _/#a-

-z4

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W

) 3-C_). 14 .-ig-io 2 -. /.jqi fI(J/J.AILtJiI

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.-. rs-1 -I7-.IO 3-17-/I i( -(3k--,. 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 week(s) of 34-,--10 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 l.-l.'.... /t. 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 SIGNATURE (2) DATE NOTE 2. ~~j,.s.wlPj2a,..f-~1.-tJ-Y ~-f--IO/f/~ Lf-1.s1tL-.. . e,t)' 1..-0-10 i~tt-Ib __ .. y....... .......... -***!J!v .5(ZD '2..-8--10 5'-IZ~/D __ SJl..o 7.-810 'i~(ND __ .... ()/J,$ $t(elbff 1-1/'-11 t{-l')-/o __ v......... ---.........,...', cr $/eo ~ -~*I.. ¥-;z. -I'- 'iZ-c.b.Q {'-r- ::5. Go.\\\\'~ok 'K-cJ 'Z..-'2.b-16 W. ~ -fq O)O~ M ~ Au.....;;,-o .. '" *.;'J"(, 3~, - j~ 'i~ 3cJ -, v 'l:tw Ll~:tft a c(-/~-ID __ .1'1-W0<..!; 5.1<0 "h7-I'~ . 'tst:.eh A~V;e,l\\q.S;, W tf-f3-r> __ A'((7f.J Y1!11)f ~o 41f70-- £ SRO -"1-(0 51<0 ~z.q-tb NOTES: ES-201, Page 27 of 28

ES-201 Examination Security Agreement Form ES-201-3 1. Pre-Examination acknowledge that have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of Iz as of the date of my signature. agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback), Furthermore, I am aware of the physical security measures and requirements (as documented in the facility, licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised. 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 5 - 1\\D. 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 /4I Ia lSi,v bi 34ML3 flAyrn (t4,s e 9. 7 Zthk L-d lO. 1 4vea o1dzu 11. E jLseaa... .12. S 4 ec.. Skef44

13. 6i cThP)

14. (&-.D,I.D NOTES:

p-o A4Mi)Y\\ SIGNATURE (1) 9 JOB TITLE / RESPONSIBILITY 2. 3. 4. 5. 6, 7. 8. DATE SIGNATURE(2) DATE NOTE r 51J-F n - if - A i7L4,_ - f-I -Ie I7 - li1ch Okj. LJf4 8 ./-Z--/D 4Z1d 2$- L. _a-3o -10 \\La -ib

2. -

ES-201, Page 27 of 28 ES~201 Examination Security ~greement 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=- lz.oI c> 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 !3 - )N\\D. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE 1- ' -:TrJ~ -:::J:?-O -/-B-IO 2: ~;p J 11y3'F~.A c'i.H <:) vv---

3. gar-. IS"""",

~ 4.~ ~tt ~ ~S-I'

5. J)'EJd>

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'Si

6.

..:>1:-+,...... ."n..v \\ At'\\" £IV 4 Li2;~ %;,f,rJj tfu¥i! ~ 10.~~ ~ldt1(.l $P--O '1-().-{o 11.=;(& r,u"w,"- slto ~/O -12. $-teV'c.. ShQ..ffi.1' J:... st""'~+SH* i...f-Id-~/() __ ~3. 13, 1\\ R~iF;I>"1 5i.tFf fr/

14.

C~fU.- D/~ fj'£~ ~ -:J5*'1)lWAe.~ ~\\if\\ABb< ~ I.J W"t:/YL NOTES: ~~C 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 week(s) of as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee, I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised. 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of ?I)./O . 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. DATE SIGNATURE(2) DATE NOTE ?4b ______________________4J4e / (\\ A14w-q p-it io 1-7/0 (L4-&L/ - Jo ft9 -mhi----- i-s-io PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1)

1. Q)s k.

&6 2. 1an Lj/E Cx:tAft-. U-4.j hS/, 3 .,tt/ Cpc pUtcbi / / f

4. &pD( &OlJ4 tcp,,.-f $r6)rLlSf

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.4tt-..--- 14. 44X . 7- #%- 15. 77 V/AJ Vo S, NOTES: I 9//° 0kM j (oyru efd 44 (24C ( 0 )c//d @) h laid aM eced eseose hs 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 week(s) of 3/j.ol{) 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 3h4/6. 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 SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE .:.~ ff;i~~:t\\;,/qsJ"'~' (!)~)(~ ~J.~~ t~6° ~':~". "<<p,,,<<- "n. 2"f":': ~ Jj~'~ '1- 'i-lD .:tldi,,.J):t"""~...,.. ( S"prIJ\\Srf" 1~1~o 1 Jf-~..fO ~ S./+,h_ (?ro... <~~. r'l*o9 ~~~ 't;Z': -f-:-L¥-"'- .h , - ??jklf - l:/riJJ V-- A,II if;

19..... 'x'.. A --~y"--

.!::::::=!I.~n~$"~rp)"~ (/~t:'-_qrzzc(7o--(..L /Z.-{Y'l /4J.t£~~' ~ '~w ~~.J.JJvJ . ) . ~¥.. li;IIO~i,!,'7 '- . 'Pr;V;'[Z;-;:-j%- .' 3~ ~:; c ~ ~~~r-lO= \\ ;; f.;~; 10 I. 'f In/ 07-Q/LM !-<:;r.L I-I1I'/J 2 f" q rl ~Le~f- /!,~ ~ Z 0 '"','"., (Lor>. tJ..d.f.~'::" /J.;""" =r!, &,;;. w~, A.e w~< {~OOf4 C",/w. (Or.V/I((J(lJ)C~Jlul (J'f:f'I'l/.-..ut "I.. A.Jf!-l(?:cJ h,'1"\\. - lold k C-/()4.(c( ej,,'i-CC1rr wi A/J-1"l'1~ht.e'\\. f: C:O p-ec.,;~veJ f'e.s,00nse::- l..Ji<..c h"s'l.' .t-,,<r\\ -e j hie"fS I ~x..C: ""'- <: 0"r'f"O ~,'t'-e C OVlcQ...-nf. ES-201, Page 27 of 28

ES-201 Examination Security Agreement Form ES-201-3 1. Pre-Examination acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 0312912010 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised. 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 03/2912010. 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. 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SlGNAT)RE (2) DATE NOTE 4/ 14. 15. NOTES: / ( 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 03/29/2010 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 03/29/2010. 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 DATE NOTE ~: 4,t, 41< Cl=*-~=-----j/;rlo~ ~. fI-

==

5.

b2

6.

7.

8.

9.

10. ______

11.

12.

13.

14.

15.

NOTES: 1-5;3 "-<i!d -('..>/' Ife' -'(I<a......,'.<10.-(.CJv.. 0_ /7<Prcx ~ s."h("t".f--.

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 03/2912010 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 requirerrients (as documented in the facility licerise&s procedures) and understand that violation of the conditions of (his aeement 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 unauthorizedpersons any information concerning the NRC licensing examinatLons administered during the week(s) of 03129/2010. 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. PRINTEONAME JOBTITLE/RESPONSIBILITY SIGNATURE(1) DATE SIGNATtJRE(2) DATE NOTE 1 U.diV4ij& 1 6 NOTES: C C C C C 1 -1 o -1 ]) r IJ lSI f\\l 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 03/29/2010 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, evatuate, or provide performance fee{!back 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 tralrling content or provide direct or indirect feedback), Furthermore, I am aware of the physical security measures and requirements (as documented in the fadlity Ilcensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations andfor 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 examinattons administered during the week(s) of 03/29/2010. From the date that I erltered into this security agreement until the completion of examination administration, I did not instruct, evatuate, 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 J RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

tk&u /.IeWe/(.,,;

tf<<ujrr.f1M.J"Wt 1fII"_fiIV ~ <tfPb_

3.

4. _______________________________________ _

5. _______________________________________

6. _______________________________________ _

7, 8.________ 9.________ 10.. ________ 11.,________

12.

13.

14,

15.

NOTES: c c ~ ~ c c C l C f'I, C f'I

ES-201 Examination Security Agreement Form ES-201-3 1. Pre-Examlnation I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and!or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised. 2. Post-ExamInation To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE ffe! i

,2I,W72 YZ NOTES: g) / 4 V 4 AJ A)ø 2.. ES-201, P 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 week( s) of as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility 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.

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

1. $:,,\\;1 D2(JI'~i I-

2.

I JOB TITLE / RESPONSIBILITY SIGNATURE (1) /.0',)<2I'D-1;) ;(1,vT t1cv/l';k)cl __________ _

3. ______

4.

5. _________ _

6.

7. ________ _

8.

9. ___________ _

10.

11. ________ _

12.

13. _________ _

14.

15.:==--_____ _ NOTES: f) i*:P1df~~4~t4J /,J;v;'e'?tUv feJ"\\,tf-+j/C-'l\\.;gz:.. ES-201, P 27 of 28 DATE SIGNATURE (2) DATE NOTE .;Ztjlz1l.1J/,JliLl ~ 0

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 3129/10 Examination Level: RO SRO El Operating Test Number: I Administrative Topic Type Describe activity to be performed (see Note) Code* Admin-114, Mode Change Verification for Mode 1&2 Conduct of Operations D,S entry GEN 2.1.25 (3.9/4.2) PT/1/A/0600/OO1B, End. 13.23 (Both) (Simulator) (20 mm) Admin-113, Calculate an Estimated Critical Rod Position Conductof Operations D,R PT/1!A!1103/015 (Reactivity Balance Procedure) End. GEN 2.1.19 (3.9/3.8) 13.4 (Computerized ECP Calculation) (RO Only) (17 Minutes) Admin-207 Perform SG Downcomer Temperature Surveillance Equipment Control N,S OP/i/Ni 105/014 End 4.1 (Mode 1&2) and End. 4.16 GEN 2.2.12 (3.7/4.1) (Channel Check Of OTSG Downcomer Temperatures) (RO Only) N/A Radiation Control ADMIN-402, Perform Actions for Medical Emergency RP/1 000/01 6, End. 4.1 (Medical Response) Emergency Procedures/Plan D,C (RO Only) (15 mm) Gen 2.4.39 (3.9/3.8) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (N)ew or (M)odified from bank ( 1) (P)revious 2 exams ( 1; randomly selected) ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 3/29/10 Examination Level: RO~ SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code* Admin-114, Mode Change Verification for Mode 1 &2 Conduct of Operations D,S entry GEN 2.1.25 (3.9/4.2) PT/1/A/0600I001 B, Enel. 13.23 (Both) (Simulator) (20 min) Admin-113, Calculate an Estimated Critical Rod Conduct of Operations Position D,R PT/1/A/1103/015 (Reactivity Balance Procedure) Enc!. GEN 2.1.19 (3.9/3.8) 13.4 (Computerized ECP Calculation) (RO Only) (17 Minutes) Admin-207 Perform SG Downcomer Temperature Equipment Control Surveillance N,S OP/1/A/11 05/014 End 4.1 (Mode 1 &2) and Enc!. 4.16 GEN 2.2.12 (3.7/4.1) (Channel Check Of OTSG Downcomer Temperatures) (RO Only) Radiation Control N/A ADMIN-402, Perform Actions for Medical Emergency Emergency Procedures/Plan D,C RP/1 000/016, Enc!. 4.1 (Medical Response) Gen 2.4.39 (3.9/3.8) (RO Only) (15 min) 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 (:0; 3 for ROs; :0; 4 for SROs & RO retakes) (N)ew or (M)odified from bank (~ 1) (P)revious 2 exams (:0; 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 3129110 Examination Level: RO SRO L1 Operating Test Number: I Administrative Topic Type Describe activity to be performed (see Note) Code* Admin-114, Mode Change Verification for Mode 1&2 Conduct of Operations D entry GEN 2.1.25 (3.9/4.2)

PT/l/AIO600IOO1B, End. 13.23 (Both) (Simulator) (20 mm) Conduct of Operations N,R Admin-117, Evaluate SSF-ASW operability based on GEN 2.1.7 (4.4/4.7) Pressurizer Relief Valve leakage PT!2/A/0610/001 (Reactor Coolant Leakage) Attach. 13.5 (Pzr Relief Valve Leakage Calculation) (SRO Only) Group Activity Admin-203, Complete Plant Configuration Sheet Equipment Control D,R GEN 2.2.18 (2.6/3.9) (Calculate Time to Core Boil) S. D. 1.3.5 Attachment 9.3A (SRO only) (group activity) (1 1 mm) Radiation Control M,R Admin-303, Stay time calculation GEN 2.3.7 (3.5/3.6) NSD-507, Radiation Protection (SRO Only) (13 minutes) Emergency Procedures/Plan D,R Admin-405, Determine Emergency Classification GEN 2.4.41 (2.9/4.6) and Protective Action Recommendations RP/0/B/1 000/01, RP/0/B/1 000/02 BASIS Document (Volume A, Section D of the Emergency Plan) (SRO Only) (20 minutes) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (N)ew or (M)odified from bank ( 1) (P)revious 2 exams ( 1; randomly selected) ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 3/29/10 Examination Level: RO D SROG Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code* Admin-114, Mode Change Verification for Mode 1&2 Conduct of Operations D,S entry GEN 2.1.25 (3.9/4.2) PT/1/A/06001001 S, Ene!. 13.23 (Both) (Simulator) (20 min) Conduct of Operations N,R Admin-117, Evaluate SSF-ASW operability based on GEN 2.1.7 (4.4/4.7) Pressurizer Relief Valve leakage PT/2/A/0610/001 (Reactor Coolant Leakage) Attach. 13.5 (pzr Relief Valve Leakage Calculation) (SRO Only) Group Activity Equipment Control D,R Admin-203, Complete Plant Configuration Sheet GEN 2.2.18 (2.6/3.9) (Calculate Time to Core Boil) S. D. 1.3.5 Attachment 9.3A (SRO only) (group activity) (11 min) Radiation Control M,R Admin-303, Stay time calculation GEN 2.3.7 (3.5/3.6) NSD-507, Radiation Protection (SRO Only) (13 minutes) Emergency Procedures/Plan D,R Admin-405, Determine Emergency Classification GEN 2.4.41 (2.9/4.6) and Protective Action Recommendations RP/0/B/1 000/01, RP/0/B/1000/02 BASIS Document (Volume "A", Section "0" of the Emergency Plan) (SRO Only) (20 minutes) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

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

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: March 29, 2010 Exam Level: RO X SRO-l SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. CRO-108 Perform Reactor Manual Trip Test PTI1IAIO3O5/00i (Reactor Manual Trip Test) N, S, L 1 014 A4.01 (3.3/3.1)_(20_mm) b. CRO-207 Pressure makeup to CFT with failure.7 of OP/i/Ni 104/01 M, A, S 2 006 A1.i3 (3.5/3.7)_(10_mm) c. CR0- 301 Verify HPI flow following LBLOCA with degraded HPI N,A,S,E, 3 EP/i/N1800/00i (Emergency Operating Procedure) EN Rule 2 (Loss Of SCM) BW/E13 EA1.i (3.4/3.2)_(10_mm) d. CRO-096, Align ECCS Suction from Emergency Sump (ILP-21 Failed Closed) D, A, 5, L, E, 4P EPI1IN1800IOO1 (Emergency Operating Procedure) EN End. 5.12 (ECCS Suction Swap to RBES) BW/E08 EA1.i (4.0/3.7)_(15_mm) e. CRO-013, Align MDEFDWP Suction To The Hotwell And Feed The Steam Generators D, 5, L, E 4S EP/1/Ni 800/001 (Emergency Operating Procedure), End. 5.9 (Extended EFDW Operation) APEO54AA1.0i (4.5/4.4)_(10_mm) f. CRO-601, Synchronization with the grid following a load rejection D, S 6 API1, (Unit Runback) 062_A4.07_(31*131*)_(10_mm) g. CRO-085, Adjust Radiation Monitor Setpoints OP/1-2/A11104/018, GWD System, End. 4.9 &4.i0 D, 5, P 7 PT/0/A1230/01, (Radiation Monitor Check) 073 A4.01 (3.9/3.9)_(8_mm) h. CRO-800, Perform Required Actions for an Intake Canal Dam Failure D, S 8 AP/13, (Dam Failure) 075 A2.01 (3.0*/3.2) (20 mm) ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: March 29, 2010 Exam Level: RO X SRO-I D SRO-U D Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function

a. CRO-108 Perform Reactor Manual Trip Test PT/1/A/0305/001 (Reactor Manual Trip Test)

N,S,L 1 014 A4.01 (3.3/3.1) (20 min)

b. CRO-207 Pressure makeup to CFT with failure.7 of OP/1/A/1104/01 M,A,S 2

006 A1.13 (3.5/3.7) (10 min)

c. CRO-301 Verify HPI flow following LBLOCA with degraded HPI N,A, S, E, 3

EP/1/A/1800/001 (Emergency Operating Procedure) EN Rule 2 (Loss Of SCM) BW/E13 EA1.1 (3.4/3.2) (10 min)

d. CRO-096, Align ECCS Suction from Emergency Sump (1 LP-21 Failed Closed)

D, A, S, L, E, 4P EP/1/A/18001001 (Emergency Operating Procedure) EN Encl. 5.12 (ECCS Suction Swap to RBES) BW/E08 EA1.1 (4.0/3.7) (15 min)

e. CRO-013, Align MDEFDWP Suction To The Hotwell And Feed The Steam Generators D,S,L,E 4S EP/1 1 A/18001001 (Emergency Operating Procedure),

Enel. 5.9 (Extended EFDW Operation) APE054 AA 1.01 (4.5/4.4) (10 min)

f.

CRO-601, Synchronization with the grid following a load rejection D,S 6 AP/1, (Unit Runback) 062 A4.07 (3.1*/3.1*) (10 min)

g. CRO-085, Adjust Radiation Monitor Setpoints OP/1-2/A/1104/018, GWD System, Ene!. 4.9 & 4.10 D,S,P 7

PT/0/A/230/01, (Radiation Monitor Check) 073 A4.01 (3.9/3.9) (8 min)

h. CRO-800, Perform Required Actions for an Intake Canal Dam Failure D,S 8

AP/13, (Dam Failure) 075 A2.01 (3.0*/3.2) (20 min)

In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i. NLO-200 Align HPI Pump Suction to BWST During a Blackout D, R, E 2 EP/2/AJl 800/001 (Emergency Operating Procedure) End 5.7 (HPI Pump Operations from ASW Pump Switchgear) APE 022 G2.4.35 (3.8/4.0)_(15_mm) j. CRO-401, Aligning SSF-ASW for SG Feed EP/2/A/1800/001 (Emergency Operating Procedure) D, A, E 4S End. 5.34, (Aligning SSF-ASW for SG Feed) APE_054_AA1.01_(4.5/4.4)_(10_mm) k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) End. 5.2, (Restoration of D, A, E 7 ICS AUTO Power) BW/A02 AK3.2 (3.7/4.0) (16 mm) All RD and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RD I SRO-l I SRO-U (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irectfrombank 9/814 (E)mergency or abnormal in-plant 1 /

1 I 1 (EN)gineered safety feature - I / 1 (control room system) (L)ow-Power I Shutdown I I I I 1 (N)ew or (M)odified from bank including 1 (A) 2 I 2 I 1 (P)revious 2 exams 3 I 3 / 2 (randomly selected) (R)CA (S)imulator In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

NLO-200 Align HPI Pump Suction to BWST During a Blackout D,R,E 2 EP/2/A/1800/o01 (Emergency Operating Procedure) Encl 5.7 (HPI Pump Operations from ASW Pump Switchgear) APE 022 G2.4.35 (3.8/4.0) (15 min)

j.

CRO-401, Aligning SSF-ASW for SG Feed EP/2/A/18001001 (Emergency Operating Procedure) D,A, E 4S End. 5.34, (Aligning SSF-ASW for SG Feed) APE 054 AA 1.01 (4.5/4.4) (10 min)

k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) Encl. 5.2, (Restoration of D,A, E 7

ICS AUTO Power) BW/A02 AK3.2 (3.7/4.0) (16 min) 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 / SRO-I / SRO-U (A)lternate 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 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: March 29, 2010 Exam Level: RD SRO-l X SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. CRO-108 Perform Reactor Manual Trip Test PT/11A10305/001 (Reactor Manual Trip Test) N, S, L 1 014 A4.0l (3.3/3.1) b. CRO-207 Pressure makeup to CFT with failure.7 of OP/1/A/1104/01 M, A, S 2 006 A1.13 (3.5/3.7) c. CR0- 301 Verify HPI flow following LBLOCA with degraded HPI N, A, S, E, 3 EP/1/A/1800/O01 (Emergency Operating Procedure) EN Rule 2 (Loss Of SCM) BW/E13 EA1.1 (3.4/3.2) d. CRO-096, Align ECCS Suction from Emergency Sump (ILP-21 Failed Closed) D, A, S, L, E, 4P EP/1/A/1800/001 (Emergency Operating Procedure) EN End. 5.12 (ECCS Suction Swap to RBES) BW/E08 EA1.1 (4.0/3.7)_(15_mm) e. CRO-013, Align MDEFDWP Suction To The Hotwell And Feed The Steam Generators D, 5, L, E 4S EP/1/A11800/001 (Emergency Operating Procedure), End. 5.9 (Extended EFDW Operation) APEO54AA1.01 (4.5/4.4)_(10_mm) f. CRO-601, Synchronization with the grid following a load rejection D, S 6 AP/1, (Unit Runback) 062 A4.07 (3 j*/3 1*)_(10_mm) g. CRO-085, Adjust Radiation Monitor Setpoints OP/1-2/A/1104/018, GWD System, End. 4.9 & 4.10 D, 5, P 7 PT/0/A1230/01, (Radiation Monitor Check) KA: 073 A4.01 (3.9/3.9)_(8_mins) h.NIA 8 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: March 29, 2010 Exam Level: RO 0 SRO-I X SRO-U 0 Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function

a. CRO-108 Perform Reactor Manual Trip Test PT/1/A/0305/001 (Reactor Manual Trip Test)

N,S,L 1 014 A4.01 (3.3/3.1)

b. CRO-207 Pressure makeup to CFT with failure.7 of OP/1/A/11 04/01 M,A,S 2

006 A 1.13 (3.5/3.7)

c. CRO-301 Verify HPI flow following LBLOCA with degraded HPI N,A, S, E, 3

EP/1/A/1800/001 (Emergency Operating Procedure) EN Rule 2 (Loss Of SCM) BW/E13 EA1.1 (3.4/3.2)

d. CRO-09S, Align ECCS Suction from Emergency Sump (1 LP-21 Failed Closed)

D, A, S, L, E, 4P EP/1/A/1800/001 (Emergency Operating Procedure) EN Encl. 5.12 (ECCS Suction Swap to RBES) BW/E08 EA1.1 (4.0/3.7) (15 min)

e. CRO-013, Align MDEFDWP Suction To The Hotwell And Feed The Steam Generators D,S,L,E 4S EP/1/A/1800/o01 (Emergency Operating Procedure),

Encl. 5.9 (Extended EFDW Operation) APE054 AA 1.01 (4.5/4.4) (10 min)

f.

CRO-601, Synchronization with the grid following a load rejection D,S 6 AP/1, (Unit Runback) 062 A4.07 (3.1*/3.1*) (10 min)

g. CRO-085, Adjust Radiation Monitor Setpoints OP/1-2/A/11 04/018, GWD System, Encl. 4.9 & 4.10 D,S,P 7

PT/0/A/230/01, (Radiation Monitor Check) KA: 073 A4.01 (3.9/3.9) (8 mins)

h. N/A 8

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. NLO-200 Align HPI Pump Suction to BWST During a Blackout D, R, E 2 EP/2/AIl 800/001 (Emergency Operating Procedure) End 5.7 (HPI Pump Operations from ASW Pump Switchgear) APEO22G2.4.35 (3.8/4.0)_(15_mm) j. CRO-401, Aligning SSF-ASW for SO Feed EP/2/A11800/001 (Emergency Operating Procedure) D, A, E 4S End. 5.34, (Aligning SSF-ASW for SG Feed) APE_054_AA1.01_(4.5/4.4)_(10_mm) k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of lOS Power) End. 5.2, (Restoration of D, A, E 7 lOS AUTO Power) BW/A02 AK3.2 (3.7/4.0) (16 mm) All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type codes criteria for RO I SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank 91814 (E)mergency or abnormal in-plant 1 I 1 I 1

(EN)gineered safety feature - I I 1 (control room system) (L)ow-Power I Shutdown 1 I 1 I 1 (N)ew or (M)odified from bank including 1 (A) 2 I 2 I 1 (P)revious 2 exams 3 / 3 I 2 (randomly selected) (R)CA 1I1/1 (S)imulator In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

NLO-200 Align HPI Pump Suction to BWST During a Blackout D,R,E 2 EP/2/A/1800/001 (Emergency Operating Procedure) Ene! 5.7 (HPI Pump Operations from ASW Pump Switchgear) APE022G2.4.35 (3.8/4.0) (15 min)

j.

CRO-401, Aligning SSF-ASW for SG Feed EP/2/A/1800/o01 (Emergency Operating Procedure) D,A, E 4S Encl. 5.34, (Aligning SSF-ASW for SG Feed) APE 054 AA 1.01 (4.5/4.4) (10 min)

k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) Encl. 5.2, (Restoration of D,A, E 7

ICS AUTO Power) BW/A02 AK3.2 (3.7/4.0) (16 min) 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 / SRO-I / SRO-U (A)lternate 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 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: March 29, 2010 Exam Level: RO SRO-I SRO-U X Operating Test No.: Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. CRO-108 Perform Reactor Manual Trip Test PT/l/A10305/001 (Reactor Manual Trip Test) N, S, L 014 A4.01 (3.3/3.1) b. NIA c. NIA d. CRO-096, Align ECCS Suction from Emergency Sump (ILP-21 Failed Closed) ID, A, S, L, E, 4P EP/1/A/1800/001 (Emergency Operating Procedure) EN End. 5.12 (ECCS Suction Swap to RBES) BW/E08 EA1.1 (4.0/3.7)_(15_mm) e. NIA f. CRO-601, Synchronization with the grid following a load rejection 6 AP/1, (Unit Runback) D,S 062 A4.07 (3.1*13.1*) (10 mm) g. NIA h. NIA ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: March 29, 2010 Exam Level: RO 0 SRO-I 0 SRO-U X Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function

a. CRO-108 Perform Reactor Manual Trip Test PT/1/A/0305/001 (Reactor Manual Trip Test)

N,S,L 1 014 A4.01 (3.3/3.1)

b. N/A

c.

N/A

d. CRO-096, Align ECCS Suction from Emergency Sump (1 LP-21 Failed Closed)

D, A, S, L, E, 4P EP/1/A/1800/001 (Emergency Operating Procedure) EN Encl. 5.12 (ECCS Suction Swap to RBES) BW/E08 EA1.1 (4.0/3.7) (15 min)

e. N/A

f.

CRO-601, Synchronization with the grid following a load rejection 6 AP/1, (Unit Runback) D,S 062 A4.07 (3.1*/3.1*) (10 min)

g. N/A

h. N/A

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. NLO-200 Align HPI Pump Suction to BWST During a Blackout D, R, E 2 EP/2/AI1 800/001 (Emergency Operating Procedure) End 5.7 (HPI Pump Operations from ASW Pump Switchgear) APEO22 G2.4.35 (3.8/4.0)_(15_mm) j. NIA k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) End. 5.2, (Restoration of D, A, E 7 ICS AUTO Power) BW/A02 AK3.2 (3.7/4.0) (16 mm) All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-l I SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrombank 91814 (E)mergency or abnormal in-plant 1 I 1 I 1

(EN)gineered safety feature - I / 1 (control room system) (L)ow-Power I Shutdown 1 I 1 I 1 (N)ew or (M)odified from bank including I (A) 2 I 2 I 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected) (R)CA (S)imulator In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

NLO-200 Align HPI Pump Suction to BWST During a Blackout D,R,E 2 EP/2/A/18001001 (Emergency Operating Procedure) Encl 5.7 (HPI Pump Operations from ASW Pump Switchgear) APE022 G2.4.35 (3.8/4.0) (15 min)

j.

N/A

k. NLO-700, Restoration of les AUTO Power AP/23 (Loss of ICS Power) Encl. 5.2, (Restoration of D,A, E 7

ICS AUTO Power) BW/A02 AK3.2 (3.7/4.0) (16 min) 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 1 SRO-I 1 SRO-U (A)lternate 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 ~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: Oconee Date of Examination: 3129/2010 Operating Test Number: 1 Initials

1. General Criteria a

b* c# a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution). Y1 1 b. There is no day-to-day repetition between this and other operating tests to be administered during this examination. c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1.a.) d. Overlap with the written examination and between different parts of the operating test is within acceptable limits. e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.

2. Walk-Through Criteria a.

Each JPM includes the following, as applicable: fr%J 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

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 4j )k/ 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.

Printed Name / Signature Date a. Author re U 2 tD b. Facility Reviewer(*) jQ4 c. NRC Chief Examiner () )2Wh (03, l_rk d. NRC Supervisor NOTE: The facility signature is not applicable for NRC-developed tests. Independent NRC reviewer initial items in Column c; chief examiner concurrence required. ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Oconee Date of Examination: 3/29/2010 Operating Test Number: 1 Initials

1. General Criteria a

b* c#

a.

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

b.

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

c.

The operating test shall not duplicate items from the applicants' audit test(s). (see Section D.1.a.) If'./ ~ v ~vJ

d.

Overlap with the written examination and between different parts of the operating test is within C/ y acceptable limits. ]j 'J

e.

It appears that the operating test will differentiate between competent and less-than-competent 145 ~w' ~ ~ applicants at the designated license level. v

2. Walk-Through Criteria L""

a.

Each JPM includes the following, as applicable: 17 ~ 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 Ti l)vV II outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance \\ I criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified I~ on those forms and Form ES-201-2.

3. Simulator Criteria

-/, "~ r roW 5 The associated simulator operating tests (scenario sets) have been reviewed in accordance with '-7 Form ES-301-4 and a copy is attached. Printed Name 1 Signature Date

a.

Author c.\\~~~~rC- ~. U\\~-e.r.\\p~ ('Qp--- 3 -?-2-{O

b.

Facility Reviewer(*) ~'i"\\~ WAh \\t-~vJW / f ~QI *1 / ill- ~-;>>. - /t1 '"'If '/ NRC Chief Examiner (#) tb~ W. ~i6/1 I~ h l LL,d', S f?-~ lZIJ J 0

c.

r/ltt\\.~ ~ Tr '-tUf't: -I NRC Supervisor )JJU:.A9w.. ~ W Ii)UANAJ / 0 b\\ ARIA. 03['2'tL Ie)

d.

-A I NUfW.W ~l t>VV1I NOTE: The facility signature is not applicable for NRC-developed tests. Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Oconee Date of Exam: 3/29/2010 Scenario Numbers: 1 / 2 / 3 / 4 Operating Test No.: 1 QUALITATIVE ATTRIBUTES Initials

a b* c# 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. 2. The scenarios consist mostly of related events. 3. Each event description consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable) 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. 5. The events are valid with regard to physics and thermodynamics. 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain

complete evaluation results commensurate with the scenario objectives. 7. If time compression techniques are used, the scenario summary clearly so indicates. /,/ Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. 8. The simulator modeling is not altered. 9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios. 10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301. 11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios). 12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios). 13. The level of difficulty is appropriate to support licensing decisions for each crew position. Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes 1. Total malfunctions (58) 8 / 7 / 9 / 5 2. Malfunctions after EOP entry (12) 2 / 2 / 2 / 1 3. Abnormal events (24) 6 / 3/ 4 / 2 4. Major transients (12) 1 / 1 / 1 / 1 5. EOP5 entered/requiring substantive actions (12) 2 / 2 / 2 / 2 6. EOP contingencies requiring substantive actions (02) 1 / 1 / 2 / 1 7. Critical tasks (23) 4 / 2 / 4 / 2 ES-301 Simulator Scenario Quality Checklist Form ES-301-4 I~ Date of Exam: 3/29/2010 Scenario Numbers: 1/2/3/4 Operating Test No.: 1 QUALITATIVE ATTRIBUTES Initials a b* c#

1.

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

2.

The scenarios consist mostly of related events. Q/ ~

3.

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

4.

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario Iv Vuvv J ~ without a credible preceding incident such as a seismic event. v ~IA/ r.t-'

5.

The events are valid with regard to physics and thermodynamics. I~ >6

6.

Sequencing and timing of events is reasonable, and allows the examination team to obtain IV ~vvI ~ complete evaluation results commensurate with the scenario objectives. f:;/ ~ ~v ~

7.

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

8.

The simulator modeling is not altered. CL rrrJ {

9.

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

10.

Every operator will be evaluated using at least one new or significantly modified scenario. I~ 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 ~ W ~~ (submit the form along with the simulator scenarios).

12.

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

13.

The level of difficulty is appropriate to support licensing decisions for each crew position. '7[ I~~ ~'l Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1.

Total malfunctions (5-8) 8 / 7 / 9/5 c.. ~~ lJ J-,

2.

Malfunctions after EOP entry (1-2) 2/ 2/ 2 / 1 V Il~' rJlII

3.

Abnormal events (2-4) 6/ 3/ 4/2 If'/ 1~"1l f1

4.

Major transients (1-2) 1/1/1/1 I~ ~ Ix.

5.

EOPs entered/requiring substantive actions (1-2) 2 / 2 / 2/2 I<,/, f}vl ~ ~l

6.

EOP contingencies requiring substantive actions (0-2) 1 / 1 / 2 / 1 t!:/ ~ ~ ~

7.

Critical tasks (2-3) 4 / 2/4/2 ~ bJ I~ i"

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Oconee Date of Exam: 3/2912010 Operating Test No.: 1 A E Scenarios P V 1 2 3 Spare T M P E I L N CREW CREW CREW CREW T N I T POSfl1ON POSfl1ON POSfl1ON POSmON A C S A B S A B S A B S A BL 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 T P R lU E RD RX 6 2 110 SROI NOR 1 iii I/C 4,7 3,4 2,4,7 4 4 4 2 SRD-U MAJ 8 6 8 7 2 2 1 TS 022 RD RX x NOR 1 1 111 SRO-l I/C 2,3 2,3,5 1, 3,4 4 4 2 D 3,5 L MAJ 9 6 8 5 221 TS 022 oi NOR ii I/C 2,3 2,3,4 1,2 3,4 4 4 2 SRO-U 4,7 5 3, MAJ 9 6 8 5 221 TS 5 2,3 4,5,7 1,3 0 2 2 Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-i event numbers for each event type; TS are not applicable for RD applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position. 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns. ES-301 Transient and Event Checklist Form ES-301-5 Facility: Oconee Date of Exam: 3/29/2010 Operating Test No.: 1 A E Scenarios P V 1 2 3 Spare T M P E 0 I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I C S A B S A B S A B S A B M 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 T P R I U E RO RX 6 2 1 1 0 X NOR 1 SRO-I 1 1 1 D I/C 4, 7 3,4 2,4,7 4 4 4 2 SRO-U MAJ 8 6 8 7 2 2 1 D TS 0 2 2 RX RO 1 1 0 X NOR 1 1 1 1 1 SRO-I I/C 2,3 2,3,5 1, 3,4 4 4 2 D 3,5 SRO-U D MAJ 9 6 8 5 2 2 1 TS 0 2 2 RO RX 6 2 1 1 0 D NOR 1 1 1 1 1 1 1 SRO-I D IIC 2,3 2,3,4 1,2 3,4 4 4 2 SRO-U 4,7 5 3,4 X 5, 7 MAJ 9 6 8 5 2 2 1 TS 5 2,3 4,5,7 1,3 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 (IIC) 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 IIC malfunctions required for the ATC position.

2.

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

3.

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

ES-301 Competencies Checklist Form ES-301-6 Facility: Oconee Date of Examination: 03/29/2010 Operating Test No.: 1 APPLICANTS RO RO RO SRO-I SRO-I SRO-I D SRO-U D SRO-U D SRO-U Competencies N4O____ SNIO SCEN!P____ 1 2 3 p 1 2 3 sp 1 2 3 sp 4,734 24 45 23 23 13 13 23 23 12 13 I nterpret/Diagnose Events and Conditions 6 7 7 8 5 5 6 5 8 5 4 5 4 5 3 4 4 5 9 7 9 8 67 56 78 9 4 24 245 13 13 12 12 12 Comply With and 6,7 46 78 34 56 58 5 34 34 34 34 UseProcedures(1) 8

9 58 7 9 56 56 56 8 78 78 9 4 24 245 13 Operate Control 6, 7 4 6 7 8 3 4 5 6 4 5 5 Boards (2) 8 7 9 5 8 7 7 8 9 45 13 12 234 12 23 13 12 12 12 12 12 Communicate and Interact 67 46 47 34 56 45 345 34 34 34 34 8 7 89 58 7 78 56 56 56 5 9 78 788 78 9 12 12 12 12 Demonstrate Supervisory Ability (3) 3 4 56 56 56 5 78 78 78 9 5 23 47 13 Comply With and 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 Competencies Checklist Form ES-301-6 Facility: Oconee Date of Examination: 03/29/2010 Operating Test No.: 1 APPLICANTS RO ~ RO ~ RO 0 SRO-I SRO-I SRO-I 0 SRO-U 0 SRO-U 0 SRO-U ~ Competencies SCENARIO SCENARIO SCENARIO 1 2 3 sp 1 2 3 sp 1 2 3 I nterpretiDiag nose 4, 7 34 24 45 23 23 1 3 1 3 23 23 1 2 Events and Conditions 67 78 5 56 5 8 5 45 45 34 9 7 9 8 67 56 78 9 Comply With and 4,5 1 3 24 245 12 23 1 3 1 3 1 2 12 12 Use Procedures (1) 6, 7 46 78 34 56 5 8 5 34 34 34 8 7 9 58 7 9 56 56 56 8 78 78 9 Operate Control 4,5 1 3 24 245 1 2 23 1 3 1 3 Boards (2) 6, 7 46 78 34 56 45 5 8 7 9 5 8 7 78 9 Communicate 45 1 3 12 234 1 2 23 1 3 1 2 12 1 2 12 and Interact 67 46 47 5 34 56 45 345 34 34 34 8 7 89 5 8 7 78 56 56 56 9 78 788 78 9 Demonstrate 12 1 2 12 Supervisory Ability (3) 34 34 34 56 56 56 78 78 78 9 Comply With and 5 23 47 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. sp 1 3 45 1 2 34 5 12 34 5 1 2 34 5 1 3

ES-401, Rev. 9E PWR Examination Outline Form ES-401-2 Facility: Oconee 2010-301 RO K/A Category Points SRO-Only Points Tier Group

KKKjKKKAAAAG A2 G* ITotal 1 2 3j4 5 6 1 2 3 4 Total I 1. 1 3 3 3 3 3 3 18 3 3f 6 Emergency &

Abnormal Plant 2 1 1 1 N/A 2 2 N/A 2 9 2 2 4 Evolutions

TierTotals 4 4 4 5 5 5 27 5 5 10 1 13332323323 28 3 2 5 2. Plant 2 11111101111 10 2 1 3 Systems TierTotals 24443424434 38 5 3 8

3. Generic Knowledge and Abilities 1

2 3 4 10 1 2 3 4 7 Categories 2 3 3 2 2 2 1 2 Note:1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e. except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements. 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution. e. Absent a plant-specific priority, only those K/As having an importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 7 The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G on the SRO only exam, enter it on the left side of Column A2 for Tier 2, Group 2. Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. ES-401, Rev. 9E PWR Examination Outline Form ES-401-2 I Facility: Oconee 2010-301 F'li/Al.- I RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1.

1 3 3 3 3 3 3 18 3 3 6 Emergency & Abnormal Plant 2 1 1 1 N/A 2 2 N/A 2 9 2 2 4 Evolutions Tier Totals 4 4 4 5 5 5 27 5 5 10 1 1 3 3 3 2 3 2 3 3 2 3 28 3 2 5

2.

Plant 2 1 1 1 1 1 1 0 1 1 1 1 10 2 1 3 Systems Tier Totals 2 4 4 4 3 4 2 4 4 3 4 38 5 3 8

3. Generic Knowledge and Abilities 1

2 3 4 10 I 1 I 2 I 3 I 4 I 7 I Categories 2 3 3 2 2 2 1 2 Note:1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals" in each KIA category shall not be less than two).

2.

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

3.

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

4.

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

e.

Absent a plant-specific priority, only those KlAs having an importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories. 7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. S. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401, Rev. 9 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Punt Evolutions - Tier 1/Group 1 (RO / SRO) E/APE#/Name/SafetyFunction K K K A A G KJATopic(s) IR 12312 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1

OO8AK1.01 Knowledge of the operational 3 000008 Pressurizer Vapor Space Accident / 3 X implications of the following concepts as .2/3.7 They apply to a Pressurizer Vapor Space Accident Thermodynamics and flow characteristics of open or leaking valves

OO9EK1.01 Knowledge of the operational 4 2/4 7 000009 Small Break LOCA / 3 X implications of the following concepts as they apply to the small break LOCA: Natural circulation and cooling, including reflux boiling

011 EK2.02 Knowledge of the interrelations 000011 Large Break LOCA / 3 X between the and the following Large Break 2.6/2.7 LOCA: Pumps

011 EG2 4 41 Knowledge of the emergency 2 9/4 6 000011 Large Break LOCA / 3 (SRO) X action level thresholds and classifications

O15AA1 21 Ability to operate and/or monitorthe 000015/17 RCP Malfunctions / 4 X following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Development of natural circulation flow 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System /4

X 025AG2.4.1 1 Knowledge of abnormal condition 4.0/4.2 procedures

026AK3.03 Knowledge of the reasons for the 000026 Loss of Component Cooling Water / 8 X following responses as they apply to the Loss of 4.0/4.2 Component Cooling Water: Guidance actions contained in EOP for Loss of CCW

0262.1.23 Ability to perform specific system and 000026 Loss of Component Cooling Water / 8 X integrated plant procedures during all modes of (SRO) plant operation.

027AK2.03 Knowledge of the interrelations 2 6/2 8 000027 Pressurizer Pressure Control System X between the Pressurizer Pressure Control Malfunction / Malfunctions and the following Controllers and Positioners 027AA2 09 Ability to determine and interpret the 3 5/3 6 000027 Pressurizer Pressure Control System X following as they apply to the Pressurizer Malfunction / 3 (SRO) Pressure Control Malfunctions: Reactor power 029EK3.12 Knowledge of the reasons for the 000029 ATWS / 1 X following responses as the apply to the ATWS: Actions contained in EOP for ATWS ES-401, Rev. 9 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO 1 SRO) E/APE # 1 Name 1 Safety Function K K K A A G KIA Topic(s) IR 1 2 3 1 2 000007 (BW IE02&E 10; CE/E02) Reactor Trip - Stabilization - Recovery 1 1 000008 Pressurizer Vapor Space Accident 1 3 X 008AK1.01 Knowledge of the operational 3.2/3.7 implications of the following concepts as They apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves 009EK1.01 Knowledge of the operational 4.2/4.7 000009 Small Break LOCA 1 3 X implications of the following concepts as they apply to the small break LOCA: Natural circulation and cooling, including reflux boiling X 011 EK2.02 Knowledge of the interrelations 2.6/2.7 000011 Large Break LOCA 13 between the and the following Large Break LOCA: Pumps 000011 Large Break LOCA 1 3 (SRO) X 011 EG2.4.41 Knowledge of the emergency 2.9/4.6 action level thresholds and classifications. X 015AA 1.21 Ability to operate and 1 or monitor the 4.4/4.5 000015/17 RCP Malfunctions 14 following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Development of natural circulation flow 000022 Loss of Rx Coolant Makeup 1 2 000025 Loss of RHR System 14 X 025AG2.4.11 Knowledge of abnormal condition 4.0/4.2 procedures. X 026AK3.03 Knowledge of the reasons for the 4.0/4.2 000026 Loss of Component Cooling Water 1 8 following responses as they apply to the Loss of Component Cooling Water: Guidance actions contained in EOP for Loss of CCW 000026 Loss of Component Cooling Water 1 8 X 0262.1.23 Ability to perform specific system and 4.3/4.4 integrated plant procedures during all modes of (SRO) plant operation. X 027 AK2.03 Knowledge of the interrelations 2.6/2.8 000027 Pressurizer Pressure Control System between the Pressurizer Pressure Control Malfunction 1 3 Malfunctions and the following: Controllers and Positioners X 027AA2.09 Ability to determine and interpret the 3.5/3.6 000027 Pressurizer Pressure Control System following as they apply to the Pressurizer Malfunction 1 3 (SRO) Pressure Control Malfunctions: Reactor power X 029EK3.12 Knowledge of the reasons for the 4.4/4.7 000029 A TWS 1 1 following responses as the apply to the ATWS: Actions contained in EOP for A TWS

029EA2.02 Ability to determine or interpret the 000029 ATWS I 1 (SRO) X following as they apply to a ATWS: Reactor trip 4.2/4.4 alarm 038EK3.01 Knowledge of the reasons for the 000038 Steam Gen. Tube Rupture / 3 X following responses as the apply to the SGTR: 4.1/4.3 Equalizing pressure on primary and secondary sides of ruptured SIG. 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer! 4

054AA1.03 Ability to operate and I or monitor the 000054 (CEIEO6) Loss of Main Feedwater! 4 X following as they apply to the Loss of Main 7 Feedwater (MEW>: AFW auxiliaries, including oil cooling water supply 055EA1.02 Ability to operate and monitor the 000055 Station Blackout / 6 X following as they apply to a Station Blackout: Manual ED/G start (Manual_start_of_Hydro_unit_acceptable) 000056 Loss of Off site Power! 6 057AA2.1 5 Ability to determine and interpret the 000057 Loss of Vital AC Inst Bus / 6 X following as they apply to the Loss of Vital AC 3 8!4 1 Instrument Bus: That a loss of ac has occurred. 058AK1.01 Knowledge of the operational 000058 Loss of DC Power! 6 X implications of the following concepts as they 2.8/3.1 apply to a Loss of DC Power: Battery charger equipment and instrumentation 058G2.4.1 I Knowledge of abnormal condition 000058 Loss of DC Power! 6 (SRO) x procedures 4 0/4 2 000062 Loss of Nuclear Svc Water! 4 X 062AG2.1.20 Ability to interpret and execute 4.6!4.6 procedure steps. 065AA2.07 Ability to determine and interpret the 000065 Loss of Instrument Air / 8 X following as they apply to the Loss of 2.8!3.2 Instrument Air: 077AG2.2.22 Knowledge of limiting conditions 000077 Generator Voltage and Electric Grid X for operations and safety limits 4 0/4 7 Disturbances! 6 W!E04 LOCA Outside Containment! 3 W/E1 I Loss of Emergency Coolant Recirc. I 4

BEO4EA2.2 Ability to determine and interpret the BW!E04 W/E05 Inadequate Heat Transfer X following as they apply to the (Inadequate Heat 3 6/4 4 Loss of Secondary Heat Sink / 4 Transfer): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

BEO4EA2.1 Ability to determine and interpret the BW/E04; W/E05 Inadequate Heat Transfer X following as they apply to the (Inadequate Heat 4.2/4.4 Loss of Secondary Heat Sink /4 (SRO) Transfer) Facility conditions and selection of appropriate procedures during abnormal and emergency operations 000029 ATWS 1 1 (SRO) X 029EA2.02 Ability to determine or interpret the 4.2/4.4 following as they apply to a ATWS: Reactor trip alarm 000038 Steam Gen. Tube Rupture 1 3 X 038EK3.01 Knowledge of the reasons for the 4.1/4.3 following responses as the apply to the SGTR: Equalizing pressure on primary and secondary sides of ruptured S/G. 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer 1 4 000054 (CE/E06) Loss of Main Feedwater 1 4 X 054AA 1.03 Ability to operate and 1 or monitor the 3.5/3.7 following as they apply to the Loss of Main Feedwater (MFW): AFW auxiliaries, including oil cooling water supply 000055 Station Blackout 1 6 X 055EA 1.02 Ability to operate and monitor the 4.3/4.4 following as they apply to a Station Blackout: Manual ED/G start (Manual start of Hydro unit acceptable) 000056 Loss of Off-site Power 1 6 000057 Loss of Vital AC Ins!. Bus 1 6 X 057 AA2.15 Ability to determine and interpret the 3.8/4.1 following as they apply to the Loss of Vital AC Instrument Bus: That a loss of ac has occurred. 000058 Loss of DC Power 1 6 X 058AK1.01 Knowledge of the operational 2.8/3.1 implications of the following concepts as they apply to a Loss of DC Power: Battery charger equipment and instrumentation 000058 Loss of DC Power 1 6 (SRO) X 058G2.4.11 Knowledge of abnormal condition 4.0/4.2 procedures. 000062 Loss of Nuclear Svc Water 1 4 X 062AG2.1.20 Ability to interpret and execute 4.6/4.6 procedure steps. 000065 Loss of Instrument Air 18 X 065AA2.07 Ability to determine and interpret the 2.8/3.2 following as they apply to the Loss of Instrument Air: 000077 Generator Voltage and Electric Grid X 077AG2.2.22 Knowledge of limiting conditions 4.0/4.7 Disturbances 1 6 for operations and safety limits. W/E04 LOCA Outside Containment 1 3 W/E11 Loss of Emergency Coolant Recirc. 14 BW/E04; W/E05 Inadequate Heat Transfer-X BE04EA2.2 Ability to determine and interpret the 3.6/4.4 following as they apply to the (Inadequate Heat Loss of Secondary Heat Sink 1 4 Transfer): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments. BW/E04; W/E05 Inadequate Heat Transfer-X BE04EA2.1 Ability to determine and interpret the 4.2/4.4 following as they apply to the (Inadequate Heat Loss of Secondary Heat Sink 1 4 (SRO) Transfer) Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

BEO5; Steam line rupture-Excessive Heat

BEO5EK2.1 Knowledge of the interrelations Transfer X between the (Excessive Heat Transfer) and the 3.8/4.0 following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 SRO K/A Category Totals: - = 3 3 Group Point Total: 6 BE05; Steam line rupture-Excessive Heat X BE05EK2.1 Knowledge of the interrelations 3.8/4.0 Transfer between the (Excessive Heat Transfer) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 SRO KIA Category Totals: 3 3 Group Point Total: 6

ES-401,Rev.9 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RD / SRO) E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR 1 2312 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2

x

028AA1.07 Ability to operate and I or monitor the following as they apply to the Pressurizer Level Control Malfunctions: Charging pumps maintenance of PZR level (including manual backup) 000032 Loss of Source Range NI / 7(SRO) X 032G2 4 45 Ability to prioritize and 4 1/4 3 interpret the significance of each annunciator or alarm 000033 Loss of Intermediate Range NI / 7(SRO)

X 033AG2.12 Ability to explain :nd apply 3.8/4.0 z.z 000036 (BW/A08) Fuel Handling Accident / 8

x

036AK2.01 Knowledge of the 2.9/3.5 interrelations between the Fuel Handling Incidents and the following: Fuel handling equipment 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9

x

059AK3.03 Knowledge of the reasons for 3.0/3.7 the following responses as they apply to the Accidental Liquid Radwaste Release: Declaration that a radioactive-liquid monitor is inoperable 000060 Accidental Gaseous Radwaste Re!. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8

x

067AA1.05 Ability to operate and I or 3.0/3.1

monitor the following as they apply to the Plant Fire on Site: Plant and control room i 000068 (BW/A06) Control Room Evac. / 8 ES-401, Rev. 9 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO) E/APE # / Name / Safety Function K K K A A G KIA Topic(s) IR 1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 X 028AA 1.07 Ability to operate and lor 3.3/3.3 monitor the following as they apply to the Pressurizer Level Control Malfunctions: Charging pumps maintenance of PZR level (including manual backup) 000032 Loss of Source Range NI /7(SRO) X 032G2.4.45 Ability to prioritize and 4.1/4.3 interpret the significance of each annunciator or alarm 000033 Loss of Intermediate Range NI /7(SRO) X 033AG2.1.2 Ability to explain and apply 3.8/4.0 system limits and 2recau~ns 'Z../.s" . t. 3 t 000036 (BW/A08) Fuel Handling Accident /8 X 036AK2.01 Knowledge of the 2.9/3.5 interrelations between the Fuel Handling Incidents and the following: Fuel handling equipment I 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum /4 000059 Accidental Liquid RadWaste ReI. / 9 X 059AK3.03 Knowledge of the reasons for 3.0/3.7 the following responses as they apply to the Accidental Liquid Radwaste Release: Declaration that a radioactive-liquid monitor is inoperable 000060 Accidental Gaseous Radwaste ReI. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 X 067 AA 1.05 Ability to operate and lor 3.0/3.1 monitor the following as they apply to the Plant Fire on Site: Plant and control room ve=sysb eb1 AA I.Os -x.. 000068 (BW/A06) Control Room Evac. / 8

000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) mad. Core Cooling / 4 X 074EG2.1.7 Ability to evaluate plant 4.4/4.7 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation as it applies to mad. Core Cooling 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure! 4 W/El 5 Containment Flooding / 5 W/E16 High Containment Radiation / 9 BA01AA2.1 Ability to determine and BW!A01 Plant Runback / 1 (SRO) X interpret the following as they apply to 3.0/3.7 The (Plant Runback) Facility conditions and selection of appropriate procedures during abnormal and emergency operations. BAO2AK1.3 Knowledge of the operational BW!A02&A03 Loss of NN implications of the following concepts as 3.8/3.8 they apply to the (Loss of NNI-X): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of NNI-X). BA04M2.1 Ability to determine and BW/A04 Turbine Trip /4 X interpret the following as they apply to the (Turbine Trip) Facility conditions and selection of appropriate procedures during abnormal and emergency operations. BAO4AA2.2 Ability to determine and BW/A04 Turbine Trip / 4 (SRO) X interpret the following as they apply to the (Turbine Trip) Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments. BW/A05 Emergency Diesel Actuation / 6 BAO7AA2.2 Ability to determine and BW/A07 Flooding / 8 X interpret the following as they apply to the (Flooding> Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments. BW!E03 Inadequate Subcooling Margin / 4

x BEO3EG2.2.3 Knowledge of the design, 3.8/3.9 procedural, and operational differences between units. BW/E08; W/E03 LOCA Cooldown - Depress. /4 000069 (W/E14) Loss of CTMT Integrity 1 5 000074 (W/E06&E07) Inad. Core Cooling 14 X 074EG2.1.7 Ability to evaluate plant 4.4/4.7 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation as it applies to inad. Core Cooling 000076 High Reactor Coolant Activity 1 9 W/E01 & E02 Rediagnosis & SI Termination 1 3 W/E13 Steam Generator Over-pressure 1 4 W/E15 Containment Flooding 1 5 W/E16 High Containment Radiation 1 9 BW/A01 Plant Runback 1 1 (SRO) X BA01AA2.1 Ability to determine and 3.0/3.7 interpret the following as they apply to The (Plant Runback) Facility conditions and selection of appropriate procedures during abnormal and emergency operations. X BA02AK1.3 Knowledge of the operational 3.8/3.8 BW/A02&A03 Loss of NNI-x/Y 1 7 implications of the following concepts as they apply to the (Loss of NNI-X): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of NNI-X). X BA04AA2.1 Ability to determine and 3.3/3.7 BW/A04 Turbine Trip 14 interpret the following as they apply to the (Turbine Trip) Facility conditions and selection of appropriate* procedures during abnormal and emergency operations. BW/A04 Turbine Trip 1 4 (SRO) X BA04AA2.2 Ability to determine and 3.7/3.7 interpret the following as they apply to the (Turbine Trip) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments. BW/A05 Emergency Diesel Actuation 1 6 X BA07 AA2.2 Ability to determine and 3.3/3.7 BW/A07 Flooding 1 8 interpret the following as they apply to the (Flooding) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments. BW/E03 Inadequate Subcooling Margin 14 X BE03EG2.2.3 Knowledge of the design, 3.8/3.9 procedural, and operational differences between units. BW/E08; W/E03 LOCA Cool down - Depress. 14

a, o 0 H H a a o 0 o_ ii 0 o 0 (90 (N (N (N (N (N Co C-) z I co 1 0 a, z 6 0:: a, C3> 0.2 O(4 w 5 ° 0 a) cj) H H cL 0 0 0 o o W 0) Co 0 C) (0

1-0) C.) w 0 0 0 Ui )< Da, a, WLL 0 0) C) a, a, 00 Ui0 00 BW/E09; CE/A13; W/E09&E10 Natural Circ. 14 BW/E13&E14 EOP Rules and Enclosures CE/A 11; W/E08 RCS Overcooling - PTS I 4 CE/A 16 Excess RCS Leakage I 2 CE/E09 Functional Recovery KIA Category Point Totals: 1 1 1 2 2 2 Group Point Total: 9 KIA Category Point Totals: (SRO) 2 2 Group Point Total: 4

ES-401,Rev.9 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2

Plant Systems - Tier 2/Group 1(RO / SRO) = System # / Name K K K K K K A A A A G K/A Topic(s) IR 1234561234

003K4. 11 Knowledge of RCPS design 003 Reactor Coolant Pump X feature(s) andlor interlock(s) which 2.8/3.1 provide for the following: Adequate cooling of RCP motor and seals

003K6.04 Knowledge of the effect of a

003 Reactor Coolant Pump X loss or malfunction on the following 2.8/3.1 will have on the RCPS Containment isolation valves affecting RCP operation

003A2.02 Ability to (a) predict the

003 Reactor Coolant Pump (SRO) X 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: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP

004K1.36 Knowledge of the physical

004 Chemical and Volume Control X connections and/or cause effect 2 6/2 8 relationships between the CVCS and the following systems: CCWS

005K3.05 Knowledge of the effect that

005 Residual Heat Removal X a loss or malfunction of the RHRS will 3.7/3.8 have on the following: ECCS

005K4.01 Knowledge of RHRS design

005 Residual Heat Removal X feature(s) and/or interlock(s) which 3 0/3 2 provide or the following: Overpressure mitigation system

006A3.05 Ability to monitor automatic

006 Emergency Core Cooling X operation of the ECCS, including: 4243 Safety Injection Pumps

007K5.02 Knowledge of the operational

007 Pressurizer Relief/Quench Tank X imphcations of the following concepts as they apply to PRTS: Method of forming a steam bubble in the PZR 008K2.02 Knowledge of bus power 008 Component Cooling Water X supplies to the following: CCW pump, 3.0/3.2 including emergency backup 010K2.03 Knowledge of bus power 010 Pressurizer Pressure Control X supplies to the following: Indicator for 2.8/3.0 1 U ES-401, Rev. 9 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO) System # / Name K K K K K K A A A A G KIA Topic(s) IR 1 2 3 4 5 6 1 2 3 4 003K4.11 Knowledge of RCPS design 2.8/3.1 003 Reactor Coolant Pump X feature(s) and/or interlock(s) which provide for the following: Adequate cooling of RCP motor and seals X 003K6.04 Knowledge of the effect of a 2.8/3.1 003 Reactor Coolant Pump loss or malfunction on the following will have on the RCPS: Containment isolation valves affecting RCP operation X 003A2.02 Ability to (a) predict the 3.7/3.9 003 Reactor Coolant Pump (SRO) 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: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 004K1.36 Knowledge of the physical 2.6/2.8 004 Chemical and Volume Control X connections and/or cause-effect relationships between the CVCS and the following systems: CCWS 005K3.05 Knowledge of the effect that 3.7/3.8 005 Residual Heat Removal X a loss or malfunction of the RHRS will have on the following: ECCS 005K4.01 Knowledge of RHRS design 3.0/3.2 005 Residual Heat Removal X feature(s) and/or interlock(s) which provide or the following: Overpressure mitigation system X 006A3.05 Ability to monitor automatic 4.2/4.3 006 Emergency Core Cooling operation of the ECCS, including: Safety Injection Pumps 007K5.02 Knowledge of the operational 3.1/3.4 007 Pressurizer Relief/Quench Tank X implications of the following concepts as they apply to PRTS: Method of forming a steam bubble in the PZR 008K2.02 Knowledge of bus power 3.0/3.2 008 Component Cooling Water X supplies to the following: CCW pump, including emergency backup 010K2.03 Knowledge of bus power 2.8/3.0 010 Pressurizer Pressure Control X supplies to the following: Indicator for P~Q~. o!Ok-3.S ~ v U

012A4.03 Ability to manually operate

012 Reactor Protection X and/or monitor in the control room: 3.6/3.6 Channel blocks and bypasses

012K2.01 Knowledge of bus power 012 Reactor Protection X supplies to the following: RPS channels, components, and interconnections

013A3.02 Ability to monitor automatic

013 Engineered Safety Features X operation of the ESFAS including: 4.1/4.2 Actuation Operation of actuated equipment

013K601 Knowledge of the effect of a

013 Engineered Safety Features X loss or malfunction on the following 2.7/3.1 Actuation will have on the ESFAS: Sensors and detectors 022 Containment Cooling X 022A3.01 Ability to monitor automatic 4.1/4.3 operation of the CCS including Initiation of safeguards mode of operation

022A2.04 Ability to (a) predict the

022 Containment Cooling (SRO) X impacts of the following malfunctions 2.9/3.2 or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water 025 Ice Condenser N/A

026A1.03 Ability to predict and/or

026 Containment Spray X monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level

026A2.04 Ability to (a) predict the

026 Containment Spray (SRO) X impacts of the following malfunctions 3.9/4.2 or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of spray pump

039G2.1.l9Abilityto use plant

039 Main and Reheat Steam X computers to evaluate system or 3.9/3.8 component status

059A2 06 Ability to (a) predict the

059 Main Feedwater X impacts of the following malfunctions 3.9/3.8 or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of steam flow to MFW system X 012A4.03 Ability to manually operate 3.6/3.6 012 Reactor Protection and/or monitor in the control room: Channel blocks and bypasses 012K2.01 Knowledge of bus power 3.3/3.7 012 Reactor Protection X supplies to the following: RPS channels, components, and interconnections X 013A3.02 Ability to monitor automatic 4.1/4.2 013 Engineered Safety Features operation of the ESFAS including: Actuation Operation of actuated equipment X 013K6.01 Knowledge of the effect of a 2.7/3.1 013 Engineered Safety Features loss or malfunction on the following Actuation will have on the ESFAS: Sensors and detectors 022 Containment Cooling X 022A3.01 Ability to monitor automatic 4.1/4.3 operation of the CCS, including Initiation of safeguards mode of operation X 022A2.04 Ability to (a) predict the 2.9/3.2 022 Containment Cooling (SRO) impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water 025 Ice Condenser N/A X 026A 1.03 Ability to predict and/or 3.5/3.5 026 Containment Spray monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level X 026A2.04 Ability to (a) predict the 3.9/4.2 026 Containment Spray (SRO) impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of spray pump X 039G2.1.19 Ability to use plant 3.9/3.8 039 Main and Reheat Steam computers to evaluate system or component status X 059A2.06 Ability to (a) predict the 3.9/3.8 059 Main Feedwater impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of steam flow to MFW system

059K3.02 Knowledge of the effect that

059 Main Feedwater X a loss or malfunction of the MFW will 3.6/3.7 have on the following: AFW system

059G2 2 42 Ability to recognize system /

059 Main Feedwater (SRO) X parameters that are entry-level 39 46 conditions for Technical

061 K6.0 Knowledge of the effect of a

061 Auxiliary/Emergency Feedwater X loss or malfunction of the following 2.6/2.7 will have on the AFW components: Pumps

062K3.03 Knowledge of the effect that

062 AC Electrical Distribution X a loss or malfunction of the ac distribution system will have on the following DC system

063K4 02 Knowledge of DC electrical

063 DC Electrical Distribution X system design feature(s) and/or 2.9/3.2 interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties

064A1.08 Ability to predict andlor 064 Emergency Diesel Generator X monitor changes in parameters 3.1/3.4 (to prevent exceeding design limits) associated with operating the EDIG system controls including Maintaining minimum load on ED/G (to prevent reverse power) (Use Hydro units if

e) A o3

064A2.02 Ability to (a) predict the 064 Emergency Diesel Generator X impacts of the following malfunctions 2.7/2.9 or operations on the EDIG system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations Load VARS pressure on air compressor speed droop frequency voltage fuel oil level temperatures

073K5 01 Knowledge of the operational

073 Process Radiation Monitoring X implications as they apply to concepts 2.5/3.0 as they apply to the PRM system: Radiation

theory, including

sources, types, units, and effects

076A2.02 Ability to (a) predict the

076 Service Water X impacts of the following mal-functions 2.7/3.1 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 Service water header pressure 059 Main Feedwater x 059 Main Feedwater (SRO) 061 Auxiliary/Emergency Feedwater x 062 AC Electrical Distribution x 063 DC Electrical Distribution x 064 Emergency Diesel Generator x 064 Emergency Diesel Generator x 073 Process Radiation Monitoring x 076 Service Water x x 059K3.02 Knowledge of the effect that a loss or malfunction of the MFW will have on the following: AFW system 059G2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical sr;;::::lnt DSq tn 2. 4*2 ~ 061 K6.02'Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps 062K3.03 Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: DC system 063K4.02 Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties 064A 1.08 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: Maintaining minimum load on ED/G (to prevent reverse power) (Use Hydro units if possible) ..f _ ('A~ IAlJ:O Ii 06'fA\\.C>5. rr* 064A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temperatures 073K5.01 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: Radiation

theory, including

sources, types, units, and effects 076A2.02 Ability to (a) predict the impacts of the following mal-functions 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: Service water header pressure 3.6/3.7 3.9/4.6 2.6/2.7 3.7/3.9 2.9/3.2 3.1/3.4 2.7/2.9 2.5/3.0 2.7/3.1

078 Instrument Air X 078A4 01 Ability to manually operate 3 1/3 1 andlor monitor in the control room Pressure gauges 103G2.1.20 Ability to interpret and 103 Containment X execute procedure steps. 4646 103 Containment X 103G2.4.20 Knowledge of operational 3.8/4.3 implications of EOP warnings, cautions and notes 1 03G2.4.9 Knowledge of low 103 Containment (SRO) X powerlshutdown implications in 3.8/4.2 accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. K/A Category Point Totals 1 3 3 3 2 3 2 I 2 I 3 I Group Point Total 28 K/A Category Point Totals (SRO)

= = =

I 3 I 2 I Group Point Total 5 078 Instrument Air X 078A4.01 Ability to manually operate 3.1/3.1 and/or monitor in the control room:. Pressure gauges 103 Containment X 1 03G2.1.20 Ability to interpret and 4.6/4.6 execute procedure steps. 103 Containment X 103G2.4.20 Knowledge of operational 3.8/4.3 implications of EOP warnings, cautions, and notes. 103 Containment (SRO) X 103G2.4.9 Knowledge of low 3.8/4.2 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. KIA Category Point Totals: 1 3 3 3 2 3 2 3 3 2 3 Group Point Total: 28 K/A Category Point Totals: (SRO) 3 2 Group Point Total: 5

ES-401, Rev. 9 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant_Systems_-_Tier 2/Group 2 (RO / SRO) System #/Name K K K K K K A A A A G K/A Topic(s) IR 123456 1234 001 Control Rod Drive 002 Reactor Coolant X 002A4.08 Ability to manually operate 3.4/3.7 and/or monitor in the control room Safety parameter display systems

011K2.02 Knowledge of bus power

011 Pressurizer Level Control X supplies to the following: PZR heaters 3.1/3.2 01 1A2.06 Ability to (a> predict the 011 Pressurizer Level Control X impacts of the following malfunctions or (SRO) operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent PZR spray actuation 014 Rod Position Indication

015 Nuclear Instrumentation

016 Non-nuclear Instrumentation

017 In-core Temperature Monitor

027A2.01 Ability to (a) predict the 027 Containment Iodine Removal X impacts of the following malfunctions or 3.0/3.3 (SRO) operations on the CIRS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences of those malfunctions or operations High temperature in the filter system

OZ72.2.1P&

028 Hydrogen Recombiner and PurgeControl

029A2.04 Ability to (a) predict the 029 Containment Purge X impacts of the following malfunctions or 2.5/3.2 operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Health physics sampling of containment atmosphere 033A3.02 Ability to monitor automatic 033 Spent Fuel Pool Cooling X operation of the Spent Fuel Pool 2.9/3.1 Cooling System including: Spent fuel leak or rupture ES-401, Rev. 9 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 2 (RO / SRO) System # / Name K K K K K K A A A A G KIA Topic(s) IR 1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant X 002A4.08 Ability to manually operate 3.4/3.7 and/or monitor in the control room Safety parameter display systems 011 Pressurizer Level Control X 011 K2.02 Knowledge of bus power 3.1/3.2 supplies to the following: PZR heaters 011 Pressurizer Level Control X 011A2.06 Ability to (a) predict the 3.7/3.9 impacts of the following malfunctions or (SRO) operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent PZR spray actuation 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal X 027 A2.01 Ability to (a) predict the 3.0/3.3 impacts of the following malfunctions or (SRO) operations on the CIRS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High temperature in the filter system ~to OZ7~Z.Z.(c) ~ 028 Hydrogen Recombiner and Purge Control 029A2.04 Ability to (a) predict the 029 Containment Purge X impacts of the following malfunctions or 2.5/3.2 operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Health physics sampling of containment atmosphere 033 Spent Fuel Pool Cooling X 033A3.02 Ability to monitor automatic 2.9/3.1 operation of the Spent Fuel Pool Cooling System including: Spent fuel leak or rupture

034 Fuel Handling Equipment 035 Steam Generator 041 K6.03 Knowledge of the effect of a 041 Steam Dump/Turbine Bypass X loss or malfunction on the following will 27/29 Control have on the SOS: Controller and positioners, including CS, S/G, CRDS

045K3.01 Knowledge of the effect that a 045 Main Turbine Generator X loss or malfunction of the MTIG system 2.9/3.2 will have on the following: Remainder of the plant 055 Condenser Air Removal

056G2.2.44 Ability to interpret control 056 Condensate X room indications to verify the status and 4.2/4.4 operation of a system, and understand how operator actions and directives affect plant and system conditions. 068 Liquid Radwaste

071 Waste Gas Disposal

072K1.03 Knowledge of the physical 072 Area Radiation Monitoring X connections andlor cause-effect 3.6/3.7 relationships between the ARM system and the following systems: Fuel building isolation

072G2.4.4 Ability to recognize abnormal 072 Area Radiation Monitoring X indications for system operating 4 5 7 (SRO) parameters that are entry level conditions for emergency and abnormal operating procedures. 075 Circulating Water

079K4.01 Knowledge of SAS design 079 Station Air X feature(s) andlor interlock(s) which 2.9/3.2 provide for the following: Cross-connect with AS 086K5 03 Knowledge of the operational 086 Fire Protection X implication of the following concepts as 3.1/3.4 they apply to the Fire Protection System: Effect of water spray on electrical components A Category Point Totals: 1 0 1 1 Group Point Total: K/A Category Point Totals: (SRO) = = = = Jf 2 = = 1 Group Point Total: 3 034 Fuel Handling Equipment 035 Steam Generator X 041 K6.03 Knowledge of the effect of a 2.7/2.9 041 Steam DumplTurbine Bypass loss or malfunction on the following will Control have on the SDS: Controller and positioners, including ICS, S/G, CRDS 045K3.01 Knowledge of the effect that a 2.9/3.2 045 Main Turbine Generator X loss or malfunction of the MT/G system will have on the following: Remainder of the plant 055 Condenser Air Removal X 056G2.2.44 Ability to interpret control 4.2/4.4 056 Condensate room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 068 Liquid Radwaste 071 Waste Gas Disposal 072K1.03 Knowledge of the physical 3.6/3.7 072 Area Radiation Monitoring X connections and/or cause-effect relationships between the ARM system and the following systems: Fuel building isolation X 072G2.4.4 Ability to recognize abnormal 4.5/4.7 072 Area Radiation Monitoring indications for system operating (SRO) parameters that are entry-level conditions for emergency and abnormal operating procedures. 075 Circulating Water X 079K4.01 Knowledge of SAS design 2.9/3.2 079 Station Air feature(s) and/or interlock(s) which provide for the following: Cross-connect with lAS 086K5.03 Knowledge of the operational 3.1/3.4 086 Fire Protection X implication of the following concepts as they apply to the Fire Protection System: Effect of water spray on electrical components KIA Category Point Totals: 1 1 1 1 1 1 0 1 1 1 1 Group Point Total: 10 K/A Category Point Totals: (SRO) 1 2 1 Group Point Total: 3

Facility: Oconee Date of Exam: 2010 RO SRO-Only Category K/A # Topic JR Q# IR Q# Knowledge of procedures and limitations 2.1.36 involved in core alterations. 3.0 4.0 Ability to identify and interpret diverse 2.1.45 indications to validate the response of 4.3 4.3 another indication. 1. Conduct of Knowledge of criteria or conditions that Operations 2.1.14 require plant-wide announcements, such as (SRO) pump starts, reactor trips, mode changes, 3.1 etc. 2.1.41 Knowledge of the refueling process 3.7 (SRO) Subtotal 2 2 Knowledge of the bases in Technical Specifications for limiting conditions for 2.2.25 3.2 4.2 operations and safety limits. Knowledge of less than or equal to one hour Technical Specification action statements for 2.2.39 3.9 4.5 systems. Ability to recognize system parameters that 2. are entry-level conditions for Technical 2.2.42 3.9 4.6 Equipment Control Specifications. Ability to manipulate the console controls as 2.2.2 required to operate the facility between 4.1 (SRO) shutdown and designated power levels. 2.2.35 Ability to determine Technical Specification 4.5 (SRO) Mode of Operation. Subtotal 3 2 2.3.11 Ability to control radiation releases. 3.8 4.3 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel 2.3.12 3.2 3.7 handling responsibilities, access to locked high-radiation areas, aligning filters, etc. 3. Radiation Control Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 3.6 conditions. 2.3.4 Knowledge of radiation exposure limits 3.7 (SRO) under normal or emergency conditions. Subtotal 3 1 Facility: I Oconee I Date of Exam: 1 2010 RO SRO-Only Category KIA # Topic IR Q# IR Q# Knowledge of procedures and limitations 2.1.36 involved in core alterations. 3.0 4.0 Ability to identify and interpret diverse 2.1.45 indications to validate the response of 4.3 4.3

1.

another indication. Conduct of Knowledge of criteria or conditions that Operations 2.1.14 require plant-wide announcements, such as (SRO) pump starts, reactor trips, mode changes, 3.1 etc. 2.1.41 Knowledge of the refueling process 3.7 (SRO) Subtotal 2 2 Knowledge of the bases in Technical 2.2.25 Specifications for limiting conditions for 3.2 4.2 operations and safety limits. Knowledge of less than or equal to one hour 2.2.39 Technical Specification action statements for 3.9 4.5 systems. Ability to recognize system parameters that

2.

are entry-level conditions for Technical Equipment Control 2.2.42 Specifications. 3.9 4.6 Ability to manipulate the console controls as 2.2.2 required to operate the facility between 4.1 (SRO) shutdown and designated power levels. 2.2.35 Ability to determine Technical Specification 4.5 (SRO) Mode of Operation. Subtotal 3 2 2.3.11 Ability to control radiation releases. 3.8 4.3 Knowledge of radiological safety principles pertaining to licensed operator duties, such 2.3.12 as containment entry requirements, fuel 3.2 3.7 handling responsibilities, access to locked

3.

high-radiation areas, aligning filters, etc. Radiation Control Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 3.6 conditions. 2.3.4 Knowledge of radiation exposure limits 3.7 (SRO) under normal or emergency conditions. Subtotal 3 1

Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. 2.4.16 4. Emergency Procedures / Plan 3.5 4.4 Knowledge of facility protection 2 4 26 requirements, including fire brigade and 3 1 3 6 portable fire fighting equipment usage. 2.4.27 (SRO) Knowledge of fire in the plant procedures. 3.9 Knowledge of how abnormal operating 2.4.8 procedures are used in conjunction with 4 (SRO) EOPs. Subtotal 2 2 Tier 3 Point Total Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, 2.4.16 operating procedures, abnormal operating 3.5 4.4 procedures, and severe accident management guidelines. Knowledge of facility protection 2.4.26 requirements, including fire brigade and 3.1 3.6

4.

portable fire fighting equipment usage. Emergency Procedures / Plan 2.4.27 Knowledge of "fire in the plant" procedures. 3.9 (SRO) Knowledge of how abnormal operating 2.4.8 procedures are used in conjunction with 4.5 (SRO) EOPs. Subtotal 2 2 Tier 3 Point Total

1010 -30f ES-401 Record of Rejected KIAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected K/A RO 2/1 003K4.04 (9/10/09) KA required CCWS question. KA changed due to oversampling of CCWS. NRC selected 003K4.1 1. RO 1/2 067AA1.05 (1 I/I 7/09) There are no plant or control room ventilation systems operated or monitored from control room as a result of a fire. NRC selected 067AA1.03. RO 2/1 064A1.08 (11/17/09) Could not make the KA apply to Keowee Hydro Units since it was specific to DGs. NRC selected 064A1.03. SRO 2/2 027A2.01 (11/17/09) Containment Iodine Removal at ONS is accomplished using Reactor Building Spray and Caustic baskets therefore there are no associated filters as required by KA. NRC selected 027G2.2.40. SRO 1/2 033AG2.1.32 (11/17/09) ONS has no Operations procedural limits and precautions specific to either Intermediate Range or Wide Range nuclear instrumentation. NRC selected 033AG2.1.23 RO 2/1 010K2.03 (1/20/1 0) Knowledge of Bus power supplies to POPRV position indication is not operationally significant. NRC Selected 010K2.0i and then 010K3.03. SRO 2/1 059G2.2.42 (1/20/1 0) Oconee does not have TS entry conditions based on Main FDW parameters. NRC selected 059G2.4.2 ES-401 Record of Rejected KlAs Form ES-401-4 Trier 1 Randomly Reason for Rejection Group Selected KIA RO 2/1 003K4.04 (9/10109) KA required CCWS question. KA changed due to oversampling of CCWS. NRC selected 003K4.11. RO 1/2 067AA1.05 (11/17/09) There are no plant or control room ventilation systems operated or monitored from control room as a result of a fire. NRC selected 067 AA 1.03. RO 2/1 064A1.08 (11/17/09) Could not make the KA apply to Keowee Hydro Units since it was specific to OG's. NRC selected 064A1.03. SRO 2/2 027A2.01 (11/17/09) Containment Iodine Removal at ONS is accomplished using Reactor Building Spray and Caustic baskets therefore there are no associated "filters" as required by KA. NRC selected 027G2.2.40. SRO 1/2 033AG2.1.32 (11/17/09) ONS has no Operations procedural limits and precautions specific to either Intermediate Range or Wide Range nuclear instrumentation. NRC selected 033AG2.1.23 RO 2/1 010K2.03 (1/20/10) Knowledge of Bus power supplies to POPRV position indication is not operationally significant. NRC Selected 010K2.01 and then 010K3.03. SRO 2/1 059G2.2.42 (1/20/10) Oconee does not have TS entry conditions based on Main FOW parameters. NRC selected 059G2.4.2

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Oconee Date of Exam: 04/0712010 Exam Level: RO SRO Initial Item Description a 1. Questions and answers are technically accurate and applicable to the facility. 2. a. NRC K/As are referenced for all questions. 1A) b. Facility learning objectives are referenced as available. 3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office). 5. Question duplication from the license screening/audit exam was controlled j as indicated below (check the item that applies) and appears appropriate: / the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed independently; or the licensee certifies that there is no duplication; or other (explain) 6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only 9 / 3 5 / 0 61 / 22 question distribution(s) at right. 12% / 12% 7% / 0% 81% / 88% 7. Between 50 and 60 percent of the questions Memory C/A on the RO exam are written at the comprehension! analysis level; the SRO exam may exceed 60 34 / 8 41 / 17 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO! 45.3% / 32% 54.7% / 68% SRO question distribution(s) at right. 8. References/handouts provided do not give away answers or aid in the elimination of distractors. 9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified. / 10. Question psychometric quality and format meet the guidelines in ES Appendix B. 11. The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet. Printed Name / Signature Date

a. Author C,i%(tS

&4f?L

d. 5or Note:

• The facility reviewers initials/signature are not applicable for NR

- eveloped 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: Oconee Date of Exam: 04/07/2010 Exam Level: RO ~ Item Description

1.

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

2.

a.

b.

NRC K/As are referenced for all questions. Facility leaming objectives are referenced as available.

3.

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

4.

The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were re eated from the last 2 NRC licensin exams, consult the NRR OL ro ram office).

5.

Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate: _ the audit exam was systematically and randomly developed; or _ the audit exam was completed before the license exam was started; or the examinations were developed independently; or x: the licensee certifies that there is no duplication; or _ other (explain)

6.

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.

7.

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 Bank Modified 9/3 5/0 12% /12% 7%/0% Memory 34 / 8 New 61 /22 81% /88% CIA 41 / 17 the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right. 45.3% / 32% 54.7% / 68%

8.

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

9.

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.

10.

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

11.

The exam contains the required number of one-point, multiple choice items; the total is correct and a rees with the value on the cover sheet. Printed Name / Signature

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor Note:

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

1. Inde endent NRC reviewer initial items in Column "c"; chief examiner concurrence re uired.

ES-401, Rev. 9 Oconee 201 0-301 RO Written Examination Review Worksheet FINAL Form ES-401-9 1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

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

1. /

Back-Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S Instructions [Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.] 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 stern). 4. Check the appropriate box if ajob content error is identified: The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content). The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements. 5. Check questions that are sampled for conformance with the approved K/A and those that are designated SR0-only (K/A and license level mismatches are unacceptable). 6. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory? 7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met). ES-401, Rev. 9 Oconee 2010*301 RO Written Examination Review Worksheet FINAL Form ES-401*9 Q#

1.

LOK (F/H)

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other LOD ~--~--~--~--~--~--~--~--~--~

(1-5) Stem Cues T/F I cred'lpartial Job-Minutia

1. 1 I Back-Q=

SRO Focus Dist. Link units I ward KIA Only Instructions

6.

U/EI S

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).

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q4 LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus j Dist. Link units ward K/A Only S H 2 X U OO8AKI.01 Question is not meeting the K/A. While a component of the question does have PZR tailpipe temperature indicating, the applicant can answer this question by knowing that tailpipe temp will increase if a safety/relief valve lifts. There is not a component of the question that tests Thermodynamics or flow characteristics. This question simply tests what goes into the QT, and what path does it take. Try asking a question with different temps etc and which one would be an indication of a PORV being open. BANK 2007 NRC EXAM (was it used on the same KA? Replaced Question SAT 3/312010 2 H 2 X E 009K1.01 Question appears to match K/A. The second part of the responses are confusing, in response A and C it seems like the second part is stating that EFDW would be throttled if boiler condenser cooling begins. If so I do not think this is plausible. Please Explain/clarify. NEW Changed two distractors and stem. SAT 3/3/2010 F 2 S OIIEK2.02 Question appears to match K/A. SAT 3 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. /

Back-Q= SRO utE/ Explanation Focus Dis!. Link units ward KIA Only S 1 H 2 X U 008AK1.01 Question is not meeting the KIA. While a component of the question does have PZR tailpipe temperature indicating, the applicant can answer this question by knowing that tailpipe temp will increase if a safety/relief valve lifts. There is not a component of the question that tests Thermodynamics or flow characteristics. This question simply tests what goes into the QT, and what path does it take. Try asking a question with different temps etc and which one would be an indication of a PORV being open. BANK 2007 NRC EXAM (was it used on the same KA? Replaced Question SAT 3/3/2010 2 H 2 X E 009K1.01 Question appears to match KIA. The second part of the responses are confusing, in response A and C it seems like the second part is stating that EFDW would be throttled if boiler-condenser cooling begins. If so I do not think this is plausible. Please Explain/clarify. NEW Changed two distractors and stem. SAT 3/3/2010 F 2 S 011 EK2.02 Question appears to match KIA. SAT 3 NEW

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD 11 1 I (F/H) (1-5) Stem Cues TIF Cred. jPartial Job-Minutia

1. 1 Back-Q=

I SRO U/El Explanation Focus Dist. Link units ward K/A Only S F 2 X E OI5AAI.21 Question kind of matches K/A. The way 4 the question is asked you actually remove the testing portion of loss of RCS flow. (You tell them in the stem natural Circulation is being formed. To better match the K/A, you should ask what would Th and Tc be approximately 15 minutes after the trip. Then use normal after trip temps and the natural circ temps. NEW Made changes as requested SAT 313/2010 H 2 S 025AG2.4.1 I Question appears to match the K/A. 5 Recommend replacing previously running LPI pump with Start C LPI pump... I know the procedure states previously but the operator would actually start the C LPI. Otherwise SAT NEW Made changes as requested. SAT 3/3/2010

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 F 2 X E 01SAA1.21 Question kind of matches KIA. The way 4 the question is asked you actually remove the testing portion of loss of RCS flow. (You tell them in the stem natural Circulation is being formed. To better match the KIA, you should ask what would Th and Tc be approximately 15 minutes after the trip. Then use normal after trip temps and the natural circ temps. NEW Made changes as requested SAT 3/3/2010 H 2 S 02SAG2.4.11 Question appears to match the KIA. 5 Recommend replacing "previously running LPI pump" with "Start C LPI pump... I know the procedure states "previously" but the operator would actually start the C LPI. Otherwise SAT NEW Made changes as requested. SAT 3/3/2010

] 1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# I LOK LOD

1 I (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link junits ward K/A Only S H 2 E 026K3.03 Question appears to match K/A. Change 6 stem to read: A reactor trip has just occurred Total RCP seal injection flow

Ogpm, Component Cooling is unavailable Based on the above conditions, Which ONE of the following describes the required procedure to be performed in conjunction with the EOP and why?

NEW Licensee to fix need to look at two procedures and different reasons. Question as written has four different procedures and reasons. Applicant need only know one of each. Made changes as requested. SAT 3110/2010 H 2 X E 027AK2.03 Question appears to match the K/A. The last bullet under current conditions 7 gives the impression that all heaters are off. The lesson plan states that Heater group A and K should be energized at all times, If this is true the stem should state this. NEW Made changes as requested SAT 3I3I2010

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 H 2 E 026K3.03 Question appears to match KIA. Change 6 stem to read: A reactor trip has just occurred Total RCP seal injection flow = Ogpm, Component Cooling is unavailable Based on the above conditions, Which ONE of the following describes the required procedure to be performed in conjunction with the EOP and why? NEW Licensee to fix need to look at two procedures and different reasons. Question as written has four different procedures and reasons. Applicant need only know one of each. Made changes as requested. SAT 3/10/2010 H 2 X E 027 AK2.03 Question appears to match the KIA. The last bullet under current conditions 7 gives the impression that all heaters are off. The lesson plan states that Heater group A and K should be energized at all times. If this is true the stem should state this. NEW Made changes as requested SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD (F/H) (1-5) Stem ICues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation jj Dist. Link units ward K/A Only S 8 H 2 X E 029EK3.12 Question appears to match K/A. The question asks for actions required by Rule 2 and the reasons for those actions. The Reasons stated in C and D are not the same reason for securing RCPs in the rule 2 lesson plan. These are:

1) to reduce the amount of RCS inventory lost, and

2) To secure RCPs before the RCS can evolve to a Void fraction >70%.

Try using these reasons in C and D to increase plausibility. NEW Made changes as asked SAT 3/3/2010 H 2 S 038EK3.01 Question appears to match the K/A. 9 SAT. NEW H 2 S 054AA1.03 Question appears to match KIA. Not very discriminating. SAT 10 NEW F 2 S 055EA1.02 Question appears to match the K/A. SAT 11 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 utEI Explanation Focus Dis!. Link units ward KIA Only S 8 H 2 X E 029EK3.12 Question appears to match KIA. The question asks for actions required by Rule 2 and the reasons for those actions. The Reasons stated in C and 0 are not the same reason for securing RCPs in the rule 2 lesson plan. These are:

1) to reduce the amount of RCS inventory lost, and

2) To secure RCPs before the RCS can evolve to a Void fraction >70%.

Try using these reasons in C and 0 to increase plausibility. NEW Made changes as asked SAT 3/3/2010 H 2 S 038EK3.01 Question appears to match the KIA. 9 SAT. NEW H 2 S 054AA1.03 Question appears to match KIA. Not very discriminating. SAT 10 NEW F 2 S 055EA1.02 Question appears to match the KIA. SAT 11 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 Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S H 2 E 057AA2.15 Question appears to match the K/A. Distractors B and D seem to lose question symmetry. 12 B states power will automatically be energized from Unit 3, and D states from the alternate unit. The way the question is written now, as an applicant I would think that either A, or C is the correct answer because both point to regulated power supplies. NEW Made Changes as requested. SAT 31312010 13 H 2 S 058AK1.01 Question appears to match the K/A. SAT Modified H 2 S 062AG2.1.20 Question appears to match the K/A. Distractor analysis is not correct. Otherwise SAT. 14 BANK 15 H 2 S 065AA2.07 Question appears to match K/A. 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 Dis!. Link units ward KIA Only S H 2 E 057 AA2.15 Question appears to match the KIA. 12 Distractors Band 0 seem to lose question symmetry. B states power will automatically be energized from Unit 3, and 0 states from the alternate unit. The way the question is written now, as an applicant I would think that either A, or C is the correct answer because both point to regulated power supplies. NEW Made Changes as requested. SAT 3/3/2010 13 H 2 S 058AK1.01 Question appears to match the KIA. SAT Modified H 2 S 062AG2.1.20 Question appears to match the KIA. Distractor analysis is not correct. Otherwise SAT. 14 BANK 15 H 2 S 065AA2.07 Question appears to match KIA. SAT NEW

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q SRO U/E/

Explanation Focus Link units ward K/A Only S 16 H 2 X U 077AG2.2.22 Question appears to match the K/A. It does not appear that distractors A and C are plausible. Why would you trip a unit off because voltage is high? Is there some other item that on another system that could cause a breaker to trip, but does not apply to the KHUs? Please make distractors A and C more plausible, or educate me as to why you think they are. NEW Made changes to stem to enhance plausibility and discussed system operation. SAT 3/3/2010 17 H 2 S BEO4EA2.2 Question appears to match K/A. SAT BANK OCONEE 2006 NRC EXAM 18 H 2 S BEO5EK2.1 Question appears to match the K/A. SAT NEW 19 F 2 S 028AA1.07 Question appears to match K/A. 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 Dis!. Link units ward KIA Only S 16 H 2 X U 077 AG2.2.22 Question appears to match the KIA. It does not appear thatdistractors A and Care plausible. Why would you trip a unit off because voltage is high? Is there some other item that on another system that could cause a breaker to trip, but does not apply to the KHUs? Please make distradors A and C more plausible, or educate me as to why you think they are. NEW Made changes to stem to enhance plausibility and discussed system operation. SAT 3/3/2010 17 H 2 S BE04EA2.2 Question appears to match KIA. SAT BANK OCONEE 2006 NRC EXAM 18 H 2 S BE05EK2.1 Question appears to match the KIA. SAT NEW 19 F 2 S 028AA1.07 Question appears to match KIA. SAT NEW

1. 2.

3. Psychometric Flaws

4. Job Content Flaws J

5. Other 7.

Q# LOK LOD

j (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-I SRO U/E/

Explanation Focus Dist. Link units ward K/A Only 20 H 2 x E 036AK2.01 Question kind of matches K/A. TS water level listed in stem Teaching use a different value and say lowering slowly. What different actions would be taken if the pool level was dropping rapidly? BANK QUESTION FROM 2009 NRC EXAM Made changes as requested. SAT 313/2010 21 F 2 S 059AK3.03 Question kind of matches K/A. Chief examiner had discussion with licensee about ways to test this K/A. This topic was deemed to be satisfactory. SAT NEW 22 F 2 S 067AA1.03 Question appears to match K/A. SAT NEW 23 F 2 S 074EG2.1.7 Question appears to match K/A. SAT Not very discriminating. 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 Dis!. Link units ward KIA Only S 20 H 2 X E 036AK2.01 Question kind of matches KIA. TS water level listed in stem "Teaching" use a different value and say lowering slowly. What different actions would be taken if the pool level was dropping rapidly? BANK QUESTION FROM 2009 NRC EXAM Made changes as requested. SAT 3/3/2010 21 F 2 S 059AK3.03 Question kind of matches KIA. Chief examiner had discussion with licensee about ways to test this KIA. This topic was deemed to be satisfactory. SAT NEW 22 F 2 S 067AA1.03 Question appears to match KIA. SAT NEW 23 F 2 S 074EG2.1.7 Question appears to match KIA. SAT Not very discriminating. NEW

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

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

1. 1 Back-Q=

SRO U/El Explanation Focus Dist. Link units ward K/A Only S 24 H 2 X U BAO2AKI.3 Question appears to match K/A. Distractors A and D do not appear to be plausible. I rods were inserting (power down) then feed water flow must decrease and visa versa for D. Need to find distractors that are more discriminating. NEW Made changes as requested. SAT 3/3/2010 25 H 2 X U BAO4AA2.1 Question appears to match K/A. If SG pressure would normally be controlled at setpoint (885 #) if the reactor did not trip, and the controller is supposed to control at 885 # ÷ 125 # which equals 1010 #, why do you have 1015 in distractors B and D? Would the plant not go to the Unit Runback AOP? Is there a correct answer? Several of the reference pages are from AP-1. Need to ensure that there is a correct answer and that B and D distractors are plausible. NEW Fixed question as requested then SAT 3/3/2010 26 F 2 X E BAO7AA2.2 Question appears to match the K/A. Distractor B does not appear to be plausible. What other sources of water could help flood the Turbine building? NEW Made changes as requested replaced distractor B. SAT 3/3/2010

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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 24 H 2 X U BA02AK1.3 Question appears to match KIA. Distractors A and 0 do not appear to be plausible. I rods were inserting (power down) then feed water flow must decrease and visa versa for D. Need to find distractors that are more discriminating. NEW Made changes as requested. SAT 3/3/2010 25 H 2 X U BA04AA2.1 Question appears to match KIA. If SG pressure would normally be controlled at setpoint (885 #) if the reactor did not trip, and the controller is supposed to control at 885 # + 125 # which equals 1010 #, why do you have 1015 in distractors Band D? Would the plant not go to the Unit Runback AOP? Is there a correct answer? Several of the reference pages are from AP-1. Need to ensure that there is a correct answer and that Band 0 distractors are plausible. NEW Fixed question as requested then SAT 3/3/2010 26 F 2 X E BA07 AA2.2 Question appears to match the KIA. Distractor B does not appear to be plausible. What other sources of water could help flood the Turbine building? NEW Made changes as requested replaced distractor B. SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 27 F 2 S BEO3EG2.2.3 Question kind of matches K/A. SAT NEW 28 F 2 X U 003K4.11 Question appears to match K/A. Distractors B and D do not appear to be plausible if you read the distractor analysis. Maybe it is not correct. If it is, why would a choose a valve opening if the valve will be interlocked closed after 1 mm of SI flow being < 4.0 gpm? Need to fix distractors B and D. NEW Changed distractors B, C, D. SAT 313/2010 29 H 2 S 003K6.04 Question appears to match K/A. SAT NEW 30 H 2 U 004K1.36 Question appears to match the K/A. Distractors A and B first part is not plausible. I do not know of any plant that has an automatic trip on loss of component cooling water. (Maybe letdown must be manually isolated, will automatically isolate, etc. NEW Made changes to distractors as requested SAT 3/3/2010

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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 Dis!. Link units ward KIA Only S 27 F 2 S BE03EG2.2.3 Question kind of matches KIA. SAT NEW 28 F 2 X U 003K4.11 Question appears to match KIA. Distractors Band D do not appear to be plausible if you read the distractor analysis. Maybe it is not correct. If it is, why would a choose a valve opening if the valve will be interlocked closed after 1 min of SI flow being < 4.0 gpm? Need to fix distractors Band D. NEW Changed distractors B, C, D. SAT 3/3/201 0 29 H 2 S 003K6.04 Question appears to match KIA. SAT NEW 30 H 2 U 004K1.36 Question appears to match the KIA. Distractors A and B first part is not plausible. I do not know of any plant that has an automatic trip on loss of component cooling water. (Maybe letdown must be manually isolated, will automatically isolate, etc. NEW Made changes to distractors as requested SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

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

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 31 H 2 E 005K3.05 Question appears to match the K/A. Question 32 may help answer this question. NEW Changed valve in stem to LP-3. SAT 3/3/2010 32 F 2 E 005K4.01 Question appears to match K/A. This question and question 31 both include LP-1. The second question asks when you can open LP-1 which is a hint (it may help answer question 31. Can we make another valve inoperable on question # 31? NEW Made changes as requested SAT 3/3/2010 33 H 2 S 006A3.05 Question appears to match K/A. SAT NEW 34 F 2 E 007K5.02 Question appears to match K/A. SAT NEW After further review and validation realized that changes were required to make question more clear. Continue to work 3/3/2010 Made changes as requested. SAT 3/1 012010

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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 31 H 2 E 005K3.05 Question appears to match the KIA. Question 32 may help answer this question. NEW Changed valve in stem to LP-3. SAT 3/3/2010 32 F 2 E 005K4.01 Question appears to match KIA. This question and question 31 both include LP-1. The second question asks when you can open LP-1 which is a hint (it may help answer question 31. Can we make another valve inoperable on question # 31? NEW Made changes as requested SAT 3/3/2010 33 H 2 S 006A3.05 Question appears to match KIA. SAT NEW 34 F 2 E 007K5.02 Question appears to match KIA. SAT NEW After further review and validation realized that changes were required to make question more clear. Continue to work 3/3/2010 Made changes as requested. SAT 3/10/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-0=

SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 35 H 2 S 008K2.02 Question appears to match K/A. SAT NEW SAT 3/3/2010 36 F 2 E 010K3.03 Question Kind of matches K/A. Not very discriminating. This is really just a question of when will the reactor trip/ES F actions occur on RCS low pressure. Please add something (like coincidence to the distractors (i.e. reactor trips when 2/3 pressures gets to... and ESF actuates.... Also give indications of a pressure malfunction. As it is you just tell the applicant that a malfunction has occurred. Question

1. 37 kind of asks something similar. Will discuss.

NEW Made changes to stem and distractors. SAT 3/3/2010 37 H 2 S 012A4.03 Question appears to match K/A. SAT NEW SAT 3/3/2010

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3. Psychometric Flaws

4. Job Content Flaws

5. Other

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7.

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

1. /

Back-Q= SRO U/E/ Explanation Focus Dis!. Link units ward KIA Only S 35 H 2 S 008K2.02 Question appears to match KIA. SAT NEW SAT 3/3/2010 36 F 2 E 010K3.03 Question Kind of matches KIA. Not very discriminating. This is really just a question of when will the reactor trip/ESF actions occur on ReS low pressure. Please add something (like coincidence to the distractors (Le. reactor trips when 2/3 pressures gets to... and ESF actuates.... Also give indications of a pressure malfunction. As it is you just tell the applicant that a malfunction has occurred. Question

1. 37 kind of asks something similar. Will discuss.

NEW Made changes to stem and distractors. SAT 3/3/2010 37 H 2 S 012A4.03 Question appears to match KIA. SAT NEW SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 11 Back-Q=

I SRO U/E/ Explanation Focus Dist. Link units ward KIA Only S 38 H 2 X E 012K2.01 Question appears to match K/A. It appear to me that D is a subset of C. If 1 DCB was correct (because it supplies 1 KVID) then C would also be correct. An applicant could rule out D because it supplies 1 KVID, knowing that there could only be 1 correct answer. Need to fix distractor D. NEW Still need to fix C distractor Fixed C distractor SAT 3/10/2010 39 F 2 S 013A3.02 Question appears to match the K/A. It is testing the same setpoint as question 36, plus the RB setpoint. As written this question is SAT. It would be double jeopardy to test on the same setpoint twice. (Suggest working on question 36). NEW SAT 31312010 40 H 3 S 013K6.01 Question appears to match K/A. SAT NEW SAT 3/3/2010

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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 38 H 2 X E 012K2.01 Question appears to match KIA. It appear~ to me that D is a subset of C. If 1 DCB was correct (because it supplies 1 KVID) then C would also be correct. An applicant could rule out D because it supplies 1 KVID, knowing that there could only be 1 correct answer. Need to fix distractor D. NEW Still need to fix C distractor Fixed C distractor SAT 3/10/2010 39 F 2 S 013A3.02 Question appears to match the KIA. It is testing the same setpoint as question 36, plus the RB setpoint. As written this question is SAT. It would be double jeopardy to test on the same setpoint twice. (Suggest working on question 36). NEW SAT 3/3/2010 40 H 3 S 013K6.01 Question appears to match KIA. SAT NEW SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 41 H 2 X E 022A3.Ol Question appears to match K/A. Change the stem to read: Based on the above conditions, which one of the flowing describes the RBCU status at 3:02. Did NOT include original bank question. BANK Made Changes as Requested SAT 3/312010 42 H 2 S 026A1.03 Question appears to match K/A. SAT NEW SAT 3/3/2010 43 H 2 S 039G2.1.19 Question appears to match K/A. SAT NEW SAT 3I3!2010 44 H 2 S 059A2.06 Question kind of matches K/A. SAT NEW SAT 3/3/2010 45 H 2 S 059K3.02 Question appears to match K/A. SAT BANK SAT 3/3/2010 46 F 2 S 061K6.02 Question appears to match K/A. SAT NEW SAT 3/3/2010

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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 41 H 2 X E 022A3.01 Question appears to match KIA. Change the stem to read: Based on the above conditions, which one of the flowing describes the RBCU status at 3:02. Did NOT include original bank question. BANK Made Changes as Requested SAT 3/3/2010 42 H 2 S 026A1.03 Question appears to match KIA. SAT NEW SAT 3/3/2010 43 H 2 S 039G2.1.19 Question appears to match KIA. SAT NEW SAT 3/3/2010 44 H 2 S 059A2.06 Question kind of matches KIA. SAT NEW SAT 3/3/2010 45 H 2 S 059K3.02 Question appears to match KIA. SAT BANK SAT 3/3/2010 46 F 2 S 061K6.02 Question appears to match KIA. SAT NEW SAT 3/3/2010

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

I SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 47 F 2 X E 062K3.03 Question appears to match K/A. Stem does not read correctly; Which ONE of the following describes actions required in that will...Fix Stem. Otherwise question appears to be acceptable. Made changes as requested. SAT 313/2010 48 F 2 X E 063K4.02 Question appears to match K/A. Distractor D may be considered or argued correct. If a single battery became inoperable, and actions were taken lAW the SLC, and a second battery became inoperable, then the system would still be cross-tied with two batteries inoperable. (Are you relying on the more part of this?) NEW Added simultaneously to B and D. SAT 3/3/2010 49 H 2 E 064A1.03 (Hydro units perform the same function as EDGs). Question appears to match the K/A. Because this is a 2009 exam question, attempt to change the second half of the distractors. What will the result of the higher voltage; increase in reactive load etc. We can do something to change the question (this is the fourth question that is repeated, including the SRO portion from the last two exams. BANK 2009 NRC EXAM Made some changes will look at minimum indication that can be seen on meter. Changed to

10. SAT 3/3/2010

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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. /

Back-Q= SRO utE/ Explanation Focus Dist. Link units ward KIA Only S 47 F 2 X E 062K3.03 Question appears to match KIA. Stem does not read correctly; Which ONE of the following describes actions required in thatwill... Fix Stem. Otherwise question appears to be acceptable. Made changes as requested. SAT 3/3/2010 48 F 2 X E 063K4.02 Question appears to match KIA. Distractor D may be considered or argued correct. If a single battery became inoperable, and actions were taken lAW the SLC, and a second battery became inoperable, then the system would still be cross-tied with two batteries inoperable. (Are you relying on the more part of this?) NEW Added simultaneously to Band D. SAT 3/3/2010 49 H 2 E 064A1.03 (Hydro units perform the same function as EDGs). Question appears to match the KIA. Because this is a 2009 exam question, attempt to change the second half of the distractors. What will the result of the higher voltage; increase in reactive load etc. We can do something to change the question (this is the fourth question that is repeated, including the SRO portion from the last two exams. BANK 2009 NRC EXAM Made some changes will look at minimum indication that can be seen on meter. Changed to

10. SAT 3/3/2010

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q I

SRO U/El Explanation Focus Dist. Link units ward K/A Only S 50 H 2 E 064A2.02 Question kind of matches KIA. The KHUs are the backup supply for electrical power at Ocoriee and some items in the K/A cannot be tested. Accepted Speed (Over-speed condition) to meet K/A. Distractor D does not appear to be plausible, if another unit sent the emergency start signal to the KHU why would an unaffected unit have to enter AP-1 1? Need to replace second part of distractor D. NEW Changed second part of distractor 0. Sat 3/3/2010 51 H 2 S 073K5.01 Question appears to match K/A. SAT BANK 2006 NRC EXAM 52 H 2 E 076A2.02 Question appears to match the K/A. Remove the water hammer prevention from distractors B and D. Otherwise SAT NEW Removed water hammer prevention form distractors B and D. SAT 31312010

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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 Dis!. Link units ward KIA Only S 50 H 2 E 064A2.02 Question kind of matches KIA. The KHUs are the backup supply for electrical power at Oconee and some items in the KIA cannot be tested. Accepted Speed (Over-speed condition) to meet KIA. Distractor D does not appear to be plausible, if another unit sent the emergency start signal to the KHU why would an unaffected unit have to enter AP-11? Need to replace second part of distractor D. NEW Changed second part of distractor D. Sat 3/3/2010 51 H 2 S 073K5.01 Question appears to match KIA. SAT BANK 2006 NRC EXAM 52 H 2 E 076A2.02 Question appears to match the KIA. Remove the water hammer prevention from distractors Band D. Otherwise SAT NEW Removed water hammer prevention form distractors Band D. SAT 3/3/2010

103G2.1.20 Question kind of matches the K/A. If an operator is required to OPEN the valve, does the operator have to remain on station to ensure that the valve closes on a subsequent ESF signal? (I am assuming that the valves normal position on containment isolation is closed). If the letdown hi temperature bypass interlock switch is used, could the valve be opened from the control room? It seems that opening the valve locally will over ride any other signals. Not sure C and D are plausible. NEW Still Need to work on this question. 3/3/2010 Made changes to C and D distractors. SAT 311012010 103G2.4.20 Question appears to match the K/A. SAT. 1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem cues TIE cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 53 H 2 X E 078A4.01 Question appears to match K/A. Not sure if B and or C is plausible. If the primary Air Compressor is running initially, what would cause it to not be running in B or C? Need to work on these two distractors. May need to add primary air compressors to them. MODIFIED BANK need to see original to count as modified. Placed Primary Air comp in stem, added only to all responses. SAT 3/3/2010 54 H 2 x U NEW

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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 UtEI Explanation Focus Dis!. Link units ward KIA Only S 53 H 2 X E 078A4.01 Question appears to match KIA. Not sure if B and or C is plausible. If the primary Air Compressor is running initially, what would cause it to not be running in B or C? Need to work on these two distractors. May need to add primary air compressors to them. MODIFIED BANK need to see original to count as modified. Placed Primary Air comp in stem, added only to all responses. SAT 3/3/2010 54 H 2 X U 1 03G2.1.20 Question kind of matches the KIA. If an operator is required to "OPEN" the valve, does the operator have to remain on station to ensure that the valve closes on a subsequent ESF signal? (I am assuming that the valves normal position on containment isolation is closed). If the letdown hi temperature bypass interlock switch is used, could the valve be opened from the control room? It seems that opening the valve locally will over ride any other signals. Not sure C and D are plausible. NEW Still Need to work on this question. 3/3/2010 Made changes to C and D distractors. SAT 3/10/2010 55 F 2 S 103G2.4.20 Question appears to match the KIA. SAT. NEW

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link Junits ward K/A Only S 56 H 2 E 002A4.08 Question appears to match the K/A (as discussed using OAC instead of SPDS). How can you tell from the print out that the reactor tripped on an AFIS actuation? f a MSLB occurs is this always the parameter that will trip the reactor? If so, why do we have it listed. You have for different accidents as the 4 responses, if you want to use the second parts we should narrow it down to MSLB and or loss of feed and then list trips. As the question is written now distractor B is not plausible (no RB pressure and RCS pressure approx 1600 psi). NEW Made changes as requested. SAT 31312010 57 F 2 X E 011 K2.02 Question appears to match K/A. Low discriminatory value. Stem should state Which one of the following is the power supply for Unit 1 Group B heaters. I also believe that D is the correct answer. You Have A as the correct answer on the key. Is this heater group a safety related heater group, and its power supply safety related. If so at least one of the other power supplies should be safety related. NEW Made changes as requested. SAT 3/3/2010

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. /

Back-Q= SRO U/E/ Explanation Focus Dis!. Link units ward KIA Only S 56 H 2 E 002A4.08 Question appears to match the KIA (as discussed using OAC instead of SPDS). How can you tell from the print out that the reactor tripped on an AFIS actuation? If a MSLB occurs is this always the parameter that will trip the reactor? If so, why do we have it listed. You have for different accidents as the 4 responses, if you want to use the second parts we should narrow it down to MSLB and or loss of feed and then list trips. As the question is written now distractor B is not plausible (no RB pressure and RCS pressure approx 1600 psi). NEW Made changes as requested. SAT 3/3/2010 57 F 2 X E 011 K2.02 Question appears to match KIA. Low discriminatory value. Stem should state Which one of the following is the power supply for Unit 1 Group B heaters. I also believe that 0 is the correct answer. You Have A as the correct answer on the key. Is this heater group a safety related heater group, and its power supply safety related. If so at least one of the other power supplies should be safety related. NEW Made changes as requested. SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues TIE Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. js ward K/A Only S 58 F 2 S 029A2.04 Question does not meet the (a) part of the K/A, but meets the (b) part of the K/A. SAT BANK 2007 NRC EXAM SAT 3/3/2010 59 F 2 S 033A3.02 Question appears to match the K/A. SAT NEW SAT 3/3/2010 60 H 2 S 041K6.03 Question appears to match the K/A SAT NEW SAT 3/3/2010 61 H 2 E 045K3.0l Question appears to match the K/A. Distractor C is not plausible. If these valves are MOVs air being dumped is not plausible. BANK Will ensure that 0 is correct, and that B is truly incorrect. 3/412010 Rewrote question to make it easier to read, changed to Reactor Trip (infers a turbine trip) and asked what would happen to valves SAT 3/10/2010

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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. /

Back-Q= SRO U/E/ Explanation Focus Dist. Link units ward KIA Only S 58 F 2 S 029A2.04 Question does not meet the (a) part of the KIA, but meets the (b) part of the KIA. SAT BANK 2007 NRC EXAM SAT 3/3/2010 59 F 2 S 033A3.02 Question appears to match the KIA. SAT NEW SAT 3/3/2010 60 H 2 S 041 K6.03 Question appears to match the KIA SAT NEW SAT 3/3/2010 61 H 2 E 045K3.01 Question appears to match the KIA. Distractor C is not plausible. If these valves are MOVs air being dumped is not plausible. BANK Will ensure that D is correct, and that B is truly incorrect. 3/4/2010 Rewrote question to make it easier to read, changed to Reactor Trip (infers a turbine trip) and asked what would happen to valves SAT 3/10/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD (F/H) (1-5) Stem Cuesi T/F Cred. Partial Job-Minutia

1. 1 Back-Q SRO U/E/

Explanation Focus Dist. Link units ward K/A Only S 62 H 2 X U 056G2.2.44 Question appears to match the K/A. There are two signals that will auto start the other CBPs if they are placed in Auto. So why would anyone pick C or D? As written these are not plausible. Need to make C and D plausible Will discuss. NEW Upon discussion will let question stand as is. SAT 3/4/2010 63 F 2 S 072K1.03 Question appears to match K/A. SAT NEW 64 H 2 S 079K4.01 Question appears to match K/A. SAT NEW

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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 Dis!. Link units ward KIA Only S 62 H 2 X U 056G2.2.44 Question appears to match the KIA. There are two signals that will auto start the other CBPs if they are placed in Auto. So why would anyone pick C or D? As written these are not plausible. Need to make C and 0 plausible Will discuss. NEW Upon discussion will let question stand as is. SAT 3/4/2010 63 F 2 S 072K1.03 Question appears to match KIA. SAT NEW 64 H 2 S 079K4.01 Question appears to match KIA. SAT NEW

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus j Dist. Link units ward K/A Only S 65 F 2 E 086K5.03 Question kind of matches K/A as discussed with staff. However, you tell them that the bus is de-energized. Try a two by two with different components powered from different buses in the area and what would cause the bust to be de energized. (Grounding of bus due to water spray). NEW Rewrote question still need to modify stem to discuss what relay actuated to de-energize bus. 3/412010 Added a 51G relay actuates (this de-energizes the bus. SAT 3I10/2010 66 F 2 E G2.1.36 Question appears to match K/A. Need to add a statement about fuel movement. As written the correct answer is B. (Core alterations are mentioned in the stem, but the procedure specifically states core geometry or positive reactivity changes and does not use the word core alterations. Post exam someone could argue this point. NEW Removed core alterations from stem. SAT 3I4/2010 67 H 2 S G2.1.45 Question appears to match K/A. SAT NEW

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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 UtEI Explanation Focus Dist. Link units ward KIA Only S 65 F 2 E 086K5.03 Question kind of matches KIA as discussed with staff. However, you tell them that the bus is de-energized. Try a two by two with different components powered from different buses in the area and what would cause the bust to be de-energized. (Grounding of bus due to water spray). NEW Rewrote question still need to modify stem to discuss what relay actuated to de-energize bus. 3/4/2010 Added a 51 G relay actuates (this de-energizes the bus. SAT 3/10/2010 66 F 2 E G2.1.36 Question appears to match KIA. Need to add a statement about fuel movement. As written the correct answer is B. (Core alterations are mentioned in the stem, but the procedure specifically states core geometry or positive reactivity changes and does not use the word core alterations. Post exam someone could argue this point. NEW Removed core alterations from stem. SAT 3/4/2010 67 H 2 S G2.1.45 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 TIF Cred. Partial Job-Minutia

1. /

Back-Q= SRO U/E/ Explanation Focus Dist. Link unitsi ward K/A Only S 68 F 2 E G2.2.25 Question appears to match KIA. Change spray valves to PORVs. Spray valves do limit pressure however are not normally used for preventing exceeding high pressure limits. PORVs are designed usually to prevent safety valves from lifting but are not safety related and not considered in RCS protection schemes. Question will then be SAT NEW Made changes as requested also made changes to stem. SAT 3/412010 69 F 2 S G2.2.39 Question appears to match K/A. SAT NEW 70 F 2 S G2.2.42 Question appears to match KA. SAT NEW 71 F 2 S G2.3.1 I Question appears to match K/A. SAT Modified from 2004 NRC Exam question

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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 68 F 2 E G2.2.25 Question appears to match KIA. Change spray valves to PORVs. Spray valves do limit pressure however are not normally used for preventing exceeding high pressure limits. PORVs are designed usually to prevent safety valves from lifting but are not safety related and not considered in RCS protection schemes. Question will then be SAT NEW Made changes as requested also made changes to stem. SAT 3/4/2010 69 F 2 S G2.2.39 Question appears to match KIA. SAT NEW 70 F 2 S G2.2.42 Question appears to match KA. SAT NEW 71 F 2 S G2.3.11 Question appears to match KIA. SAT Modified from 2004 NRC Exam question

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues TIF Cred. Partial Job-Minutia

1. 1 Back-Q=

SRO UIE/ Explanation Focus Dist. Link units ward K/A Only S 72 F 2 X E G2.3.12 Question Kind of matches K/A. Distractor D does not appear to be plausible. Why would any one think that the RB must be evacuated if the running LPI pump loses power? Another question on the exam tests whether we can secure a pump for 1 hour. Replace distractor D. NEW Replaced distractor D. SAT 31412010 73 F 2 S G2.3.7 Question appears to match K/A. SAT Modified Bank (need to see original) 74 F 2 X E G2.4.16 Question appears to match K/A. Need to reword distractors C and D. C. RO will begin AP-1 1 actions. SRO will continue in EOP. SRO can re-direct RO actions. D. RO will begin AP-1 1 actions. SRO will continue in EOP. RO must remain in AP-1 1 until the procedure is complete. NEW Made changes as requested SAT 3/4/2010

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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 72 F 2 X E G2.3.12 Question Kind of matches KIA. Distractor D does not appear to be plausible. Why would anyone think that the RB must be evacuated if the running LPI pump loses power? Another question on the exam tests whether we can secure a pump for 1 hour. Replace distractor D. NEW Replaced distractor D. SAT 3/4/201 0 73 F 2 S G2.3.7 Question appears to match KIA. SAT Modified Bank (need to see original) 74 F 2 X E G2.4.16 Question appears to match KIA. Need to reword distractors C and D. C. RO will begin AP-11 actions. SRO will continue in EOP. SRO can re-direct RO actions. D. RO will begin AP-11 actions. SRO will continue in EOP. RO must remain in AP-11 until the procedure is complete. NEW Made changes as requested SAT 3/4/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

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

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. Link units ward KIA Only S 75 F 2 X U G2.4.26 Question appears to match KIA. Distractors C and D are not plausible as written. Try dispatch a qualified NEO (or some position that not qualified Fire Brigade). Made changes to C and D and changed stem. SAT 31412010 39 Sats, 9 Unsats, and 27 Enhancements

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 75 F 2 X U G2.4.26 Question appears to match KJA. Distractors C and 0 are not plausible as written. Try dispatch a qualified NEO (or some position that not qualified Fire Brigade). Made changes to C and 0 and changed stem. SAT 3/4/2010 39 Sats, 9 Unsats, and 27 Enhancements

ES-401, Rev. 9 Oconee 2010-301 SRO Written Examination Review Worksheet FINAL Form ES-401-9 1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

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

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link Instructions [Refer to Section D of ES-401 and Appendix B for additiona information regarding each of the following concepts.] 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 ajob content error is identified: The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content). The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements. 5. Check questions that are sampled for conformance with the approved K/A and those that are designated SR0-only (K/A and license level mismatches are unacceptable). 6. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory? 7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met). ES-401, Rev. 9 Oconee 2010-301 SRO Written Examination Review Worksheet FINAL Form ES-401-9

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

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

1. 1 Back-Q=

SRO UtEI Explanation Focus Dis!. units ward KIA Only S Link Instructions [Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1.

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

2.

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

3.

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

4.

Check the appropriate box ifajob content error is identified: The question is not linked to the job requirements (i.e., the question has a valid K/ A but, as written, is not operational in content). The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements.

5.

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

6.

Based on the 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 "UH ratings (e.g., how the Appendix B psychometric attributes are not being met).

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q SRO U/E/

Explanation Focus Dist. units ward K/A Only S Link 1/76 H 2 X E OIIEG2.4.41 Question appears to match K/A. Question appears to be SRO only. Distractor A is not plausible. LBLOCA in progress (leak> 160 gpm is an alert), so the Unusual Event is not plausible. Is 35 # in containment operationally valid for the entire RCS being released without RB spray or cooling, or should this pressure be higher? You might try doing a two by two format with an additional item, for example: A. Alert based on... B. Alert based on... C. Site Area based on D. Site Area based on... NEW Changed question as requested. SAT 3/312010 2/77 H 2 S 026G2.1.23 Question appears to match K/A. Question appears to be SRO only. 2009 Oconee exam question-BANK Question SAT 3/3/2010

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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 UtEI Explanation Focus Dist. units ward KIA Only S Link 1/76 H 2 X E 011 EG2.4.41 Question appears to match KIA. Question appears to be SRO only. Distractor A is not plausible. LBLOCA in progress (leak> 160 gpm is an alert), so the Unusual Event is not plausible. Is 35 # in containment operationally valid for the entire RCS being released without RB spray or cooling, or should this pressure be higher? You might try doing a two by two format with an additional item, for example: A. Alert based on... B. Alert based on... C. Site Area based on... D. Site Area based on... NEW Changed question as requested. SAT 3/3/2010 2/77 H 2 S 026G2.1.23 Question appears to match KIA. Question appears to be SRO only. 2009 Oconee exam question-BANK Question SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues TIF Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/El Explanation Focus Dist. units ward K/A Only S Link H 2 E 027AA2.09 Question kind of matches KJA. With 3/78 basis information, appears to be SRO only. What is the maximum temperature of 375 °F based on? After reading the technical specification, the plant could be a any temperature up to normal operating temperature. Is D a correct answer? In reading the distractor analysis, it does not make sense to me. I could be at 380°F or 400 °F. Please explain. NEW Made changes as requested. SAT 3/312010

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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. units ward KIA Only S Link H 2 E 027 AA2.09 Question kind of matches KIA. With 3/78 basis information, appears to be SRO only. What is the maximum temperature of 375 of based on? After reading the technical specification, the plant could be a any temperature up to normal operating temperature. Is 0 a correct answer? In reading the distractor analysis, it does not make sense to me. I could be at 380°F or 400 of. Please explain. NEW Made changes as requested. SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link H 2 X X U 029EA2.02 Question appears to match K/A. 4/79 Not SRO only. Typically procedures are written assuming one train of power is available. If a blackout was in process the team would have to enter the blackout procedure because any other procedure would not be effective. Entry conditions for all EOP/AOPs are considered RO knowledge. Therefore this questions is not SRO only. Also need to determine if blackout tab is the only transfer out of the UNPP. It appears that the parallel action page directs several different procedures to be performed based on plant conditions. Why is distractors A and C plausible? Reactor Vessel heal level 0 inches, does not seem plausible. NEW Changed second part of question to actions that are directed in the UNPP, while the individuals were performing rules. SAT 31312010

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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 Dis!. units ward KIA Only S Link H 2 X X U 029EA2.02 Question appears to match KIA. 4/79 Not SRO only. Typically procedures are written assuming one train of power is available. If a blackout was in process the team would have to enter the blackout procedure because any other procedure would not be effective. Entry conditions for all EOP/AOPs are considered RO knowledge. Therefore this questions is not SRO only. Also need to determine if blackout tab is the only "transfer" out of the UNPP. It appears that the parallel action page directs several different procedures to be performed based on plant conditions. Why is distractors A and C plausible? Reactor Vessel heal level = 0 inches, does not seem plausible. NEW Changed second part of question to actions that are directed in the UNPP, while the individuals were performing rules. SAT 3/3/2010

Q# LOK LCD

1. 2.

3. Psychometric Flaws

4. Job Content Flaws 5.

7. (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. /

Back-Q= SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link H 2 X X U 058G2.4.1 I Question kind of matches the K/A, 5/80 Distractors A and B do not appear to be plausible. There is an IAAT step that states if the reactor trips and lOS auto power is not available then trip the reactor. (that would make this a RO knowledge element) The lesson material for RPS objective 4 also describes the reason for the anticipatory trip and has it listed as an RO objective. Therefore the question is not SRO only. NEW Requested K/A Change. Changed to 058G2.2.23. Replaced question, made changes to stem. SAT 3/3/2010

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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. units ward KIA Only S Link H 2 X X U 058G2.4.11 Question kind of matches the KIA, 5/80 Distractors A and B do not appear to be plausible. There is an IAAT step that states if the reactor trips and ICS auto power is not available then trip the reactor. (that would make this a RO knowledge element) The lesson material for RPS objective 4 also describes the reason for the anticipatory trip and has it listed as an RO objective. Therefore the question is not SRO only. NEW Requested KIA Change. Changed to 058G2.2.23. Replaced question, made changes to stem. SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link H 2 X U BEO4EA2.1 Question appears to match K/A. 6/81 Question appears to be SRO only. Distractors A and B are like subsets of each other. If the procedure directed an immediate transfer based on having the TDEFWP available, then why would it not direct an immediate transfer based on having condensate booster pump feed available? Therefore A and B are not plausible. Distractor C does not appear to be plausible either in that this EOP would be used even if at power in conjunction with other procedures, so why would anyone leave the LOHT tab to go the SGTR procedure. Need to enhance/replace distractors? NEW Changed 3 distractors and portions of the stem SAT 3/3/2010.

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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 utEI Explanation Focus Dis!. units ward KIA Only S Link H 2 X U BE04EA2.1 Question appears to match K/A. 6/81 Question appears to be SRO only. Distractors A and B are like subsets of each other. If the procedure directed an immediate transfer based on having the TDEFWP available, then why would it not direct an immediate transfer based on having condensate booster pump feed available? Therefore A and B are not plausible. Distractor C does not appear to be plausible either in that this EOP would be used even if at power in conjunction with other procedures, so why would anyone leave the LOHT tab "to go" the SGTR procedure. Need to enhance/replace distractors/ NEW Changed 3 distractors and portions of the stem SAT 3/3/2010.

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q SRO U/El Explanation Focus Dist.

units ward K/A Only S Link 2 H X X U 032G2A.45 Question kind of matches K/A at 7/82 the RO level, but we are not testing the K/A at the SRO level Only one annunciator deals with NIs. Chief examiner allowed question that deals with a loss of Nis associated with this alarm. Second part of question appears to be SRO only knowledge but has nothing to do with the KA. I am not sure how these items relate to each other? What happens if a startup is in progress and an NI (like this one fails) do you stop the start up? If we keep the original question the second part of distractors should have the, modes 3 and 4 removed from the distractor. Mode 3 is stated in the stem. NEW Changed second part of question to actions allowed by Technical Specifications. SAT 3/32010.

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 Dis!. units ward KIA Only S Link 2 H X X U 032G2.4.45 Question kind of matches KIA at 7/82 the RO level, but we are not testing the KIA at the SRO level Only one annunciator deals with Nls. Chief examiner allowed question that deals with a loss of Nls associated with this alarm. Second part of question appears to be SRO only knowledge but has nothing to do with the KA. I am not sure how these items relate to each other? What happens if a startup is in progress and an NI (like this one fails) do you stop the start up? If we keep the original question the second part of distractors should have the, modes 3 and 4 removed from the distractor. Mode 3 is stated in the stem. NEW Changed second part of question to actions allowed by Technical Specifications. SAT 3/32010.

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link H 1 X X U 033AG2.1.23 Question kind of matches K/A, but not 8/83 at the SRO level. Using TIS as the procedure is not optimum but sometimes okay, however in this case the K/A asks for specific system and integrated plant procedures, therefore I do not think this is appropriate. Is it operationally valid for all wide range Nis to fail low at the same time? The first part of the question is RD knowledge, (1 hr T/S). The second part of the distractors appears to be the reason you have wide range Nis, and believe this is RD knowledge (function of system). Maybe you can enlighten me. Just because the component is in the bases document does not mean that it is SRO only knowledge. If the basis is the system function, then the knowledge is at the RD level. At what level would Rx power be while withdrawing just the safety banks? Question is also not very discriminating. SELECT NEW KIA. NEW Changed to BWO8G2.1.20 Question sub mitted for this KIA meets the KIA. Appears to be SRO only. SAT 31312010

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. units ward KIA Only S Link H 1 X X U 033AG2.1.23 Question kind of matches KIA, but not 8/83 at the SRO level. Using TIS as the procedure is not optimum but sometimes okay, however in this case the KIA asks for specific system and integrated plant procedures, therefore I do not think this is appropriate. Is it operationally valid for all wide range Nls to fail low at the same time? The first part of the question is RO knowledge, (1 hr TIS). The second part of the distractors appears to be the reason you have wide range Nls, and I believe this is RO knowledge (function of system). Maybe you can enlighten me. Just because the component is in the bases document does not mean that it is SRO only knowledge. If the basis is the system function, then the knowledge is at the RO level. At what level would Rx power be while withdrawing just the safety banks? Question is also not very discriminating. SELECT NEW KIA. NEW Changed to BW08G2.1.20 Question sub mitted for this KIA meets the KIA. Appears to be SRO only. SAT 3/3/2010

1. 2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q SRO U/E/

Explanation Focus Dist. units ward K/A Only S Link H 2 X X U BAOIAA2.I Question appears to match the K/A 9/84 at the RO level. Question is not testing the K/A at the SRO level. The part of the question that appears to be SRO knowledge is not related to the K/A. Procedure entry conditions are RO knowledge. NEW Rewrote question INot sure that question is SRO only. Will ask another examiner. APII5 was the dropped rod procedure, but is not used anymore, API runback is used. This is a new change. Gerry will get back to Licensee.313/201 0 Had two other examiners review the question. Not SRO only. Replaced KIA. BAOIAAI.1. New Question SAT 3123/2010

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3. Psychometric Flaws

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

1. /

Back-Q= SRO U/E/ Explanation Focus Dis!. units ward KIA Only S Link H 2 X X U BA01AA2.1 Question appears to match the KIA 9/84 at the RO level. Question is not testing the KIA at the SRO level. The part of the question that appears to be SRO knowledge is not related to the KIA. Procedure entry conditions are RO knowledge. NEW Rewrote question INot sure that question is SRO only. Will ask another examiner. AP/15 was the dropped rod procedure, but is not used anymore, AP1 run back is used. This is a new change. Gerry will get back to Licensee.3/3/2010 Had two other examiners review the question. Not SRO only. Replaced KIA. BA01AA1.1. New Question SAT 3/23/2010

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(FIH) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. /

Back-Q= SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link H 2 X X U BAO4 AA2.2 Question does not meet the K/A. While a turbine trip has occurred, the actions 10/85 that are being tested are for the stuck rod. If the reactor had tripped for any other reason the actions would be the same, It also appears that the basis portion of the question is in the Main steam lesson material under the discussion for Main steam stop valves (turbine stop valves). Therefore I do not believe that this is SRO only knowledge. I do not believe that as written there is a correct answer, unless the unit 2 HPI pumps can take a suction from Unit 1. NEW Rewrote question appeared to match KIA. appears to be SRO only. SAT 3/3/2010

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3. Psychometric Flaws

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

1. 1 Back-Q=

SRO u/EI Explanation Focus Dis!. units ward KIA Only S Link H 2 X X U BA04 AA2.2 Question does not meet the KIA. 10/85 While a turbine trip has occurred, the actions that are being tested are for the stuck rod. If the reactor had tripped for any other reason the actions would be the same. It also appears that the basis portion of the question is in the Main steam lesson material under the discussion for Main steam stop valves (turbine stop valves). Therefore I do not believe that this is SRO only knowledge. I do not believe that as written there is a correct answer, unless the unit 2 HPI pumps can take a suction from Unit 1. NEW Rewrote question appeared to match KIA. appears to be SRO only. SAT 3/3/2010

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job Minutia j I Back-Q= SRO UIE/ Explanation Focus Dist. units ward K/A Only S Link H 2 U 003A2.02 Question appears to match K/A. Why do you state in the stem and a natural Circ 1 1/86 cooldown is required? This is teaching in the stem. Without a LOCA in progress why would anyone go to the LOCA Cooldown procedure? This makes B and D not plausible. There are several ways to make this question acceptable. The procedure flow path that you sent with the question is not correct with respect to proceeding through the AR NEW Increased leakage to 140 gpm to make distractors plausible. SAT 3/3/2010. H 2 X X U 022A2.04 Question appears to match the K/A at the RD level. Does not appear to be SRO only. 12/87 The first part of the question is above the line on TS 3.6.5 (making it RO knowledge) and because the second part is < 1 hour, and immediately it is also RD knowledge. There are several ways to fix this question also. NEW Need to change one of 87 or 88 Still need to fix second half (SRO only portion) Added 3.03 statement and hours to be in mode 3. SAT 3110/2010

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3. Psychometric Flaws

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

1. 1 Back-Q=

SRO UtEI Explanation Focus Dist. units ward KIA Only S Link H 2 U 003A2.02 Question appears to match KIA. Why 11/86 do you state in the stem "and a natural Circ cooldown is required"? This is teaching in the stem. Without a LOCA in progress why would anyone go to the LOCA Cooldown procedure? This makes Band D not plausible. There are several ways to make this question acceptable. The procedure flow path that you sent with the question is not correct with respect to proceeding through the AP. NEW Increased leakage to 140 gpm to make distractors plausible. SAT 3/3/2010. H 2 X X U 022A2.04 Question appears to match the KIA at the RO level. Does not appear to be SRO only. 12/87 The first part of the question is above the line on TS 3.6.5 (making it RO knowledge) and because the second part is < 1 hour, and immediately it is also RO knowledge. There are several ways to fix this question also. NEW Need to change one of 87 or 88 Still need to fix second half (SRO only portion) Added 3.03 statement and hours to be in mode 3. SAT 3/10/2010

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

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

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Back-Q SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link 13/88 H 2 X X U 026A2.04 Question appears to match K/A at the RO level, is not meeting K/A at the SRO level. Does not appear to be SRO only. The first part of the question deals with systems knowledge o what is required to satisfy the ESF function (RO knowledge). The second part of the question deals with RO actions, again this is RO knowledge. What would be SRO specific knowledge in relation to basis or T/S? May need to change the K/A. PNS systems not included in references. NEW Need to change one of 87 or 88 Changed K/A to 062A2.04 Replaced Question Appears to match KIA, SRO only. SAT H 2 X E 059G2.2.42 Question appears to match K/A. 14/89 May be SRO only, more discussion is needed. The stem of the question asks for the conditions that would require entry into the EOP, and the INITIAL actions required by the EOP.... Are these actions considered initial? Question needs some enhancements. NEW Made changes to stem to correct problems. SAT 31312010.

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3. Psychometric Flaws

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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. units ward KIA Only S Link 13/88 H 2 X X U 026A2.04 Question appears to match KIA at the RO level, is not meeting KIA at the SRO level. Does not appear to be SRO only. The first part of the question deals with systems knowledge 0 what is required to satisfy the ESF function (RO knowledge). The second part of the question deals with RO actions, again this is RO knowledge. What would be SRO specific knowledge in relation to basis or TIS? May need to change the KIA. PNS systems not included in references. NEW Need to change one of 87 or 88 Changed KIA to 062A2.04 Replaced Question Appears to match KIA, SRO only. SAT H 2 X E 059G2.2.42 Question appears to match KIA. 14/89 May be SRO only, more discussion is needed. The stem of the question asks for the conditions that would require entry into the EOP, and the INITIAL actions required by the EOP.... Are these actions considered initial? Question needs some enhancements. NEW Made changes to stem to correct problems. SAT 3/3/2010.

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/El Explanation Focus Dist. units ward K/A Only S Link H 2 U 103G2.4.9 Question appears to match the K/A 15/90 at the RO level, but not at the SRO level. The piece of the question that appears to be addressing the SRO level of the question may also be RO systems knowledge. But in any case the KA is not matched at the SRO level. NEW Replaced Question Appears to be SRO only, and match K/A. SAT 3/3/2010. H 2 X X U 011A2.06 Question appears to match the KA at 16/91 the RO level. First partof the answers/distractors is systems (RO) knowledge and deals with how a stuck open spray valve effects the level control system as required by the K/A. The second part of the question can also be answered using systems knowledge. If I understand the first part of the question (that this failure has no effect on IHP-120, why would I throttle it? NEW Changed 2 part of question and two distractors. SAT. 3/312010

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

1. 1 Back-Q=

SRO UtEI Explanation Focus Dist. units ward KIA Only S Link H 2 U 103G2.4.9 Question appears to match the KIA 15/90 at the RO level, but not at the SRO level. The piece of the question that appears to be addressing the SRO level of the question may also be RO systems knowledge. But in any case the KA is not matched at the SRO level. NEW Replaced Question Appears to be SRO only, and match KIA. SAT 3/3/2010. H 2 X X U 011A2.06 Question appears to match the KA at 16/91 the RO level. First part of the answersldistractors is systems (RO) knowledge and deals with how a stuck open spray valve effects the level control system as required by the KIA. The second part of the question can also be answered using systems knowledge. If I understand the first part of the question (that this failure has no effect on 1HP-120, why would I throttle it? NEW Changed 2nd part of question and two distractors. SAT. 3/3/2010

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Q LOK LOD

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I (F/H)

(1-5) Stem Cues TIE Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/El Explanation Focus Dist. units ward K/A Only S Link H 2 U 027G2.2.40 Question appears to match the K/A. 17/92 May not be SRO only. The purpose for the TSP is to keep the iodine in solution, preventing high offsite doses. (this is RD knowledge). Also the TSP is only used when on recirculation phase, also systems knowledge. Although these statements are in the basis, they are system/purpose knowledge that is typically required for all ROs. Distractors A and B do not appear to be plausible. How would going to single Reactor Building spray pump operation help with inadequate TSP volume? NEW Replaced first part of distractors. SAT 3/3/2010. H 2 S 072G2.4.4 Question appears to match K/A. 18/93 Appears to be SRO only. NEW

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dis!. units ward KIA Only S Link H 2 U 027G2.2.40 Question appears to match the KIA. 17/92 May not be SRO only. The purpose for the TSP is to keep the iodine in solution, preventing high offsite doses. (this is RO knowledge). Also the TSP is only used when on recirculation phase, also systems knowledge. Although these statements are in the basis, they are system/purpose knowledge that is typically required for all ROs. Distractors A and B do not appear to be plausible. How would going to single Reactor Building spray pump operation help with inadequate TSP volume? NEW Replaced first part of distractors. SAT 3/3/2010. H 2 S 072G2.4.4 Question appears to match K/A. 18/93 Appears to be SRO only. NEW

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3. Psychometric Flaws

4. Job Content Flaws

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7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/El Explanation Focus Dist. units ward K/A Only S Link H 2 E G2.1.14 Question appears to match K/A, and 19/94 may be SRO only, but the second part of the stem seems to point the applicant in the direction of the SGTR. Consider changing the stem to read Which ONE.... AND whether to include the leakage when calculating the RCS pressure boundary leakage (gpm) in accordance with TS... Consider changing the RCS leakage to something higher, but less than the 160 stated in procedure AP-2 NEW Changed stem and distractors. SAT 313/2010 H 2 E G2.1.41 Question appears to match K/A. 20/95 Appears to be SRO only knowledge. The FTC level in the initial conditions needs to be a value greater than the TS limit, but not >21.34 feet. What is the normal value of the FTC when refueling? BANK 2009 NRC EXAM Made changes as requested. SAT. 31312010

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3. Psychometric Flaws

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

1. 1 Back-Q=

SRO u/EI Explanation Focus Dis!. units ward KIA Only S Link H 2 E G2.1.14 Question appears to match KIA, and 19/94 may be SRO only, but the second part of the stem seems to point the applicant in the direction of the SGTR. Consider changing the stem to read Which ONE.... AND whether to include the leakage when calculating the RCS pressure boundary leakage (gpm) in accordance with TS... Consider changing the RCS leakage to something higher, but less than the 160 stated in procedure AP-2 NEW Changed stem and distractors. SAT 3/3/2010 H 2 E G2.1.41 Question appears to match KIA. 20/95 Appears to be SRO only knowledge. The FTC level in the initial conditions needs to be a value greater than the TS limit, but not" >21.34 feet". What is the normal value of the FTC when refueling? BANK 2009 NRC EXAM Made changes as requested. SAT. 3/3/2010

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3. Psychometric Flaws

4. Job Content Flaws

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7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia j

1. 1 Back-Q SRO U/E/

Explanation Focus Dist. units ward K/A Only S Link H 2 X E G2.2.2 Question appears to match K/A. 21/96 Appears to contain some SRO knowledge. With the plant in the current conditions, is the plant in the unacceptable region, and is the listed consequence applicable? If so, then the question is SAT. If not then there is some more work to do. Is there anything wrong with performing A? If not this could be considered a correct answer. Do quadrant power tilt limits apply with reactor power less than 50%? If not then distractors B and D are not plausible. Completely rewrote question Appears to be SRO only. SAT 3/3/2010 H 2 X X U G2.2.35 Question appears to match K/A at the 22/97 RO level. It does not appear to be at the SRO level. All items being tested are plant mode (RO knowledge) and whether a DHR loop that is not aligned for cooldown is considered operable. This item is above the line on the TS 3.4.7, and 3.4.6, and is considered RO knowledge. Are all RCS loops filled? The stem does not mention this. NEW Changed stem and distractors SAT. 31312010

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3. Psychometric Flaws

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5. Other

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

1. 1 Back-Q=

SRO u/EI Explanation Focus Dis!. units ward KIA Only S Link H 2 X E G2.2.2 Question appears to match KIA. 21/96 Appears to contain some SRO knowledge. With the plant in the current conditions, is the plant in the unacceptable region, and is the listed consequence applicable? If so, then the question is SAT. If not then there is some more work to do. Is there anything wrong with performing A? If not this could be considered a correct answer. Do quadrant power tilt limits apply with reactor power less than 50%? If not then distractors Band 0 are not plausible. Completely rewrote question Appears to be SRO only. SAT 3/3/2010 H 2 X X U G2.2.35 Question appears to match KIA at the 22/97 RO level. It does not appear to be at the SRO level. All items being tested are plant mode (RO knowledge) and whether a OHR loop that is not aligned for cooldown is considered operable. This item is above the line on the TS 3.4.7, and 3.4.6, and is considered RO knowledge. Are all RCS loops filled? The stem does not mention this. NEW Changed stem and distractors SAT. 3/3/2010

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

7. Q# LOK LOD

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia

1. 1 Back-Q=

SRO U/El Explanation Focus Dist. units ward K/A Only S Link H 2 X X U G2.3.4 Question appears to match the K/A at 23/98 the RO level. Does not appear to meet it at the SRO level. NEW Rewrote question with whose permission is required lAW EPIPs. SAT 3/3/2010 H 2 S G2.4.27 Question appears to match K/A. Need 24/99 to ensure that the reference does not aide in answering any other questions. SAT NEW SAT 31312010

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3. Psychometric Flaws

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

1. 1 Back-Q=

SRO U/EI Explanation Focus Dist. units ward KIA Only S Link H 2 X X U G2.3.4 Question appears to match the KIA at 23/98 the RO level. Does not appear to meet it at the SRO level. NEW Rewrote question with whose permission is required lAW EPIPs. SAT 3/3/2010 H 2 S G2.4.27 Question appears to match KIA. Need 24/99 to ensure that the reference does not aide in answering any other questions. SAT NEW SAT 313/2010

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3. Psychometric Flaws

4. Job Content Flaws

5. Other 6.

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

1. 1 Back-Q=

SRO U/E/ Explanation Focus Dist. units ward K/A Only S Link H 2 X E G2.4.8 Question appears to match the K/A. 25/1 00 Similar in respect to a SGTR as question #94. Does any part of API31, or the SGTR tab direct draining the SG to the Hotwell? If not this is probably not plausible. Is this operationally valid, can the OTSG level approach overfill conditions at 75% power and only a 28 gpm leak. It appears that the question is actually asking for what happens after the plant is offline and a cooldown is initiated. If so is should be explained in a more clear manner. Does AP/31 have actions do deal with SGTL if it is less than 25 gpm? If it does not then question needs to be re-written. NEW Rewrote question to address concerns, including stating the Isolated SC. SAT 3/3/2010 3 Sats, 15 Unsats, and 7 Enhancements Several of these questions were rated as unsatisfactory due to the same error. The licensee reworked/replaced these questions and they were not counted as unsat.

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3. Psychometric Flaws

4. Job Content Flaws

5. Other

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

1. 1 Back-Q=

SRO UtEI Explanation Focus Dist. units ward KIA Only S Link H 2 X E G2.4.8 Question appears to match the KIA. 25/100 Similar in respect to a SGTR as question #94. Does any part of AP/31, or the SGTR tab direct draining the SG to the Hotwell? If not this is probably not plausible. Is this operationally valid, can the OTSG level approach overfill conditions at 75% power and only a 28 gpm leak. It appears that the question is actually asking for what happens after the plant is offline and a cooldown is initiated. If so is should be explained in a more clear manner. Does AP/31 have actions do deal with SGTL if it is less than 25 gpm? If it does not then question needs to be re-written. NEW Rewrote question to address concerns, including stating the Isolated SG. SAT 3/3/2010 3 Sats, 15 Unsats, and 7 Enhancements Several of these questions were rated as unsatisfactory due to the same error. The licensee reworked/replaced these questions and they were not counted as unsat.

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Oconee Date of Exam: April 07, 2010 Exam Level: ROISRO In itia Is Item Description a b c 1. Clean answer sheets copied before grading iv/, 2. Answer key changes and question deletions justified and / /, documented Jo_Kej 3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)

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

5. All other failing examinations checked to ensure that grades J are justified AJo -I)ures o 14 &Ycw

y 6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants = 7 PhntedName/Signa re Date

a. Grader

b. Facility Reviewer(*)

c. NRC Chief Examiner(*)

d. NRC Supervisor (*)

C0UTWtLL4AW/ (*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. ES-403 Written Examination Grading Quality Checklist Facility: Oconee Date of Exam: April 07, 2010 Item Description

1.

Clean answer sheets copied before grading

2.

Answer key changes and question deletions justified and documented Yo Ke'-/ C~h"~ ""eve Ma6e

3.

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

4.

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

5.

All other failing examini3tions checked to ensure that grades are justified ~o tQIJurti Oil ~~ Bil'\\'w\\

6.

Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants ~ W, ~5:tJ,

b. Facility Reviewer(*)

---'tV'-I-f-.:A-'---_____ _

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

FhAV"\\C- '5- /..A).tl.dt..)J. T. W tDl,tMlN Form ES-403-1 Exam Level: RO/SRO Initials a b c ~ N/A 'It, ~ /' /i: [',/ /;;1 £11 11~/f 1~ 1\\ I/~ tllJr + Date i S/S/ZDO ~7 tV/it /';'_/.::;~ {:/ tJ'5" I (J(p ltD (*) The facility reviewer'S signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.}}