Text

Initial Exam 2009-301 Final Administrative Documents Region Ii/Drs/Operator Licensing Branch/Initial Examinations/Mcguire/Exam 2009-301
	ML092400626
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/11/2009
From:	; NRC/RGN-II
To:	; Duke Energy Corp
References
	05000369/09-301, 05000369/09-370
	Download: ML092400626 (91)
	v • d • e

FACILITY NAME:

McGuire Nulear Plant Section 7 REPORTNUMBER: ____ ~O=S~OO~O=3~69~/~37~O~~~O~09~-~30~1~ ____ _

FINAL ADMINISTRATIVE DOCUMENTS CONTENTS:

ri. Exam Preparation Checklist

~Final Exam Outline Quality Checklist

[3 Exam Security Agreements ci Final Administrative Topics Outline

[i Final Control Room & Walk-Through Test Outline l3"')=inal Operating Test Quality Check Sheet

[3' Final Simulator Scenario Quality Check Sheet

~ Final Transient and Event Check Sheet

~

)=inal Competencies Check Sheet

[!J Final Written Exam Sample Plan if Final Record of Rejected KAs

[!('final Written Exam Quality Check Sheet UiJl'"Final Written Exam Review Work Sheet B' Written Exam Grading Quality Check Sheet Location of Electronic Files:

Submitted By:

.!:.-.....:::......L...;;:;...",::....L......;.'------___

(ES-301-S)

(ES-401-1/2)

FACILITY NAME:

McGuire Nulear Plant Section 7 REPORTNUMBER: ____ ~O~S~OO~O~3~69~/~37~O~~~O~09~-~30~1~ ____ _

FINAL ADMINISTRATIVE DOCUMENTS CONTENTS:

~ Exam Preparation Checklist

~Final Exam Outline Quality Checklist

[3 Exam Security Agreements ci Final Administrative Topics Outline

[i Final Control Room & Walk-Through Test Outline B'~inal Operating Test Quality Check Sheet B Final Simulator Scenario Quality Check Sheet

~ Final Transient and Event Check Sheet

~

~inal Competencies Check Sheet 0' Final Written Exam Sample Plan if"Final Record of Rejected KAs EB"final Written Exam Quality Check Sheet uYFinal Written Exam Review Work Sheet B Written Exam Grading Quality Check Sheet Location of Electronic Files:

(ES-301-1 )

(ES-301-S)

(ES-401-1/2)

Submitted By: --'---""---'---"----____ _

V erifi ed B y--'-L----=----'--7f------=-->O<-=~~

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: McGuire Nuclear Station Date of Examination:

OS/11/2009 Developed by: Written - Facility -1l NRC _ II Operating - Facility.lL NRC -

Target Chief Task Description (Reference)

Examiner's Date*

Initials

-180

1.

Examination administration date confirmed (C.1.a; C.2.a & b) 11/12/2008

-120

2.

NRC examiners and facility contact assigned (C.1.d; C.2.e) 01/11/2009

-120

3.

Facility contact briefed on security and other requirements (C.2.c) 01/11/2009

-120

4.

Corporate notification letter sent (C.2.d) 01/11/2009

[-90]

[5. Reference material due (C.1.e; C.3.c; Attachment 3)]

02/10/2009

6.

Integrated examination outlines(s) due including forms ES-201-2, ES-201-3, ES-

{-7S}

301-1, ES-301-2, ES-301-5, ES-D-1 's, ES-401-1/2, ES-401-3 and 02/2S/2009 ES-401-4 as applicable (C.1.e & f; C.3.d)

{-70}

7.

Examination outline(s) reviewed by NRC and feedback provided to facility licensee 03/02/2009 (C.2.h; C.3.e)

8.

Proposed examinations (including written, walk-through JPMs, and

{-4S}

scenarios, as applicable), supporting documentation (including Forms 03/27/2009 ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g & h; C.3.d)

-30

9.

Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.g; 04/11/2009 ES-202)

-14

10. Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; 04/27/2009 ES-202)

-14

11. Examination approved by NRC supervisor for facility licensee review 04/27/2009 (C.2.h; C.3.f)

-14

12. Examinations reviewed with facility licensee (C.1.j; C.2.f & h; C.3.g) 04/27/2009

-7

13. Written examination and operating tests approved by NRC supervisor OS/04/2009 (C.2.i; C.3.h)

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

-7 qualifications / eligibility; and examination approval and waiver letters sent OS/04/2009 (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

-7

15. Proctoring/written exam administration guidelines reviewed OS/04/2009 with facility licensee. (C.3.k)

-7

16. Approved scenarios, job performance measures, and questions OS/04/2009 distributed to NRC examiners (C.3.i)

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

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

ES-201, Page 2S of 28 ES-201 Examination Preparation Checklist Form ES-201-1 Facility: McGuire Nuclear Station Date of Examination:

05/11/2009 Developed by: Written - Facility ---X. NRC _ II Operating - Facility.lL NRC -

Target Chief Task Description (Reference)

Examiner's Date*

Initials

-180

1.

Examination administration date confirmed (C.1.a; C.2.a & b) 11/12/2008

-120

2.

NRC examiners and facility contact assigned (C.1.d; C.2.e) 01/11/2009

-120

3.

Facility contact briefed on security and other requirements (C.2.c) 01/11/2009

-120

4.

Corporate notification letter sent (C.2.d) 01/11/2009

[-90]

[5. Reference material due (C.1.e; C.3.c; Attachment 3)]

02/10/2009

6.

Integrated examination outlines(s) due including forms ES-201-2, ES-201-3, ES-

{-75}

301-1, ES-301-2, ES-301-5, ES-D-1 's, ES-401-1/2, ES-401-3 and 02/25/2009 ES-401-4 as applicable (C.1.e & f; C.3.d)

{-70}

7.

Examination outline(s) reviewed by NRC and feedback provided to facility licensee 03/02/2009 (C.2.h; C.3.e)

8.

Proposed examinations (including written, walk-through JPMs, and

{-45}

scenarios, as applicable), supporting documentation (including Forms 03/27/2009 ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g & h; C.3.d)

-30

9.

Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.g; 04/11/2009 ES-202)

-14

10. Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; 04/27/2009 ES-202)

-14

11. Examination approved by NRC supervisor for facility licensee review 04/27/2009 (C.2.h; C.3.f)

-14

12. Examinations reviewed with facility licensee (C.1.j; C.2.f & h; C.3.g) 04/27/2009

-7

13. Written examination and operating tests approved by NRC supervisor 05/04/2009 (C.2.i; C.3.h)

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

-7 qualifications / eligibility; and examination approval and waiver letters sent 05/04/2009 (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

-7

15. Proctoring/written exam administration guidelines reviewed 05/04/2009 with facility licensee. (C.3.k)

-7

16. Approved scenarios, job performance measures, and questions 05/04/2009 distributed to NRC examiners (C.3.i)

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

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

ES-201, Page 25 of 28

ES-201 Examination Outline Quality Checklist Facllit :

McGuire Date of Examination:

Item Task De&Cription W

R I

T T

E N

2.

S I

M U

l A

T o

R

3.

W I

T

4.

G E

N E

R A

l

a.

Author

b. Asnss whethef the outline was sys,tematioally and randomly prepared in ac::coo:.fance with Section 0.1 of ES-401 and Whd'Ier aJl KIA ~

are appropOatety sampled.

d. Assess whethef the justificdom; for deftlacted Of rejected KIA statementtJ are appropriate.

a. Using Form ES-301-5, verify that the propo$ed scenario set:s cover tha required number of normal evolutions, Instrument and component failures, technieal ~.

and major transients.

b. Assess whether there are enough scenario sem (and speres) to test the projected number and mil( of applicants in accordance with the expected crew oompo1'llition and rotation schedule without compromising eXam integrity; and ensure that eaoh appHcant can be tested using at least one new Of significantly modified soenario, that no e<:enanos are dupHcat&d from tha appHcants' audit lest(s), and soenarios wm not be repeated on subsequent days.

c. To the extent poesIIIe, aaess whether the outRne(s} conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and dee<:ribed In Appendix D.

a. Vefly that aystema walk..furough outline meets the aitsria apectfted on Form e8-301-2:

(1) the outline(a) contB./n($) the required number of control room and in-plant tasks, distributed among the safety fUnotions 1iI$ specified on the form (2) tast repetition from the last two NRC examinations is within the Jlmb apeolfied on the fOrm.

(3}'" no 18. afe duplicated from the appbnta' audit test(s)

(4) the number of~

path. ~,

emergeMy' and RCA tasks meet the erIerla on the fOrm.

b. Verify that the IIdministrative outline meets the erIerla spedfied on Form E8-301-1:

(1) the tasb are distributed among the topic& as apecmed on the fOrm (2) at least one t&sk Is new Of significantly modtfted (3) no more then one task is repeated from the last two NRC Ii'Censing examinations

c. Determine if there are enough dlffinnt outlines to te. the projected number and robe: of appUcanta and ensure that 00 Items ere dupbted on subsequent days.

a. Assess whether ptant-speoific priorities (indudlng PRA and IPE insights) are covered in the appropriate exam section.

b. As$$$$ whether the 10CFR 55.41/43 and 55.45 sampfing is appropriate.

c. Ensure that KiA importance ratings (except for plant-apecfflc prlorilies) are at least 2.5.

d. Check for dupHca1lon and overlap among exam seotions.

e. Check the entire exam for balance of coverage.

1.

Assess whether the exam fb the IiIpproprlate job lave! (RO or SRO).

b.

Facility Revlewer r)

c.

NRC Chief Examiner (#)

d.

NRC Sl.Ipervisor NOTE:

., Independent NRC revlewer Initial items in Column "c*, chtef examiner concurrence required.

Not applicable for NRC-prepared examination outlines NUREG.. 1 021, Revision 9 Form ES-201-2 5111109

_E=S:::..--=2=O~1 ______

E_x_a_m.,..:.cj.,..:.cna.,..:.ct_io_n_O_u_t_lin_e_Q~ua_1.,..:.city"--C_h_ec_k_li_st ____ F_o_rm_ES-201-2 Facilit :

Item

1.

W R

i T

T E

N

2.

s M

U L

A T

o R

3.

W I

T

4.

G E

N E

R A

L

a.

Author McGuire Date of Examination:

Task Description

a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and Whether all KJA categortes 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 KJA 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.

f--.--

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 composltion 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 00 scenarios are duplicated from the applicants' audit test(s), and scenarios will not be repeated on subsequent days.

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

a. Vertfy that systems walk-through olrtline 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, dlstrtbuted 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 altema1e path, low-power, emergency and RCA tasks meet the criteria on the form.

b. Verify that the administrative oLltiine meets the criteria specified on Form E5-301-1:

(1) the tasks are distributed among the topicS as specified on the form

c.

a.

b.

c.

d.

e.

f.

(2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC ticensing examinations 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.

Assess whether plant-specific prtorities (including PRA and IPE insights) are covered in the appropriate exam section.

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

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

Check for duplication and overlap among exam sections.

Check the entire exam for balance of coverage.

.--,---.--------------+J'oL...-t~

Assess whether!:he exam fits the appropriate level (RO or SRO)...... _.... _-,f'--.F

b.

Facility Reviewer (0)

c.

NRC Chief Examiner (#)

d.

NRC Supervisor NOTE:

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

Not applicable for NRC-prepared examination ou1lfnes NUREG-1021, Revision 9

JAd1W~ UVl-30J 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 May 11, May18, May 25 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 May 11, May18, May 25. 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)

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

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of May 11, May18, May 25 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 May 11, May18, May 25. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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SIGNATURE (2)

DATE NOTE

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 May 11, May18, May 25 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 May 11, May18, May 25. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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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 May 11, May18, May 25 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 May 11, May18, May 25. 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

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 May 11. May18. May 25 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 May 11. May18. May 25. 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

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~ --T 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 May 11, May18, May 25 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 May 11, May18, May 25. 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

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 May 11, May18, May 25 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 May 11, May18, May 25. 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 ~rr"1 ~~ \\ \\

OJ's Ti<,,<~"s TL

_ ~~

~3,!t G~~ ~

('LlI/oCf _,_

2. ~(i-J~dps-

?)J$ Sh,-', <f;./I fif'9h ~~

6~,;2

t~ ~

--4j--Cl-'--J-r£i-

3.

C-

4.

5.

6.

7.

8. ________

9.

10.

11.________

12.

13.

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 May 11, May18, May 25 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 May 11, May18, May 25. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1)

DATE SIGNATURE (2)

DATE NOTE

~ ~:i ~i~p-"

~?Js,;~;~;Tkft 1119-, ~~

~;!~ ~

~

./!';:~/a;

3. _______________________ ~

__ ____'~___________

4. __________________________________________________ _

5. __________________________________________________ _

6. __________________________________________________ _

7. __________________________________________________ _

8. __________________________________________________ _

9. __________________________________________________ _

10. ____________________________________________________ _

11. ____________________________________________________ _

12. ____________________________________________________ _

13. ____________________________________________________ _

14. ____________________________________________________ _

15. ____________________________________________________ _

NOTES:

ES-201 Examin~tiQn 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 SllO'"zYdi.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 andlor an enforcement action against me or the facility licensee. I will immecliately 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 knowled e, I did not divulge to any unauthorized persons any information concerning the NRC licenslngexaminations administered during the weekes) of :r-.. tll~-~ 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.

. ~RINTED NA.ME JOB TITLE I RESPONSIBILI~:::;:J.

~....

DATE Sl~

DATE NOTE 1.~\\J.LA"AAro,.;Ji EXbA.- be.we-\\or=r.:::=t:2c~

q\\,Ac>~.g~(o\\\\&t'~

2. ______________________

3. _____________________ --'------------..,..---_-----

4. ______________________________________ _

5.

6. - - -

7. _____________

8.

9.

10.

11.

12.

13.

14.

15.

NOTES:

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 $llo~Z"Zldjas 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 knowled e, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of :;--11 I~-Qj 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 RESPONSIBILI~

.. ~::;S~-- DATE Sl~

DATE NOTE

1. be,,'\\J LA"J:A(QN~

E x,A-r-.. be...,;?\\or=' ~

~.-:::......:r=='~====--_I-4-__ q\\LA<'>~ g~

<ol \\~ 101.

2.~ ____________________________________________________________________________________ _

3. ____________________________________________________________________________________ _

4. ~

5. ____________________________________________________________________________ _

6. ______________________________________________________________________________ _

7. __________________________________________________________________________________ _

8. _________________________________________________________________________________ _

9. _______________________

~

10. _____________________________________________________________________________ _

11. ______________________________________________________________________ _

12. __________________________________________________________________ _

13. ________________________________________________________________ _

14. _________________________________________________________________ _

15.

~~---------------------------------------------------------------------

NOTES:

ES-201, Page 27 of 28

fl!1 f:- (;(Jlte6 ES-201 Examination Security Agreement Form ES-201-3

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes) of S h I ~ 5¥ as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes) of

. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILITY 1.l'asefJIl G AR:)6J/lf/t."r tf..VIGrJ/fIe.

1"Y'-~ ~l

2.

V

---4b~l--------------------

3. ________________________________________ _

4. ______________________________________ _

5. ________________________________________________ _

6. _________________________________________________ _

7. ___________________________________________ _

8. _______________________________________ _

9. ____________________________________

10.

11.

12.

13.

14.

15.

NOTES:

ES-201, Page 27 of 28 ES-201 Examination Security Agreement Fonn 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 sf I ~ 5/zs"" 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 [ 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 speclfically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable ifthe 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 andlor an enforcement action against me or the facility licensee. I wi!! 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 knowfedge, I did not divulge to any unauthorized persons any information conceming 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 1.l'asefJlI G AR56JA<lt,,-j'

,eeV/~NIJI.

2. __________________________________________ ~~

__________________________,+-----------------

3. ____________________________________________________________ _

4. ___________________________________________________ _

5. ____________________________________________________________ _

6. ________________________________________________________________________ _

7. _____________________________________________________________________________ _

8. _______________________________________________________________________________ _

9. ____________________________________________. ______________ ___

10. ____________________________________________________________________________________ _

11. ____________________________________________________________________________________ _

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

14. ________________________________________________________________________________ _

15.=:-=-_______________________________________________________ _

NOTES:

ES-201, Page 27 of 28

ES*201 Examination Seqllrity Agreement Fonn ES-201-3 MCGUIR 4RC.

i

1.

pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weeks(s) of May 2009 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 (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 andlor 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-f;xamination 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.

1.

2.

3.

4.

5.

6.

7.

8.

9, PRINTED NAME Jacqueline Schelkly 10, ____

11. ____

12, ____

13. ____

14. ____

15.

NOTES:

JOB TITLE I RESPONSIBILITY SIGNATURE (1)

DATE SIGNATURE (2)

DATE Admin I ~ L,.,./

' IJt. Jv1J.d~1 J, ' J.

~/Ldul1)lJelutk.y ~~ifcf~~

~,

NOTE NUREG-1021, Revision 9 ES*201

...:E::.;,x=a:.:..:.m.:.,::ln..:..::a:.::ti:.::.o:.;,.n...::S:.::..;e91Irity Agreement FolTl'l ES-201-3 MCGUIf{

~RC.

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weeks(s) of May 2009 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 (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 andlor 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

1.

Jacqueline Schelkly

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

NOTES:

NOTE NUREG-1021. Revision 9

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 May 11. May18. May 25 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 May 11. May18, May 25. 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. 'M<..6D <"2> K\\R\\<¢ JR.

SRQ/EXAm n=.Affi l.M4O q~.21-08

2. 'l~\\e. [... N5~5 Adm. -:S"p~.

q-Z'I-08 3.ft[;~t:Fkt"Q\\tL NRc ~

~

li!%:

4. S-k0<M l-MDb~

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5. -JqrW':> D. Schell sIS D p..-s-b3

6. react-IN.

fi1ose~

S~O 1,;/-1'1-'*" _______

7. Jo.... s..,..,eu.

""'..,_<2t>1"..

~i

8. tf/,(lfIN W1Ct11tf;

,5 R a

9.

W'ljb,1l tl'1MII\\

go 0'1, _______ _

10. -.::r;(Sa.-.J M c..t.:.v.,iZ~

..51<0

~ -~. <1 ~ ___________

11. Skin S\\\\d-e-r tLO I -,7J-09

12. M/l.{l.\\L '0r;kL R.O

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13. "5p;t;( t1)W~

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==

14. Cc..tbfCiYlf b\\Qffmllo

.s~o 1-".5"-0"1

15. ::ro.s:J.. :$.-ty"o'-'=fJ{L 1\\0

~

I-lt-oq 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 May 11. May18. May 25 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 specificaJly 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 May 11. May18. May 25. 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 SIGNATURE (1)

DATE SIGNATURE (2)

DATE NOTE

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 May 11, May18, May 25 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 appHcants 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 May 11, May18, May 25. 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 DATE SIGNATURE (2)

DATE NOTE

1. McM;$S4.. Silver go nL~

.. gID.I J'V'. ~

.-.... "VI

~:&w~c. ~s~p:,-~a.e." R..{'p!+4£f

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11

13.

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14.

Sil.O

. 1d1 15.

.s7~'1tl Xl:"".:s-I{~oe~

3-5'-p9-------====

NOTES:

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

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC [icensing examinations scheduled for the week(s) of May 11, May18, May 25 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 May 11! May18, May 25. 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. Me~

Si\\\\le("

~

--'-'---'--_o<.....:...=-.!-J-_______ -"~.L.J,.~~~Ck~----- _-'--'-~L-------------

2. W c.. 5 pe"1c..etC.

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8. I:)a..n <9!L W~

--""-"'~---'J.:~CZ£.J'-----~~- _-.6(d~~~=---.L~ __.t $ 0

9. kI. B~ ~

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10. $. k..!J~

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11.

'111.IJ 12~~

13.

,-~-oj--------- _____ _

14.

,()f

15. S"7/t:v.

.s-t{t'Cll~

'3 -t?9====================

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 weekes) of May 11, May18, May 25 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes} of May 11, May18, May 25. 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

,.......,'-"'\\' -, -

v;-,

,.....,....,,.-'Vc;-lf\\.1 TL....-

A:>'"

~

-r.~-y-~

~iVI

/.2t.!~"-r&-/L-OJ76"??A/IJ/J.

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~.

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P'='!~

'=="'-" 1!.N'...I!..1-S Ro

~'Z.Q o{ ________

. IJoU6tJ\\S (. WA\\(f.~

({,Ef,{~ o('ERwfoR If/1,9!o9 ________====

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 May 11, May18, May 25 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 May 11, May18, May 25. 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

-=--fr-=--n-:~=-==--- ----"----"-:;F--"------ ----",---;.,----"----- --rl---r'-. -------------

-~-------- ---------------------------------------- -------

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 May 11. May1B. May 25 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 May 11. May18. May 25. 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

1. __________________

2.

3.~~ ________________ _

4.

5. __________________ __

6.

7. __________________

8.

9._~ ________________ __

10.

11.

12.

13. __________________ _

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 May 11. May18. May 25 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 May 11, May18, May 25. 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. __________________________________________________ _

2. __________________________________________________ _

3. __________________________ --'--_______________________ _

4. __________________________________________________ _

5. __________________________________________________ _

6. __________________________________________________ _

7. __________________________________________________ _

8. __________________________________________________ _

9. __________________________ -'---_______________________ _

10. ____________________________________________________ _

11. ____________________________________________________ _

12.. ____________________________________________________ _

13. ____________________________________________________ _

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 weekes) of May 11, May18. May 25 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes) of May 11. May18. May 25. 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.

2. ______________________________________ _

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

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 May 11, May18. May 25 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 May 11. May18. May 25. 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. __________________________________________________ _

2. __________________________________________________ _

3. __________________________________________________ _

4. __________________________________________________ _

5. __________________________________________________ _

6. __________________________________________________ _

7. __________________________________________________ _

8. __________________________________________________ _

9. __________________________________________________ _

10. ____________________________________________________ _

11. ____________________________________________________ _

12. ____________________________________________________ _

13. ____________________________________________________ _

14. ____________________________________________________ _

15. ____________________________________________________ _

NOTES:

ES-201 ElCamination Security Agreement Form ES-201*l

1.

Pre-Examination I acknowledge Ihti.l have acquired specalized knmlfledge about the NRC licensing examinatons scheduleo for the week(s) of s: Ilo-n{dfas of the date of my signature. I agree ihat I will not koot,wngly divulge any intormation about these examinations to any persons who hav~ not been oott.arized by the NRC chief ~xamjner, I understand thi:lt I a1'1 nollo ~nsfruet, evaluate, or provide performance feedback to those applicanl:: scheduled 10 De administered these licensing examinalions from this dale until c011pielion of examhation admin;straton except as spcifically noted tfelow and authmize£! f}y lhe NRC (e,g.. acting as a s:m,-,Iatorboolr, uperator or communicator is acceptable rt the irldividual does nol select the training co['\\tent Of provide tireet or indirect feedback). Furthermore I am 8\\vare of the physical security measures and requifements (as documented in the faciUty liCensees prO[:eduresJ and understaoo that violation of the conditions of 1 Iris agreement may result in cancellation of the examinations andlor an enfOfCament action agai:Jsl me o~

lr.e faCility licensee. I will immediately report to faciMy ma'1agemem Of 1he ~JRC chief examiner any indications or stJgQestians thaI examination security may have been compromised.

2.

Post*Examinatiol1 To the ttesl of my knowle<ige, I did nol divulge to any unslilhofized peff>Ons any inforrr,aUol1 conceming the NRC licensing examinations administered during tr,e week(s) of

. from the date that I entered into thiz; security agreement until the completion of examination administration, I did not instruct, evaluate. Of provide performance f6dback ~{) those applicarns who were administered these licensing examioations, excep; as specificaly noter.i below and authorized by the NRC.

PRINTED NAME

1. >>,a.))'\\~ LI\\MCC*J*i

2. _____

JOB TillE! RESPONSIBIU~IG~==_ DATE E x,Ar--. be....,c,\\,¥r- --==t:2~

-t:==.D\\7:jo-<l-,-, _____,

SIGNATURE {2J DATE t\\lOTE

3. _______________________

4. _______________________

6. __________________________ _

7. __________________________ _

e. __________________________ _

9. __________________________ _

10. _________________

11. _________________, ________ _

12. __________________________ _

13., __________________________ _

14., __________________________ _

15., _________________

Nor:::S ES-201, Page 27 of 28 o

ill i\\}

.j>.

i\\}

o o co o

(:)

lJ1

t>

S

'0 rv ES-201 Examination Security Agreement Form ES-201-l

1.

Pre-Examination I acknowledge IhEi. f have acquired spec;alized knowledge about thE; NRC licensing examin<ltons scheduloo for the week(s) of S; I,o-u{dfas of the date of my signature. I agree -that I will nol kno'...,~ngfy divulge any in1ormation about these examinations to any persons who hav~ not been authorized by me NRC chief f;xaminer. I understand that I a1'1 not to }nslruct, evaluale, or provide peliormance feedback to those applicanl:: scheduled 10 be admir.istered these licensing examinations from this <late until c011pielion of exami!lation admin;straJ;on, excep1 as specifically noted tlelow and authorize{i I>y If;e NRC (e,g., acting as a SlmLdatorboot'l Dperator or communicator is acceptable ff the individual dOES no! select the training content Of provide drect or in~jjrect feedback), Furthermore I am aware of the physical securtty measures and requifemenls (as documented in the faciUly licensees proc:eduresl and understand ti1at vio~tion 01 the conditions of jt\\is agreement may result in cancellation of Ihe examinations andlor an enfOfC1:lment action agai:Jsl me O~

tr-.e facility licensee. I will immediately report to faciliiy ma'tagement Of 1he ~jRC chief examiner any indications or stJgQestinns thaI examination serurily may have been compromised.

2.

Post-Elaminatiol1 To the oosl of my knowlecige, I did no! divulge to any una.... thorized per~ons any information conceming the NRC licensing examinations administered during tre wBek(s} of

. from the date that I er1tered into this security agreement untfl the completion of examination ooministration, I did not instruct evaluate, Of provide periormance feedbacl< jo lhose applicarns who were administered these licensing examioations, excep: as specificaly noted below and authorized by tre NRC.

PRINTED NAME JOBTITlEIRESPONSIBILlHI~ DATE l.t>,o.>>'l~ ltls"%ACQ.Ji Ex.A~ 'be....,c\\~r ---=t:2~~D\\7:Ao-<6 _____ _

2. _______________________________________________________ _

StGNATURE {2J DATE NOTE

3. ___________________________________________ _

4. _______________________________________ _

h u. __________________________________________________ __

6. ______________________________________________ __

7. _______________________________________________ _

B. ___________________________________________ __

8. _____________________________________________ _

10. __________________________________________ _

11. ____________________________________________ _

12. ______________________________________________ _

13. _______________________________________ __

14, _________________________________________ _

15. _______________________________________________ _

NOTES ES-201, Page 27 of 28 o

ill

~

./>.

~

o o co o o lJ1 l> s:

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

1.

Pre-Examination I acknowledge that t have acquired specialized knowledge about the NRC licensing examinations scheduled for the weeks(s) of May 2009 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 {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

, 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 ~he NRC.

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

PRINTED NAME Jacqueline Schelkly NOTES:

JOB TITLE f RESPONSIBILITY SIGNATURE (1)

DATE SIGNATURE (2)

DATE NOTE Admin I '\\ '- /} j

~l~iJeIu1Jz1g ~~------'----

NUREG-1021, Revision 9 ES-201 Examination Security Agreement Form ES-201-3 MCGUIRE NRC

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the Weeks(s) of May 2009 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 (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

. 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)

1.

Jacqueline Sche!kly

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

NOTES:

Admin cac~ttduV,£k'/uJJ<.Lr/J-k-q/D'(------'---

DATE NOTE NUREG-1021, Revision 9

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

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes} of sA [

~ 5/ts'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, J 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. J 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 conceming 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 DATE SIGNATURE (2)

DATE NOTE

1. '(f(JsefJII G A,e~I.;r,(IIIGWeR.

~ ~r-.' _____ _

2. ________________ ---"'-________,

3. __________________

4. __________________. ___________,

5. ___________________________,

a _______________________________________,

~------------

7. ___________________________,

8. ___________________________,

9. _________________

10., __________________

11., __________________

12.

13.

14.

15.:=,--_______________

NOTES:

E5-201. Page 27 of 28

c------,.,---~-------------.-.--.-.--.. -_-_____.... _______ _

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

1.

Pre.-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes) of S hI -5¥ 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

. From the date that [ 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 f RESPONSIBILITY DATE SIGNATURE (2)

DATE NOTE

1. -;roseN", G ARSGJAVl-r. _.....j&~G.~II~/G.~vJ.~~!?!!:::. ___

7'fJJ.~~:...J..a~~'1C..L~_ I I, &,

2.

~z--___________ _

3. ____________________________________________________________ ~

4. ____________________________________________________________ _

5. _______________________________________________________________ _

6. __________________________________________________________ __

7. ____________________________________________________________ _

8. ___________________________________________________________ _

9. ______________________________________________________ ___

10. ____________________________________________________________ _

11. _____________________________________________________ _

12. __________________________________ ~

13. __________________________________________________ _

14. _____________________________________________________________ _

15.==--______________________________ ___

NOTES:

ES-201, Page 27 of 28

ES-*301 Administrative Topics Outline Final Form ES-301-1 Facility:

McGuire ( r=,IlAl.)

Date of Examination:

5/11/09 Examination Level:

RO Operating Test Number:

N09-1 Administrative Topic Type Code*

Describe activity to be performed (see Note) 2.1.25 (3.9)

Ability to interpret reference materials, such Conduct of Operations M,R as graphs, curves, tables, etc.

JPM:

Determine Boric Acid Addition to FWST 2.1.7 (4.4)

Ability to evaluate plant performance and Conduct of Operations make operational judgments based on M,R operating characteristics, reactor behavior, and instrument interpretation.

JPM:

Calculate QPTR 2.2.44 (4.2)

Ability to interpret control room indications Equipment Control to verify the status and operation of a system, and understand how operator N,S actions and directives affect plant and system conditions.

JPM:

Perform Daily Surveillance Items Checklist 2.4.39 (3.9)

Knowledge of RO responsibilities in Emergency D,S emergency plan implementation.

Procedures/Plan JPM:

Conduct a Site Assembly NOTE:

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

Type Codes & Criteria:

(C)ontrol room, (0) (S)imulator, (2) or Class(R)oom (2)

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

(N)ew or (M)odified from bank (;::. 1) (3)

(P)revious 2 exams (:::; 1; randomly selected) (0)

NUREG-1021, Revision 9 ES-301 Administrative Topics Outline Final Form ES-301-1 Facility:

McGuire (r-,PAL)

Date of Examination:

5/11/09 Examination Level:

RO Operating Test Number:

N09-1 Administrative Topic Type Code*

Describe activity to be performed (see Note) 2.1.25 (3.9)

Ability to interpret reference materials, such Conduct of Operations M,R as graphs, curves, tables, etc.

JPM:

Determine Boric Acid Addition to FWST 2.1.7 (4.4)

Ability to evaluate plant performance and Conduct of Operations make operational judgments based on M,R operating characteristics, reactor behavior, and instrument interpretation.

JPM:

Calculate QPTR 2.2.44 (4.2)

Ability to interpret control room indications Equipment Control to verify the status and operation of a system, and understand how operator N,S actions and directives affect plant and system conditions.

JPM:

Perform Daily Surveillance Items Checklist 2.4.39 (3.9)

Knowledge of RO responsibilities in Emergency D,S emergency plan implementation.

Procedures/Plan JPM:

Conduct a Site Assembly NOTE:

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

Type Codes & Criteria:

(C)ontrol room, (0) (S)imulator, (2) or Class(R)oom (2)

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

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

(P)revious 2 exams (::; 1; randomly selected) (0)

NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Final RO Admin JPM Summary Form ES-301-1 A 1 a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A/62001014, "Refueling Water System" is in progress and completed through Step 3.9, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480" using the RHT in accordance with Step 3.10 of Enclosure 4.4 of

. OP/1/A/62001014, "Refueling Water System." The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST as 7,912 gallons +/- 75 gallons.

A 1 b This is a modified JPM using bank JPM ADM-NRC-A 1-004 as its basis. With the plant at 100% power, the operator will be told that the Unit 1 OAC failed and is not operating, and that the crew has implemented PT/1/A/46001021 A, Loss of Operator Aid Computer while in Mode* 1.

The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PT/1/A/4600/21A Loss of Operator Aid Computer while in Mode 1. The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4, Quadrant Power Tilt Ratio, has been exceeded.

A2 This is a new JPM. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, and provided with a just completed portion of PT/1/A/46001003B, "Daily Surveillance Items," that reflects those items NOT simulated. The operator will be directed to perform Enclosure 13.1, Daily Surveillance Items Checklist in accordance with PT/1/A/4600/003B. The operator will be required to identify four items on the Checklist that do not meet the identified acceptance criteria, and one item that requires CRSRO notification.

A4

. This is bank JPM ADM-NRC-A4-005. The operator will told that Unit 1 was at 100% power when it experienced a loss of electrical power, that an ALERT has been declared, and that a Site Assembly is required.

The operator will be directed to conduct a Site Assembly in accordance with Step 1 of Enclosure 4.3, OSM Actions for Site Assembly, of RP/O/A/57001011, "Conducting a Site Assembly, Site Evacuation or Containment Evacuation." The operator will be expected to inform the Security Department that a Site Assembly is being performed, determine whether or not the Card Reader System is functioning properly, turn the Outside Page Speakers on, operate the Site Assembly alarm, make announcements pertinent to a Site Assembly, and direct the Security Department to ensure that the Site Assembly is thorough.

NUREG-1021, Revision 9 ES-301 Administrative Topics Outline Final RO Admin JPM Summary Form ES-301-1 A 1 a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A/62001014, "Refueling Water System" is in progress and completed through Step 3.9, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480" using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/1/A/62001014, "Refueling Water System." The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST as 7,912 gallons +/- 75 gallons.

A 1 b This is a modified JPM using bank JPM ADM-NRC-A 1-004 as its basis. With the plant at 100% power, the operator will be told that the Unit 1 OAC failed and is not operating, and that the crew has implemented PT/1/A/46001021 A, Loss of Operator Aid Computer while in Mode* 1.

The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PT/1/A/4600/21A Loss of Operator Aid Computer while in Mode 1. The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4, Quadrant Power Tilt Ratio, has been exceeded.

A2 This is a new JPM. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, and provided with a just completed portion of PT/1/A/46001003B, "Daily Surveillance Items," that reflects those items NOT simulated. The operator will be directed to perform Enclosure 13.1, Daily Surveillance Items Checklist in accordance with PT/1/A/46001003B. The operator will be required to identify four items on the Checklist that do not meet the identified acceptance criteria, and one item that requires CRSRO notification.

A4 This is bank JPM ADM-NRC-A4-005. The operator will told that Unit 1 was at 100% power when it experienced a loss of electrical power, that an ALERT has been declared, and that a Site Assembly is required.

The operator will be directed to conduct a Site Assembly in accordance with Step 1 of Enclosure 4.3, OSM Actions for Site Assembly, of RP/O/A/57001011, "Conducting a Site Assembly, Site Evacuation or Containment Evacuation." The operator will be expected to inform the Security Department that a Site Assembly is being performed, determine whether or not the Card Reader System is functioning properly, turn the Outside Page Speakers on, operate the Site Assembly alarm, make announcements pertinent to a Site Assembly, and direct the Security Department to ensure that the Site Assembly is thorough.

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Final Form ES-301-1 Facility:

McGuire ('r:IUIL)

Date of Examination:

5/11/09 Examination Level:

SRO Operating Test Number:

N09-1 Administrative Topic Type Code*

Describe activity to be performed (see Note) 2.1.25 (4.2)

Ability to interpret reference materials, such Conduct of Operations M,R as graphs, curves, tables, etc.

JPM:

Determine Boric Acid Addition to FWST 2.1.5 (3.9)

Ability to use procedures related to shift Conduct of Operations staffing, such as minimum compliment N,R overtime limitations, etc.

JPM:

Determine Proper Shift Staffing 2.2.42 (4.6)

Ability to recognize system parameters that Equipment Control are entry level conditions for Technical N,R Specifications.

JPM:

Perform Daily Surveillance Items Checklist 2.3.6 (3.8)

Ability to approve release permits.

Radiation Control M,R JPM:

Approve a Gaseous Waste Release Permit 2.4.41 (4.6)

Knowledge of emergency action level Emergency thresholds and classifications.

Procedures/Plan N,R JPM:

Classify an Emergency Event NOTE:

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

Type Codes & Criteria:

(C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5)

(D)irect from bank (:::; 3 for ROs; :::; 4 for SROs & RO retakes) (0)

(N)ew or (M)odified from bank (::! 1) (5)

(P)revious 2 exams (:::; 1; randomly selected) (0)

NUREG-1021, Revision 9 ES-301 Administrative Topics Outline Final Form ES-301-1 Facility:

McGuire CF=/~IL)

Date of Examination:

5/11/09 Examination Level:

SRO Operating Test Number:

N09-1 Administrative Topic Type Code' Describe activity to be performed (see Note) 2.1.25 (4.2)

Ability to interpret reference materials, such Conduct of Operations M,R as graphs, curves, tables, etc.

JPM:

Determine Boric Acid Addition to FWST 2.1.5 (3.9)

Ability to use procedures related to shift Conduct of Operations staffing, such as minimum compliment N,R overtime limitations, etc.

JPM:

Determine Proper Shift Staffing 2.2.42 (4.6)

Ability to recognize system parameters that Equipment Control are entry level conditions for Technical N,R Specifications.

JPM:

Perform Daily Surveillance Items Checklist 2.3.6 (3.8)

Ability to approve release permits.

Radiation Control M,R JPM:

Approve a Gaseous Waste Release Permit 2.4.41 (4.6)

Knowledge of emergency action level Emergency thresholds and classifications.

Procedures/Plan N,R JPM:

Classify an Emergency Event NOTE:

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

'Type Codes & Criteria:

(C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5)

(D)irect from bank (:::; 3 for ROs; :::; 4 for SROs & RO retakes) (0)

(N)ew or (M)odified from bank (::! 1) (5)

(P)revious 2 exams (:::; 1; randomly selected) (0)

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Final SRO Admin JPM Summary Form ES-301-1 A 1 a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A/6200/014, "Refueling Water System" is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Separate Verification of the calculation in Step 3.10 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480" using the RHT. The operator will discover two errors within the RO's calculation, and determine the correct volume of Boric Acid to add. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION.

The operator will be required to identify that ACTION C is applicable after one hour.

A 1 b This is a new JPM that combines elements of two bank JPMs, ADM-NRC-A 1-001 and ADM-NRC-A 1-010. The operator will be told that Units 1 and 2 are at 100%

power and that it is a specific time and date. The operator will be provided with a Work Schedule of personnel that are reporting for work, and told that three individuals have expressed concerns regarding overtime limitations, and present their recent work history. After being provided a work history for those that have expressed concerns, the operator will be directed to evaluate the work history of the three individuals who have expressed overtime limitation concerns; and then assign personnel to a shift position on Attachment 12.1, Control Room Supervisor Turnover Checklist, in accordance with the attached Work Schedule.

The operator will directed to identify any arriving personnel that cannot be assigned to a shift position; and to hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met. The operator will be expected to evaluate the work history of three individuals in accordance with section 200.6 of NSD 200, and determine that one RO cannot report for work, however, the other individuals with work history concerns may report for work.

The operator will also be expected to assign all other personnel reporting to work in accordance with an attached Key, identifying that that STA must be held over from the previous shift, and that one RO must be held over, or a Request for Work Hours Extension must be approved.

A2 This is a new JPM. The operator will be provided with a completed Enclosure 13.1, "Daily Surveillance Items Checklist" of PT/1/A/4600/003B, as well as a completed Enclosure 13.2, "NAC-UMS Cask Monitoring" of PT/1/A/4600/003B and directed to evaluate the completed Enclosures in accordance with PT/1/A/4600/003B, and identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken. The operator will need to evaluate the four discrepancies discovered against the Technical NUREG-1021, Revision 9 ES-301 Administrative Topics Outline Final SRO Admin JPM Summary Form ES-301-1 A 1 a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A/6200/014, "Refueling Water System" is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Separate Verification of the calculation in Step 3.10 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480" using the RHT. The operator will discover two errors within the RO's calculation, and determine the correct volume of Boric Acid to add. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION.

The operator will be required to identify that ACTION C is applicable after one hour.

A 1 b This is a new JPM that combines elements of two bank JPMs, ADM-NRC-A 1-001 and ADM-NRC-A 1-010. The operator will be told that Units 1 and 2 are at 100%

power and that it is a specific time and date. The operator will be provided with a Work Schedule of personnel that are reporting for work, and told that three individuals have expressed concerns regarding overtime limitations, and present their recent work history. After being provided a work history for those that have expressed concerns, the operator will be directed to evaluate the work history of the three individuals who have expressed overtime limitation concerns; and then assign personnel to a shift position on Attachment 12.1, Control Room Supervisor Turnover Checklist, in accordance with the attached Work Schedule.

The operator will directed to identify any arriving personnel that cannot be assigned to a shift position; and to hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met. The operator will be expected to evaluate the work history of three individuals in accordance with section 200.6 of NSD 200, and determine that one RO cannot report for work, however, the other individuals with work history concerns may report for work.

The operator will also be expected to assign all other personnel reporting to work in accordance with an attached Key, identifying that that STA must be held over from the previous shift, and that one RO must be held over, or a Request for Work Hours Extension must be approved.

A2 This is a new JPM. The operator will be provided with a completed Enclosure 13.1, "Daily Surveillance Items Checklist" of PT/1/A/4600/003B, as well as a completed Enclosure 13.2, "NAC-UMS Cask Monitoring" of PT/1/A/4600/003B and directed to evaluate the completed Enclosures in accordance with PT/1/A/4600/003B, and identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken. The operator will need to evaluate the four discrepancies discovered against the Technical NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Final Form ES-301-1 Specifications and Selected Licensee Commitments, and identify all required actions.

A3 This is a modified JPM using bank JPM ADM-NRC-A3-001 as its basis. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, that OP/0/A/6200/019, Enclosure 4.1, Waste Gas Decay Tank Release to Unit Vent, is in progress in preparation for release of the C WGDT, and completed through Step 3.11, and that RP has just delivered the GWR package # 2009010 to the Control Room.

The operator will be directed to review and approve GWR Package # 2009010 for the C Waste Gas Decay Tank by performing Step 3.12 of.1 of OP/0/A/6200/019, Waste Gas Decay Tank Release.

The operator will be expected to discover three errors in the submitted release package, and delay approval of the package until the errors are corrected.

A4 This is a new JPM. The operator will be given a timeline of events that span a few hours, and asked to classify the event at the point where each procedure identifies a need to address RP/0/A/S700/000, Classification of Emergency. The operator will be expected to recognize that an Unusual Event is declared at the first procedure direction, the Unusual Event is updated at the second procedure direction, and that a Site Area Emergency exists upon entry into the EOP network.

NUREG-1021, Revision 9 ES-301 Administrative Topics Outline Final Form ES-301-1 Specifications and Selected Licensee Commitments, and identify all required actions.

A3 This is a modified JPM using bank JPM ADM-NRC-A3-001 as its basis. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, that OP/0/A/6200/019, Enclosure 4.1, Waste Gas Decay Tank Release to Unit Vent, is in progress in preparation for release of the C WGDT, and completed through Step 3.11, and that RP has just delivered the GWR package # 2009010 to the Control Room.

The operator will be directed to review and approve GWR Package # 2009010 for the C Waste Gas Decay Tank by performing Step 3.12 of.1 of OP/0/A/6200/019, Waste Gas Decay Tank Release.

The operator will be expected to discover three errors in the submitted release package, and delay approval of the package until the errors are corrected.

A4 This is a new JPM. The operator will be given a timeline of events that span a few hours, and asked to classify the event at the point where each procedure identifies a need to address RP/0/A/5700/000, Classification of Emergency. The operator will be expected to recognize that an Unusual Event is declared at the first procedure direction, the Unusual Event is updated at the second procedure direction, and that a Site Area Emergency exists upon entry into the EOP network.

NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 Facility:

McGuire

( FIUII,..)

Date of Examination:

5/11/09 Exam Level (circle one):

RO (only) 1 SRO(I) I SRO (U)

Operating Test No.:

N09-1 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.

004 Chemical and Volume Control System S,D,A 1

Emergency Borate the Reactor Coolant System Using the PD Pump

b.

006 Emergency Core Cooling System 5,D,A,EN 2

Align the ND, NI, and NV Systems to Cold Leg Recirculation

c.

010 Pressurizer Pressure Control System 5,D,L 3

Place L TOP in Service

d.

059 Main Feedwater System S,D 4S Establish Feedwater Flow to the SIG's Following a Reactor Trip

e.

028 Hydrogen Recombiner and Purge Control System S,N,EN 5

Manually Align Phase B HVAC Equipment

f.

064 Emergency Diesel Generators 5,N,A 6

Perform Diesel Generator Operability Test

g.

015 Nuclear Instrumentation System S,D,A 7

Restore Repaired Power Range Channel to Service

h.

008 Component Cooling Water System S,D 8

Place Standby Component Cooling Train in Operation In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i.

APE 054 Loss of Main Feedwater Reset Unit 2 Turbine Driven CA Pump Stop Valve per Generic D,R,E 45 4

j.

APE 065 Steam Loss of Instrument Air D,A,E 8

Aligning Nitrogen To Supply Control Air to D, E and F VI Compressors

k.

APE 058 Loss of DC Power D,R,E 6

Swap Battery Charger EVCA Power Supply from Unit 1 to Unit 2 NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 Facility:

McGuire

( F/PII..)

Date of Examination:

5/11/09 Exam Level (circle one):

RO (only) I SRO(l) I SRO (U)

Operating Test No.:

N09-1 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.

004 Chemical and Volume Control System S,D,A 1

Emergency Borate the Reactor Coolant System Using the PD Pump

b.

006 Emergency Core Cooling System 5,D,A,EN 2

Align the ND, NI, and NV Systems to Cold Leg Recirculation

c.

010 Pressurizer Pressure Control System 5,D,L 3

Place L TOP in Service

d.

059 Main Feedwater System S,D 4S Establish Feedwater Flow to the SIG's Following a Reactor Trip

e.

028 Hydrogen Recombiner and Purge Control System S,N,EN 5

Manually Align Phase B HVAC Equipment

f.

064 Emergency Diesel Generators 5,N,A 6

Perform Diesel Generator Operability Test

g.

015 Nuclear Instrumentation System S,D,A 7

Restore Repaired Power Range Channel to Service

h.

008 Component Cooling Water System S,D 8

Place Standby Component Cooling Train in Operation In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i.

APE 054 Loss of Main Feedwater Reset Unit 2 Turbine Driven CA Pump Stop Valve per Generic D,R,E 45 4

j.

APE 065 Steam Loss of Instrument Air D,A,E 8

Aligning Nitrogen To Supply Control Air to 0, E and F VI Compressors

k.

APE 058 Loss of DC Power D,R,E 6

Swap Battery Charger EVCA Power Supply from Unit 1 to Unit 2 NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 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 (5) /4-6 (5) /2-3 (3)

(C)ontrol room (D)irect from bank

<,: 9 (9) /s 8 (8) / :~ 4 (4)

(E)mergency or abnormal in-plant

1 (3) />~ 1 (3) / ~

1 (2)

(EN)gineered Safety Feature

/

/ 2: 1 (1) (Control Room System)

(L)ow-Power / Shutdown

?: 1 (1)/21 (1)/21 (1)

(N)ew or (M)odified from bank including 1 (A) 2 2 (2) / 2 2 (2) / ?: 1 (1)

(P)revious 2 exams

3 (0) /: s 3 (0)/ :::; 2 (0) (Randomly Selected)

(R)CA 2: 1 (2 )/2': 1 (2) / 2: 1 (1)

(S)imulator JPM Summary JPM A This is bank JPM PS-NV-200A. The operator will be told that Unit 1 was at 100% power with "A" NV pump tagged for maintenance, when a failure of an automatic reactor trip occurred causing entry into EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/ATWS. The operator will be directed to emergency borate the NC System per Step 5 of EP/1/A/5000/FR-S.1. During the course of the procedure implementation the operator will discover that the "B" NV Pump has tripped (Alternate Path).

The operator will be expected to place the PO pump in service in accordance with EP/1/A/5000/G-1, Generic Enclosures, Enclosure 17, PO Pump Startup, and complete the emergency boration.

JPM B This is Bank JPM-ECC-NI-116A. The Operator will be placed in a post-Large Break LOCA situation at Unit 1 with the FWST trending toward Cold Leg Recirculation Switchover Criteria. The operator will be told that the unit is presently implementing EP/1/A/5000/E-1, Loss of Reactor or Secondary Coolant. The operator will be asked to monitor FWST level and perform transfer to Cold Leg Recirculation at the appropriate time. During the transfer to Cold Leg Recirculation in accordance with EP/1/A/5000/ES-1.3, Transfer to Cold Leg Recirculation, 1 NI-184B, RB Sump to Train B NO & NS, will fail to open, and the B NO Pump will need to be stopped (Alternate Path). The operator will place the A Train of NO, NI and NVon Cold Leg Recirculation.

JPM C This is a bank JPM. The Operator will be placed in a situation in which Unit 1 IS In a cooldown and depressurization in accordance with OP/1/A/6100/SD-4, "Cooldown to 240 Degrees F." The operator will be told that the 1A and 18 NCPs are operating, that NC System pressure is 340 psig and NC System temperature is 306-312°F.

The operator will be asked to place the L TOP System in operation in accordance with.1 of OP/1/A/6100/S0-10, "Controlling Procedure for LTOP Operation," and monitor for proper operation.

JPM 0 This is bank JPM CF-CF-036. The operator will be told that Unit 1 has experienced a Reactor Trip, that EP/1/A/5000/ES-0.1, "Reactor Trip Response," has been completed through step 11, total feed flow to S/G's is < 450 gpm, that no CA Pumps are running or available, and that CF Isolation has not occurred. The operator will be directed to place NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 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 (5) /4-6 (5) /2-3 (3)

(C)ontrol room (D)irect from bank

<,~ 9 (9) /s 8 (8) / s 4 (4)

(E)mergencyor abnormal in-plant

1 (3) />~ 1 (3) / ~

1 (2)

(EN)gineered Safety Feature

/

/ 2: 1 (1) (Control Room System)

(L)ow-Power / Shutdown

?: 1 (1) I?: 1 (1) I?: 1 (1)

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

?: 2 (2) /?: 2 (2) /?: 1 (1)

(P)revious 2 exams

3 (0) / S 3 (0)/: :; 2 (0) (Randomly Selected)

(R)CA 2: 1 (2 )/2: 1 (2) / 2: 1 (1)

(S)imulator JPM Summary JPM A This is bank JPM PS-NV-200A. The operator will be told that Unit 1 was at 100% power with "A" NV pump tagged for maintenance, when a failure of an automatic reactor trip occurred causing entry into EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/ATWS. The operator will be directed to emergency borate the NC System per Step 5 of EP/1/A/5000/FR-S.1. During the course of the procedure implementation the operator will discover that the "B" NV Pump has tripped (Alternate Path).

The operator will be expected to place the PO pump in service in accordance with EP/1/A/5000/G-1, Generic Enclosures, Enclosure 17, PO Pump Startup, and complete the emergency boration.

JPM B This is Bank JPM-ECC-NI-116A. The Operator will be placed in a post-Large Break LOCA situation at Unit 1 with the FWST trending toward Cold Leg Recirculation Switchover Criteria. The operator will be told that the unit is presently implementing EP/1/A/5000/E-1, Loss of Reactor or Secondary Coolant. The operator will be asked to monitor FWST level and perform transfer to Cold Leg Recirculation at the appropriate time. During the transfer to Cold Leg Recirculation in accordance with EP/1/A/5000/ES-1.3, Transfer to Cold Leg Recirculation, 1 NI-184B, RB Sump to Train B NO & NS, will fail to open, and the B NO Pump will need to be stopped (Alternate Path). The operator will place the A Train of NO, NI and NV on Cold Leg Recirculation.

JPM C This is a bank JPM. The Operator will be placed in a situation in which Unit 1 IS In a cooldown and depressurization in accordance with OP/1/A/6100/SD-4, "Cooldown to 240 Degrees F." The operator will be told that the 1A and 1B NCPs are operating, that NC System pressure is 340 psig and NC System temperature is 306-312°F.

The operator will be asked to place the L TOP System in operation in accordance with.1 of OP/1/A/6100/S0-10, "Controlling Procedure for LTOP Operation," and monitor for proper operation.

JPM 0 This is bank JPM CF-CF-036. The operator will be told that Unit 1 has experienced a Reactor Trip, that EP/1/A/5000/ES-0.1, "Reactor Trip Response," has been completed through step 11, total feed flow to S/G's is < 450 gpm, that no CA Pumps are running or available, and that CF Isolation has not occurred. The operator will be directed to place NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 the 1 A CF Pump in service, and establish CF to the S/G's in accordance with Enclosure 4 of EP/1/A/5000/ES-0.1. The operator will be expected to place the 1A CF Pump in service and provide feedwater flow to all four S/G's.

JPM E This is a new JPM. The operator will be told that they are the Unit 2 BOP, and that Unit 1 has experienced a Large Break LOCA. The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, "Phase B HVAC Equipment," of EP/1/A/5000/E-O, "Reactor Trip or Safety Injection."

During the performance of, the operator will recognize that neither train of the VE and VX Systems automatically started. The operator will be expected to manually start the both Trains of VE and VX Systems.

JPM F This is a new JPM. The operator will be told that Unit 1 is operating at 100% power, that a monthly test of the 1 B Emergency Diesel Generator is required, and that the System Engineer wants to start and stop the Diesel from the Control Room. The operator will be directed to conduct a Slow Start of the 1 B Emergency Diesel Generator using 3.1 of PT/1/A/4350/002B, "Diesel Generator 1 B Operability Test." During the performance of Enclosure 13.1, a sudden loss of crankcase vacuum will be indicated together with a loss of engine speed (Alternate Path). The operator will be expected to stop the engine with the normal stop switch.

JPM G This is a bank JPM. The Operator will be placed in a situation with Unit 1 at 100%

power. The operator will be told that Power Range Channel N43 has previously failed high, and that the channel has been defeated in accordance with AP/1/A/5500/16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." The operator will be asked to restore Power Range Channel N43 to service in accordance with Step 22 of AP16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction."

During the restoration, N43 will fail a second time, rendering this an Alternate Path JPM.

The operator will be required to use, an Annunciator Response/Abnormal Response Procedure and place Rod Control manual.

JPM H This is bank JPM PSS-KC-029. The operator will be told that Unit 1 is in a post-trip situation with "A" train RN and KC in service, and that 1 A 1 KC pump has tripped on overcurrent and will not restart. The crew has implemented AP/1/A/5500/21, "Loss of KC or KC System Leakage," and has completed step 8. The operator will be directed to start the standby KC train starting at Step 9 of AP/1/A/5500/21. The operator will be expected to place the B Train of KC in service, and place the A Train of KC in standby.

JPM I This is Bank JPM CF-CA-248. The Operator will be told that the Unit 2 reactor has tripped due to a loss of all offsite power, that 2ETA and 2ETB are deenergized, that the crew has entered EP/2/A/5000/ECA-0.0, "Loss of All AC Power," and that the "TDCA PUMP STOP VLV NOT OPEN" alarm (2AD-5, F-3) is lit. The operator will be directed to reset the stop valve PER EP/2/A/5000/G-1, "Generic Enclosures," Enclosure 24, "Resetting TO CA Stop Valve."

The operator will be expected to reset 2SA-3 in accordance with Generic Enclosure 24.

JPM J This is bank JPM SS-VI-110A. The operator will be told that a total loss of VI has occurred.

The operator will be directed to perform AP/1/A/5500/22, "Loss of VI,, "0, E, and F VI Compressor Operation With Low Control Air." During the implementation of Enclosure 6, the operator will discover that the Breathing Air (VB)

Compressors are tripped, and that another strategy will need to be implemented to NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 the 1 A CF Pump in seNice, and establish CF to the S/G's in accordance with Enclosure 4 of EP/1/A/5000/ES-0.1. The operator will be expected to place the 1A CF Pump in service and provide feedwater flow to all four S/G's.

JPM E This is a new JPM. The operator will be told that they are the Unit 2 BOP, and that Unit 1 has experienced a Large Break LOCA. The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, "Phase B HVAC Equipment," of EP/1/A/5000/E-0, "Reactor Trip or Safety Injection."

During the performance of, the operator will recognize that neither train of the VE and VX Systems automatically started. The operator will be expected to manually start the both Trains of VE and VX Systems.

JPM F This is a new JPM. The operator will be told that Unit 1 is operating at 100% power, that a monthly test of the 1 B Emergency Diesel Generator is required, and that the System Engineer wants to start and stop the Diesel from the Control Room. The operator will be directed to conduct a Slow Start of the 1 B Emergency Diesel Generator using 3.1 of PT/1/A/4350/002B, "Diesel Generator 1 B Operability Test." During the performance of Enclosure 13.1, a sudden loss of crankcase vacuum will be indicated together with a loss of engine speed (Alternate Path). The operator will be expected to stop the engine with the normal stop switch.

JPM G This is a bank JPM. The Operator will be placed in a situation with Unit 1 at 100%

power. The operator will be told that Power Range Channel N43 has previously failed high, and that the channel has been defeated in accordance with AP/1/A/5500/16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." The operator will be asked to restore Power Range Channel N43 to service in accordance with Step 22 of AP16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction."

During the restoration, N43 will fail a second time, rendering this an Alternate Path JPM.

The operator will be required to use, an Annunciator Response/Abnormal Response Procedure and place Rod Control manual.

JPM H This is bank JPM PSS-KC-029. The operator will be told that Unit 1 is in a post-trip situation with "A" train RN and KC in seNice, and that 1 A 1 KC pump has tripped on overcurrent and will not restart. The crew has implemented AP/1/A/5500/21, "Loss of KC or KC System Leakage," and has completed step 8. The operator will be directed to start the standby KC train starting at Step 9 of AP/1/A/5500/21. The operator will be expected to place the B Train of KC in service, and place the A Train of KC in standby.

JPM I This is Bank JPM CF-CA-248. The Operator will be told that the Unit 2 reactor has tripped due to a loss of all offsite power, that 2ETA and 2ETB are deenergized, that the crew has entered EP/2/A/5000/ECA-0.0, "Loss of All AC Power," and that the "TO CA PUMP STOP VLV NOT OPEN" alarm (2AD-5, F-3) is lit. The operator will be directed to reset the stop valve PER EP/2/A/5000/G-1, "Generic Enclosures," Enclosure 24, "Resetting TO CA Stop Valve."

The operator will be expected to reset 2SA-3 in accordance with Generic Enclosure 24.

JPM J This is bank JPM SS-VI-110A. The operator will be told that a total loss of VI has occurred.

The operator will be directed to perform AP/1/A/5500/22, "Loss of VI,, "0, E, and F VI Compressor Operation With Low Control Air." During the implementation of Enclosure 6, the operator will discover that the Breathing Air (VB)

Compressors are tripped, and that another strategy will need to be implemented to NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 restore VI System pressure (Alternate Path). The operator will be expected to align Nitrogen from backup cylinders to D, E, and F VI compressors with pressure set between 90-100 psig.

JPM K This is bank JPM EL-EPL-166T.

The operator will be told that Unit 1 has just experienced a Loss of Offsite Power, that the 1A D/G will not start, and that 1 ETA is de-energized. AP/1/A/5500/07, "Loss of Electrical Power," Case 1 has been implemented.

The operator will be directed to swap power supplies to the EVCA Battery Charger from Unit 1 to Unit 2 in accordance with AP/1/A/5500/07, "Loss of Electrical Power," 2, Swapping Battery Charger Power Supplies."

The operator will be expected to place Battery Charger EVCA in service with power being supplied from Unit 2 within 20 minutes of dispatch. This is a Time Critical JPM.

NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 restore VI System pressure (Alternate Path). The operator will be expected to align Nitrogen from backup cylinders to D, E, and F VI compressors with pressure set between 90-100 psig.

JPM K This is bank JPM EL-EPL-166T.

The operator will be told that Unit 1 has just experienced a Loss of Offsite Power, that the 1A D/G will not start, and that 1 ETA is de-energized. AP/1/A/5500/07, "Loss of Electrical Power," Case 1 has been implemented.

The operator will be directed to swap power supplies to the EVCA Battery Charger from Unit 1 to Unit 2 in accordance with AP/1/A/5500/07, "Loss of Electrical Power," 2, Swapping Battery Charger Power Supplies."

The operator will be expected to place Battery Charger EVCA in service with power being supplied from Unit 2 within 20 minutes of dispatch. This is a Time Critical JPM.

NUREG-1021, Revision 9

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility:

McGuire Date of 5/11/09 Operating Test Number: N09-1 Examination:

1. GENERAL CRITERIA Initials a

b*

C#

a.

The operating test conforms with the previously approved outline; changes are consistent I~\\

with sampling requirements (e.g. 10 CFR 55.45, operational importance, safety function

~

distribution).

b.

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

I~*t during this examination.

9-""

c.

The operating test shall not duplicate items from the applicants' audit testes) (see Section e~

~I O.1.a).

<pi'

d.

Overlap with the written examination and between different parts of the operating test is

~

within acceptable limits.

9.-""

e.

It appears that the operating test will differentiate between competent and less-than-

<~ Stf" ;~tf competent applicants at the designated license level.

2. WALK*THROUGH CRITERIA

a.

Each JPM includes the following, as applicable:

I,,~

initial conditions

~

Sr/"

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 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 j,

The associated simulator operating tests (scenario sets) have been reviewed in accordance with 41L Slf"\\. §~f(

Form ES-301-4 and a copy is attached.

~~t Printed Name 1 Signature Date

a.

Author o

eJ azaro y, West;n Technical Services, Inc.

4/23/09

b.

Facility Reviewer (*)

,S-Ie.,Jen Mo.!.. k:\\'c:r m N5. of'e1.o..~'.. n> M f/&.1>>

Lj/~fJ/t;<j

c.

NRC Chief Examiner (#)

G~c,i) ~J. LA.sK A.. tl'k'l£Ud'j}CJ, ~

~iAJL 5#4/ ?.. Q}':;

d.

NRC Supervisor lIU~N liT* W1J)~ I ({iIJ;;;mUJl}---~-

6/1()1{ / lJ' V

NOTE:

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

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

NUREG-1021, Revision 9 ES-301 Operating Test Quality Checklist Form ES-301-3 Facility:

McGuire Date of Examination:

5/11/09 Operating Test Number: N09-1

a.

b.

c.

d.

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

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

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

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

11------

e.

a.

b.

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

2. WALK*THROUGH CRITERIA Each JPM includes the following, as applicable:

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

detailed expected actions with exact criteria and nomenclature 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 Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.

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

a.

Author

b.

Facility Reviewer (*)

c.

NRC Chief Examiner (#)

d.

NRC Supervisor

~

--;::)1.. Printed Name 1 Signature

~~~~,

West;n Technical Services, Inc.

5-ie.Jen Mo.!.. k:\\'c:r m N5. of'e1.o..~'o""> fiJt HR<f>>

G~cl) ~J Li~.'5KA. k~,"'ttJrEjJCJ. ;:~

J.n.u-N.tAT* WtDA.J.A.NN I ~;;;;rtfWf}----

CI NOTE:

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

Initials a

b*

Date 4/23/09 Independent NRC reviewer initial items in Column "c n

chief examiner concurrence required.

NUREG-1021, Revision 9 c#

ES-3,-'O",,;,1 _________

Simulator Scenario Quality Checklist Form ES-301-4 I Facility:

McGuire Date of Exam:

5/11/09 Scenario Numbers:

123 Operating Test No,:

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,

>W' 2,

The scenarios consist mostly of related events,

~ if I..M 3,

Each event description consists of

~ At the point in the scenario when it is to be initiated if" 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

~tr 5,

The events are valid with regard to physics and thermodynamics,

~ yJ" 6,

Sequencing and timing of events is reasonable, and allows the examination team to obtain complete ~ ~

I,iIi' evaluation results commensurate with the scenario objectives.

7.

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

~

tP'" I:i~-

have sufficient time to carry out expected activities without undue time constraints,

8.

The simulator modeling is not altered.

I~

~tJfI jf 9,

The scenarios have been validated, Pursuant to 10 CFR 55.46(d), any open simulator performance ~ Ir' deficiencies or deviations from the referenced plant have been evaluated to ensure that functional 0/

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 ~

tv" t 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

~ 4f' ~~

/

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,

~

Sui'"' I~

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

Actual Attributes 1

2 3

1, Total malfunctions (5-8) 8 8

10

2.

Malfunctions after EOP entry (1-2) 1 2

4 3,

Abnormal events (2-4) 4 3

3

4.

Major transients (1-2) 1 1

1

5.

EOPs entered/requiring SUbstantive actions (1-2) 1 1

0 6,

EOP contingencies requiring substantive actions (0-2) 0 1

2 7,

Critical tasks (2-3) 3 2

3 NUREG-1021, Revision 9 ES-3.~O_1 _________

Simulator Scenario Quality Checklist Form ES-301-4 Facility:

McGuire Date of Exam:

5/11/09 Scenario Numbers:

1 23 Operating Test No.:

N09-1

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

QUALITATIVE ATTRIBUTES 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.

The scenarios consist mostly of related events.

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)

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.

The events are valid with regard to physics and thermodynamics.

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

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.

The simulator modeling is not altered.

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.

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.

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

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).

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

Target Quantitative Attributes (Per Scenario; See Section D.S.d)

Actual Attributes 1

2 3

1.

Total malfunctions (5-8) 8 8

10

2.

Malfunctions after EOP entry (1-2) 1 2

4

3.

Abnormal events (2-4) 4 3

3

4.

Major transients (1-2) 1 1

1

5.

EOPs entered/requiring SUbstantive actions (1-2) 1 1

0

6.

EOP contingencies requiring substantive actions (0-2) 0 1

2

7.

Critical tasks (2-3) 3 2

3 NUREG-1021, Revision 9 Initials a

b*

c#

.n

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

McGuire Date of Exam:

5/11/09 Operating Test No.:

N09-1 A

E Scenarios P

V N09-1-1 N09-1-3 T

M P

E 0

I L

N CREW CREW CREW CREW T

N I

T POSITION POSITION POSITION POSITION A

I C

L M

A T

U N

Y M('

T P

S A

B S

A B

S A

B S

A B

R I

U E

R T

0 R

T 0

R T

0 R

T 0

0 C

P 0

C P

0 C

P 0

C P

RX 0

1 1

0 NOR 1

4 2

1 1

1 RO-3 lie 2.4 2,3 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 1

1 1

1 0

NOR 1

1 1

RO-4 lie 3,5 5,6 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 0

1 1

0 NOR 1

4 2

1 1

1 RO-5 lie 2.4 2,3 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 1

1 1

1 0

NOR 1

1 1

RO-6 lie 3,5 5,6 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 Instructions:

1.

Check the applicant level and enter the operating test number and Form ES*D-t event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; InstantSROs 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.S.d) but must be significant per Section C.2.a of Appendix D. n Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a !-for-! 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.

NUREG 1021 Revision 9 ES-301 Transient and Event Checklist Form ES-301-5 Facility:

McGuire Date of Exam:

5/11/09 Operating Test No.:

N09-1 A

E Scenarios P

V N09-1-1 N09-1-3 T

M P

E 0

I L

N CREW CREW CREW CREW T

N I

T POSITION POSITION POSITION POSITION A

I C

L M

A T

U N

Y M(*\\

T P

S A

B S

A B

S A

B S

A B

R I

U E

R T

0 R

T 0

R T

0 R

T 0

0 C

P 0

C P

0 C

P 0

C P

RX 0

1 1

0 NOR 1

4 2

1 1

1 RO-3 lie 2.4 2,3 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 1

1 1

1 0

NOR 1

1 1

RO-4 lie 3,5 5,6 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 0

1 1

0 NOR 1

4 2

1 1

1 RO-5 lie 2.4 2,3 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 1

1 1

1 0

NOR 1

1 1

RO-6 lie 3,5 5,6 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 Instructions:

1.

Check the applicant level and enter the operating test number and Form ES*D-t event numbers for each event type; TS are not applicable for RO applicants. ROs must service 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 additionaJlyserves in the BOP position, one I/C malfunction can be credited toward the two IIC malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controJledabnormal conditions (refer to Section D.S.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 t-for-t 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.

NUREG 1021 Revision 9

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

McGuire Date of Exam:

5/11/09 Operating Test No.:

N09-1 A

E Scenarios P

V N09-1-1 N09-1-3 T

M P

E 0

I L

N CREW CREW CREW CREW T

N I

T POSITION POSITION POSITION POSITION A

I C

L M

A T

U N

Y M(*

T P

S A

B S

A B

S A

B S

A B

R I

U E

R T

0 R

T 0

R T

0 R

T 0

0 C

P 0

C P

0 C

P 0

C P

RX 0

1 1

0 NOR 1

1 2

1 1

1 SROU-1 lie 2,3, 2,3, 9

4 4

2 4,5 4,5, 6

MAJ 6

7 2

2 2

1 TS 3,4, 2,3, 6

0 2

2 5

5 RX 0

1 1

0 NOR 1

1 2

1 1

1 SROU-2 lie 2,3, 2,3, 9

4 4

2 4,5 4,5, 6

MAJ 6

7 2

2 2

1 TS 3,4, 2,3, 6

0 2

2 5

5 RX 0

1 1

0 NOR 1

4 2

1 1

1 RO-1 lie 2,4 2,3 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 1

1 1

1 0

NOR 1

1 1

RO-2 lie 3,5 5,6 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 Instructions:

1.

Check the applicant level and enter the operating test number and Form ES*D*1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service 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.S.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.

NUREG 1021 Revision 9 ES-301 Transient and Event Checklist Form ES-301-5 Facility:

McGuire Date of Exam:

5/11/09 Operating Test No.:

N09-1 A

E Scenarios P

V N09-1-1 N09-1-3 T

M P

E 0

I L

N CREW CREW CREW CREW T

N I

T POSITION POSITION POSITION POSITION A

I C

L M

A T

U N

Y M(*

T P

S A

B S

A B

S A

B S

A B

R I

U E

R T

0 R

T 0

R T

0 R

T 0

0 C

P 0

C P

0 C

P 0

C P

RX 0

1 1

0 NOR 1

1 2

1 1

1 SROU-1 lie 2,3, 2,3, 9

4 4

2 4,5 4,5, 6

MAJ 6

7 2

2 2

1 TS 3,4, 2,3, 6

0 2

2 5

5 RX 0

1 1

0 NOR 1

1 2

1 1

1 SROU-2 lie 2,3, 2,3, 9

4 4

2 4,5 4,5, 6

MAJ 6

7 2

2 2

1 TS 3,4, 2,3, 6

0 2

2 5

5 RX 0

1 1

0 NOR 1

4 2

1 1

1 RO-1 lie 2,4 2,3 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 RX 1

1 1

1 0

NOR 1

1 1

RO-2 lie 3,5 5,6 4

4 4

2 MAJ 6

7 2

2 2

1 TS 0

0 2

2 Instructions:

1.

Check the applicant level and enter the operating test number and Form ES*D*l event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the "at*the*controls (ATC)" and "balance*of*plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.S.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 l*for*l 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.

NUREG 1021 Revision 9

ES-301 Competencies Checklist Form ES-301-6 Facility:

McGuire Date of Examination:

5/11/09 Operating Test No.:

N09-1 APPLICANTS SRO (U/I)

ROIATC BOP Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

I nterpretiDiag nose 1-3, 1,2,4 2,3,5 1,5,6, 1,3,5 1,2,4 2,3,4 Events and 1-7 1-8 5-10

,6,7

,6 7,8,9,

,6,7

,6,7,

,7,8, Conditions 10 8

9, 10 Comply With and Use 1,2,4 2,3,5 1,5,6, 1,3,5 1,2,4 2,3,4 Procedures (1) 1-7 1-8 1-10

,6,7

,6 7,8,9,

,6,7

,6,7,

,7,8, 10 8

9, 10 Operate Control 1,2,4 2,3,5 1,5,6, 1,3,5 1,2,4 2,3,4 Boards (2)

NA NA NA

,6,7

,6 7,8,9,

,6

,6,7,

,7,8, 10 8

9,10 Communicate and 1-7 Interact 1-8 1-10 1-7 1-8 1-10 1-7 1-8 1-10 Demonstrate Supervisory Ability 1-7 1-8 1-10 NA NA NA NA NA NA (3)

Comply With and Use 3,4,5 1,4 2,3,5 NA NA NA NA NA NA Tech. Specs. (3)

Notes:

(1 )

Includes Technical Specification compliance for RO.

(2)

Optional for an SRO-U.

(3)

Only applicable to SROs.

Instructions:

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

NUREG-1021, Revision 9 4

ES-301 Competencies Checklist Form ES-301-6 Facility:

McGuire Date of Examination:

5/11/09 Operating Test No.:

N09-1 APPLICANTS SRO (U/I)

RO/ATC BOP Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

I nterpretiDiagnose 1-3, 1,2,4 2,3,5 1,5,6, 1,3,5 1,2,4 2,3,4 Events and 1-7 1-8 5-10

,6,7

,6 7,8,9,

,6,7

,6,7,

,7,8, Conditions 10 8

9, 10 Comply With and Use 1,2,4 2,3,5 1,5,6, 1,3,5 1,2,4 2,3,4 Procedures (1) 1-7 1-8 1-10

,6,7

,6 7,8,9,

,6,7

,6,7,

,7,8, 10 8

9, 10 Operate Control 1,2,4 2,3,5 1,5,6, 1,3,5 1,2,4 2,3,4 Boards (2)

NA NA NA

,6,7

,6 7,8,9,

,6

,6,7,

,7,8, 10 8

9,10 Communicate and 1-7 Interact 1-8 1-10 1-7 1-8 1-10 1-7 1-8 1-10 Demonstrate Supervisory Ability 1-7 1-8 1-10 NA NA NA NA NA NA (3)

Comply With and Use 3,4,5 1,4 2,3,5 NA NA NA NA NA NA Tech. Specs. (3)

Notes:

(1 )

Includes Technical Specification compliance for RO.

(2)

Optional for an SRO-U.

(3)

Only applicable to SROs.

Instructions:

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

NUREG-1021, Revision 9 4

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: McGuire Nuclear Station Date of Exam: 5/22/09 Exam Level: RO D SRO D Initial II _______________

--"tem Oescriplion

1.

Questions and answers are technically accurate and a~"-p!:Clc.:lc;c:;a:::.b:.;;le...:t;:.o..:.;th.:.:e:...f:::ac::.ci;.:;.lit=.. ------+I.C:~r==-~+~yl

2.

a,

b.

NRC KlAs are referenced for all questions, 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 re eated from the last 2 NRC licensinQ exar.ns, 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

_ 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 I SRO-only Bank Modified

7.

uestion distribution s at ri ht.

Between 50 and 60 percent of the questions on the RO exam are written at the comprehensionl analysis level; the SRO exam may exceed 60 percent If the randomly selected KlAs support the higher cognitive levels; enter the actual RO I SRO question distribution(s) at ri hI.

8.

References/handouts provided do not give away answers or aid in the elimination of distractors, 37/6 10/4 Memory

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 'ustified, 10, 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.

a. Author b, Facility Reviewer (*)

c. NRC Chief Examiner (#)

d, NRC Regional Supervisor New 28/15 CIA Note:

The facility reviewer's initialslsignature are not applicable for NRC-developed examinations.

Independent NRC reviewer initial items in Column "c"; chief examiner concurrence re uired.

~

9.rA J!< St-fA

~

tj;V' dJ<

Su-"

62l<

<;.fA otJ<

~l-r" Date 4130109 4130lQB 1/If'1 4

"1 ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: McGuire Nuclear Station Date of Exam: 5/22/09 Exam Level: ROO SRoD Initial Item Description a

b' c#.

1.

Questions and answers are technicall~ accurate and applicable to the facilitv.

]t 9-M At r---'

~\\

2.

a.

NRC KlAs are referenced for all questions, f£

b.

Facility learning objectives are referenced as available.

9--011 ft.:

p" I~

i}

3, SRO guestions are af!prof!riate in accordance with Section D,2,d of ES-401 Stf"\\ I~

4, The sampling process was random and systematic (If more than 4 RO or 2 SRO questions JJ<

H r were repeated from the last 2 NRC licensing exams, consult the NRR OL program office),

{t.M 5,

Question duplication from the license screening/audit exam was controlled JJ(

as indicated below (check the item that applies) and appears appropriate:

t L the audit exam was systematically and randomly developed; or SUV\\

_ 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 II) from the bank, at least 10 percent new, and the rest

~

9.rA new or modified); enter the actual RO / SRO-only 37/6 10/4 28/15 question distribution(s) at right.

7.

Between 50 and 60 percent of the questions on the RO Memory CIA Il exam are written at the comprehension/ analysis level; 33(jA'" T JK the SRO exam may exceed 60 percent if the randomly 4204,*

SL"f'I' selected KlAs support the higher cognitive levels; enter the actual RO / SRO guestion distribution(s) at right.

1.:£

' 13

~

,j, 8,

References/handouts provided do not give away answers tj.rt' 1j or aid in the elimination of distractors.

9, Question content conforms with specific KIA statements in the previously approved c?J<

'\\~O examination outline and is appropriate for the tier to which they are assigned; Su" deviations are justified.

10, Question psychometric quality and format meet the guidelines in ES Appendix S, 62l<

~ '~

t;

~.

11 The exam contains the required number of one-point, multiple choice items; oY<

~l-r" I:%~

the total is correct and agrees with the value on the cover sheet.

Printed Name / Si9~~

Date

a. Author Fred B Kirk Jr. / Duke Enemv.

4/30/09 b, Facility Reviewer (')

Steven L Mosteller / Duke EI 6rg\\li ~,I r!itt:::. -/ /1 4/301Q9 t ' II' J.", h-£r J'JLf, "=J.u;:,:'rr c, NRC Chief Examiner (#)

~,-,,-.v\\0 ~('l ) V J: t'. ~~~)t~;/~\\t

"_\\.iR'\\.,f~~

ie' 7/1 J!jj//'i

~_~~. c.... "

". 1-t

~ '-"'".'

.~

I d, NRC Regional Supervisor A..1J.1(tj! JJ,~. \\LlIr::if.'I...u.IAt /4:~

=

A

~1 I

( 51111..R '/.~f i..I Note:

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

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

I ES-401 R I ev.

amna on ne onn 9

PWREx ti Outll F

ES-4012 1 Facility: Me: c;,UI l'fb Date of Exam:

MA~ zuJi:;t I

RO KIA Category Points SRO-Only Points Tier Group 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 18 3

3 6

Emergency &

2 1

2 2

2 1

1 9

2 2

4 Abnormal Plant N/A N/A Evolutions Tier Totals 4

5 5

5 4

4 27 5

5 10 I

1 2

3 4

2 3

1 3

2 3

28 3

2 5

2.

Plant 2

1 1

1 0

1 1

1 10 2

1 3

I Systems Tier Totals 3

4 5

3 4

2 4

2 4 '3 4

38 5

3 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

3 2

2 1

2 2

2 I

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 I

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.

5.

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

I

6.

Select SRO topiCS for Tiers 1 and 2 from the shaded systems and KIA categories.

7.

The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics I

I must be relevant to the applicable evolution or system.

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the pOint totals (#) for each system and category. Enter the group and tier totals for each category In the table above; iffuel handling equipment Is sampled in other than Category A2 or G* on the SRO-only exam, enter It on the left side of Column A2 for TIer 2, Group 2 (Note

1 does not apply). Use duplicate pages for RO and SRO-only exams.

i

9.

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

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

I i

I I

I t:=IJ.}AL E8-401, Rev. 9 PWR examination Outline Form E8-401-2)

Facility: JAr: C~I' I 'I!

Date of Exam:

/\\il/~\\j 7r'L~*

I

~,LA! ':./

L...(Jt"'

I RO KIA Category Points SRO-Only Points Tier Group 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 18 3

3 6

Emergency &

2 1

2 2

2 1

1 9

2 2

4 Abnormal Plant N/A N/A Evolutions Tier Totals 4

5 5

5 4

4 27 5

5 10 1

2 3

4 2

3 1

3 2

3 28 3

2 5

2.

2 1

1 1

0 1

1 1

10 2

1 3

I Plant Systems Tier Totals 3

4 5

3 4

2 4

3 4

38 5

3 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

3 2

2 1

2 2

2

1.

Ensure that at least two topiCS from everY applicable KIA categorY are sampled within each tier of the RO and SRO-only outlines (I.e., except for one categorY In Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA categorY shall not be less than two).

2.

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

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

3.

Systemslevolutions 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.

5.

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

6.

Select SRO topiCS for Tiers 1 and 2 from the shaded systems and KIA categories.

7.

The generiC (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.

B.

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; Iffuel handling equipment is sampled in other than CategorY A2 or G* on the SRO-only exam. enter it on the left side of Column A2 for Tier 2, Group 2 (Note

1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

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

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

I

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 007EK1.06 Reactor Trip - Stabilization - Recovery 3.7 4.1

~DDD[JDDDD[J 008AK3.05 009EK3.21 011 EK3.14 015AA2.11 11 Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10 145.3)

Pressurizer Vapor Space Accident / 3 4

4.5 0 0 ~ 0 0 0 0 0 0 Small Break LOCA 1 3 Large Break LOCA 1 3 RCP Malfunctions/ 4 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.101 45.6/45.13) 4.5 0 [J ~ [J 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10/45.61 45.13) 4.1 4.2 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 3.4 3.8 0 0 0 0 DD~D o Ability to determ ine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.51 45.13)

FORM ES-401-2 TOPIC:

Relationship of emergency feedwater flow to SIG and decay heat removal following reactor trip termination or throttling criteria Actions contained in EOP for small break LOCAlleak RCP tripping requirement When to jog during ICC

.--~~"

.. ~~

.. ~--.--

.-~

-"--------~-.-

~--------"--... -

022AK1.03 Loss of Rx Coolant Makeup 12 3

3.4

~ 0 0 0 0 0 0 0 0 0 0 Relationship between charging flow and PZR level Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10 I 45.3)

Page 1 of 3 101712008 7:20 AM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 007EK1.06 Reactor Trip - Stabilization - Recovery 3.7 4.1

~DDDUDDDDnD Relationship of emergency feedwater flow to S/G and decay heat removal following reactor trip 11

--~~~ ~----

Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) 008AK3.05 Pressurizer Vapor Space Accident 1 3 4

~

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

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

4.5 0 D ~ 0 0 0 DOD [] D ECCS termination or throttling criteria Knowledge of the reasons for the following responses as they apply to (ASNORMAL PLANT EVOLUTION):(CFR: 41.5/41.101 45.6/45.13)

~-~~~------------

4.2 4.5 0 [J ~ [J DOD 0 D D D Actions contained in EOP for small break LOCAlleak Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10/45.61 45.13)

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

-~ ---~~~-~-------~~

~-~~~-

---~

~~~----~---------

011EK3.14 Large Break LOCA 1 3 4.1 4.2 0 0 ~ DOD D D DOD Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7 1 45.6)

RCP tripping requirement

~ -------~

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

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

---~--~-~--~-~~~--

~---~

015AA2.11 RCP Malfunctions 1 4 022AK1.03 Loss of Rx Coolant Makeup 1 2 3.4 3.8 0 0 DOD 0 0 ~ 0 0 0 When to jog RCPs during ICC 3

Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.51 45.13)

'--'~----------

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

3.4

~ DOD DOD [] [J U 0 Relationship between charging flow and PZR level Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3)

Page 1 of 3 101712008 7:20 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

025AK2.01 Loss of RHR System /4 RePIAteO LJ.. ~ OZ.5I&IL'Z..02..

029EA2.04 ATWS/l 040AG2.1.31 Steam Line Rupture - Excessive Heat Transfer / 4 054AA 1.04 Loss of Main Feedwater I 4 055EK2.04 Station Blackout 1 6.

(2Ii!f>~ vJ '"1 05S~I'O~

056AG2.4.35 Loss of Off-site Power 16 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7 I 45.7 / 45.8) 3.2 3.3 0 0 0 0 0 0 0 ~ 0 [J 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.51 43.5 I 45.31 45.13) 4.6 4.3 0 0 [] 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

4.4 4.5 0 0 0 0 0 0 ~ 0 0 0 0 Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I 45.51 45.6) o~oooo 0000 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) 3.8 4.0 0 0 0 0 0 0 0 0

[J ~

This is a Generic, no stem statement is associated.

Page 2 of 3 FORM ES-401-2 TOPIC:

RHR heat exchangers CVCS centrifugal charging pump operating indication Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

HPJ, under total feedwater loss conditions Pumps Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 10/7/2008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

025AK2.01 Loss of RHR System 14 T1G1 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.9 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the following:(CFR: 41.7/45.7 I 45.8)

FORM ES-401-2 TOPIC:

RHR heat exchangers

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

029EA2.04 ATWS I 1 3.2 3.3 0 0 0 0 0 0 0 ~ 0 [J 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 I 43.5 I 45.3 I 45.13)

CVCS centrifugal charging pump operating indication

.. ~-

-.. -------.- - -... ---- --*---:-c-~-__=_-c_::_---::c=_-=__=

040AG2.1.31 Steam Line Rupture - Excessive Heat 4.6 4.3 0 0 [] 0 0 0 0 0 0 [J ~

Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Transfer I 4 054AA1.04 Loss of Main Feedwater I 4 055EK2.04 Station Blackout I 6 056AG2.4.35 Loss of Off-site Power I 6 This is a Generic, no stem statement is associated.

4.4 4.5 0 0 0 DOD ~ 0 D [] D HPI, under total feedwater loss conditions Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTlON):(CFR: 41.7 I 45.5 I 45.6)

---~

D~D[]DD[]DDDD Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7 I 45.7 I 45.8)

Pumps 3.8 4.0 DOD DOD 0 0 0 [J ~

This is a Generic, no stem statement is associated.

Page 2 of 3 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 10/7/2008 7:20 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 057AA2.09 Loss of Vital AC Inst. Bus / 6 3.1 3.4 DDDDDDD~DDD Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13}

.-----~-

058AA1.03 Loss of DC Power / 6 3.1 3.3 DDDDD

~DDDD Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5 f 45.6) 062AG2.2.40 Loss of Nuclear Svc Water 1 4 3.4 4.7

[JDDDDDDDD[J~

This is a Generic, no stem statement is associated.

065AA1.01 Loss of Instrument Air / 8 2.7 2.5 DDDDDD~DD D Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6)

-~-----,-,.------.---

077AK2.07 Generator Voltage and Electric Grid 3.6 3.7 D~DDDDDDDDD Disturbances f 6 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7 f 45.8)

WEll EK1.2 Loss of Emergency Coolant Recirc. f 4 3.6 4.1

~ D D D DOD D D D D Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10 / 45.3)

Page 3 of 3 FORM ES-401-2 TOPIC:

T-ave. and T-ref. chart recorder Vital and battery bus components Ability to apply technical specifications for a system.

Remote manual loaders Turbine / Generator control Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recir).

101712008 7:20 AM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 057AA2.09 Loss of Vital AC Ins!. Bus / 6 3.1 3.4 0 0 0 0 0 0 0 ~ 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTlON):(CFR: 41.10/43.5/

45.13)

O~58~A~A~1.63**

Loss of DC Power / 6---

--3~.1-3~.3~*-O-O-D-D-[j"--::D=--~---:O 0 0 0

~~

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

062AG2.2.40 loss of Nuclear Svc Water /4 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6) 3.4 4.7

["J 0 0 0 0 0 0 0 0 [J ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

T-ave. and T-ref. chart recorder

~

Vital and battery bus components Ability to apply technical specifications for a system.

.~--~~

.. ~~~~-

065AA1.01 Loss of Instrument Air / 8 2.7 2.5 0 0 0 0 0 0 ~ 0 0 [J [J Remote manual loaders Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6) 077AK2.07 Generator Voltage and Electric Grid 3.6 3.7 0 ~ 0 0 0 [J 0 0 0 L"J 0 Disturbances / 6 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8)

.*..,--~-

WE11EK1.2 Loss of Emergency Coolant Recirc. /4 3.6 4.1

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3)

Page 3 of 3 Turbine / Generator control Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recir).

101712008 7:20 AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 003AK3.10 Dropped Control Rod 11 3.2 4.2 DD~DDDDDDDD Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.101 45.6/45.13)

--~-.-.

028AA 1.07 Pressurizer Level Malfunction 12 3.3 3.3 DDDDDD~DDDD Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 J 45.51 45.6) 051 AG2.4.11 Loss of Condenser Vacuum I 4 4.0 4.2 DDDDDDDDDD~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

RILand POlL Charging pumps maintenance of PZR level (including manual backup)

Knowledge of abnormal condition procedures.

068AK2.02 Control Room Evac. 1 8 3.7 3.9 0 ~ 0 0 0 0 0 0 0 0 0 Reactor trip system Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7 I 45.8)

WE03EA1.3 LOCACooldown-Depress./4 3.7 4.1 0 0 0 0 0 0 ~ 0 0 0 0 Desired operating results during abnormal and emergency situations.

Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.7/45.5 J 45.6)

WE07E'i<1:3Saturated Core CoOling Core Cooling 3.2 3.6

~ 0 0 0 0 0 0 0 0 0 0 1 4 Knowledge of the phYSical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9 J 45.7 to 45.8)

Page 1 of 2 Annunciators and conditions indicating signals, and remedial actions aSSOCiated with the (Saturated Core Cooling).

101712008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003AK3.10 Dropped Control Rod 1 1 T1G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.2 4.2 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.101 45.6/45.13)

--,--c--"'--'- -------

028AA 1.07 Pressurizer Level Malfunction 1 2 3.3 3.3 0 0 0 0 0 0 ~ 0 0 LJ Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.51 45.6)

FORM ES-401-2 TOPIC:

RIL and POlL Charging pumps maintenance of PZR level (including manual backup)

~----

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

051 AG2.4.11 Loss of Condenser Vacuum 14 4.0 4.2 o 0 0 0 0 0 0 0 0 0 ~

Knowledge of abnormal condition procedures.

068AK2.02 Control Room Evac. 1 8 This is a GeneriC, no stem statement is associated.

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

3.7 3.9 0 ~ 0 0 [J 0 0 0 0 0 0 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8)

WE03EA1.3 LOCA Cooldown - Depress. 1 4 3.7 4.1 0 0 0 0 0 0 ~ [J 0 0 0 Ability to operate and 1 or monitor the following as they apply to (EMERGENCY PLANT EVOLUTlON):(CFR: 41.7/45.51 45.6)

Reactor trip system Desired operating results during abnormal and emergency situations.

WE07EK1.3 Saturated Core Cooling Core Cooling 3.2 3.6 14

~DODDDODDDO Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.91 45.7 to 45.8)

Page 1 of 2 Annunciators and conditions indicating signals, and remedial actions associated with the (Saturated Core Cooling).

10n/2008 7:20 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

WE08EK2.1 RCS Overcooling - PTS 1 4 WE09EK3.2 Natural Circ. 1 4 WE16EA2.1 High Containment Radiation 1 9 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.4 3.7 0 ~ 0 0 0 [J 0 0 0 0 0 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the following:(CFR: 41.7/45.7/45.8) 3.2 3.6 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10/45.6/

4S.13) 2.9 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.SI 45.13)

Page 2 of 2 FORM ES-401-2 TOPIC:

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

10/7/2008 7:20 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

WE08EK2.1 RCS Overcooling - PTS / 4 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.7 0 ~ 0 0 0 [J 0 0 0 l_J 0 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the following:(CFR: 41.7 / 45.7 / 45.8)

-~- -- -

~~.. --

~~.-_._- -

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

WE09EK3.2 Natural Circ. / 4 3.2 3.6 0 0 ~ 0 0 0 0 0 0 0 0 WE16EA2.1 High Containment Radiation /9 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTlON):(CFR: 41.5/41.10/45.6/

45.13) 2.9 3.3 0 0 0 0 0 0 0 ~ 0 0 [J Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTlON):(CFR: 41.10/43.5/

45.13)

Page 2 of 2 FORM ES-401-2 TOPIC:

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

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

-~.. -

Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

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

~.

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

10/7/2008 7:20 AM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003K1.03 Reactor Coolant Pump 004K5.50 Chemical and Volume Control 005K6.03 Residual Heat Removal 006A3.06 Emergency Core COOling 007A2.05 Pressurizer Relief/Quench Tank 007K5.02 Pressurizer Relief/Quench Tank T2Gl PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.6

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.8) 2.6 2.7 0 0 0 0 ~ 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7)

FORM ES-401-2 TOPIC:

RCP seal system Design basis letdown system temperatures: resin integrity

=--:==--=:--==-==--:==--=-----=:-:

2.5 2.6 0 0 0 0 0 ~ 0 0 0 0 0 RHR heat exchanger Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 3.9 4.2 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5)

Valve lineups c-,:----,-,---,------==-=-==-==----:---_**------=-=:-:-:-:----

3.2 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Exceeding PAT high-pressure limits Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFA: 41.5/43.5/45.3/45.13) 3.1 3_4 0 0 0 0 ~ 0 0 0 0 0 0 Knowledge of the operational implications of _the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7)

Page 1 of 5 Method of forming a steam bubble in the PZR 101712008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003K1.03 Reactor Coolant Pump 004K5.50 Chemical and Volume Control 005K6.03 Residual Heat Removal 006A3.06 Emergency Core Cooling 007A2.05 Pressurizer Relief/Quench Tank T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.6

~ D D D D D D D D D D Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.8)

TOPIC:

RCP seal system FORM ES-401-2 2.6 2.7 D D D D ~ D D D D D D Design basis letdown system temperatures: resin integrity Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 2.5 2.6 0 D D D D ~ D D D D D RHR heat exchanger Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 3.9 4.2 D D D D D D D D ~ 0 0 Valve lineups Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 3.2 3.6 D D D D D D D ~ D D D Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 / 43.5 / 45.3 / 45.13)

Exceeding PRT high-pressure limits 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 0 D D D ~ DOD D [J D Method of forming a steam bubble in the PZR Knowledge of the operational implications of.the following concepts as they apply to the (SYSTEM):(CFR: 41.5 / 45.7)

Page 1 of 5 101712008 7:20 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM E8-401-2 KA NAME / SAFETY FUNCTION:*

IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 00BK3.03 Component Cooling Water 4.1 4.2 DD~DDDDDDDD RCP Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)

-~-.-----,.-

010A4.01 Pressurizer Pressure Control 3.7 3.5 DDDDDDDDD~D PZR spray valve Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 012A1.01 Reactor Protection 2.9 3.4 DDDDDD~DDDD Trip setpoint adjustment Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 012K3.0l Reactor Protection 3.9 4.0 UU~ULJUUUUUU CRDS Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the followlng:(CFR: 41.7/45.6) 013K2.01 Engineered Safety Features Actuation 3.6 3.B D~DDDDDDDDD ESFAS/safeguards equipment control Knowledge of electrical power supplies to the following:(CFR: 41.7) 022K1.04 Containment Cooling 2.9 2.9

~DOOOOOODOD Chilled water Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 022K2.02 Containment Cooling 2.5 2.4 O~DDDDDOODD Chillers

~

"j,l-\\

Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 02Z.~ 4.0s Page 201 5 1Onl2008 7:20 AM ES-401, REV 9 KA NAME! SAFETY FUNCTION:

008K3.03 Component Cooling Water 010A4.01 Pressurizer Pressure Control 012A 1.01 Reactor Protection T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.2 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 3.7 3_5 0 0 [J 0 0 0 0 0 0 ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 2.9 3.4 0 0 0 0 0 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 012K3.01 Reactor Protection 3.9 4.0 LJ LJ blI LJ LJ LJ LJ U LJ LJ U Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7 1 45.6) 013K2.01 Engineered Safety Features Actuation 3.6 3.8 0 ~ 0 0 0 0 0 DOD 0 022K1.04 Containment Cooling 022K2.02 Containment Cooling Knowledge of electrical power supplies to the following:(CFR: 41.7) 2.9 2.9

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 2.5 2.4 0 ~ DOD 0 0 0 0 0 0 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7)

Page 2 of 5 FORM ES-401-2 TOPIC:

RCP PZR spray valve Trip setpoint adjustment CADS ESFAS/safeguards equipment control Chilled water Chillers 1017/2008 7:20 AM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

025K501 Ice Condenser 026G2.1.32 Containment Spray 039G2.2.38 Main and Reheat Steam 059A4.03 Main Feedwater 061A2.05 Auxiliary/Emergency Feedwater 062A3.05 Electrical Distribution 062G2.2.39 AC Electrical Distribution T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.4 0 0 0 0 ~ 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 3.8 4.0 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

3.6 4.5 0 0 0 0 0 0 0 0 0

~

This is a Generic, no stem statement is associated.

2.9 2.9 0 0 0 0 0 0 0 0 [J ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 3.1 3.4 0 0 0 0 0 0 LI ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5 / 45.31 45.13) 3.5 3.6 0 0 0 0 LJ 0 [J 0 ~ 0 0 3.9 4.5 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 000 ODDOOO~

This is a Generic, no stem statement is associated.

Page 3 of 5 FORM ES-401-2 TOPIC:

Relationships between pressure and temperature Ability to explain and apply all system limits and precautions.

Knowledge of conditions and limitations in the facility license.

Feedwater control during power increase and decrease Automatic control malfunction Safety-related indicators and controls Knowledge of less than one hour technical specification action statements for systems.

lOnJ2008 7:20 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

025K501 Ice Condenser 026G2.1.32 Containment Spray T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.4 0 0 0 0 ~ 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 3.8 4.0 0 0 0 0 0 0 0 0 0 0 ~

This is a GeneriC, no stem statement is associated.

FORM ES-401-2 TOPIC:

Relationships between pressure and temperature Ability to explain and apply all system limits and precautions.

. -.-..... ---~.-... =--::=-=c-Main and Reheat Steam 3.6 4.5 0 0 0 0 0 0 0 0 0 0 ~

Knowledge of conditions and limitations in the facility 039G2.2.38 059A4.03 This is a Generic, no stem statement is associated.

Main Feedwater 2.9 2.9 0 0 0 0 0 0 0 0 [J ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7 J 45.5 to 45.8) license.

.-.~-

Feedwater control during power increase and decrease

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

061A2.05 Auxiliary/Emergency Feedwater 3.1 3.4 0 0 0 0 0 0 0 ~ 0 0 0 Automatic control malfunction Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 J 43.5 / 45.3 /45.13)

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

.. --c--. -----,---.. -.

062A3.05 AC Electrical Distribution 3.5 3.6 0 0 0 0 LJ 0 [J 0 ~ 0 0 Safety-related indicators and controls 062G2.2.39 AC Electrical Distribution Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

Page 3 of 5 Knowledge of less than one hour technical specification action statements for systems.

101712008 7:20 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

063A3.01 DC Electrical Distribution 063K2.01 DC Electrical Distribution 064K4.11 Emergency Diesel Generator

---~

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

073Al.0l Process Radiation Monitoring 073K3.01 Process Radiation Monitoring 076Al.02 Service Water 078K3.02 Instrument Air T2Gl PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.7 3.1 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 2.9 3.1 0 ~ 0 0 0 DOD 0 0 0 Knowledge of electrical power supplies to the following:(CFR: 41.7) 3.5 4.0 0 0 0 ~ 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foUowing:(CFA: 41.7)

FORM ES-401-2 TOPIC:

Meters, annunciators, dials, recorders and indicating lights Major DC loads Automatic load sequencer: safeguards

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

3.2 3.5 0 DOD 0 0 ~ 0 0 0 0 Radiation levels Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5) 3.6 4.2 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 2.6 2.6 DODD 0 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5 /

45.5) 3.4 3.6 D D ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)

Page 401 5 Radioactive effluent releases Reactor and turbine building closed cooling water temperatures.

Systems having pneumatic valves and controls 101712008 7:20 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

063A3.01 DC Electrical Distribution 063K2.01 DC Electrical Distribution 064K4.11 Emergency Diesel Generator

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

073A 1.01 Process Radiation Monitoring 073K3.01 Process Radiation Monitoring 076A1.02 Service Water T2Gl PWR EXAMINATION OUTLINE IA Kl K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 2.7 3.1 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 2.9 3.1 0 ~ 0 0 0 0 [J 0 LJ ::J 0 Knowledge of electrical power supplies to the following:(CFR: 41.7) 3.5 4.0 0 0 0 ~ DOD D D D D Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7)

FORM ES-401-2 TOPIC:

Meters, annunCiators, dials, recorders and indicating lights Major DC loads Automatic load sequencer: safeguards 3.2 3.5 0 DOD 0 0 ~ 0 DOD Radiation levels Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR: 41.5 /

45.5) 3.6 4.2 0 0 ~ 0 DOD 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7/45.6) 2.6 2_6 0 0 0 0 0 0 ~ D DOD Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR: 41.5/

45.5)

Radioactive effluent releases Reactor and turbine building closed cooling water temperatures.

078K3.02 Instrument Air 3.4 3.6 0 0 ~ 0 0 0 0 0 0 0 0 Systems having pneumatic valves and controls Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7/45.6)

Page 4 of 5 10nJ2008 7:20 AM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

103K4.01 Containment 0;t:tI\\c.e() W c ~

(O'5"q.o~

T2Gl PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.7 0 0 0 ~ 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7)

Page 5 of 5 FORM ES-401-2 TOPIC:

Vacuum breaker protection 101712008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

103K4.01 Containment

£?6t:tI\\ q:() W I ~

(03\\(.4.o~

T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.7 0 0 0 ~ 0 0 0 0 0 [] 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7)

Page 5 of 5 FORM ES-401-2 TOPIC:

Vacuum breaker protection 10/7/2008 7:20 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

011A3.03 015K5.02 017K6.01 027K2.01 028K3.01 033G2.4.31 034K1.02 Pressurizer Level Control Nuclear Instrumentation In-core Temperature Monitor Containment Iodine Removal Hydrogen Recombiner and Purge Control Spent Fuel Pool Cooling Fuel Handling Equipment T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 3.2 3.3 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 2.7 2.9 0 0 D~[JDDDDD Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 2.7 3.0 0 0 0 0 0 ~ 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 3.1 3.4 0 ~ 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 3.3 4.0 0 0 ~ 0 0 0 0 0 0 [] 0 4.2 4.1 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) o DDDD[]DDD~

This is a Generic, no stem statement is associated.

2.5 3.2

[.l] 0 0 00000 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8)

Page 1 of 2 FORM ES-401-2 TOPIC:

Charging and letdown Discriminator/compensation operation Sensors and detectors Fans Hydrogen concentration in containment Knowledge of annunciators alarms, indications or response procedures 10/7/2008 7:20 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

011A3.03 Pressurizer Level Control 015K5.02 Nuclear Instrumentation 017K6.01 In-core Temperature Monitor 00 027K2.01 Containment Iodine Removal T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 3.2 3.3 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 2.7 2.9 ODD 0 ~ [J 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 2.7 3.0 0 0 0 0 0 ~ 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7 / 45.7) 3.1 3.4 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the following:(CFR: 41.7)

FORM ES-401-2 TOPIC:

Charging and letdown Discriminator/compensation operation Sensors and detectors Fans 028K3.01 Hydrogen Recombiner and Purge Control 3.3 4.0 0 0 ~ 0 0 0 0 DOLl 0 Hydrogen concentration in containment 033G2.4.31 Spent Fuel Pool Cooling Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7/45.6) 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

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

Fuel Handling Equipment 2.5 3.2

~ 0 0 0 0 0 0 0 0 [J 0 034K1.02 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.8)

Page 1 of 2 Knowledge of annunciators alarms, indications or response procedures RHRS 10/7/2008 7:20 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

071 A 1.06 Waste Gas Disposal 079A4.01 Station Air OS6K4.02 Fire Protection

)

T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 2.S 0 0 0 0 0 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5) 2.7 2.7 0 0 0 0 0 0 0 0 0 ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.S) 3.0 3.4 0 0 0 ~ 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7)

Page20f 2 FORM ES-401-2 TOPIC:

Ventilation system Cross-tie valves with lAS Maintenance of fire header pressure 10171200S 7:20 AM ES-401, REV 9 KA NAME! SAFETY FUNCTION:

071A1.06 Waste Gas Disposal 079A4.01 Station Air

~~~~-~-----,=---=-~

OB6K4.02 Fire Protection T2G2 PWR EXAMINATION OUTLINE fR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 2.5 2.B ODD D D 0 ~ LJ 0 [J 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5)

---~-----~-~--

2.7 2.7 0 0 0 0 0 0 ODD ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)

~-------~:_:__:=_-__:c_c_

3.0 3.4 0 0 0 ~ 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7)

Page 2 of 2 FORM ES-401-2 TOPIC:

Ventilation system Cross-tie valves with lAS Maintenance of fire header pressure lOnt200B 7:20 AM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.1 Conduct of operations T3 PWR EXAMINATION OUTLINE JR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4_2 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Knowledge of conduct of operations requlrements_

G2.1.27 G2.1.37 G2.2.17 G2.2.4 G2.2.40 G2.3.14 Conduct of operations 3.9 4

DOD 0 D D DOD [J ~

Knowledge of system purpose and or function.

Conduct of operations Equipment Control Equipment Control Equipment Control This is a Generic, no stem statement is associated.

4.3 4.6 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

3.6 3.6 0 0 DOD 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

3.4 4.7 [l DOD 0 0 DOD 0 ~

This is a Generic, no stem statement is aSSOCiated.

Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

Page 1 of 2 Knowledge of procedures, guidelines or limitations associated with reactivity management Knowledge of the process for managing maintenance activities during power operations.

(multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a faCility.

Ability to apply technical specifications for a system.

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 1017/2008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.1 Conduct of operations G2.1.27 Conduct of operations G2.1.37 Conduct of operations G2.2.17 Equipment Control G2.2.4 Equipment Control

---~.-.-~--.---~"

G2.2.40 Equipment Control G2.3.14 Radiation Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.2 0 0 0 0 0 0 0 0 0 [J ~

3.9 4

4.3 4.6 This is a Generic, no stem statement is associated.

DDDDDDDDD[J~

This is a Generic, no stem statement is associated.

[JDDDD.D[JDDLJ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Knowledge of conduct of operations requirements.

Knowledge of system purpose and or function.

Knowledge of procedures, guidelines or limitations associated with reactivity management

.--.--~. --,----:----_

2.6 3.8 D D DOD D D D D D ~

Knowledge of the process for managing maintenance This is a Generic, no stem statement is associated.

3.6 3.6 0 DOD [J [J D D D 0 ~

This is a Generic, no stem statement is associated.

3.4 4.7

[] D D DODD D D D ~

This is a Generic, no stem statement is associated.

3.4 3.8 D D DOD 0 DOD 0 ~

This is a Generic, no stem statement is associated.

Page 1 of 2 activities during power operations.

(multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

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

Ability to apply technical specifications for a system.

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 10/7/2008 7:20 AM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.3.4 Radiation Control G2.4.39 Emergency Procedures/Plans G2.4.45 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.2 3.7 3.9 3.8 o

D[JDDDDDD~

This is a Generic, no stem statement is associated.

o 00000

[J~

This is a Generic, no stem statement is associated.

4.1 4.3 DOD 0 0 0 0 0 0 [] ~

This is a Generic, no stem statement is associated.

Page 2 of 2 FORM ES-401-2 TOPIC:

Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of the RO's responsibilities in emergency plan implementation.

Ability to prioritize and interpret the significance of each annunciator or alarm.

1Onl200B 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.3.4 Radiation Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.7 0 0 0 0 0 0 0 0 0 n ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Knowledge of radiation exposure limits under normal and emergency conditions G2.4.39

-.-~--.--.

..~~---- ---:--c------:

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

Emergency Procedures/Plans 3.9 3.8 0 [J 0 0 0 0 0 0 0 [j ~

Knowledge of the RO's responsibilities in emergency plan G2.4.45 Emergency Procedures/Plans This is a Generic, no stem statement is associated.

4.1 4.3 [l 0 DOD 0 0 0 0 [J ~

This is a Generic, no stem statement is associated.

Page 2 of 2 implementation.

Ability to prioritize and interpret the significance of each annunciator or alarm.

1Oni200B 7:20 AM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 007EG2.4.35 Reactor Trip - Stabilization - Recovery 3.B 4.0 ODOOOOOOOO~

OOBAA2.10 022AG2.4.4 025AA2.07 027AA2.03 062AG2.1.31

/ 1 This is a Generic, no stem statement is associated.

Pressurizer Vapor Space Accident / 3 3.6 3.6 0 0 0 0 LJ 0 Loss of Rx Coolant Makeup / 2 Loss of RHR System /4 Pressurizer Pressure Control System Malfunction / 3 Loss of Nuclear Svc Water / 4.

fZEPlAceC> W.~

O~'2.A~ z. \\.32-4.5 4.7 3.4 3.7 3.3 3.4 4.6 4.3 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13)

DOD oooooo~

This is a Generic, no stem statement is associated.

OOOOOOO~OOO Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13)

OODOO[J[]~O 0 Ability to determ ine and interpret the following as they apply to *ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13)

OOOODODOOO~

This is a Generic, no stem statement is associated.

Page 1 of 1 FORM ES-401-2 TOPIC:

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects High-pressure injection valves controliers Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

cavitation Effects of RCS pressure changes on key components in plant Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

1On/200B 7:20 AM ES-401, AEV 9 KA NAME / SAFETY FUNCTION:

007EG2.4.35 Reactor Trip - Stabilization - Recovery

/ 1 SAO T1G1 PWA EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.0 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

FOAM ES-401-2 TOPIC:

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 008AA2.10

--::--:c----.-.-----

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

Pressurizer Vapor Space Accident / 3 3.6 3.6 0 0 0 0 0 0 0 ~ 0 L"] 0 High-pressure injection valves and controllers 022AG2.4.4 Loss of Rx Coolant Makeup / 2 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTlON):(CFR: 41.10/43.5/

45.13)

.-----~ --

4.5 4.7 [J 0 DOD 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

025AA2.07 Loss of RHR System /4 027AA2.03 Pressurizer Pressure Control System Malfunction / 3 062AG2.1.31 Loss of Nuclear Svc Water / 4 3.4 3.7 0 DOD 0 0 0 ~ 0 0 0 Ability to detennine and interpret the following as they apply to ABNORMAL PLANT EVOLUTlON):(CFR: 41.10/ 43.5 /

45.13)

Pump cavitation

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

3.3 3.4 0 0 0 0 0 [J 0 ~ D [] 0 Effects of RCS pressure changes on key components in plant Ability to determine and interpret the following as they apply to -ABNORMAL PLANT EVOLUTlON):(CFR: 41.10/43.5/

45.13) 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

Page 1 of 1 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

101712008 7:20 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

003AG2.4.11 Dropped Control Rod 11

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

051AA2.02 Loss of Condenser Vacuum 14 WE15EA2.2 Containment Flooding 1 5 we16EG2.4.41 High Containment Radiation 19 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 0 0 0 0 0 0 0 0 0 [J ~

This is a Generic, no stem statement is associated.

3.9 4.1 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTlON):(CFR: 41.10/43.51 45.13) 2.9 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13) 2.9 4.6 0 [J 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

Page 1 of 1 FORM ES-401-2 TOPIC:

Knowledge of abnormal condition procedures.

Conditions requiring reactor and/or turbine trip Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Knowledge of the emergency action level thresholds and classifications.

101712008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003AG2.4.11 Dropped Control Rod 11 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 0 0 0 0 0 0 0 0 0 [J ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Knowledge of abnormal condition procedures. 1AA2.02::----:L-o-ss-of:-:CondenservacuumT4----*****-3-.9-4-.-1 0 0 0 0 0 0 0 ~ 0 0-0-*'-' --C-o-n-d,-'tionsieqU"ir,:-'n-g-re-a-ct-o-ra-n-cdlorturbine'trip'-'--'---

Ability to determine and interpret the WE15EA2.2 Containment Flooding 1 5

-.. -.-=--~~

we16EG2.4.41 High Containment Radiation 19 following as they apply to ABNORMAL PLANT EVOLUTION):(CFA: 41.10/43.51 45.13) 2.9 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.51 45.13) 2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

Page 1 of 1 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Knowledge of the emergency action level thresholds and classifications.

10/7/2008 7:20 AM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

004G2.1.20 Chemical and Volume Control SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.6 4.6 DOD 0 DOD DOD ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Ability to execute procedure steps.

012<32.1.32 ReactorProtection------.--3.84.0-- 0 D -DODo 0 D'O [J D ~-Abiiity to explain and apply all system limits and This is a Generic, no stem statement is associated.

precautions.

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

063A2.02 DC Electrical Distribution 2.3 3.1 0 DOD 0 0 0 ~ 0 D D Loss of ventilation during battery charging 076A2.01 Service Water 078A2.01 Instrument Air Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 3.5 3.7 D DODD 0 D ~ 0 D 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)

Loss ofSWS 2.4 2.9 0 0 DOD D D ~ D D 0 Air dryer and filter malfunctions Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/ 43.5 / 45.3 / 45.13)

Page 1 of 1 101712008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

004G2.1.20 Chemical and Volume Control SRO T2G1 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 4.6 4.6 0 0 0 [J 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Ability to execute procedure steps.

012G2.1.32 Reactor Protection 3.8 4.0 0 0 0 0 0 [] [J 0 lJ [] ~

Ability to explain and apply all system limits and 063A2.02 076A2.01 078A2.01 This is a Generic. no stem statement is associated.

precautions.

DC Electrical Distribution Service Water Instrument Air 2.3 3.1

[] [] [] [] [] [] [] ~ [] CJ 0 Loss of ventilation during battery charging Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 3.5 3.7 0 [] 0 0 [] [] [] ~ 0 [J []

Loss of SWS Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct. control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5 I 45.3 / 45.13) 2.4 2.9 0 [] 0 0 [] 0 [] ~ [] [] []

Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)

Page 1 of 1 Air dryer and filter malfunctions 1017/2008 7:20 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

034G2.4.11 Fuel Handling Equipment 072A2.02 Area Radiation Monitoring 086A2.03 Fire Protection SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Knowledge of abnormal condition procedures.

2.8 2.9 0 0 0 0 0 [J 0 ~ 0 0 0 Detector failure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 2.7 2.9 0 0 0 [J 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)

Page 1 of 1 Inadvertent actuation of the FPS due to circuit failure or welding 101712008 7:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

034G2.4.11 Fuel Handling Equipment SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 0 D D D D D D D D 0 ~

This is a Generic, no stem statement is associated.

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

Area Radiation Monitoring 2.8 2.9 D D D D 0 [J D ~ DOD 072A2.02 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.S / 43.5 / 45.3 / 45.13)

FORM ES-401-2 TOPIC:

Knowledge of abnormal condition procedures.

Detector failure DOD [J 0 0 0 ~ 0 D D Inadvertent actuation of the FPS due to circuit failure or 086A2.03 Fire Protection 2.7 2.9 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 f 43.5 f 45.3 / 45.13)

Page 1 of 1 welding lOnl2008 7:20 AM

ES-401, REV 9 KA G2.1.5 G2.2.11 G2.2.3 G2.3.12 G2.3.14 NAME / SAFETY FUNCTION:

Conduct of operations Equipment Control Equipment Control

~E" ft,AQloO W Lf\\....

~ 2.1..40 Radiation Control Radiation Control SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 3.9 D D D D D D D D D D ~

This is a Generic, no stem statement is associated.

2.3 3.3 nOD D DOD D D i1 ~

3.8 3.9 3.2 3.7 3.4 3.8 This is a Generic, no stem statement is associated.

DDDDDD DU~

This is a Generic, no stem statement is associated.

DD[]DDDDDDD~

This is a GeneriC, no stem statement is associated.

DDDDDDDD[JD~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Knowledge of the process for controlling temporary design changes.

(multi-unit license) Knowledge of the design, procedural and operational differences between units.

Knowledge of radiological safety principles pertaining to licensed operator duties Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.20 Emergency Procedures/Plans 3.8 4.3 0 DOD D D DOD D ~

Knowledge of operational implications of EOP warnings, This is a Generic, no stem statement is associated.

cautions and notes.

Eme;gency P~ocedures/Plaris---3A-,i4 0 D"E] D 0 D-D D b D ~

Knowledge of the bases for prioritizing emergency------

G2.4.23 This is a Generic, no stem statement is associated.

Page 1 of 1 procedure implementation during emergency operations.

10/7/2008 7:20 AM ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G G2.1.5 Conduct of operations RO SRO 2.9 3.9 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

G2.2.11 Equipment Control 2.3 3.3 0 0 0 0 0 [] 0 0 0 1: ~I G2.2.3 Equipment Control This is a Generic, no stem statement is associated.

--... -------.. --c------::-:

3.8 3.9 D D D [J D D 0 [1 D u ~

This is a Generic, no stem statement is associated.

G2.3.12

-c:-----------::--:---c... -.---.-.. --.. ----.. ----.-...

Radiation Control 3.2 3.7 D 0 [] D D DOD 0 D ~

G2.3.14 Radiation Control G2.4.20 Emergency Procedures/Plans This is a Generic, no stem statement is associated.

3.4 3.8 0 0 0 DOD D 0 [J 0 ~

This is a Generic, no stem statement is associated.

---'C'. :-----:-::---.-.. ---... --... -- ---

3.8 4.3 DOD DOn 0 0 0 0 ~

This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC:

Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Knowledge of the process for controlling temporary design changes.

(multi-unit license) Knowledge of the design, procedural and operational differences between units.

Knowledge of radiological safety principles pertaining to licensed operator duties Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities

.--.. -.. --::--c:---

Knowledge of operational implications of EOP warnings, cautions and notes.

...... --- -----.. ----.. --.. --:::-,-------c.--------.--.---:------:

G2.4.23 Emergency Procedures/Plans 3.4 4.4 DOD 0 D [J [] 0 0 0 ~

Knowledge of the bases for prioritizing emergency This is a Generic, no stem statement is associated.

Page 1 of 1 procedure implementation during emergency operations.

10/7/2008 7:20 AM

ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA T1/G1 025 AK2.01 Q 61 This KIA and the KIA for Q-35 (005 K6.03) effectively sample the same knowledge. Question was developed for the original KIA for Q-35.

Randonly selected replacement KIA (025 AK2.02) for Q-61 was provide by Chief Examiner.

T2/G1 022 K2.02 Q-74 This KIA tests the knowledge of power supplies to the Containment cooling system chillers. MNS has no chillers associated with containment cooling.

Randonly selected replacement KIA (022 K4.03) for Q-74 was provide by Chief Examiner.

T2/G1 103 K4.01 Q-62 The containment structure at MNS does not utilize a "Vacuum Breaker" Randonly selected replacement KIA (103 K4.06) for Q-62 was provide by Chief Examiner.

T1/G1 055A<2.04 Q-36 RO IR value is less than 2.5 Randonly selected replacement KIA (055 EA 1.06) for Q-36 was provide by Chief Examiner.

SROT3 G2.2.3 Q-78 KIA replaced due to inability to construct an acceptable SRO level question.

Randomly selected replacement KIA (G2.2.40) for Q-78 was provided by the Chief Examiner.

T1/G1 062AG2.1.31 Q-99 KIA replaced due to inability to construct an acceptable SRO level question.

Randomly selected replacement KIA (062 AG2.1.32) for Q-99 was provided by the Chief Examiner.

ES-401, Page 27 of 33 ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KJ A T1/G1 025 AK2.01 Q 61 This KJA and the KJA for Q-35 (005 K6.03) effectively sample the same knowledge. Question was developed for the original KJA for Q-35.

Randonly selected replacement KJA (025 AK2.02) for Q-61 was provide by Chief Examiner.

T2/G1 022 K2.02 Q-74 This KJA tests the knowledge of power supplies to the Containment cooling system chillers. MNS has no chillers associated with containment cooling.

Randonly selected replacement KJA (022 K4.03) for Q-74 was provide by Chief Examiner.

T2/G1 103 K4.01 Q-62 The containment structure at MNS does not utilize a "Vacuum Breaker" Randonly selected replacement KJA (103 K4.06) for Q-62 was provide by Chief Examiner.

T1/G1 05&\\<2.04 Q-36 RO IR value is less than 2.5 Randonly selected replacement KJA (055 EA 1.06) for Q-36 was provide by Chief Examiner.

SROT3 G2.2.3 Q-78 KJA replaced due to inability to construct an acceptable SRO level question.

Randomly selected replacement KJA (G2.2.40) for Q-78 was provided by the Chief Examiner.

T1/G1 062 AG2.1.31 Q-99 KJA replaced due to inability to construct an acceptable SRO level question.

Randomly selected replacement KJA (062 AG2.1.32) for Q-99 was provided by the Chief Examiner.

ES-401, Page 27 of 33

(FINAL.)

ES-401, Rev. 9 McGuire 2009-301 SRO Written Examination Review Worksheet Form ES-401-9

4. Job Content Flaws

5. Other

1. I 2. I

3. Psychometric Flaws LOK LOD r---,---,---,----.---;---,----,---,---,

(F/H)* (1-5)

6.

7.

Q#

Stem I Cues I T/F I cred*1 Partial I JOb-I Minutia I #1 I Back-I Q= I SRO I U/EI Focus Dist.

Link units ward KIA Only S

Explanation Instructions

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

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).

14.

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

The question is not linked to the job requirements (i.e., the question has a valid 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 "U" ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401, Rev. 9 McGuire 2009-301 SRO Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

LOD ~--~~~--~--~---r--~--~---r--~

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following poncepts.j

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.

0#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partia I Job-Minutia

1 Back-0=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

76 051AA2.02 The question appears to match the KIA.

H 2

X E The licensee's statement that the question must have actions associated with a required turbine and Reactor trip is not totally correct. The question should test either/or. If an operator understood that the turbine trip setpoint has been exceeded (RO knowledge) distractors A and B would be discounted If the operator further understood that the condenser would no longer be available for steam dump operation (RO Knowledge) then distractor C would be discounted. Leaving only D as a possible correct answer. Therefore, this is not an SRO only level question. Rewrote question, changed stem and distractors. Closer to SRO only. Must use other items besides procedure entry requirements, no trip setpoints have been reached yet. Will allow. SAT.

NEW SAT4/1/2009 77 012G2.1.32 Question appears to match KIA.

F 2

S Appears to be SRO only.

NEW SAT i

Very Wordy will look at changes to make less wordy on validation. SAT 4/1/2009

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 Partia I Job-Minutia

1 Back-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

76 051AA2.02 The question appears to match the KIA.

H 2

X E The licensee's statement that the question must have actions associated with a required turbine and Reactor trip is not totally correct. The question should test either/or. If an operator understood that the turbine trip setpoint has been exceeded (RO knowledge) distractors A and B would be discounted.

If the operator further understood that the condense would no longer be available for steam dump operation (RO Knowledge) then distractor C would be discounted. Leaving only 0 as a possible correct answer. Therefore, this is not an SRO only level question. Rewrote question, changed stem and distractors. Closer to SRO only. Must use other items besides procedure entry requirements, no trip setpoints have been reached yet. Will allow. SAT.

NEW SAT4/1/2009 77 012G2.1.32 Question appears to match KIA.

F 2

S Appears to be SRO only.

NEW SAT Very Wordy will look at changes to make less wordy on validation. SAT 4/1/2009

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 Partia I Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

78 G2.2.3 Question appears to match KIA. This is H

2 U systems knowledge. This question on the 2007 McGuire NRC exam was an RO question, the only difference is the realignment to the SNSWP which is in all distractors. Need to write at the SRO level. Listed as BANK May need another KIA. 4/1/2009 G2.2.22 or G2.2.40 Will look at rewrite.

79 003AG2.4.11 Question appears to match KIA.

F 2

E Is this operationally valid. Does McGuire have reduced axial offset? If so it would be very difficult to actually exceed tech spec limits on a drop of one control rod. I understand that this is a step in the procedure. I am just not sure that it is operationally valid will discuss.

NEW Changed stem to state required actions lAW AP-14. SAT 4/1/2009 80 076A2.01 Question appears to match KIA.*

H 2

S Appears to be SRO only.

MODIFIED SAT SAT 4/1/2009

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 Partia I Job-Minutia

/

Back-Q=

SAO U/EI Explanation Focus Dist.

Link units ward KIA Only S

78 G2.2.3 Question appears to match KIA. This is H

2 U systems knowledge. This question on the 2007 McGuire NRC exam was an RO question, the only difference is the realignment to the SNSWP which is in all distractors. Need to write at the SRO level. Listed as BANK May need another KIA. 41112009 G2.2.22 or G2.2.40 Will look at rewrite.

79 003AG2.4.11 Question appears to match KIA.

F 2

E Is this operationally valid. Does McGuire have reduced axial offset? If so it would be very difficult to actually exceed tech spec limits on a drop of one control rod. I understand that this is a step in the procedure. I am just not sure that it is operationally valid will discuss.

NEW Changed stem to state required actions lAW AP-14. SAT 41112009 80 076A2.01 Question appears to match KIA.

H 2

S Appears to be SRO only.

MODIFIED SAT SAT 41112009

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 Partia I Job-Minutia

1 Back-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

81 WE15EA2.2 Question does not totally match H

2 X

X U the KIA (adherence to appropriate procedures) will get a second opinion. Not SRO only this question can be answered using systems knowledge. Knowledge that a LOCA and a Feed line break has occurred will rule out A and B. Knowing the limit for sump level in containment (12.5 feet) appears to be systems knowledge. Again I will get a second opinion.

NEW Continue to work on question 4/1/2009 Also has two correct answers as written.

Added only to distractors C and D. this makes D wrong. SAT 4.24.2009.

82 00BAA2.10 Question kind of matches KIA. Appears H

2 X

E to be SRO only. With the conditions in the stem an entry into C.1 is not warranted. The distractor analysis states this. However the correct answer marked is C which states that an entry into C.1 is required. With CETs at 586°F entry into C.1 is not really plausible unless there are other conditions that direct entry. To make C.1 plausible temperature should be closer to 700 of (maybe even exceeding it but then RVLlS level should be greater than the value that would require entry into C.1. Will discuss NEW Made changes to stem {increased RCS temp to 705 degrees, and RVLlS to 45%. This made C.1 distractors more plausible. Also increased Subcooling to indication limit.

NOW SAT 4/1/2009

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 Partia I Job-Minutia

1 Back-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

81 WE1SEA2.2 Question does not totally match H

2 X

X U the KiA (adherence to appropriate procedures) will get a second opinion. Not SRO only this question can be answered using systems knowledge. Knowledge that a LOCA and a Feed line break has occurred will rule out A and B. Knowing the limit for sump level in containment (12.5 feet) appears to be systems knowledge. Again I will get a second opinion.

NEW Continue to work on question 4/1/2009 Also has two correct answers as written.

Added only to distractors C and D. this makes 0 wrong. SAT 4.24.2009.

82 00SAA2.10 Question kind of matches KIA. Appears H

2 X

E to be SRO only. With the conditions in the stem an entry into C.1 is not warranted. The distractor analysis states this. However the correct answer marked is C which states that an entry into C.1 is required. With CETs at 586°F entry into C.1 is not really plausible unless there are other conditions that direct entry. To make C.1 plausible temperature should be closer to 700 of (maybe even exceeding it but then RVLlS level should be greater than the value that would require entry into C.1. Will discuss NEW Made changes to stem (increased RCS temp to 705 degrees, and RVLlS to 45%. This made C.1 distractors more plausible. Also increased Subcooling to indication limit.

NOW SAT 411/2009

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 Partia I Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

IVOI 022AG2.4.2 Question appears to match the KIA.

83 H

2

?

E Borderline SRO, I believe that this can be answered with systems knowledge but will have another examiner review the question and verify.

NEW Made changes to stem SAT 4/1/2009 84 G2.4.20 Question appears to match the KIA, F

2 S and appears to be SRO only.

NEW SAT 004G2.1.20 Question appears to match the 85 H

2 E KIA. Appears to be SRO only. Not sure if the correct answer listed is totally correct.

The procedure states EVALUATE starting the Standby makeup pump using enclosure 3~ The correct answer listed states: Start the standby pump immediately. These are not consistent.

NEW Changed stem and all distractors. Added per enclosures.

SAT 4/1/2009

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 Partia I Job-Minutia

1 Back-Q=

SRO u/E1 Explanation Focus Dist.

Link units ward KIA Only S

IV,",I 022AG2.4.2 Question appears to match the KIA.

83 H

2

?

E Borderline SRO, I believe that this can be answered with systems knowledge but will have another examiner review the question and verify.

NEW Made changes to stem SAT 4/1/2009 84 G2.4.20 Question appears to match the KIA, F

2 S and appears to be SRO only.

NEW SAT 004G2.1.20 Question appears to match the 85 H

2 E KIA. Appears to be SRO only. Not sure if the correct answer listed is totally correct.

The procedure states EVALUATE starting the Standby makeup pump using enclosure

3. The correct answer listed states: Start the standby pump immediately. These are not consistent.

NEW Changed stem and all distractors. Added per enclosures.

SAT 4/1/2009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD I

(F/H)

(1-5) 8tem Cues T/F Credo Partia I Job-Minutia

1 Back-Q=

8RO U/EI Explanation Focus Dist.

Link units ward KIA Only 8

86 G2.1.5 Question appears to match the KIA.

F 2

X E The question appears to be SRO only. Should not the STA also have an active SRO license?

The Technical Specification does not speak to this. I do not think that 10CFR50 allows an ST A (that does not have an active license) to fill that position. Will Discuss.

NEW Added Active to stem. SAT 4/1/2009 i

87 2.3.14 Question appears to match the KIA. If F

2 X

E this is taught in Rad worker training then it is not SRO knowledge. At most sites this is taught in RAD worker training. Will review McGuire Rad worker training to verify.

BANK Made change to be in accordance with RP-

04. This made the question more SRO only.

SAT 4/112009 88 G2.3.12 Question may not match the KIA. It F

2 S appears to be SRO only. Will get a second opinion on KIA match. Second opinion on KIA match is that is kind of matches KIA. (So its okay)

BANK SAT 4/1/2009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

0#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partia I Job-Minutia

1 Back-0=

SAO U/EI Explanation Focus Dist.

Link units ward KIA Only S

86 G2.1.S Question appears to match the KIA.

F 2

X E The question appears to be SRO only. Should not the STA also have an active SRO license?

The Technical Specification does not speak to this. I do not think that 10CFR50 allows an STA (that does not have an active license) to fill that position. Will Discuss.

NEW Added Active to stem. SAT 4/1/2009 87 2.3.14 Question appears to match the KIA. If F

2 X

E this is taught in Rad worker training then it is not SRO knowledge. At most sites this is taught in RAD worker training. Will review McGuire Rad worker training to verify.

BANK Made change to be in accordance with RP-

04. This made the question more SRO only.

SAT 4/1/2009 88 G2.3.12 Question may not match the KIA. It F

2 S appears to be SRO only. Will get a second opinion on KIA match. Second opinion on KIA match is that is kind of matches KIA. (So its okay)

BANK SAT 4/1/2009

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 Partia I Job-Minutia

1 Back-Q=

SRO u/EI Explanation Focus Dist.

Link units ward KIA Only S

89 WE1SG2.4.41 Question appears to match KIA.

H 2

S Questions appears to be SRO only.

Containment radiation level is above the entry conditions for entry into Z.3. Will allow as is.

BANK SAT SAT 4/112009 90 G2.2.11 Question appears to match KIA.

F 2

S Question appears to be SRO only.

BANK SAT 4/1/2009 91 034G2.4.11 Question appears to match KIA.

H 2

X U May be SRO only, Distractors B, C, and 0 do not appear to be plausible. The original question had more plausible actions. The actions (procedure selection is Okay) do not appear to be plausible for the annunciators that have come into alarm.

BANK 2003 CATAWBA NRC Rework using a actual fuel handling piece of equipment.

Added an alarm for ctmt sump to make the correct answer clearer and remove doubt from stem.

SAT 4/28/2009 I.....-. -

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partia I Job-Minutia

1 8ack-Q=

SAO u/EI Explanation Focus Dist.

Link units ward KIA Only S

89 WE16G2.4.41 Question appears to match KIA.

H 2

S Questions appears to be SRO only.

Containment radiation level is above the entry conditions for entry into Z.3. Will allow as is.

BANK SAT SAT 4/1/2009 90 G2.2.11 Question appears to match KIA.

F 2

S Question appears to be SRO only.

BANK SAT 4/112009 91 034G2.4.11 Question appears to match KIA.

H 2

X U May be SRO only, Distractors B, C, and 0 do not appear to be plausible. The original question had more plausible actions. The actions (procedure selection is Okay) do not appear to be plausible for the annunciators that have come into alarm.

BANK 2003 CATAWBA NRC Rework using a actual fuel handling piece of equipment.

Added an alarm for ctmt sump to make the correct answer clearer and remove doubt from stem.

SAT 4/28/2009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws S.Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partia I Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

92 086A2.03 Question matches KIA. Appears to F

2 E be SRO only. (not very discriminating) In reading your distractor analysis you state that this room is different that's why Condition A is applicable. But a continuous fire watch is always required when welding is present. Will Discuss NEW Removed welding from the stem and added maintenance is being performed.

SAT 4/1/2009 93 G2.4.23 Question does not meet the KIA. There H

2 U is not a priority asked for in the stem. The question is basically asking how are NS pumps operated in ECA 1.1. There is also way too much information in the stem. There is also teaching (complete procedure flow path is given) so no prioritization takes place.

BANK Changed stem and all Distractors, however there are still two correct answers Band D.

Still work to be done. 4/1/2009 SAT 4.24.2009.

_1.....--

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 Partia I Job-Minutia

1 Back-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

92 086A2.03 Question matches KIA. Appears to F

2 E be SRO only. (not very discriminating) In reading your distractor analysis you state that this room is different that's why Condition A is applicable. But a continuous fire watch is always required when welding is present. Will Discuss NEW Removed welding from the stem and added maintenance is being performed.

SAT 4/112009 93 G2.4.23 Question does not meet the KIA. There H

2 U is not a priority asked for in the stem. The question is basically asking how are NS pumps operated in ECA 1.1. There is also way too much information in the stem. There is also teaching (complete procedure flow path is given) so no prioritization takes place.

BANK Changed stem and all Distractors, however there are still two correct answers Band D.

Still work to be done. 411/2009 SAT 4.24.2009.

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 Partia I Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

94 072A2.02 Question appears to match KIA.

H 2

X S Borderline SRO I will have another examiner review.

I understand that the sensitivity is in the SLC Basis document, but is it also common knowledge in the lesson plan? If not it is probably SRO only.

MODIFIED 2008 McGuire NRC EXAMINATION Change the non correct distractors to 5 gpd, then SAT 4/1/2009 95 063A2.02 Question appears to match the KIA. I F

2 X

E believe 4% is the standard flammability limit for H2.

With the 2% number coming from the basis document this may be SRO only knowledge. I will have another examiner review. This is a fundamental level question (applicant must recall two actions and both are immediate (RO knowledge) and recall some design basis information.

NEW Changed limit to volume limit in the battery room. Changed to 4%.

SAT 4/1/2009 96 025AA2.07 Question appears to match the KIA.

H 2

S Appears to be SRO only. Not Very Discriminating.

NEW SAT 97 078A2.01 Question appears to match KIA.

H 2

S Appears to be SRO only.

NEW SAT 4/1/2009

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 Partia I Job-Minutia

/

Back-Q=

SAO u/E1 Explanation Focus Dist.

Link units ward KIA Only S

94 072A2.02 Question appears to match KIA.

H 2

X S Borderline SRO I will have another examiner review.

I understand that the sensitivity is in the SLC Basis document, but is it also common knowledge in the lesson plan? If not it is probably SRO only.

MODIFIED 2008 McGuire NRC EXAMINATION Change the non correct distractors to 5 gpd, then SAT 4/1/2009 95 063A2.02 Question appears to match the KIA. I F

2 X

E believe 4% is the standard flammability limit for H2.

With the 2% number coming from the basis document this may be SRO only knowledge. I will have another examiner review. This is a fundamental level question (applicant must recall two actions and both are immediate (RO knowledge) and recall some design basis information.

NEW Changed limit to volume limit in the battery room. Changed to 4%.

SAT 4/112009 96 025AA2.07 Question appears to match the KIA.

H 2

S Appears to be SRO only. Not Very Discriminating.

NEW SAT 97 078A2.01 Question appears to match KIA.

H 2

S Appears to be SRO only.

NEW SAT 4/1/2009

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 Partia I Job-Minutia

1 Back-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

98 027AA2.07 Question appears to match the KIA. Not H

2 X

X X

U sure this is SRO only. A could also be considered correct. C and D have reasons, A does not. I will have another operator look at to ensure it is SRO only.

BANK Still to Work 4/1/2009 SAT 4/24/42009.

99 062AG2.1.31 Question appears to match KIA.

H 2

X X

E Distractor B is not plausible, why would you initiate another train of phase B and then go to the AP?

Does not appear to be SRO only. Knowledge of valves that close on a phase B is RO knowledge, Procedure entry is RO knowledge, and knowledge of how to use Abnormal and Emergency procedures is RO knowledge.

NEW Gerry to supply NEW KIA. 062AG2.1.32 or G2.1.2C Use of the word preferred, need to limit this as much as we can. New question uses precaution and limitation basis documentation and the lineup causes a degradation in SW flow, although this is a borderline match for the KIA will allow. Otherwise SAT 4.28.2009.

100 007EG2.4.35 Question appears to match the KIA.

H 2

X X

E Borderline SRO will have another examiner review to ensure question is SRO only. Distractors C and D do not appear to be plausible from the information you submitted with the question. The times listed in the procedure are 30 minutes, the times in the question distractors are 37.5 min, and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 15 min.

NEW Times are for actual time critical actions.

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 Partia I Job-Minutia

1 Back-Q=

SAO U/EI Explanation Focus Dist.

Link units ward KIA Only S

98 027AA2.07 Question appears to match the KIA. Not H

2 X

X X

U sure this is SRO only. A could also be considered correct. C and 0 have reasons, A does not. I will have another operator look at to ensure it is SRO only.

BANK Still to Work 4/1/2009 SAT 4/24/42009.

99 062AG2.1.31 Question appears to match KIA.

H 2

X X

E Oistractor B is not plausible, why would you initiate another train of phase B and then go to the AP?

Does not appear to be SRO only. Knowledge of valves that close on a phase B is RO knowledge, Procedure entry is RO knowledge, and knowledge of how to use Abnormal and Emergency procedures is RO knowledge.

NEW Gerry to supply NEW KIA. 062AG2.1.32 or G2.1.20 Use of the word preferred, need to limit this as much as we can. New question uses precaution and limitation basis documentation and the lineup causes a degradation in SW flow, although this is a borderline match for the KIA will allow. Otherwise SAT 4.28.2009.

100 007EG2.4.35 Question appears to match the KIA.

H 2

X X

E Borderline SRO will have another examiner review to ensure question is SRO only. Oistractors C and 0 do not appear to be plausible from the information you submitted with the question. The times listed in the procedure are 30 minutes, the times in the question distractors are 37.5 min, and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 15 min.

NEW Times are for actual time critical actions.

1.

2.

3. Psyctiometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partia I Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

Reduced information in all distractors.

SAT 4/1/2009 10Sats, 5 Unsats, and 10 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 8ack-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

Reduced information in all distractors.

SAT 4/112009 10 Sats, 5 Unsats, and 10 Enhancements

( FI~L)

ES-401, Rev. 9 McGuire 2009-301 RO Written Examination Review Worksheet Form ES-401-9

4. Job Content Flaws

5. Other

6.

7.

1. I 2. I

3. Psychometric Flaws LOK

LOD, (F/H)

(1-5)

Q#

Explanation Stem ! cues! T IF ! cred.! partial! JOb-! Minutia! #1 ! Back-! Q= ! SRO I utE!

Focus Dist.

Link units ward, KIA Only S

Instructions

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

1.

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

2.

Enter the level of difficulty (LaD) 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 dis tractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

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

14.

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

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

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

The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

The question requires reverse logic or application compared to the job requirements.

5.

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

6.

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

7.

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

ES-401, Rev. 9 McGuire 2009-301 RO Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

LOD.~--.--.r---.---~--~--~--~---r--~

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

/

8ack-Q=

SRO U/EI Explanation Focus Dist.

Link units ward* KIA Only S

Instructions

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

1.

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

2.

Enter the level of difficulty (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 stern lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

The stern 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 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.

I Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

/

B<;!ck-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

007EKt.06 Question appears to match KIA.

1 H

2 X

E Were RCPs secured due to loss of RN? Actually the first bullet does not add anything to the question (is not needed) if bullet two informs the operator that the NC pumps were secured. Move the answers around so that B is not the correct answer (as it is in the bank question)

BANK 2007 Harris NRC Exam Changed stem SAT 4/1/2009 001 EK3.14 Question appears to match KIA.

2 H

2 S BANK SAT SAT 4/1/2009 003K1.03 Question appears to match KIA. The 3

H 2

X E distractors have three parts to them. The applicant need only know two parts and can arrive at the correct answer. (#1 sealleakoff goes down, and NCDT level rises) the only distractor with these indications is B. The standpipe level alarm is not required to be known to answer this question. Need to limit the number of parts of the distractor to two.

Also some how we need to state that all of the items listed in the distractors are from the 1 B NC pump BANK Removed the NCDT reference in all distractors.

SAT 4/1/2009

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/EI Explanation Focus Dis!.

Link units ward KIA Only S

007EK1.06 Question appears to match KIA.

1 H

2 X

E Were RCPs secured due to loss of RN? Actually the first bullet does not add anything to the question (is not needed) if bullet two informs the operator that the NC pumps were secured. Move the answers around so that B is not the correct answer (as it is in the bank question)

BANK 2007 Harris NRC Exam Changed stem SAT 4/1/2009 001 EK3.14 Question appears to match KIA.

2 H

2 S BANK SAT SAT 4/1/2009 003K1.03 Question appears to match KIA. The 3

H 2

X E distractors have three parts to them. The applicant need only know two parts and can arrive at the correct answer. (#1 sealleakoff goes down, and NCDT level rises) the only distractor with these indications is B. The standpipe level alarm is not required to be known to answer this question. Need to limit the number of parts of the distractor to two.

Also some how we need to state that all of the items listed in the distractors are from the 1 B NC pump BANK Removed the NCDT reference in all distractors.

SAT 4/1/2009

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/EI Explanation Focus Dist.

Link units ward KIA Only S

007K5.02 Not sure if this matches the KIA. If the 4

F 2

X E Reactor vessel head vents discharge to the PRT/Quench tank, then it matches KIA if not then it does not. It appears from your explanation that it does not so the KIA is not matched. May need to change the KIA. I will get another examiners opinion prior to changing the KIA.

BANK 2005 McGuire NRC EXAM Head Vents do go to the PRT, so question is okay.

SAT 4/1/2009 012A1.01 Question kind of matches KIA.

5 H

2 S BANK 2005 McGuire NRC Exam SAT G2.1.1 Question appears to match the KIA. Not very 6

F 1

U discriminating.

BANK 2005 McGuire NRC Exam Will Replace 4/1/2009 Replaced Question. Distractor A appears to be correct. 4/23/2009.

SAT 2.24.2009.

040AG2.1.3 Question appears to match KIA.

7 H

2 S NEW SAT Made changes due to two correct answers found on validation.

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 Sack-Q=

SRO UlEi Explanation Focus Dis!.

Link units ward KIA Only S

007K5.02 Not sure if this matches the KiA. If the 4

F 2

X E Reactor vessel head vents discharge to the PRT/Quench tank, then it matches KiA if not then it does not. It appears from your explanation that it does not so the KiA is not matched. May need to change the KiA. I will get another examiners opinion prior to changing the KiA.

BANK 2005 McGuire NRC EXAM Head Vents do go to the PRT, so question is okay.

SAT 4/1/2009 012A1.01 Question kind of matches KiA.

5 H

2 S BANK 2005 McGuire NRC Exam SAT G2.1.1 Question appears to match the KiA. Not very 6

F 1

U discriminating.

BANK 2005 McGuire NRC Exam Will Replace 4/1/2009 Replaced Question. Distractor A appears to be correct. 4/23/2009.

SAT 2.24.2009.

040AG2.1.3 Question appears to match KiA.

7 H

2 S NEW SAT Made changes due to two correct answers found on validation.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (FIH)

(1-5)

Stem Cues TtF Creel. Partial Job-Minutia

t 8ack-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

008AK3.05 Question does NOT meet the KIA. The 8

H 2

X U KIA asks for the reasons for the SI termination criteria. There are no reasons in this question.

Furthermore there is way too much information on this page. Need to develop another question that matches the KIA, and does not have this much information on the page.

In this question criteria is not met so are we really testing any reasons? This question is listed as bank, is the question in the bank exactly like this?

BANK Still to work on using two criteria/adverse numbers.

Will continue to work. SAT 4.24.2009.

009EK3.21 Question kind of matches KIA.

9 H

2 X

U Distractors Band C do not appear to be plausible.

Saving borated water in CLA in case the reactor goes critical again? With a safety injection in progress? Why would anyone pick distractor B while in ES-1.2? The boron in the CLA is not much different than the boron in the RWST, but you have not isolated it? Need to rewrite.

BANK 2005 McGuire NRC Exam After changes this will be SAT.

4/23/2009. SAT 064K4.11 Question appears to match KIA.

10 H

2 S BANK SAT

~~~~--

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SAO U/EI Explanation Focus Dist.

Link units ward KIA Only S

008AK3.05 Question does NOT meet the KIA. The 8

H 2

X U KIA asks for the reasons for the SI termination criteria. There are no reasons in this question.

Furthermore there is way too much information on this page. Need to develop another question that matches the KIA, and does not have this much information on the page.

In this question criteria is not met so are we really testing any reasons? This question is listed as bank, is the question in the bank exactly like this?

BANK Still to work on using two criteria/adverse numbers.

Will continue to work. SAT 4.24.2009.

009EK3.21 Question kind of matches KIA.

9 H

2 X

U Distractors Band C do not appear to be plausible.

Saving borated water in CLA in case the reactor goes critical again? With a safety injection in progress? Why would anyone pick distractor B while in ES-1.2? The boron in the CLA is not much different than the boron in the RWST, but you have not isolated it? Need to rewrite.

BANK 2005 McGuire NRC Exam After changes this will be SAT.

4/23/2009. SAT 064K4.11 Question appears to match KIA.

10 H

2 S BANK SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

s. Other

6.

7.

Q#

LOK LOD (FfH)

(1-S)

Stem Cues TfF Credo Partial Job-Minutia

f Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

054AA 1.04 Question kind of matches the KIA. It 11 H

2 X

E would have been a better match to ask a question about indications that high pressure injection was in servicelbeing effective. Will let another examiner look at before making a decision.

NEW Will allow KIA and question Changed order of distractors due to validation. Answer changed to C.

SAT 4/1/2009 WE09EK3.2 Question appears to match* KIA.

12 H

2 S NEW SAT 058AA1.03 Question appears to match KIA. Need to 13 H

2 E explain distractors A and B. These may be plausible, but your explanation is not complete enough for me to understand if they are plausible or not. BANK B distractor okay, will replace A. 4/1/2009 Changed to Unit 2 b train SAT 4/23/2009 004K5.50 Question appears to match KIA.

14 F

1 E Distractors C and 0 may not be plausible. The reason for bypassing the demineralizers to protect the VCT from high temperature may not be plausible.

NEW Changed distractors B, C, and D.

SAT 4/1/2009 008K3.03 Question kind of matches KIA. This is 15 H

2 S more of an effect of a phase B on the RCPs. I understand that this is how CCW is lost but we really don't ask about the effect on RCPS.

BANK SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO u/E1 Explanation Focus Dist.

Link units ward KIA Only S

054AA 1.04 Question kind of matches the KIA. It 11 H

2 X

E would have been a better match to ask a question about indications that high pressure injection was in servicelbeing effective. Will let another examiner look at before making a decision.

NEW Will allow KIA and question Changed order of distractors due to validation. Answer changed to C.

SAT 4/1/2009 WE09EK3.2 Question appears to match* KIA.

12 H

2 S NEW SAT 058AA 1.03 Question appears to match KIA. Need to 13 H

2 E explain distractors A and B. These may be plausible, but your explanation is not complete enough for me to understand if they are plausible or not. BANK B distractor okay, will replace A. 4/1/2009 Changed to Unit 2 b train SAT 4/23/2009 004K5.50 Question appears to match KIA.

14 F

1 E Distractors C and D may not be plausible. The reason for bypassing the demineralizers to protect the VCT from high temperature may not be plausible.

NEW Changed distractors B, C, and D.

SAT 4/1/2009 008K3.03 Question kind of matches KIA. This is 15 H

2 S more of an effect of a phase B on the RCPs. I understand that this is how CCW is lost but we really don't ask about the effect on RCPS.

BANK SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (FfH)

(1-5)

Stem Cues TfF Credo Partial Job-Minutia

f Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

I I

010A4.01 Question appears to match KIA.

16 F

1 X

X E Distractor B does not appear to be plausible. 0 Should read Manually energize back up heaters to...

Are these actions in accordance with a procedure (AOP or ARP)? If so, the stem should state lAW...

Your KA match statement states that the operator is required to determine that the spray valve is failed open, however you give this data in the stem.

This question as written is not very discriminating.

The question is also a fundamental level question because all the operator needs is to remember the actions to take if a spray valve fails open.

Needs to be enhanced.

NEW Replaced some stem and distractors (8 and D)

Removed words.

SAT 4/1/2009 I

062AG2.2.40 Question appears to match KIA.

17 H

2 S NEW SAT WE11 EK1.2 Question appears to match KIA.

i 18 F

2 S NEW SAT i

073K3.01 Question appears to match KIA. Use a 19 F

2 E fourth bullet and state that power is lost to 1 EMF-38L. Then: Which one of the following describes the components that will receive an automatic action based on this lost? VQ only, VQ and VP etc.

-~--

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=

SAO u/EI Explanation Focus Dis!.

Link units ward KIA Only S

010A4.01 Question appears to match KIA.

16 F

1 X

X E Distractor B does not appear to be plausible. 0 Should read Manually energize back up heaters to...

Are these actions in accordance with a procedure (AOP or ARP)? If so, the stem should state lAW...

Your KA match statement states that the operator is required to determine that the spray valve is failed open, however you give this data in the stem.

This question as written is not very discriminating.

The question is also a fundamental level question because all the operator needs is to remember the actions to take if a spray valve fails open.

Needs to be enhanced.

NEW Replaced some stem and distractors (8 and D)

Removed words.

SAT 4/1/2009 062AG2.2.40 Question appears to match KIA.

17 H

2 S NEW SAT WE11 EK1.2 Question appears to match KIA.

18 F

2 S NEW SAT 073K3.01 Question appears to match KIA. Use a 19 F

2 E fourth bullet and state that power is lost to 1 EMF-38L. Then: Which one of the following describes the components that will receive an automatic action based on this lost? VQ only, VQ and VP etc.

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 Dist.

Link units ward KIA Only S

BANK 1999 McGuire NRC EXAM Made Changes as Requested.

SAT 4/1/2009 022AK1.03 Question appears to match KIA. Are 20 H

2 S these conditions operationally valid? Would not the actions in the plant have the operator control excess letdown flow to maintain pressurizer level? I know that you have procedures to deal with this and I do not believe that you would allow this to happen.

Please Explain. Explanation Okay, verify numbers.

MODIFIED SAT 4/112009 015K5.02 Question appears to match KIA. The 21 H

2 X

E explanation for D is much more in-depth than the other distractors. This makes a test taker tend to believe it is the correct answer. (and in this case it is)

Need to change distractor D to be more like distractor C. Source range will not energize...

BANK Changed distractor D to be more like C SAT 41212009 039G2.2.38 Question appears to match KIA. With 22 F

2 X

E two distractors with the setpoint of 1170, an operator would discount both A and D. Use two distractors with 1170 as the first number, and one of the others like 1190. The same for the second number. With 15# between most setpoints, use 1190 and 1235 for one of the distractors etc.

BANK

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (FfH)

(1-5)

Stem Cues TfF Credo Partial Job-Minutia

f Back-Q=

SRO U/EI Explanation Focus Dis!.

Link units ward KIA Only S

BANK 1999 McGuire NRC EXAM Made Changes as Requested.

SAT 4/1/2009 022AK1.03 Question appears to match KIA. Are 20 H

2 S these conditions operationally valid? Would not the actions in the plant have the operator control excess letdown flow to maintain pressurizer level? I know that you have procedures to deal with this and I do not believe that you would allow this to happen.

Please Explain. Explanation Okay, verify numbers.

MODIFIED SAT 4/1/2009 015K5.02 Question appears to match KIA. The 21 H

2 X

E explanation for D is much more in-depth than the other distractors. This makes a test taker tend to believe it is the correct answer. (and in this case it is)

Need to change distractor D to be more like distractor C. Source range will not energize...

BANK Changed distractor D to be more like C SAT 41212009 039G2.2.38 Question appears to match KIA. With 22 F

2 X

E two distractors with the setpoint of 1170, an operator would discount both A and D. Use two distractors with 1170 as the first number, and one of the others like 1190. The same for the second number. With 15# between most setpoints, use 1190 and 1235 for one of the distractors etc.

BANK

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

I Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO u/EI Explanation Focus Dist.

Link units ward KIA Only S

Changed as requested SAT 41212009 026G2.1.32 Question appears to match KIA.

23 F

2 S NEW SAT SAT 41212009 062G2.2.39 Question appears to match KIA.

24 F

2 S NEW SAT Changed distractor C to be more like D.

SAT 41212009 051AG2.4.11 Question appears to match KIA.

25 H

2 X

E Distractor 0 is not plausible. (Would not mitigate the event, it just would not matter any more). Remove the Trip the turbine and just leave the "Open Exhaust Hood Sprays. This will not improve vacuum. It will lower the exhaust hood temperature.

NEW Removed turbine trip D is now correct.

SAT 41212009 086K4.02 Question appears to match KIA.

26 F

2 X

E Recommend changing the A and B jockey pumps to lead and standby as you have it stated in the question explanation. This is a lot of information for the applicants to read.

BANK Changed to STBY and lead SAT 41212009

~

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 Dist.

Link units ward KIA Only S

Changed as requested SAT 41212009 026G2.1.32 Question appears to match KIA.

23 F

2 S NEW SAT SAT 41212009 062G2.2.39 Question appears to match KIA.

24 F

2 S NEW SAT Changed distractor C to be more like D.

SAT 41212009 OS1AG2.4.11 Question appears to match KIA.

25 H

2 X

E Distractor D is not plausible. (Would not mitigate the event, it just would not matter any more). Remove the Trip the turbine and just leave the "Open Exhaust Hood Sprays. This will not improve vacuum. It will lower the exhaust hood temperature.

NEW Removed turbine trip 0 is now correct.

SAT 41212009 086K4.02 Question appears to match KIA.

26 F

2 X

E Recommend changing the A and 8 jockey pumps to lead and standby as you have it stated in the question explanation. This is a lot of information for the applicants to read.

BANK Changed to STBY and Lead SAT 41212009

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 Dist.

Link units ward KIA Only S

0631<2.01 Question appears to match KIA, if you 27 F

2 X

E assume that the Back up Vapor extractor is a major DC load. 1 CXA is also a 125 VDC bus and 1 DP is a 250 volt bus. Is there not another DC bus with the same voltage? Distractors Band D may not be plausible. Will discuss.

NEW Will rewrite question. 41212009 This is a 125V valve/power supply and only one item is 125V. Need to fix distractors, all are 250V.

4/23/2009.

Made changes. SAT 2.24.2009.

029EA2.04 Does the direction to close the mini 28 F

2 X

U flow valves only apply to S.1? If so, then the question will match the KIA. If this is a generic system operating parameter then is does not match the KIA. The top of the stem could be removed and the applicant asked, WOOTF describes the maximum allowed NV flow-rate, and the value of NC system pressure that the mini-flow valve are closed.... This is a systems knowledge question as written, and is not really tied to FRP-S.1.

NEW Will attempt to write new question based on PORV step of S.1 orsomething similar SAT 4/23/2009.

028AA 1.01 Question appears to match the KIA.

29 H

2 X

E Again you are testing three items in the distractors, and the applicant need only know 2

_L-of the 3 to get the correct answer. Need to onlv

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/EI Explanation Focus Dist.

Link units ward KIA Only S

063K2.01 Question appears to match KIA, if you 27 F

2 X

E assume that the Back up Vapor extractor is a major DC load. 1 CXA is also a 125 VDC bus and 1 DP is a 250 volt bus. Is there not another DC bus with the same voltage? Distractors Band D may not be plausible. Will discuss.

NEW Will rewrite question. 41212009 This is a 125V valve/power supply and only one item is 125V. Need to fix distractors, all are 250V.

4/23/2009.

Made changes. SAT 2.24.2009.

029EA2.04 Does the direction to close the mini 28 F

2 X

U flow valves only apply to S.1? If so, then the question will match the KIA. If this is a generic system operating parameter then is does not match the KIA. The top of the stem could be removed and the applicant asked, WOOTF describes the maximum allowed NV flow-rate, and the value of NC system pressure that the mini-flow valve are closed.... This is a systems knowledge question as written, and is not really tied to FRP-S.1.

NEW Will attempt to write new question based on PORV step of S.l or something similar SAT4/23/2009.

028AA 1.07 Question appears to match the KIA.

29 H

2 X

E Again you are testing three items in the distractors, and the applicant need only know 2 of the 3 to get the correct answer. Need to onlv

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 Dist.

Link units ward KIA Only S

have two items in the distractors.

MODIFIED Changed distractors all A, Band D licensee requested 3 items and we tried to make it flow as appropriate for the charging flow.

SAT 41212009 WE03EA1.3 Question kind of matches the KIA.

30 F

2 X

E As written, three of the distractors contain reasons. The correct answer does not contain reasons. The KIA does not ask for reasons, and the question does not ask for reasons.

Need to add reasons to the stem and distractor A, or remove all of the reasons. (I understand that they are there to increase plausibility.)

NEW*

Removed all reasons, and changed stem.

SAT 41212009 022K1.04 Question appears to match KIA.

31 H

2 X

E Oistractor A should state lie" RV pump (if this is the only RV pump that will be running after the LOOP If it does not have power, we will have to look at different wording. If none of the RV pumps get emergency power then you should have listed the pumps that normally run).

Oistractor 0, pump should be plural Pumps.

BANK Changed A distractor and added (s)

SAT 41212009 I-.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

have two items in the distractors.

MODIFIED Changed distractors all A, Band D licensee requested 3 items and we tried to make it flow as appropriate for the charging flow.

SAT 41212009 WE03EA1.3 Question kind of matches the KIA.

30 F

2 X

E As written, three of the distractors contain reasons. The correct answer does not contain reasons. The KIA does not ask for reasons, and the question does not ask for reasons.

Need to add reasons to the stem and distractor A, or remove all of the reasons. (I understand that they are there to increase plausibility.)

NEW*

Removed all reasons, and changed stem.

SAT 41212009 022K1.04 Question appears to match KIA.

31 H

2 X

E Distractor A should state "C" RV pump (if this is the only RV pump that will be running after the LOOP If it does not have power, we will have to look at different wording. If none of the RV pumps get emergency power then you should have listed the pumps that normally run).

Distractor D, pump should be plural Pumps.

BANK Changed A distractor and added (s)

SAT 41212009

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/EI Explanation Focus Dist.

Link units ward KIA Only S

027K2.01 Question appears to match KIA. Why not 32 H

2 X

E change the last bullet to state containment pressure has just reached 3 psig. Get rid of phase B statement and have the distractors state1 B VE fan will be running. 1 A and 1 B will be running 1 B VE fan will start in 10 min etc. The phase B terminology could be viewed as a cue.

NEW Changed stem and all distractors SAT 41212009 077AK2.07 Question appears to match KIA. Stem 33 F

2 X

E should read: Which one of the following describes the reason that Turbine First Stage Impulse pressure is reduced to less than 340 psig prior to opening the Switchyard PCBs in accordance with AP-5? The lesson plan provided has the number listed as 360 psig.

BANK Made changes as requested SAT 41212009 01SAA2.11 Question appears to match KIA.

34 H

2 X

E Distractor D does not appear to be plausible. (with NI and NV unavailable how could you start feed and bleed) I think this was one of the questions you sent me earlier and I said it was okay. It still is okay, but with further review it appears that with the conditions in the stem it is not plausible.

MODIfiED Changed Distractor D as requested.

SAT 41212009 1---

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues TIF Credo Partial Job-Minutia

/

8ack-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

027K2.01 Question appears to match KIA. Why not 32 H

2 X

E change the last bullet to state containment pressure has just reached 3 psig. Get rid of phase B statement and have the distractors state 1 B VE fan will be running. 1 A and 1 B will be running 1 B VE fan will start in 10 min etc. The phase B terminology could be viewed as a cue.

NEW Changed stem and aI/ distractors SAT 41212009 077AK2.07 Question appears to match KIA. Stem 33 F

2 X

E should read: Which one of the following describes the reason that Turbine First Stage Impulse pressure is reduced to less than 340 psig prior to opening the Switchyard PCBs in accordance with AP-5? The lesson plan provided has the number listed as 360 psig.

BANK Made changes as requested SAT 41212009 01SAA2.11 Question appears to match KIA.

34 H

2 X

E Distractor 0 does not appear to be plausible. (with NI and NV unavailable how could you start feed and bleed) I think this was one of the questions you sent me earlier and I said it was okay. It still is okay, but with further review it appears that with the conditions in the stem it is not plausible.

MODIFIED Changed Distractor D as requested.

SAT 41212009

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 UlEI Explanation Focus Dist.

Link units ward KIA Only S

005K6.03 Question appears to match the KIA.

35 H

2 S MODIFIED SAT SAT 41212009 055EA1.06 Question appears to match the KIA. The 36 H

2 E stem is a little confusing considering a time line.

What happens first the LOCA, LOOP and 28 diesel failure? What are the conditions that we are asking for in the answers (if any other Sis' or auto starts occur?

BANK Made changes as requested.

SAT 41212009 003AK3.10 Question appears to match KIA.

37 H

2 S MODIFIED SAT SAT 41212009 006A3.06 Question appears to match KIA.

38 H

2 S BANK SAT SAT 41212009 068AK2.02 Question appears to match KIA.

39 F

2 X

E Teaching in the stem. Have a bullet state AP-17 Loss of control room has been entered. Which ONE of the following describes the reason why the operator at the reactor trip breakers shall not trip the reactor until directed to do so by the SRO at the ASP?

BANK SAT 41212009

~--

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

/

Back-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

005K6.03 Question appears to match the KIA.

35 H

2 S MODIFIED SAT SAT 41212009 055EA1.06 Question appears to match the KIA. The 36 H

2 E stem is a little confusing considering a time line.

What happens first the LOCA, LOOP and 28 diesel failure? What are the conditions that we are asking for in the answers (if any other Sis' or auto starts occur?

BANK Made changes as requested.

SAT 41212009 003AK3.10 Question appears to match KIA.

37 H

2 S MODIFIED SAT SAT 41212009 006A3.06 Question appears to match KIA.

38 H

2 S BANK SAT SAT 41212009 068AK2.02 Question appears to match KIA.

39 F

2 X

E Teaching in the stem. Have a bullet state AP-17 Loss of control room has been entered. Which ONE of the following describes the reason why the operator at the reactor trip breakers shall not trip the reactor until directed to do so by the SRO at the ASP?

BANK SAT 41212009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws S.Other

6.

7.

Q#

LOK LOD (F/H)

(1-S)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-0=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

078K3.02 Question appears to match the KIA. Is I

40 F

2 X

X E 1 NV-35A an indication that is listed in a procedure?

If it is then it is okay, but if it is not, it really only informs the operator that air pressure has lowered to the point that the valve has went closed. Distractor 'A does not appear to be plausible. It is normally closed. Question needs some enhancements.

Will Discuss.

NEW Changed stem SAT 41212009 011 A3.03 Question appears to match KIA.

41 H

2 S BANK SAT

,~-~- -- ~

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

0#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-0=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

078K3.02 Question appears to match the KIA. Is 40 F

2 X

X E 1 NV-35A an indication that is listed in a procedure?

If it is then it is okay, but if it is not, it really only informs the operator that air pressure has lowered to the point that the valve has went closed. DistractorA does not appear to be plausible. It is normally closed. Question needs some enhancements.

Will Discuss.

NEW Changed stem SAT 41212009 011A3.03 Question appears to match KIA.

41 H

2 S BANK SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO UlEi Explanation Focus Dist.

Link units ward KIA Only S

056AG2.4.35 Question appears to match KIA. I 42 F

2 X

E believe that B is also correct. There have been several instances where this has occurred in actual operating plants that have had a loss of power.

While your background document states that the thermal barrier is isolated to prepare the plant for recovery while protecting the CCW system from steam formation due to RCP thermal barrier heating.

This heating will cause steam formation in the thermal barrier. When the CCW pumps are started the steam in the thermal barrier will compress as system pressure rises causing a water hammer. The information in yellow does state that the steam will be flushed into the rest of the CCW system but it states that a an abnormal seal leakage would have to be present to exceed the cooling capacity of the CCW flow to that pump generating more steam to be swept in to the system. I feel that an applicant could argue that either B or C is correct.

BANK Is this not a JPM performed at your site? This is a very important task. I will get the opinion of another examiner before deciding what to do.

Changed distractor analysis, this is the reason for isolation, so we capitalized ISOLATION so that is would not be confused with restoring.

After much discussion SAT 41212009

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/EI Explanation Focus Dist.

Link units ward KIA Only S

056AG2.4.35 Question appears to match KIA. I 42 F

2 X

E believe that B is also correct. There have been several instances where this has occurred in actual operating plants that have had a loss of power.

While your background document states that the thermal barrier is isolated to prepare the plant for recovery while protecting the CCW system from steam formation due to RCP thermal barrier heating.

This heating will cause steam formation in the thermal barrier. When the CCW pumps are started the steam in the thermal barrier will compress as system pressure rises causing a water hammer. The information in yellow does state that the steam will be flushed into the rest of the CCW system but it states that a an abnormal seal leakage would have to be present to exceed the cooling capacity of the CCW flow to that pump generating more steam to be swept in to the system. I feel that an applicant could argue that either B or C is correct.

BANK Is this not a JPM performed at your site? This is a very important task. I will get the opinion of another examiner before deciding what to do.

Changed distractor analysis, this is the reason for isolation, so we capitalized ISOLATION so that is would not be confused with restoring.

After much discussion SAT 41212009

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/EI Explanation Focus Dist.

Link units ward KIA Only S

WE07EK1.3 Question appears to match KIA.

43 H

2 E Distractor A is not plausible as written. If you actuall~

had saturated conditions, why would no additional actions be required? Does ES-1.2 direct the operators to use enclosed reference Enclosure 4.3 curve 1.108 of OP/11A161 00/22? If not then this would be a hint to the operator that this was included, therefore it must be used. Need to discuss.

NEW Add new actions for A and B Will look at after completion.

SAT 2.24.2009.

WEOBEK2.1 Not sure if this meets the KIA. I believe 44 H

2 X

X U the KIA is assuming that you already have conditions that have placed the plant in the FRPs.

Also in the bank question that you submitted, distractor C was listed as one way to halt the cooldown, is this also correct?

MODIFIED Will replace question Rewrote question SAT 2.24.2009.

Question number 45 in the presented material is 45 H

2 S the same as question # 72 012K3.01 Question appears to match the KIA.

BANK SAT SAT 41212009 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 Dist.

Link units ward KIA Only S

WE07EK1.3 Question appears to match KIA.

43 H

2 E Distractor A is not plausible as written. If you actually had saturated conditions, why would no additional actions be required? Does ES-1.2 direct the operators to use enclosed reference Enclosure 4.3 CUNe 1.108 of OP/1/A/61 00/22? If not then this would be a hint to the operator that this was included, therefore it must be used. Need to discuss.

NEW Add new actions for A and B Will look at after completion.

SAT 2.24.2009.

WEOSEK2.1 Not sure if this meets the KIA. I believe 44 H

2 X

X U the KIA is assuming that you already have conditions that have placed the plant in the FRPs.

Also in the bank question that you submitted, distractor C was listed as one way to halt the cooldown, is this also correct?

MODIFIED Will replace question Rewrote question SAT 2.24.2009.

Question number 45 in the presented material is 45 H

2 S the same as question # 72 012K3.01 Question appears to match the KIA.

BANK SAT SAT 41212009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (FIH)

(1-5)

Stem Cues T/F Creel. Partial Job-Minutia

/

Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

033G2.4.31 Question appears to match KIA. What 46 H

2 E are the switch positions for the KF pumps? Typically if there is an on-off switch the pump does not auto-start on any condition. If there is not an auto position on the switch then it is probably not a plausible distractor. The material you sent describes a Start/Stop switch, Will discuss.

NEW Pump gets a permissive to start, but not an auto signal SAT 41212009 G2.2.40 Question appears to match KIA. Not sure 47 H

2 X

E distractor A is plausible. I do not know of a time that at least one charging pump is required to be operable. (are we talking NI pumps or NV pumps)

Which ever one it is we need to use that terminology.

BANK Add subsystems to all distractors and change distractor A to be one RHR and Both Charging.

SAT 41212009 WE16EA2.1 Question does not meet the KIA.

48 F

2 X

U WE16 refers to high containment radiation in the accident mode. And this question refers to conditions in containment during refueling. Need to write a question that matches the KIA.

BANK Will write a new question.

SAT 4/23/2009

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/EI Explanation Focus Dist.

Link units ward KIA Only S

033G2.4.31 Question appears to match KiA. What 46 H

2 E are the switch positions for the KF pumps? Typically if there is an on-off switch the pump does not auto-start on any condition. If there is not an auto position on the switch then it is probably not a plausible distractor. The material you sent describes a Start/Stop switch, Will discuss.

NEW Pump gets a permissive to start, but not an auto signal SAT 41212009 G2.2.40 Question appears to match KiA. Not sure 47 H

2 X

E distractor A is plausible. I do not know of a time that at least one charging pump is required to be operable. (are we talking NI pumps or NV pumps)

Which ever one it is we need to use that terminology.

BANK Add subsystems to all distractors and change distractor A to be one RHR and Both Charging.

SAT 41212009 WE16EA2.1 Question does not meet the KiA.

48 F

2 X

U WE16 refers to high containment radiation in the accident mode. And this question refers to conditions in containment during refueling. Need to write a question that matches the KiA.

BANK Will write a new question.

SAT 4/23/2009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

I Q#

LOK LCD (FtH)

(1-5)

Stem Cues TtF Credo Partial Job-Minutia

t 8ack-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

071A1.06 Question appears to match the KIA.

49 F

2 X

E Distractor C EMF-36 does not have a title after it, all of the others do. Not sure about the plausibility of distractor A. Needs further explanation.

Fundamental level question.

BANK After discussion decided that A was acceptable added name for EMF-36.

SAT 41212009 G2.1.37 Question kind of matches KIA. A better KIA 50 F

2 X

E match would be what administrative controls are maintained in the control room that the Reactor Operator must adhere to. Will discuss BANK Will rewrite question to better satisfy KIA.

SAT $/2312009 G2.1.27 Question appears to match KIA. D may be 51 F

2 X

E a subset of B. If the setpoint is <385 psig, then <

365 also meets this. May need to reword the distractors or stem.

BANK Changed all distractors.

SAT 41212009 079A4.01 Question appears to match KIA. Need to 52 F

2 X

E add a statement like Air systems are in their normal lineups.

BANK Removed U1 shutdown in a refueling outage from stem. (Air systems are in normal line up.)

SAT 41212009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 8ack-0=

SAO u/E1 Explanation Focus Dist.

Link units ward KIA Only S

071 A1.0S Question appears to match the KIA.

49 F

2 X

E Distractor C EMF-36 does not have a title after it, all of the others do. Not sure about the plausibility of distractor A. Needs further explanation.

Fundamental level question.

BANK After discussion decided that A was acceptable added name for EMF-3S.

SAT 41212009 G2.1.37 Question kind of matches KIA. A better KIA 50 F

2 X

E match would be what administrative controls are maintained in the control room that the Reactor Operator must adhere to. Will discuss BANK Will rewrite question to better satisfy KIA.

SAT $/23/2009 G2.1.27 Question appears to match KIA. 0 may be 51 F

2 X

E a subset of B. If the setpoint is <385 psig, then <

365 also meets this. May need to reword the distractors or stem.

BANK Changed all distractors.

SAT 41212009 079A4.01 Question appears to match KIA. Need to 52 F

2 X

E add a statement like Air systems are in their normal lineups.

BANK Removed U1 shutdown in a refueling outage from stem. (Air systems are in normal line up.)

SAT 41212009

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

/

Back-Q=

SRO UJEI Explanation Focus Dist.

Link units ward KIA Only S

034K1.02 Question appears to match the KIA.

I 53 F

2 S BANK SAT 028K3.01 Question appears to match KIA.

54 F

2 S BANK SAT 007A2.05 Question kind of matches KIA. Distractors 55 H

2 X

X U G and D are not plausible. These are a combination of the actual cooling methods and the applicant need not determine that a cooldown is not required, but that the methods are not correct. The stem also states that the PRT has just been cooled down. It should state that following conditions exist in the PRT and allow the operator to understand what parameter is exceeded and what actions need to be performed in accordance with a procedure.

(Procedure needs to be listed. (OP/1(2)/A6150/004)

BANK Will rewrite using cooldown that can be performed.

41212009 Made Changes SAT 4/23/2009 013K2.01 Question appears to match KIA. Is some 56 H

2 X

E of the "8" train EGGS equipment running? One could claim that there is not a correct answer because (with the 8 train components in service) 8 train components would still be operating. Need to change the stem to ask which train of EGGS equipment will get an auto start signal from the sequencer or something to that effect.

MODIFIED Made changes to auto start signal.

SAT41212009

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=

SAO U/EI Explanation Focus Dist.

Link units ward KIA Only S

034K1.02 Question appears to match the KIA.

53 F

2 S BANK SAT 028K3.01 Question appears to match KIA.

54 F

2 S BANK SAT 007A2.05 Question kind of matches KIA. Distractors 55 H

2 X

X U G and 0 are not plausible. These are a combination of the actual cooling methods and the applicant need not determine that a cooldown is not required, but that the methods are not correct. The stem also states that the PRT has just been cooled down. It should state that following conditions exist in the PRT and allow the operator to understand what parameter is exceeded and what actions need to be performed in accordance with a procedure.

(Procedure needs to be listed. (OP/1 (2)/A6150/004)

BANK Will rewrite using cooldown that can be performed.

41212009 Made Changes SAT 4123/2009 013K2.01 Question appears to match KIA. Is some 56 H

2 X

E of the "B" train EGGS equipment running? One could claim that there is not a correct answer because (with the B train components in service) B train components would still be operating. Need to change the stem to ask which train of EGGS equipment will get an auto start signal from the sequencer or something to that effect.

MODIFIED Made changes to auto start signal.

SAT41212009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues TIF Credo Partial Job-Minutia

1 8ack-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

025K5.01 Question appears to match the KIA.

57 H

2 X

U Distractors A and 8 are not plausible. 3 psig is a very low pressure and is the point that a phase "8" initiates, why would anyone think that this is the design pressure. It might be better to use the design bases accident. If the pressure for implementing Z.1 based on a red path is greater than 3 psig, then maybe this number could be used. Will discuss.

NEW After discussion left question as is. Much discussion on 3 psig and many things happening at this pressure. SAT 41212009 059A4.03 Question kind of matches KIA. Teaching 58 H

1 X

X X

X U in stem. Should not have statements like "best"in the stem. Use "correctly describes". This question better fits the KIA's that refer to a main feedwater malfunction or what will happen on a P-14 signal.

Will get another operator to review.

BANK Will write another question.

41212009 SAT 4123/2009 062A3.05 Question appears to match the KIA.

59 F

2 S BANK SAT 063A3.01 Question appears to match the KIA.

60 F

2 S BANK2007 McGuire NRC EXAM. SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO u/E1 Explanation Focus Dist.

Link units ward KIA Only S

025K5.01 Question appears to match the KIA.

57 H

2 X

U Distractors A and 8 are not plausible. 3 psig is a very low pressure and is the pOint that a phase "8" initiates, why would anyone think that this is the design pressure. It might be better to use the design bases accident. If the pressure for implementing Z.1 based on a red path is greater than 3 psig, then maybe this number could be used. Will discuss.

NEW After discussion left question as is. Much discussion on 3 psig and many things happening at this pressure. SAT 41212009 059A4.03 Question kind of matches KIA. Teaching 58 H

1 X

X X

X U in stem. Should not have statements like "best"in the stem. Use "correctly describes". This question better fits the KIA's that refer to a main feedwater malfunction or what will happen on a P-14 signal.

Will get another operator to review.

BANK Will write another question.

41212009 SAT 4/23/2009 062A3.05 Question appears to match the KIA.

59 F

2 S BANK SAT 063A3.01 Question appears to match the KIA.

60 F

2 S BANK2007 McGuire NRC EXAM. SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

025AK2.02 Question kind of matches the KIA.

61 H

2 X

U Will get another examiner to verify. Question is somewhat confusing. Does any other hot leg loop have SI flow or recirc flow? If not (I cannot tell from the documentation) then A could also be correct. If an ND train is aligned for spray, will it also be aligned for hot leg recirc?

BANK (This has NRC 1027 after it, what does that mean?)

Write new question on RHR. 41212009 SAT 4123/2009 103K4.06 Question appears to match the KIA.

62 F

2 S BANK SAT 017K6.01 Question appears to match the KIA. After 63 H

2 X

S reading the documentation provided I am still not sure that a 20 of temperature increase will yield an exact 20 of temperature indication decrease.

NEW Procedure supports above.

SAT 41212009 065AA1.01 Question appears to match the KIA.

64 H

2 S NEW SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 8ack-Q=

SRO U/EI Explanation Focus Dist.

Link units ward KIA Only S

025AK2.02 Question kind of matches the KIA.

61 H

2 X

U Will get another examiner to verify. Question is somewhat confusing. Does any other hot leg loop have SI flow or recirc flow? If not (I cannot tell from the documentation) then A could also be correct. If an NO train is aligned for spray, will it also be aligned for hot leg recirc?

BANK (This has NRC 1027 after it, what does that mean?)

Write new question on RHR. 41212009 SAT 4123/2009 1 03K4.06 Question appears to match the KIA.

62 F

2 S BANK SAT 017K6.01 Question appears to match the KIA. After 63 H

2 X

S reading the documentation provided I am still not sure that a 20 OF temperature increase will yield an exact 20 OF temperature indication decrease.

NEW Procedure supports above.

SAT 41212009 065AA1.01 Question appears to match the KIA.

64 H

2 S NEW SAT

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 Back-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

G2.3.4 Question appears to match the KIA. Not sure 65 F

2 X

E about the plausibility of Distractors A, G, and D. Will have another examiner look at the question. G and 0 distractors are actually measuring the same thing (extremities). 0 is a subset of G. Sent question to 4 other examiner. Administrative limits are more site specific, maybe this question could be asked using site admin limits. (Check to see if this is an appealed question)

MODIDIED Changed (deleted the given items in the stem SAT 41212009 073A1.01 Question appears to match KIA. The stem 66 F

2 X

E lists the radiation monitors as 1 EMF 38.39, and 40.

Is 1 EMF 38.39 one monitor? If you swap the sample point for one does it swap the sample point for all? It appears (but is not totally clear) that this is the case. Will discuss.

NEW After discussion and correct labeling of monitors determined to be SAT41212009 076A1.02 Question mayor may not meet the KIA, I 67 H

2 X

X X

U need to determine if we are testing reactor building or turbine building closed loop cooling systems.

From the information that you have given me it appears we are testing the RN effect on the KG system. The drawings that were included were for the Unit 1 RN system. The question stem refers to Unit 2 RN system. The analysis on distractor A states that if the trains were not split, this would be the correct answer. I don't think that if you increase flow to the KG heat exchanger that you will lower containment temperature, in fact it should rise

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/EI Explanation Focus Dist.

Link units ward KIA Only S

G2.3.4 Question appears to match the KIA. Not sure 65 F

2 X

E about the plausibility of Distractors A, G, and D. Will have another examiner look at the question. G and D distractors are actually measuring the same thing (extremities). D is a subset of G. Sent question to 4 other examiner. Administrative limits are more site specific, maybe this question could be asked using site admin limits. (Check to see if this is an appealed question)

MODIDIED Changed (deleted the given items in the stem SAT 41212009 073A1.01 Question appears to match KIA. The stem 66 F

2 X

E lists the radiation monitors as 1 EMF 38.39, and 40.

Is 1 EMF 38.39 one monitor? If you swap the sample point for one does it swap the sample point for all? It appears (but is not totally clear) that this is the case. Will discuss.

NEW After discussion and correct labeling of monitors determined to be SAT41212009 076A1.02 Question mayor may not meet the KIA, I 67 H

2 X

X X

U need to determine if we are testing reactor building or turbine building closed loop cooling systems.

From the information that you have given me it appears we are testing the RN effect on the KG system. The drawings that were included were for the Unit 1 RN system. The question stem refers to Unit 2 RN system. The analysis on distractor A states that if the trains were not split, this would be the correct answer. I don't think that if you increase flow to the KG heat exchanger that you will lower containment temperature, in fact it should rise

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/EI Explanation Focus Dist.

Link units ward KIA Only S

because flow would be taken away from it. I may have this all wrong, please explain. (I got the correct answer by just seeing what valve was adjusted and by looking for a component that was cooled by this valve.)

NEW Rewrote question SAT41212009 G2.4.39 Question appears to match the KIA.

68 F

2 S MODIFIED SAT G2.3.14 Question kind of matches the KIA. Why 69 H

2 X

X E does the stem state a Male worker... Is it different for a female? Distractor C has backward logic/language in it.

BANK Rewrite question C is correct also 41212009 Rewrote distractor C. 4/23/2009 057AA2.09 Question may match KIA. Does EVCA 70 H

2 X

E supply power to first stage turbine impulse pressure, and N-41? If so, why can you not leave power removed? By using the failed conditions of these instruments the question would then meet the KIA. If the instruments are not powered form EVCA then the KIA is not matched.

MODIFIED Take question back to work on. 41212009 Continued to work, changed question so that control rods moved and D was correct answer.

SAT 4/23/2009

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/EI Explanation Focus Dist.

Link units ward KIA Only S

because flow would be taken away from it. I may have this all wrong, please explain. (I got the correct answer by just seeing what valve was adjusted and by looking for a component that was cooled by this valve.)

NEW Rewrote question SAT41212009 G2.4.39 Question appears to match the KIA.

68 F

2 S MODIFIED SAT G2.3.14 Question kind of matches the KIA. Why 69 H

2 X

X E does the stem state a Male worker... Is it different for a female? Distractor C has backward logic/language in it.

BANK Rewrite question C is correct also 41212009 Rewrote distractor C. 4/23/2009 057AA2.09 Question may match KIA. Does EVCA 70 H

2 X

E supply power to first stage turbine impulse pressure, and N-41? If so, why can you not leave power removed? By using the failed conditions of these instruments the question would then meet the KIA. If the instruments are not powered form EVCA then the KIA is not matched.

MODIFIED Take question back to work on. 41212009 Continued to work, changed question so that control rods moved and D was correct answer.

SAT 4123/2009

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 8ack-Q=

SRO U/EI Explanation Focus Dist Link units ward KIA Only S

G2.2.17 Question appears to match the KIA. This 71 F

1 U question is not discriminating. Try listing a component in the stem and having the applicant determine what color should be applied.

BANK Continue to work.

41212009 SAT 4/23/2009 G2.4.45 Question appears to match the KIA.

72 H

2 X

X U Distractor D is not plausible. In the stem it is stated that reactor power is at 45%, why would you have to reduce power? What procedure would this be in accordance with? With power at 45% would this be an ATW8 as stated in the distractor analysis? It appears as written that there is not a correct answer.

BANK Rewrote question May have been a typo will investigate 41212009 8till working SAT 4/23/2009 G2.2.4 Question appears to match KIA.

73 F

2 8

NEW SAT 022K4.03 Question appears to match KIA.

74 H

2 8 NEW SAT

-I...- _'------

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 8ack-Q=

SAO u/E1 Explanation Focus Dist.

Link units ward KIA Only S

G2.2.17 Question appears to match the KIA. This 71 F

1 U question is not discriminating. Try listing a component in the stem and having the applicant determine what color should be applied.

BANK Continue to work.

41212009 SAT 4123/2009 G2.4.45 Question appears to match the KIA.

72 H

2 X

X U Distractor 0 is not plausible. In the stem it is stated that reactor power is at 45%, why would you have to reduce power? What procedure would this be in accordance with? With power at 45% would this be an ATWS as stated in the distractor analysis? It appears as written that there is not a correct answer.

BANK Rewrote question May have been a typo will investigate 41212009 Still working SAT 4123/2009 G2.2.4 Question appears to match KIA.

73 F

2 S NEW SAT 022K4.03 Question appears to match KIA.

74 H

2 S NEW SAT

I

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 8ack-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

061 A2.05 Question does not appear to meet the 75 H

2 X

U KIA. If the operator can take these actions with out the use of a procedure then the KIA is not met.

Need to ask a question where procedures direct the actions to mitigate/control the consequences of the malfunction.

NEW Need to ask question in a different way the way it is asked now, there is really no procedure guidance to do this. 41212009 Still needs work. 4123/2009 Tied question to Operations Management Expectations to close valves immediately.

Matches KIA. SAT 4/29/2009 25 Sats, 14 Unsats, and 36 Enhancements Generic Comments: All bank or modified questions should have the answers rotated from original (i.e. if the answer was originally A, swap the correct answer to B, C, or D.

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Credo Partial Job-Minutia

1 8ack-Q=

SRO utE!

Explanation Focus Dist.

Link units ward KIA Only S

061 A2.05 Question does not appear to meet the 75 H

2 X

U KIA. If the operator can take these actions with out the use of a procedure then the KIA is not met.

Need to ask a question where procedures direct the actions to mitigate/control the consequences of the malfunction.

NEW Need to ask question in a different way the way it is asked now, there is really no procedure guidance to do this. 41212009 Still needs work. 4123/2009 Tied question to Operations Management Expectations to close valves immediately.

Matches KIA. SAT 4/29/2009 25 Sats, 14 Unsats, and 36 Enhancements Generic Comments: All bank or modified questions should have the answers rotated from original (i.e. if the answer was originally A, swap the correct answer to 8, C, or D.

ES-403 Written Examination Grading Quality Checklist Facilit : McGuire 2009-301 Date of Exam: 05/22/09

1.

2.

3.

4.

5.

6.

Item Descri tion Clean answer sheets copied before Answer key changes and question deletions justified and documented Applicants' scores checked for addition errors reviewers s ot check> 25% of examinations Grading for all borderline cases (80 +/-2% overall and 70 or 80, as ap licable, +/-4% on the SRO-onl reviewed in detail All other failing examinations checked to ensure that grades are 'ustified Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed b half or more of the a licants Printed Name/Signature

a. Grader MAR~ A~!~!D / (rjl&lTTd-~

1---*--

b. Facility Reviewer(*)

NA

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

Form ES-403-1 Initials Date rJ& h sfoOfJ9 N/A

(*)

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

ES-403, Page 6 of 6 ES-403 Written Examination Grading Quality Checklist Facilit : McGuire 2009-301 Date of Exam: OS/22/09

1.

2.

3.

4.

5.

6.

Item Descri tion Clean answer sheets copied before Answer key changes and question deletions justified and documented Applicants' scores checked for addition errors reviewers s ot check> 25% of examinations Grading for all borderline cases (80 +/-2% overall and 70 or 80, as ap licable, +/-4% on the SRO-onl reviewed in detail All other failing examinations checked to ensure that grades are 'ustified Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed b half or more of the a licants Printed Name/Signature

a. Grader N\\1Wl' A:l3,~,£> ~

b. Facility Reviewer(*)

Nit

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

Form ES-403-1 Initials Date tJ& h S;kf)(l9 NJA

(*)

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

ES-403, Page 6 of 6

ES-403 Written Examination Grading Quality Checklist Form ES-403-1 Facility: fficGult"e Date of Exam: 5" -~ -cA Exam Level: RO~ SRO~

Initials Item Description a

b c

1.

Clean answer sheets copied before grading Icf3K

2.

Answer key changes and question deletions justified

~

and documented

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, I~

as applicable, +/-4% on the SRO-only) reviewed in detail

5.

All other failing examinations checked to ensure that grades 1fJ(

are justified

6.

Performance on missed questions checked for training

~

deficiencies and wording problems; evaluate validity of questions missed by half or more of the af>plicants Printed Name/Signature Date

a. Grader

b. Facility Reviewer(*)

\\=red G Kl~ ~(' ~AfI!

S-:lb-iA

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

(*)

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

ES-403, Page 6 of 6 ES-403 Written Examination Grading Quality Checklist Form ES-403-1 Facility: ffiCbu)re Date of Exam: S-~ -oq Exam Level: RO[2S SROJ&1 Initials Item Description a

b c

1.

Clean answer sheets copied before grading I ilK

2.

Answer key changes and question deletions justified V<<

and documented

3.

Applicants' scores checked for addition errors f~

(reviewers spot check> 25% of examinations)

4.

Grading for all borderline cases (80 +/-2% overall and 70 or 80, I~

as applicable, +/-4% on the SRO-only) reviewed in detail

5.

All other failing examinations checked to ensure that grades 11K are justified

6.

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

a. Grader

b. Facility Reviewer(*)

\\ red G Kirk ~(' ~AfI!

S-.J8-ifj

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

(*)

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

ES-403, Page 6 of 6

ML092400626

Text

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