ML100410113

Initial Exam 2009-302 Final Administrative Documents

ML100410113
Person / Time
Site:	Harris
Issue date:	01/05/2010
From:	NRC/RGN-II
To:
References
Download: ML100410113 (123)

Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Harris 2009-302 Date of Examination: 11/31/2009 Developed by: Written - Facility X NRCO II Operating - Facility X NRCO Target Chief Date* Task Description (Reference) Examiner's Initials

-180 1. Examination administration date confirmed (C.1.a; C.2.a and b) 4/28/2009

-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) 6/29/2009

-120 3. Facility contact briefed on security and other requirements (C.2.c) 7/0212009

-120 4. Corporate notification letter sent (C.2.d) 7/7/2009

[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 3)] 10/16/2009*

{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d) 9/16/2009

{-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility 9/2112009 licensee (C.2.h; C.3.e)}

. {-45} 8. Proposed examinations (including written, walk-through JPMs, and 10/16/2009 scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.g; 10/30/2009 ES-202)

-14 10. Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; 11/16/2009 ES-202)

-14 11. Examination approved by NRC supervisor for facility licensee review 11116/2009 (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) 11116/2009

-7 13. Written examinations and operating tests approved by NRC supervisor 11123/2009 (C.2.i; C.3.h)

-7 14. Final applications reviewed; 1 or 2 (if> 10) applications audited to confirm 11123/2009 qualifications I eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed 11123/2009 with facility licensee (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions 11123/2009 distributed to NRC examiners (C.3.i)

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

[Applies only] {Does not apply} to examinations prepared by the NRC. 'Licensee prepared exam, due with submittal.

• ES-201 Facility:

Item Examination Outline Quality Checklist Task Description Form ES-201-2 Date of Examination:

Initials a b* C#

1.

w R

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

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b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of E8-401 and whether ali KiA categories are appropriately sampled. ~ ~ ,

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

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

a. USing Form E8-301-5, verify that the proposed scenario sets cover the required number

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I of normal evolutions, instrument and component failures, technical specifications, and major transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected number X B1

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U and mix of applicants in accordance with the expected crew composition and rotation schedule

• " htt L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated \)

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

0 c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R and quantitative criteria specified on Form E8-301-4 and described in Appendix D. ~ r, lt

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

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

1 (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) testes)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form Ifr Ifr B

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

b. Verify that the administrative outline meets the criteria specified on Form E8-301-1:

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

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

~ ot su~uent days.

of applicants and ensure that no items are duplicated on sut>sequent ~ \)

4. a. Assess whether plant-specific priorities (inciuding PRA and IPE inSights) are covered l-in the appropriate exam sections. X S G

E

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. ~ 0D N

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c. Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5. ~ B 1-

d. Check for duplication and over1ap among exam sections. ~

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e. Check the entire exam for balance of coverage. '*"

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

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b. Facility Reviewer (*)

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c. NRC Chief Examiner (#) i(J(

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IVJJ1JUIU. Lr Note: # Independent NRC reviewer initial items in COiumn *c"; chief examiner concurrence required.

• Not applicable for NRC-prepared examination outlines

• ES-201 r Page 26 of 28

~~

ATTACHMENT 3 c- ~

. ,' . INITIAL EXAMINATION SECURITY AGREEMENT

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the period indicated below 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, provide performance feedback or allow an exam candidate to obtain under instruction watch standing time while under my direct control from this date until completion of the examination administration, except. except,as as specifically noted below and authorized by the NRC. Furthermore, I am aware ofthe physical security measures, requirements 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 period indicated below. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations, except as specifically noted below and authorized by the NRC.

Examination Period .JJ v..,\'-t l.o" OS v..,\Lf lo" 0S to bee. \.\.~'J ~'J 01 .

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ATTACHMENT 3 ,.-

INITIAL EXAMINATION SECmp:TY AGREEMENT

1. 'Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the period indicated below 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, provide performance feedback or allow an exam candidate to obtain under instruction watch standing time while under my direct control from this date until completion of the examination administration, except as specifically noted below and authorized by the NRC. Furthermore, I am aware of the physical security measures, requirements and understand that violation of the conditions of this agreement may result in cancellatLon 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 indioations 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 period indicated below. From the date that I entered into this security agreement until the completion of examination admi!;listration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations, except as specifically noted below and authorize,d by the NRC.

Examination Period '(;)

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ATTACHMENT 3 INITIAL EXAMINATION SECURITY AGREEMENT

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the period indicated below 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, provide performance feedback or allow an exam candidate to obtain under instruction watch standing time while under my direct control from this date until completion of the examination administration, except as specifically noted below and authorized by the NRC. Furthermore, I am aware of the physical security measures, requirements and understand that .vinlation (lfthec0nditions of this agreement may result in ca!l(;elbti0~ oftne eX:lmi:~2.t:o:1S a:-:ci/or a:1 enf;)r::ement 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 period indicated below. From the date that 1 entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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I TAP-410 I Rev. 13 I Page 18 of2S1

Lucky, Archie From: MacDougall, Don Sent: Tuesday, December 22,2009 10:21 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement To the best of my knowledge, i did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations.

Don MacDougall From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 To: Kennedy, Alan T.; MacDou9all, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, f\latthew; Overly, John; Dills, John; Weber, r"like; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-03.02) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me' for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

liTo the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this,stateme,nt you may remove your exam ba<;lge. Eithar send me your badge through the company mail or leave your security badge on rny desk the next time you are at the HNP Training center.

Thank you again, IIl"e;(,/& lae'ff Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386 1

Lucky. Archie From: O'keefe, James Sent: Tuesday, December 22, 2009 5:44 AM To: Lucky, Archie

Subject:

2009B ILC

Archie, To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations.

Jint (9':Keefe Shift Manager - Work Control Center HNP Operations 5413 Shearon Harris Road HNP Zone 6 New Hill, NC 27562 Caronet: 8-751-2956 Bell: 919-362-2956 Pager: 919-982-3613 mailto:james.o'keefe@pgnmail.com 1

Lucky, Archie From: Embree, Randall Sent: Tuesday, December 22,200912:07 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations.

~~&m&tee Senior Reactor Operator / Shift Technical Advisor Harris Nuclear Plant From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, fVlatthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, Ifl"e~;e Lae~

Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 1

Lucky, Archie From: Butner, Richard (Keith)

Sent: Wednesday, December 30, 2009 7:33 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations --- Keith Butner 12/30/09 From: Lucky, Archie Sent: Monday, December 21,2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, Matthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

liTo the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion ofthe examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, l1t<'eirie /t{ci;t Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386

~

~: Progress Energy 1

Lucky, Archie From: Kang, Myung Sent: Tuesday, December 22, 2009 7:55 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement Take me off the list, I no longer want the red badge.

From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, ~1atthew; Overly, John; Dills, John; Weber, IVJike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to hove an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NR.C licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing e~aminations."

After you send me this statement you may remove your exam badge. Either ser.tdme your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, If~o!t;e LaOl!

Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386

"~

~~ Progress Energy 1

Lucky, Archie From: Seeley, Michael Sent: Monday, December 21, 20094:00 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement Attachments: image001.gif To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6,2009 - December 18,2009. From the d.ate that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

1

Lucky, Archie From: Bunt, David Sent: Tuesday, December 22, 2009 11 :02 AM To: Lucky, Archie

Subject:

exam security

Archie, To the best of my knowledge, I did not divulge to any unauthorized persQlls any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations. I will be sending my badge to you via company mail with the rest of C shift.

Dave Bunt RO C-shift 1

Lucky, Archie From: Stephenson, Robert Sent: Monday, December 21, 2009 1:49 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement Attachments: image001.gif To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18,2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations.

Robert D Stephenson Sr.

1

Lucky, Archie From: Kelly, Kyle Sent: Saturday, December 26, 2009 6:24 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations.

1<Jfe1<effJ Senior Control Operator / Shift Technical Advisor

'B'Shift From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, Matthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, Ift<'e!t;~ ((l.ei, Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 1

Lucky, Archie From: Kennedy, Alan T.

Sent: Monday, December 21, 2009 3:21 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement Merry, Merry Christmas.

I did not divulge any exam related knowledge to any HNP license candidates.

Alan Kennedy From: Lucky, Archie Sent: Mon 12/21/2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, fvlatthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, If~olv;e  !'ao'tJ Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386

.~

~ Progress Energy 1

Lucky, Archie From: Moore, Rick Sent: Monday, January 04,20109:20 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement I concur with the examination security statement.

Rick Moore From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, 1'1atthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, IfI"O~/~  !.ao't Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386

.~

~j Progress Energy 1

Lucky, Archie From: Nemec, Michael Sent: Monday, December 28, 2009 7:58 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement "To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

Operations Initial Training Brunswick Nuclear Plant 910.457.2204 From: Lucky, Archie Sent: Monday, December 21,2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, Matthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, 1

11t<'(}!v;~ /.t(ot, Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386

~ Progress Energy 2

Lucky, Archie Bolin, Bob From:

Sent: Tuesday, December 22, 2009 9:40 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement

Archie, I agree with the statement below.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion ofthe examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was ad ministered these licensing examinations."

You can remove my name from your security agreement.

Bob Bolin From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 PM .

To: Kennedy, AI:ln T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, !'vlatthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry .

Subject:

2009B NRC Exam Security Agreement Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion ofthe examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security bad~e on my desk the next time yo.u are at the HNP Training center.

Thank you again, lft<'e~/~ iaet, Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 1

Lucky, Archie From: Christopherson, Mark Sent: Monday, December 21, 2009 1:02 PM To: Lucky, Archie

Subject:

NRC Security Agreement "To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

Merry Christmas Archie!

!Iat<-t Ch,N6>to;kl",sw(

(]tJl(tl"tJ/ RtJtJ/!( t"l~I"(}/J'tJr-If ti,ift 1

Lucky, Archie From: Leech, Matthew Sent: Monday, December 21, 2009 12:36 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement Archie "To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

Yes, this statement is still true.

Matthew S. Leech From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, Matthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, 1If<'(},~;~ Lt{(J.f;j Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 1

Lucky, Archie From: Overly, John Sent: Monday, December 21,2009 12:37 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement Archie:

((To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations./I

Thanks, John From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, tvlatthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

((To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations./I After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, Ifl"(}k/~ ta(}~

Senior Nuclear Operations Instructor 1

Lucky, Archie From: Dills, John Sent: Monday, December 21, 2009 1:28 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement This is my conformations that: "To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6,2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

John Dills From: Lucky, Archie Sent: Mon 12/21/2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, Matthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, 1I~6~/~ !.ae~

Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386 1

Lucky. Archie From: Weber, Mike Sent: Thursday, December 31, 20097:54 AM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations.

Superintendent - Operations Support Harris Plant - Progress Energy Bell: (919) 362-2894/ Voicenet: 8-751-2894 Pager: (919) 565-1088/ Fax (919) 362-2960 mike.weber@pgnmail.com From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 PM To: Kennedy, Alan T.; MacDougall, Don; McLaughlin, Duane; O'keefe, James; Embree, Randall; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Kelly, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, Matthew; Overly, John; Dills, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you all for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I will get take you off the agreement.

liTo the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, 1

/freitie- Lae~

Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386

~ Progress Energy 2

Lucky, Archie From: English, Tim Sent: Monday, December 21, 2009 6: 18 PM To: Lucky, Archie

Subject:

RE: 2009B NRC Exam Security Agreement "To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion of the examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

Tim English From: Lucky, Archie Sent: Monday, December 21, 2009 12:29 To: Kennedy, Alan T.; MacDouga", Don; McLaughlin, Duane; O'keefe, James; Embree, Randa"; Kang, Myung; Butner, Richard (Keith); Seeley, Michael; Bunt, David; Stephenson, Robert; Ke"y, Kyle; Moore, Rick; Nemec, Michael; Bolin, Bob; Christopherson, Mark; Leech, rv1atthew; Overly, John; Di"s, John; Weber, Mike; English, Tim Cc: Bailey, Ken; Toler, Terry

Subject:

2009B NRC Exam Security Agreement Importance: High Happy Holidays to you and your family, The 2009B NRC Exam (2009-0302) has been completed. Thank you a" for contribution to this exam. I need to have an email conformation sent to me for the security agreement post-examination sign off.

Send me conformation that you can sign off for this post-examination statement and I wi" get take you off the agreement.

"To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during July 6, 2009 - December 18, 2009. From the date that I entered into this security agreement until the completion ofthe examination administration, I did not instruct, evaluate, provide performance feedback or allowed under instruction watches while under my direct control to any applicant who was administered these licensing examinations."

After you send me this statement you may remove your exam badge. Either send me your badge through the company mail or leave your security badge on my desk the next time you are at the HNP Training center.

Thank you again, lf~eJt/~  !.ae't Senior Nuclear Operations Instructor Licensed Operator Continuing Training Harris Nuclear Plant 919-362-3386 VNet 772-3386 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Harris Nuclear Plant Date of Examination: 11/30/2009 Examination Level: RO

• SRO 0 Operating Test Number: 05000400/2009302 Administrative Topic Type Describe activity to be performed (see Note) Code*

Response to Voids In the Reactor Vessel - Calculate Conduct of Operations Reactor Vessel Maximum Vent Time. (JPM ADM-096)

M,R KIA EPE E10 EK3.2 2009B NRC RO A1-1 Perform A Manual Shutdown Margin Calculation Conduct of Operations (JPM-ADM-019)

M,R KIA G2.1.25 2009B NRC RO A1-2 Determine Clearance Requirements for a CSIP Equipment Control D,R (JPM ADM-021)

KIA G.2.2.13 2009B NRC RO A2 Using Survey Maps, Simplified Drawings, Plant Maps and valve lists, determine stay times while Radiation Control N,R performing a clearance activity (JPM ADM-100)

KIA G2.3.4 2009B NRC RO A3 NOT SELECTED FOR RO Emergency Procedures/Plan N/A 2009B NRC RO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; S 4 for SROs & RO retakes) (1 )

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

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

November 30, 2009 FINAL

2009B NRC RO Admin JPM Summary 20098 NRC RO A1 Response to Voids In Reactor Vessel- Calculate Reactor Vessel Maximum Vent Time (JPM ADM-096) Modified KIA EPE E10 EK3.2 - Natural Circulation with Steam Void in Vessel withlwithout RVLlS - Normal, abnormal and emergency operating procedures associated with (Natural Circulation with Steam Void in Vessel with/without RVLlS). RO 3.2/ SRO 3.7 The plant was at 100 percent power when a Small Break LOCA occurred. The RCP have been secured, SI terminated, RVLlS Upper Range reads 85 percent, PZR level is 90 percent, RCS Pressure is 1560 psig, Containment Temp is 195°F and Containment Hydrogen concentration is 2.15 percent. Based on these conditions a void has formed in the Reactor Vessel. The crew has completed preparing the Containment for Reactor Vessel venting.

The applicant is required to calculate the maximum time the Reactor Vessel should be vented, using Attachment 1 of FRP-I-3, Response To Voids In Reactor Vessel. The calculation should be determined to the second to allow timing using the MCR timer.

This JPM has been modified by changing all values provided as initial conditions. The answer is now over one minute different than the original version with a tolerance of +/- 5 seconds.

20098 NRC RO A1 Perform A Manual Shutdown Margin Calculation (JPM-ADMIN-019)

Modified KIA G2. 1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10/43.5/45.12) RO 3.9 SRO 4.2 The plant is operating at 52% power and the CRS will direct the applicant to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, for the current plant conditions.

This JPM has been modified by changing all values provided as initial conditions and using current cycle curves will yield a different value of Shutdown margin.

20098 NRC RO A2 - Determine the Maximum Allowed Indicated Flow for MCR Ventilation (JPM ADM-101) NEW Equipment Control KIA G 2.2.13 Knowledge of tagging and clearance procedures.

(CFR: 41.10/45.13) RO 4.1 SRO 4.3 The plant is defueled. CSIP 1B-SB is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. The applicant will be directed to determine the clearance requirements for CSIP 1B-SB using the SFDs, and System Operating Procedures, as necessary. They must provide complete electrical and mechanical protection and provide the necessary vent and drain paths. The will be informed that the SSO has approved using single valve isolation.

November 30, 2009 FINAL

20098 NRC RO Admin JPM Summary (continued) 20098 NRC RO A3 (Common) - Using Survey Maps, Simplified Drawings, Plant Maps and valve lists, determine stay times while performing a clearance activity (JPM ADM-100) New KIA G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12143.4145.10) RO 3.2 SRO 3.7 The applicant will be supplied a survey map of a location in the RAB and a clearance mission to complete in this radioactive area. The location also contains one or more hot spots. They must determine the individual stay times for two Auxiliary Operators (AD) without exceeding the annual administrative dose limits. They will be provided Survey Maps, Simplified plant drawings to locate valves, Plant Maps of the area and a plant valve list to determine the location of the valves they will be hanging a clearance on. The given information will supply the accumulated annual whole body doses for the two ADs, one of which recently worked for another utility. They must perform their calculations based on Progress Energy Administrative Dose Limits.

20098 NRC RO A4 - NOT SELECTED FOR RO FINAL Revision summary:

Replaced Admin RO JPM A2 - Bank JPM ADM-021 "Determine Clearance Requirements for a CSIP" November 30, 2009 FINAL

FnJAL sf<<)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Harris Nuclear Plant Examination Level: RO D SRO

. Date of Examination: 1113012009 Operating Test Number: 0500040012009302 Administrative Topic Type Describe activity to be performed (see Note) Code*

During a loss of shutdown cooling, determine the time Conduct of Operations that the RCS will reach core boiling and core boil-off N,R conditions (JPM ADM-005)

KIA G2.1.20 20098 NRC SRO A1-1 Determine Boric Acid Addition Following Control Room Evacuation (JPM IP-049)

Conduct of Operations M,R KIA G2.1.25 20098 NRC SRO A1-2

'I

, " Perform Review of Partial OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4.

Equipment Control N,R (JPM ADM-102)

KIA G2.2.37 20098 NRC SRO A2 Using Survey Maps, Simplified Drawings, Plant Maps and valve lists, determine stay times while Radiation Control N,R performing a clearance activity (JPM ADM-100)

KIA G2.3.4 20098 NRC SRO A3 Given a set of conditions, Classify an Event Emergency Procedures/Plan (JPM ADM-099)

N,R KIA G2.4.41 20098 NRC SRO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:::; 3 for ROs; :::; 4 for SROs & RO retakes) (0)

(N)ew or (M)odifiedfrom bank (2: 1) (5)

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

November 30, 2009 FINAL

2009B NRC SRO Admin JPM Summary 2009B NRC SRO A1 During a loss of shutdown cooling, determine the time that the RCS will reach core boiling and core boil-off conditions. (SRO JPM ADM-005) New KIA G2.1.20 - Ability to interpret and execute procedure steps.

(CFR: 41.10/43.5/45.12) RO 4.6 SRO 4.6 The applicant will be provided with initial plant conditions. A plant shutdown for refueling is in progress with the Reactor Vessel head, off when a loss of RHR has occurred. The crew is implementing AOP-020, Loss of RCS Inventory or Residual Heat Removal While Shutdown.

The SRO applicants must first determine which of the four plant curves to use (H-X-8 through H-X-11) and then calculate the time the RCS will reach core boiling and core boil-off.

2009B NRC SRO A1 Determine Boric Acid Addition Following Control Room Evacuation (JPM IP-049) Modified KIA G2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10/43.5/45.12) RO 3.9 SRO 4.2 The Control Room has been evacuated and the MCB transfer to the ACP has been completed. Plant management has directed a plant cooldown to mode 5 utilizing AOP-004.

Given an OST-1036 cold shutdown boron requirement, the candidate must use curves to calculate gallons of Boric Acid and change in Boric Acid Tank level to complete section 3.2 step 25.

This JPM has been modified by providing new initial conditions which leads to a new answer that is substantially different than the original.

2009B NRC SRO A2 (Common) - Perform Review of Partial OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4. (JPM ADM-102) New KIA G2.2.37 - Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7/43.5/45.12) RO 3.6 SRO 4.6 Acting as the CRS and with the plant operating at 100% power the applicant will review a completed Operational Surveillance Test for the CVCS/SI systems. They will be required to identify any deficiencies. Next they will make an operability determination based on their findings.

November 30, 2009 FINAL

2009B NRC SRO Admin JPrJi' Summary (continued) 2009B NRC SRO A3 (Common) - Using Survey Maps, Simplified Drawings, Plant Maps and valve lists, determine stay times while performing a clearance activity. (JPM ADM-1 00)

KIA G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12/43.4 /45.10) RO 3.2 SRO 3.7 The applicant will be supplied a survey map of a location in the RAB and a clearance mission to complete in this radioactive area. The location also contains one or more hot spots. They must determine the individual stay times for two Auxiliary Operators (AO) without exceeding the annual administrative dose limits. They will be provided Survey Maps, Simplified plant drawings to locate valves, Plant Maps of the area and a plant valve list to determine the location of the valves they will be hanging a clearance on. The given information will supply the accumulated annual whole body doses for the two AOs, one of which recently worked for another utility. They must perform their calculations based on Progress Energy Administrative Dose Limits.

2009B NRC SRO A4 - Given a set of conditions, Classify an Event (JPM ADM-099) New KIA G2.4.41 Knowledge of the emergency action level thresholds and classifications (CFR: 41.10/43.5/45.11) RO 2.9 SRO 4.6 Given a set of initial conditions and the EAL Flow Path, the candidate must classify the appropriate Emergency Action Level for the event in progress.

FINAL Replaced SRO Admin JPM A2 with "Perform Review of Partial OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4.

November 30,2009 FINAL

F itVAL ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Shearon Harris Date of Examination: 11/30/2009 Exam Level: RO SRO-I SRO-U Operating Test No.: OSOO0400/2009302 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1JPM Title Type Code* Safety Function

a. .Initiate Emergency Boration following a Reactor Trip A,M,S,L 1 (AOP-002) (JPM CR-037)

KIA APE024AA1.17

b. Fill a Cold Leg Accumulator (at power and level has D,S 2 decreased to 68%, fill accumulator level to normal)

(OP-110) (JPM CR-21S)

KIA 006A1.13 RO ONLY

c. Loss Of Service Water (Line Break) N,S 4S (AOP-022) (JPM CR-238)

KIA APE 062 AK3.03

d. Decreasing CCW Surge Tank Level A,D,S 8 (AOP-014) (JPM CR-044)

KIA APE 026 AA1.05

e. Respond to High RCS Pressure at Power A,D,S 3 (AOP-019) (JPM CR-OS1)

KIA APE 027 AA2.16

f. Loss of All AC A,D,EN,S 6 (EOP-EPP-001) (JPM CR-059)

KIA APE 056 AK3.02

g. Startup a Reactor Coolant Pump following Maintenance A,M,S,L 4P (OP-l00) (JPM CR-005)

KIA 003A2.02

h. Place an Excore NI Channel Out Of Service at Power D,S 7 (OWP-RP-26) (JPM CR-019)

KIA 015 A4.03 November 30, 2009 - FINAL Page 1 of 7

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Shearon Harris Date of Examination: 11/30/2009 Exam Level: RO SRO-I SRO(U) Operating Test No.: 05000400/2009302 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Restore Power To An Emergency Bus E,EN,N 6 (OP-155) (JPM IP-238)

KIA 068 AA 1.10

j. Transfer Control To the ACP D,E,L 7 (AOP-004) (JPM IP-050)

KIA 068 AA 1.21

k. Torque Shut The VCT Outlet Valves D,E,R 2 (AOP-017) (JPM IP-212)

KIA 004A1.06

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (5/5/3)

(C)ontrol room (D)irect from bank :59/:58/:54 (7/6/3)

(E)mergency or abnormal in-plant  ::::1/::::1/<:1 (3/3/2)

(EN)gineered safety feature - / - / ::::1 (2/2/1 )

(L)ow-Power / Shutdown  ::::1/::::1/::::1 (3/3/3)

(N)ew or (M)odified from bank including 1(A)  ::::2/::::2/::::1 (4/4/2)

(P)revious 2 exams S3/S3/S2 (0/0/0)

(R)CA  ::::1/::::1/::::1 (1/1/1 )

(S)imulator November 30,2009 - FINAL Page 2 of 7

2009B NRC Control Room/ln-Plant JPM Summary Operating Test No.: 05000400/2009302 JPM a - Initiate Emergency Boration Following a Reactor Trip (JPM CR-037) Alternate Path and Modified KIA APE024 AA 1.17 (3.9/3.9) Ability to operate and / or monitor the following as they apply to Emergency Boration: Emergency borate control valve and indicators (GFR 41.7 / 45.5/45.6) RO 3.9 SRO 3.9 Initiate Emergency Boration in accordance with AOP-002, EMERGENCY BORATION, following a reactor trip. The alternate path is to take corrective action for two or more stuck rods as determined in EPP-004, REACTOR TRIP. Used in 2008 NRC Exam this JPM was modified from Bank JPM CR-037 by failing first boration path driving the applicant to use secondary means. 1CS-278 Emergency Boric Acid Addition valve will not open (Green light) RNO to step 3, 1CS-156, Make Up to CSIP Suction FCV-113B will have double indication and flow will be less than the required 30 gpm, RNO to step 6, the applicant will not be able to verify at least 90 gpm flow from the RSWT and with one BA pump in operation RNO to step 7. The alternate boric acid flow path must now be re-aligned and 1CS-155 must be opened. The applicant will be able to verify and maintain >30 gpm boric acid flow to the CSI P suction until the boration is completed.

JPM b - Fill a Cold Leg Accumulator (at power - level has decreased to 68%, fill level to normal) (JPM CR-215) RO ONLY KIA 006 A 1.13 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the EGGS controls including: Accumulator pressure (level, boron concentration)

(GFR: 41.5/45.5) RO 3.5 SRO 3.7 With the plant operating at 100% power the 'A' Accumulator level has decreased over time to - 68%. The CRS directs the applicant to fill the 'A' Accumulator level to 72% in accordance with OP-11 0 section 8.1. To fill the Accumulator will require coordination between local operators and the MCR. The lineup to fill the Accumulator contains a portion of piping that is Non-Safety related. Due to this line being placed in service the RWST and the Accumulator will become inoperable per Tech Specs during the fill (a one hour action statement). The fill will be concluded when level is returned in the 'A' Accumulator is 72% and pressures are balanced.

HNP 2009B NRC Exam Form ES-301-2 November 30,2009 - FINAL Page 3 of 7

2009B NRC Control Room/ln-Plant JPM Summary Operating Test No.: 05000400/2009302 JPM c - Loss of Service Water Line (line break) (JPM CR-238) New KIA APE 062 AK3.03 Knowledge of the operational implications of the following concepts as they apply to the Loss of Nuclear Service Water: Guidance actions contained in EOP for Loss of nuclear service water (CFR 41.8/41.10/45.3) RO 4.0 SRO 4.2 With the unit operating at 100% power steady state conditions a large service water leak occurs. The applicant will identify that the condition by MCB annunciators and notification from the RAB NLO. The applicant will be expected to verbalize the immediate actions of AOP-022, Loss of Service Water. They will be challenged with determining the appropriate section the procedure to transition into and then continue with the identification of the leak. They will be required to secure the running ESW pump on the ruptured header and maintain the pump in STOP until the discharge pressure is low enough to lock out the auto start feature.

JPM d - Decreasing CCW Surge Tank Level (JPM CR-044) Alternate Path KIA APE 026 AA 1.05 - Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: The CCWS surge tank, including level control and level alarms, and radiation alarm (CFR 41.7 / 45.5 / 45.6) RO 3.1 / SRO 3.1 With the plant operating at 100% steady state the applicant will respond to a computer alarm for the Component Cooling Water systems. When the alarm is checked the applicant will identify that the CCW surge tank level is lower than normal. Soon after the first indication additional alarms will actuate indicating that the tank level is continuing on a lowering trend. The applicant is expected to recognize entry conditions for AOP-014, Loss of Component Cooling Water are met. The applicant will work through the procedure in attempts to maintain surge tank level and the running CCW pump in service. The leak size is large enough that level will not be maintained. lAW AOP-014 they must isolate charging flow and subsequently manually trip the Reactor.

JPM e - Respond to High RCS Pressure (JPM CR-051) Alternate Path KIA APE 027 AA2.16 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: Actions to be taken if PZR pressure instrument fails low (CFR: 43.5/45.13) RO 3.6 SRO 3.9 With the plant operating at 100% steady state the applicant will respond to increasing RCS pressure which will be identified by MCB annunciators and Pressurizer pressure indications. The applicant is expected to recognize entry conditions are met for AOP-019, Malfunction of RCS Pressure Control and perform the immediate actions. This will require RNO actions to manually control the Pressurizer spray valves and control RCS pressure prior to reaching the auto Reactor protection actuation setpoint of 2385 psig.

HNP 2009B NRC Exam Form ES-301-2 November 30.2009 - FINAL Page 4 of 7

2009B NRC Control Room/In-Plant JPM Summary Operating Test No.: 05000400/2009302 JPM f - Loss of All AC Power (JPM-CR-059) Alternate Path KIA APE 056 AK 3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power (CFR 41.5,41.10/45.6/45.13) RO 4.4 SRO 4.7 With the plant at 100% power the applicant will be directed to maintain current plant conditions. Subsequently the Reactor will trip on a loss of all AC power. The applicant will be expected to perform the immediate actions associated with EOP-EPP-001, Loss of AC Power to 1A-SA and 1B-SB Buses. During the performance of this emergency procedure they will have to manipulate components that have failed to go to their expected position. They will also have to increase AFW flow to meet the minimum required flow rate by adjusting the TDAFW pump speed control to obtain flow. All SG levels will be lower than required and flow will have to continue until adequate levels are being established.

JPM g - Startup a Reactor Coolant Pump following Maintenance (JPM-CR-005)

Modified and Alternate Path KIA 003 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP (CFR: 41.5/43.5/45.3/45/13) RO 3.7 SRO 3.9 A plant startup will be in progress with the 'A' and 'B' RCPs in operation. Maintenance has been completed on the 'C' RCP and the applicant will be directed to start the 'C' RCP in accordance with OP-100, Reactor Coolant System. Soon after the RCP is started the RCP oil level alarm will come in and bearing temperatures will be increasing as indicated on ERFIS and OSI PI. The applicant will be expected to determine that entry conditions are met for AOP-018, Reactor Coolant Pumps Abnormal Conditions and enter the AOP. As bearing temperatures continue to rise, the applicant is expected to secure the 'C' Rep lAW AOP-018 when the trip limits are exceeded.

JPM h - Place an Excore NI Channel Out Of Service at Power (JPM CR-019)

KIA 015 A4.03 Ability to manually operate and/or monitor in the control room: Trip bypasses (CFR: 41.7 / 45.5 to 45.8) RO 3.8 SRO 3.9 Prior to taking watch, with the plant operating at 100% power steady state conditions, Nuclear Instrument 44 has failed low. The CRS has directed the applicant to remove NI-44 from service lAW OWP-RP-26, Reactor Protection. This will require placing rod control to manual. The applicant will then remove the detector from service at the detector current comparator drawer, the miscellaneous control and indication panel, and the comparator and rate drawer. They will then contact I&C to lift leads from the circuit.

They will then check the bistable status panels for proper responses. The applicant will also have to log onto the ERFIS computer and remove the channel from scan.

HNP 2009B NRC Exam Form ES-301-2 November 30,2009 - FINAL Page 5 of 7

2009B NRC Control Room/In-Plant JPM Summary Operating Test No.: 05000400/2009302 JPM i-Restore Power to an Emergency Bus (JPM IP-238) New KIA 068 AA 1.10 Ability to operate and I or monitor the following as they apply to the Control Room Evacuation: Power distribution: ac and dc (CFR 41.7145.5145.6) RO 3.71 SRO 3.9 Following a Main Control Room Evacuation due to a fire, the Emergency Bus 'A' is not powered. The applicant will be directed to start and load the 'A' Emergency Diesel locally lAW OP-155, Diesel Generator Emergency Power System sections 8.13 and 8.14.

JPM i-Transfer Control to the ACP (JPM-IP-050)

KIA 068 AA 1.21 Ability to operate and I or monitor the following as they apply to the Control Room Evacuation: Transfer of controls from control room to shutdown panel or local control (CFR 41.7145.5145.6) RO 3.91 SRO 4.1 With the plant in Hot Standby at 557°F, a fire has started in the Main Control Room, and the Shift Manager has directed an evacuation of the Main Control Room. Per AOP-004, Remote Shutdown, the Reactor has been tripped and the operators are relocating to the ACP. The applicant will be' directed by the CRS to perform a transfer of one train of controls to the ACP.

JPM k - Torque Shut the VCT Outlet Valves (JPM IP-212) RCA KIA 004 A 1.06 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: VeT level (CFR: 41.5/45.5) RO 3.0 SRO 3.2 NOTE: This JPM will be performed in the RCA.

With the plant operating at 100% steady state conditions an instrument air leak causes IA pressure to decrease. The crew has entered AOP-017, Loss of Instrument Air and air pressure continues to decrease. A Reactor Trip was required based on the continued decreasing IA pressure. The operators performed the actions of Path-1 and have transitioned to EPP-004, Reactor Trip Response while continuing the implementation of AOP-017. The RO has just identified that VCT level cannot be maintained> 5%. The RO will direct the applicant to perform the local operator actions of AOP-017 Section 3.2 step 2 RNO 2.c to realign RCP Seal return to the Charging Pump suctions and step 3 RNO to locally torque shut the VCT outlet valves.

HNP 2009B NRC Exam Form ES-301-2 November 30, 2009 - FINAL Page 6 of 7

( ES-301 Operating Test Quality Checklist Form ES-301-3 I HAltll.15 Facility: HAIl.Il15 Nuu.e(l. PLIW'r Date of Examination: II ~ 3D-O q OperatinQ Test Number:

Operating

..,.~~.,.~ OSooO'-loo/2.~O~ 302-Initials

1. General Criteria a b* C#

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

samplinQ ~ .b 11

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

during ~ 011

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

~

d. Overlap with the written examination and between different parts of the operating test is within acceptable limits. ~ f!:> )

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

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a.

applicants at the designated license level.

2. Walk-Through Criteria Each JPM includes the following, as applicable:

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• • 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:

i

- 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

!)

b.

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 k £;, J~~

on those forms and Form ES-201-2.

3. Simulator Criteria - - rifI rrf\

The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached. ~ .8 I~

[~

~""' Name I Sig",'"" Date

a. Author ~/.A/2.cltle LuCJi:.,/ /(7 ~/S--p9 b.

c.

Facility Reviewer(*)

NRC Chief Examiner (#) G~\)

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NOTE:

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

n

1. Independent NRC reviewer i1iitial items in Column "c ; chief examiner concurrence re-'Luired.

required.

ES-301, Page 24 of 27

c ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Harris Date of Exam: 11-30-09 Scenario Numbers: 1 / 2 /3 Operating Test No.: 05000400/2009302 QUALITATIVE ATTRIBUTES Initials a b* C#

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~ J3

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. IA 1.-1

2. The scenarios consist mostly of related events. ~ 12

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3. Each event description consists of

• the point in the scenario when it is to be initiated

• the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable) ~

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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.

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5. The events are valid with regard to physics and thermodynamics. ~ J?;, ,

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6. Sequencing and timing of events is reasonable, and allows the examination team to obtain X .e>

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complete evaluation results commensurate with the scenario objectives. ~

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

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

Cues are given. )( 13 I~  ! ~

8. The simulator modeling is not altered. ~ .b )~

( 9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated ~

X to ensure that functional fidelity is maintained while running the planned scenarios. B

10. Every operator will be evaluated using at least one new or significantly modified scenario.

All other scenarios have been altered in accordance with Section 0.5 of ES-301.  % b Itt* }

11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the fomi along with the simulator scenarios). ,:< D l<d X .d V

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios). X f; 11

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

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1-<1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes - - --

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(}) ):

1. Total malfunctions (5-8) / 7 / 9 X 2> J

2. Malfunctions after EOP entry (1-2) / 2 / 4 ~ .Q, J J

3. Abnormal events (2-4) / .3~ / 4 :K 8 V

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4. Major transients (1-2) / 2 / 1 .:< 8£3:> ~ ~)

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

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6. EOP contingencies requiring substantive actions (0-2) / 1 / 1 :x

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7. Critical tasks (2-3) ~~ ~'2/

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( ES-301 SPARE Simulator Scenario Quality Checklist Form ES-301-4

~acility:

Facility: Harris Date of Exam: 11-30-09 Scenario Numbers: 4 (Spare) Operating Test No.: 05000400/2009302 QUALITATIVE ATIRIBUTES 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. 5K f) IJJ 5t

2. The scenarios consist mostly of related events. J< p:;) PJ ~

3. Each event description consists of

-- the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event

-. the symptoms/cues that will be visible to the crew X

4.

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

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Ill without a credible preceding incident such as a seismic event. ~ {};; IJ~ V

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6.

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.

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

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

Cues are given.  ;< b ~j II The simulator modeling is not altered.  ;)(

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( 8.

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator 10.

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.

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All other scenarios have been altered in accordance with Section 0.5 of ES-301.  :< JbfL:,

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11. . All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios). ~ h Ij I~4~ ~

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

13. The level of difficulty is appropriate to support licensing decisions for each crew position. j( .b Ii,;~

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

1. Total malfunctions (5-8) 7 ~ JiJ Jr ~ It /Iy

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

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3. Abnormal events (2-4) 4 ;y

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4. Major transients (1-2) 1 !t fft b Ii~ /I

5. EOPs entered/requiring substantive actions (1-2) p-Z ptZ ~ h iJj l

-g£ EOP contingencies requiring substantive actions (0-2) "}2:1 1f2:1 gz b  :;.;.

6. 'i.'li

7. Critical tasks (2-3) 3 ~!k ~ )i- f

SCENARIO'S 2 - 3 (Selected by NRC)

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: 11-30-09 Operating Test No.: 05000400/2009302 A E Scenarios P V 2 3 4 T M P E 0 I L N CREW POSITION CREW POSITION CREW POSITION T N I T A B S B I S A B S A A M

C R T 0 R T 0 R T 0 L U A T 0 C P 0 C P 0 C P M(*)

N Y R I U T P E

RO -1 RX 1 0 1 1 1 0 SRO-I NOR IIC 0

213 1

2/4m8 1

7 1

4 1

4 1

2 D

SRO-U 10 MAJ 5/7 6 3 2 2 1 D TS 0 0 0 0 2 2 RO-2 RX 0 1 1 1 1 0 SRO-I NOR IIC 1

4/5/6/8 0

3/5/9 1

7 1

4 1

4 1

2 D

SRO-U MAJ 5/7 6 3 2 2 1 D TS 0 0 0 0 2 2 RO-3 RX 1 0 1 1 1 0 SRO-I NOR IIC 0

213 1

2I4m8 1

7 4 1 1 4

1 2

DSRO-U 10 MAJ 5/7 6 3 2 2 1 D TS 0 0 0 0 2 2 RO-4 RX 0 1 1 1 1 0 SRO-I NOR IIC 1

4/5/6/8 0

3/5/9 1

7 1

4 1

4 1

2 DSRO-U MAJ 5/7 6 3 2 2 1 D TS 0 0 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 serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

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

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

November 30, 2009 - Final Page lof3

SCENARIO'S 2 - 3 (Selected by NRC)

ES-301 Transient and Event Checklist Form ES-301-5 Facility:. Shearon Harris Date of Exam: 11-30-09 Operating Test No.: 05000400/2009302 A E Scenarios P V 2 3 4 T M P E 0 I L N CREW POSITION CREW POSITION CREW POSITION T N I T I S A B S A B S A B A M

C R T 0 R T 0 R T 0 L U A T 0 c p 0 c p 0 c P M(*)

N Y R I U T P E

RO-5 RX 1 0 1 1 1 0 SRO-I NOR I/C 0

2/3 1

2/4m8 1

7 1

4 1

4 1

2 D

SRO-U 10 MAJ 5/7 6 3 2 2 1 D TS 0 0 0 0 2 2 RX 1 1 2 1 1 0 RO NOR 1 1 1 1 D

SRO-I 2 1 I/C 2/3/4/5 2/3/4/5 14 4 4 2 D

SRO-U1 6/8 7/8/9 10

• MAJ TS 5/7 2/4 6

3/4/5 3

5 2

0 2

2 1

2 RO RX 1 1 2 1 1 0 D

SRO-I NOR 1 1 2 1 1 1 D I/C 2/3/4/5 6/8 2/3/4/5 7/8/9 14 4 4 2 SRO-U2 10

• MAJ TS 5/7 2/4 6

3/4/5 3

5 2

0 2

2 1

2 RO RX 1 1 2 1 1 0 D

SRO-11 NOR 1 0 1 1 1 1 SRO-U I/C MAJ 2/3/4/5 6/8 5/7 3/5/9 6

9 3

4 2

4 2

2 1

D TS 2/4 0 2 0 2 2 November 30, 2009 - Final Page 2 of3

SPARE SCENARIO #4 Attributes ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: 11-30-09 Operating Test No.: 05000400/2009302 A E Scenarios P V 2 3 4 T M P E 0 I L N CREW POSITION CREW POSITION CREW POSITION T N I T I S A B S A B S A B A M

C R T 0 R T 0 R T 0 L U A T 0 C P 0 C P 0 C P M(*)

N Y R I U T P E

RO RX 1/5 1/5 0 1 1 0 D

0SRO-I NOR 1 0 1 1 1 1 D

0SRO-U I/C 2/3/4/5 7/8 3/4fi 2/518 4 4 2 D

0 MAJ 6 6 6 2 2 1 T8 2/3/4 0 0 0 2 2 RO RX 1 1 0 D

0SRO-I NOR 1 1 1 D

0SRO-U2 I/C 4 4 2 MAJ 2 2 1 In 10 TS 0 2 2 RO RX 1 1 0 D

0SRO-11 NOR 1 1 1 D0SRO-U I/C 4 4 2 MAJ 2 2 1 10 TS 0 2 2 November 30, 2009 - Final Page 3 of3

ES-301 Competencies Checklist Form ES-301-6 Facility: Harris Date of Examination: 11-30-09 Operating Test No.: 05000400/2009302 APPLICANTS RO RO (BOP) SRO-U SRO-I SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Competencies I nterpretiDiagnose 2/3 3/5 3/4 4/5 2/4 2/5 2/3 2/3/4/5 2/3 2/3 3/5 Events 7 6/9 6/7 6/7 6/7 6/8 4/5 6/7/8/9 4/5 4/5 6/9 and Conditions 8 8 6/7 10 6/7 6/7 10 8 8 8 Comply With and 112 113 113 114 112 112 112 1/2/3/4 112 112 113 Use Procedures (1) 3/5 5/6 4/6 5/6 4/6 5/6 3/4 5/6/7/8 3/4 3/4 5/6 7 9 7 7/8 7/8 8 5/6 9/10 5/6 5/6 9 10 7/8 7/8 7/8 Operate Control 112 113 113 114 112 112 113 Boards (2) 3/5 5/6 4/6 5/6 4/6 5/6 5/6 7 9 7 7/8 7/8 8 9 10 Communicate 112 113 113 114 112 112 112 1/2/3/4 112 112 113 and Interact 3/5 5/6 4/6 5/6 4/6 5/6 3/4 5/6/7/8 3/4 3/4 5/6 7 9 7 7/8 7/8 8 5/6 9/10 5/6 5/6 9 10 7/8 7/8 7/8 Demonstrate 112 112/3/4 1/2 112 Supervisory Ability 3/4 5/6/7/8 3/4 3/4 (3) 5/6 9/10 5/6 5/6 7/8 7/8 7/8 Comply With and 2/4 3/4/5 2/3 2/4 Use Tech. Specs. 4 1(3)

Notes:

(1 ) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

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

NOTE: Scenarios 1,2,3 and 4 were originally submitted to support nine candidates. Scenario 1 was eliminated following removal of one candidate from the program. Scenarios 2 and 3 were selected for the examination, with Scenario 4 to be utilized as a spare scenario. SRO-I information assumes they will be the SRO in Scenario 2 and RO in Scenario 3.

November 30, 2009 - Final

ES-401 1 Rev. 9 PWR Examination Outline Form ES-401-2 Facility: HARRIS Date of Exam: 2010 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

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

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

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

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

1. Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

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

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

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

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

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.

S. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; 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. 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. LimitSRO selections to KIAs that are linked to 10 CFR 55.43.

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 007EK3.01 Reactor Trip - Stabilization - Recovery 4 4.6 DD~DDDDDDDD Actions contained in EOP for reactor trip 11 008AK1.01 Pressurizer Vapor Space Accident 1 3 3.2 3.7 ~DDDDDDDDDD Thermodynamics and flow characteristics of open or leak- ing valves 009EK1.02 Small Break LOCA 1 3 3.5 4.2 ~ D D D D D* DDDDD

~DDDD DDDDD Use of steam tables 011 EG2.4.4 Large Break LOCA 1 3 4.5 4.7 DDDDDDDDDD~ Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

015AK1.02 RCP Malfunctions 1 4 3.7 4.1 ~DDDDDDDDDD Consequences of an RCPS failure 022AA1.03 Loss of Rx Coolant Makeup 1 2 3.2 3.2 DDDDDD~DDDD PZR level trend 025AK2.03 Loss of RHR System 14 2.7 2.7 D~DDDDDDDDD Service water or closed cooling water pumps 027AK3.02 Pressurizer Pressure Control System 2.9 3 DD~DDDDDDDD Verification of alternate transmitter and/or plant computer Malfunction 1 3 prior to shifting flow chart transmitters 029EA2.02 ATWS/1 4.2 4.2 4.4 4.4 D DDDDDD~ DDD DDDDDDD~DDD Reactor trip alarm 038EG2.4.4 Steam Gen. Tube Rupture 1 3 4.5 4.5 4.7 4.7 D DDDDDDDDD~

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

040AA2.04 Steam Line Rupture - Excessive Heat 4.5 4.7 D DDDDDD~ DDD DDDDDDD~DDD Conditions requiring ESFAS initiation Transfer 1 4 Page 1 of 2 5/21/2009 12:29 PM

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 056AA1.01 Loss of Off-site Power / 6 4 3.8 DDDDDD~DDDD Power relief controllers to maintain no-load T-ave 057AG2.2.38 Loss of Vital AC Inst. Bus 16 3.6 4.5 D D D D D D D D D D ~ Knowledge of conditions and limitations in the facility license.

058AA 1.01 Loss of DC Power 1 6 3.4 3.5 D D D D D D ~ D D D D Cross-tie of the affected dc bus with the aJternate supply 062AA2.03 Loss of Nuclear Svc Water 14 2.6 2.9 D D D D D D D ~ D D D The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 065AK3.03 Loss of Instrument Air 18 2.9 3.4 D D ~ D D D D D D D D Knowing effects on plant operation of isolating certain equipment from instrument air WE04EK2.1 LOCA Outside Containment / 3 3.5 3.9 D ~ D D D D D D D D D Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE05EK2.2 Inadequate Heat Transfer - Loss of 3.9 4.2 D ~ D D D D D D D D D Facility's heat removal systems, including primary Secondary Heat Sink / 4 coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

Page 2 of 2 5/21/2009 12:29 PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO 001AA2.04 Continuous Rod Withdrawal / 1 4.2 4.3 DD D DD DD DD DD DD D ~ DD D DD D Reactor power and its trend 003AK3.0S Dropped Control Rod / 1 3.4 3.4 4.1 4.1 D D ~ D D D D D D D D DD~DDDDDDDD ech-Spec limits for reduction of load to SO% power if Tech-Spec flux cannot be brought back within specified target band 00SAG2.1.20 Inoperable/Stuck Control Rod / 1 4.6 4.6 4.6 4.6 D D D D D D D D D D ~

DDDDDDDDDD~ Ability to execute procedure steps.

024AK1.04 Emergency Boration /1 2.8 2.8 3.6 3.6 ~ D D D D D D D D D D

~DDDDDDDDDD Low temperature limits for boron concentration 076AG2.1.2S High Reactor Coolant Activity / 9 3.9 3.9 4.2 4.2 D D D D D D D D D D ~

DDDDDDDDDD~ Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

WE03EK1.1 LOCA Cooldown - Depress. /4 3.4 3.4 4.0 4.0 ~ D D D D D D D D D D

~DDDDDDDDDD Components, capacity, and function of emergency systems.

WE06EK3.3 Degraded Core Cooling / 4 4.0 4.0 3.9 3.9 D D ~ D D D D D D D D DD~DDDDDDDD Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

WE1SEK2.1 Containment Flooding / S 2.8 2.8 2.9 2.9 D ~ D D D D D D D D D D~DDDDDDDDD Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE16EA 1.1 High Containment Radiation / 9 3.1 3.1 3.2 3.2 D D D D D D ~ D D D D DDDDDD~DDDD Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Page 1 of 1 S/21/2009 12:29 PM

ES-401, REV 9 T2G1 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 003K2.02 Reactor Coolant Pump 2.5 2.6 D~DDDDDD DD CCW pumps 004A1.11 Chemical and Volume Control 3.0 3.0 DDDDDD~DDDD Letdown and charging flows 004K2.05 Chemical and Volume Control 2.7 2.9 D~DDDDDDDDD MOVs 005A1.02 Residual Heat Removal 3.3 3.4 DDDDDD~DDDD RHR flow rate 005K5.03 Residual Heat Removal 2.9 3.1 DDDD~DDDDDD Reactivity effects of RHR fill water 006K6.13 Emergency Core Cooling 2.8 3.1 DDDDD~DDDDD Pumps 007A1.03 Pressurizer Relief/Quench Tank 2.6 2.7 DDDDDD~DDDD Monitoring quench tank temperature 008K4.02 Component Cooling Water 2.9 2.7 DDD~DDDDDDD Operation of the surge tank, including the associated valves and controls 010A3.01 Pressurizer Pressure Control 3.0 3.2 DDDDDDDD~DD PRT temperature and pressure during PORV testing 010K3.03 Pressurizer Pressure Control 4.0 4.2 DD~DDDDDDDD ESFAS 012A2.04 Reactor Protection 3.1 3.2 DDDDDDD~DDD Erratic power supply operation Page 1 of 3 5/21/2009 12:29 PM

ES-401, REV 9 T2G1 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 013K2.01 Engineered Safety Features Actuation 3.6 3.8 0 ~ 0 0 0 0 0 0 0 0 0 ESFAS/safeguards equipment control 013K6.01 Engineered Safety Features Actuation 2.7 3.1 0 0 0 0 0 ~ 0 0 0 0 0 Sensors and detectors 022A3.01 Containment Cooling 4.1 4.3 0 0 0 0 0 0 0 0 ~ 0 0 Initia tion of safeguards mode of operation 026K3.01 Containment Spray 3.9 4.1 0 0 ~ 0 0 0 0 0 0 0 0 CCS 039A4.04 Main and Reheat Steam 3.8 3.9 0 0 0 0 0 0 0 0 0 ~ 0 Emergency feed water pump turbines 059A3.02 Main Feedwater 2.9 3.1 0 0 0 0 0 0 0 0 ~ 0 0 Programmed levels of the S/G 059A4.12 Main Feedwater 3.4 3.5 0 0 0 0 0 0 0 0 0 ~ 0 Initiation of automatic feedwater isolation 061A2.03 Auxiliary/Emergency Feedwater 3.1 3.4 0 0 0 0 0 0 0 ~ 0 0 0 Loss of dc power 062A2.03 AC Electrical Distribution 2.9 3.4 0 0 0 0 0 0 0 ~ 0 0 0 Consequences of improper sequencing when transferring to or from an inverter 062G2.2.36 AC Electrical Distribution 3.1 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 063G2.2.22 DC Electrical Distribution 4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of limiting conditions for operations and safety limits.

Page 2 of 3 5/21/2009 12:29 PM

ES-401, REV 9 T2G1 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 063K1.03 DC Electrical Distribution 2.9 3.5 ~ D D D D D D D D D D Battery charger and battery 064K6.08 Emergency Diesel Generator 3.2 3.3 D D D D D ~ D D D D D Fuel oil storage tanks 073K5.01 Process Radiation Monitoring 2.5 3.0 D D D D ~ D D D D D D Radiation theory, including sources, types, units and effects 076K1.01 Service Water 3.4 3.3 ~ D D D D D D D D D D CCW system 078G2.4.47 Instrument Air 4.2 4.2 D D D D D D D D D D ~ Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

103A4.01 Containment 3.2 3.3 D D D D D D D D D ~ D Flow control, pressure control and temperature control valves, including pneumatic valve controller Page 3 of 3 5/21/2009 12:29 PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO 001K2.0S Control Rod Drive 3.1 3.S D~DDDDDDDDD MIG sets 011KS.09 Pressurizer Level Control 2.6 2.7 DDDD~DDDDDD Reason for manually controlling PZR level 014G2.4.21 Rod Position Indication 4.0 4.6 DDDDDDDDDD~ Knowledge of the parameters and logic used to assess the status of safety functions 01SA1.03 Nuclear Instrumentation 3.7 3.7 DDDDDD~DDDD NIS power indication 016A4.01 Non-nuclear Instrumentation 2.9 2.8 DDDDDDDDD~D NNI channel select controls 017A3.02 In-core Temperature Monitor 3.4 3.1 DDDDDDDD~DD Measurement of in-core thermocouple temperatures at panel outside control room 028A2.02 Hydrogen Recombiner and Purge 3.S 3.9 DDDDDDD~DDD LOCA condition and related concern over hydrogen Control 03SK6.01 Steam Generator 3.2 3.6 DDDDD~DDDDD MSIVs 041K4.09 Steam Dumpffurbine Bypass Control 3.0 3.3 DDD~DDDDDDD Relationship of lOW/low T-ave. setpoint in SDS to primary cooldown OS6K1.03 Condensate 2.6 2.6 ~DDDDDDDDDD MFW Page 1 of 1 S/21/2009 12:29 PM

ES-401, REV 9 T3 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 G2.1.20 Conduct of operations 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to execute procedure steps.

G2.1.38 Conduct of operations 3.7 3.8 DOD 0 0 0 0 0 0 0 ~ Knowledge of the stations requirements for verbal communication when implamenting procedures G2.2.13 Equipment Control 4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of tagging and clearance procedures.

G2.2.5 Equipment Control 2.2 3.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process for making design or operating changes to the facility G2.3.11 Radiation Control 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to control radiation releases.

G2.3.5 Radiation Control 2.9 2.9 0 0 0 0 0 0 0 0 0 0 ~ Ability to use radiation monitoring systems G2.3.6 Radiation Control 2.0 3.8 0 0 0 0 0 0 0 0 0 0 ~ Ability to aprove release permits G2.4.2 Emergency Procedures/Plans 4.5 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

G2.4.38 Emergency Procedures/Plans 2.4 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.

G2.4.4 Emergency Procedures/Plans 4.5 4.7 0 0 0 0 0 0 0 0 0 0 ~ Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 5/21/2009 12:29 PM

ES-401, REV 9 SRO T1 G1 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 007EG2.4.45 Reactor Trip - Stabilization - Recovery 4.1 4.3 DDDDDDDDDD~ Ability to prioritize and interpret the significance of each 11 annunciator or alarm.

009EA2.11 Small Break LOCA 1 3 3.8 4.1 DDDDDDD~DDD Containment temperature, pressure, and humidity 040AA2.01 Steam Line Rupture - Excessive Heat 4.2 4.7 DDDDDDD~DDD Occurrence and location of a steam line rupture from Transfer 1 4 pressure and flow indications 054AG2.2.40 Loss of Main Feedwater 1 4 3.4 4.7 DDDDDDDDDD~ Ability to apply technical speCifications for a system.

055EA2.02 Station Blackout 1 6 4.4 4.6 DDDDDDD~DDD RCS core cooling through natural circulation cooling to S/G cooling 057AG2.2.4 Loss of Vital AC Inst. Bus 1 6 3.6 3.6 DDDDDDDDDD~ (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

Page 1 of 1 5/21/2009 12:29 PM

ES-401, REV 9 SRO T1G2 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 033AG2.4.30 Loss of Intermediate Range NI /7 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

061M2.02 ARM System Alarms / 7 2.9 3.2 0 0 0 0 0 0 0 ~ 0 0 0 Normal radiation intensity for each ARM system channel WE10EA2.2 Natural eirc. With Seam Void! 4 3.4 3.9 0 0 0 0 0 0 0 ~ 0 0 0 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Page 1 of 1 5/21/2009 12:29 PM

ES-401, REV 9 SRO T2G1 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 003G2.4.41 Reactor Coolant Pump 2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the emergency action level thresholds and classifications.

005G2.4.34 Residual Heat Removal 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 008A2.05 Component Cooling Water 3.3 3.5 0 0 0 0 0 0 0 ~ 0 0 0 Effect of loss of instrument and control air on the position of the CCW valves that are air operated 059A2.04 Main Feedwater 2.9 3.4 0 0 0 0 0 0 0 ~ 0 0 0 Feeding a dry S/G 064G2.2.37 Emergency Diesel Generator 3.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to determine operability and/or availability of safety related equipment Page 1 of 1 5/21/2009 12:29 PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

AO SAO 033A2.01 Spent Fuel Pool Cooling 3.0 3.5 D D D D D D D ~ D D D Inadequate SDM 068G2.1.7 Liquid Aadwaste 4.4 4.7 D D D D D D D D D D ~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

071 G2.1.31 Waste Gas Disposal 4.6 4.3 D D D D D D D D D D ~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Page 1 of 1 5/21/2009 12:29 PM

ES-401, REV 9 SRO T3 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 G2.1.28 Conduct of operations 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the purpose and function of major system components and controls.

G2.1.44 Conduct of operations 3.9 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of RO duties in the control room during fuel handling.

G2.2.20 Equipment Control 2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process for managing troubleshooting activities.

G2.2.35 Equipment Control 3.6 4.5 0 0 0 0 0 0 0 0 0 0 ~ Ability to determine Technical Specification Mode of Operation G2.3.4 Radiation Control 3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.4.16 Emergency Procedures/Plans 3.5 4.4 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

G2.4.20 Emergency Procedures/Plans 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of operational implications of EOP warnings, cautions and notes.

Page 1 of 1 5/21/2009 12:29 PM

ES-401 Record of Rejected KlAs Form ES-401-4 T1IG1 057AG2.2.4 KJ A is designated for a multi unit plant.

SRO Exam Replaced with KJA 057AG2.2.38, provided by Gerald Laska via telecom with Bailey/Carney on 7/21109 Tl/G1 054 AG2.2.40 Re~l~ced w,th KJ A054AG2.1.20, provided by Gerald Laska via SROExam telebbill with Archie Lucky on 1119/09 Q#4 j I' ~ , I T2G1 008 A2.05 Replaced with KJA 008A4.1 0, provided by Gerald Laska via SRO Exam telecom with Archie Lucky on 1119/09 Q#12 T1G2 076AG2.1.25 Replaced with KJA 076AG2.1.28, provided by Gerald Laska via ROExam telecom with Archie Lucky on 1119/09 Q#23 2009-302 HNP NRC Written Exam Outline - RO and SRO

ES-401 Record of Rejected KlAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KIA T1IG1 027AK3.02 HNP does not have the ability to shift flow chart transmitters for the Pressurizer Pressure Control system (only level control).

Replaced with KIA 027AK3.04, provided by Gerald Laska via telecom with Bailey/Carney on 7/21/09 T1IG! OS8 AAl.01 HNP does not have crosstie to alternate DC source ability. Also, the DC busses do not have breakers between the batteries and the busses.

Replaced with KIA OS8AAl.03, provided by Gerald Laska via telecom with Bailey/Carney on 7/21109 TlIG2 ElS EK2.l Containment flooding does not challenge safety components at Harris.

RO exam Q#26 Replaced with KIA E02 EK2.1, provided by Gerry Laska via telecom to Carney on 1119/09.

T2/G1 007Al.03 KI:t(:9.v~r~ap r ith K(A 010A3.01.

Replaced with KIA 007Al.01, provided by Gerald Laska via telecom with Bailey/Carney on 7/21/09 T2/G1 OS9A3.02 HNP does not vary SG program level.

Replaced with KIA OS9A3.06, provided by Gerald Laska via Bail~/Carney on 7/21109 telecom with Bailey/Carney T3 G2.2.S RO/SRO KIA values are < 2.S Replaced with KIA G2.2.3S, provided by Gerald Laska via telecom with Bailey/Carney on 7/21/09 T3 G2.3.6 RO/SRO KIA values are < 2.S Replaced with KIA G2.3.7, provided by Gerald Laska via telecom with Carney on 7122/09 T3 G2.4.38 RO/SRO KIA values are < 2.S RO exam Replaced with KIA G2.4.39, provided by Gerald Laska via telecom Q#74 with Bailey/Carney on 7/21109 Replaced KIA G2.4.39 with KIA G2.4.23 on 11109/09 following week, of eXaJ,TI review via telecom with Carney. G2.4.39 deals with RQ:~sjsponsibilities during E-Plan. Harris does not have unique res'p6nsibilities for ROs during implementation of the E-Plan.

2009-302 HNP NRC Written Exam Outline - RO and SRO

ES-401 Written Examination Quality Checklist Form ES-401-6 I~r Facility: Date of Exam: 12 ~/'" - O'fExam Level: RO[2g SRO~

Initial Item Description a b* c#

1. Questions and answers are technically accurate and applicable to the facility. kY 'llf I~

1. i?/

1. jjf l~

2. a.

b.

NRC KJAs are referenced for all questions.

Facility learning objectives are referenced as available. k --?!( 1ft,P- t, O--

~

3. SRO questions are appropriate In accordance with Section D.2.d of ES-401 X ~ j~ ~

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

5. Question duplication from the license $creeningfaudit screeningfaudit 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

.....tfhe licensee certifies that there is no duplication; or

_ other (explain)

~ 14 4 t I

Bank use meets limits (no more than 75 percent tj $

6. Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only 29 f 3 29/3 6/1 40/21 X 1/

question dlstribution(s}

dlstribution(s) at right.

Ji Ii

7. Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehensionl comprehension! analysis level; the SRO exam may exceed 60 percent if the randomly selected KJAs support the higher cognitive levels; enter 41.3/36 41.3!36 58.7/64 .x -?If the actual RO I SRO question distributlon(s) at right. rYI

(\

8. Referencesfhandouts provided do not give away answers or aid In the elimination of distractors. k 4! IJf A~

9. Question content conforms with specific KiA statements in the previously approved )

examination outline and is appropriate for the tier to which they are assigned; deviations are justified. ~

'/ 411 'l~. 01

10. Question psychometric quality and format meet the guidelines in ES Appendix B. y 4i 141.~

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

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ES-401 Written Examination Quality Checklist Form ES-401-6 Ib Facility: Date of Exam: 12~/" - o'fExam Level: RO~ SRO,g[

SR Initial Item Description a b* c#

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NRC KlAs are referenced for all questions.

Facility learning objectives are referenced as available. Jr W ~

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

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

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

_ the audit exam was systematically and randomly developed; or j;(' 14

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_ the audit exam was completed before the license exam was started; or

_ the examinations were developed independently; or

~e licensee certifies that there is no duplication; or

_ other (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only 29/3 6/1 40/21 X '11 question distribution(s) at right.

7. Between 50 and 60 percent of the questions on the RO Memory CIA X 'JJf exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly 41.3/36 58.7/64 selected KlAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right.

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

9. Question content conforms with specific KIA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified. ~ 411

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

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ES-401, Rev. 9 Harris 2009-302 SRO Written Examination Review Worksheet Final Form ES-401-9

1. ~

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

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(FIH) (1-5) Stem Cues T/F Stem Icuesl Focus T/F I Credo cred'l Partial Dist.

Job- Minutia Partial I JOb-1 Link Minutia I #/ 8ack- Q=

1. / I Back-I units ward KIA Q= I SAOSAO Only IutE!

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S Explanation Instructions

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

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

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

3. Check the appropriate box if a psychometric flaw is identified:

• The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

• The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

• The answer choices are a collection of unrelated true/false statements.

• The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

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

1

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).

1/76 H 2 X X  ? E 007G2.4.45 Question appears to match KIA.

Borderline SRO (priority). What is the purpose of the S last bullet? Is this required? If an applicant assumes that greater than five minutes has elapsed since the loss of the bus, The CCW pump would be addressed first.

NEW

• 11/6/09 Gerry reviewed proposed changes (below) and accepted question as SA T.

• The last bullet is intended to address which procedures are in progress.

• In AOP-025, addressing the charging pump it. i~

prioritized within the procedure (step 4). CC~

is addressed after the charging pump in step

5. We added 3 minutes (time restrictions) to the question stem to address the 5 minute concern. Maintained the last bullet, otherwise the question portion of the stem becomes extremely long due to the title of AOP-025 being moved down into this area.

Allowed question based on prioritization within the procedure. (Still borderline) but SAT 12108/2009

~

2177 H 2 X X E 009EA2.11 Question does not meet KIA. Not sure it is SRO Only as written, but it is close. Both of the S Pressurizer level values listed in the responses are adverse numbers, and the question is attempting to meet the KIA by the applicant observing that containment pressure is greater than the value requiring adverse numbers to be used in the procedure. How are we meeting the KIA? The pressure in the step is moot. If a cooldown is in progress (depressurization step is after the step to commence a cooldown, why is pressurizer level already rising?

NEW

• 11/6/09 Gerry reviewed proposed changes (below) and accepted question as SA T.

• KA is met by having applicant interpret Containment pressure in order to make procedure decisions. Requires detailed knowledge the steps contained in EPP-009.

The applicant must know the steps in EPP-009 and that the pressurizer is refilled to greater than 40% to provide margin to SI reinitiation.

• 30% is the adverse number for SI initiation criteria, however, it is also a normal value tha EPP-009 would require securing depressurization while refilling the pressurize pressurizel if adverse conditions were NOT identified.

• With a cooldown in progress, it is possible to have a depressurization occur solely based on the cooldown. Cooldown is a result of steps taken in EP-009 as well as cold RWST injection. Dependent on the size of the break, conditions would be established where SI

flow exceeds break flow and the pressurizer would start to fill. Utilizing the PORVs to PORVs allows for a more rapid depressurization in order to allow termination of SI earlier.

• Changed stem to read "Minimum Pressurizer level required to secure" and change distracters A and D to 26% and Band D to 41%..

Accepted questions after changes. SAT 12108/2009

H 2 X X E 040AA2.01 Question appears to match KIA.

Appears to be SRO only. How can these conditions 3/78 S exist? If A is faulted, and all MSIV were open all S/G pressures would begin to fall. With the TDAFW pump supplied steam from the Band C S/Gs, and both connected it would also be very close in pressure to B S/G. I don't think that you can reach these conditions in the plant. If the leak was in the C S/G, why would I transition to EPP-14 and isolate the A S/G. An applicant could determine from distractor C, that C was not faulted simply because you state tc isolate the A S/G Please explain the thinking on this question.

NEW

• Question Enhancement made 11116109 AL

• Changed SG 'C' pressure to 535 pSig and lowering. It is plausible to have one SG pressure lag and perform as a heat sink.

• Changed C distracter to isolate the 'C'SG".

Transition criteria in EPP-015 to EPP-0014 would remain plausible since 1 SG is rising.

1214/09 Gerry accepted changes and approved SAT.

H 2 X S 054AG2.2.40 Question does not meet the KIA, but is a good try. Would you be in the ESFAS tech spec if 4n9 a MFRV was stuck and would not move? (This has happened in the industry). This could be another angle, or an ESF relay has been determined to be inoperable, etc. Otherwise I may have to change the KIA.

NEW

• KIA was rep/aced by Gerry Laska on 11/9/09

• New KIA is 054AG2. 1.20

• Rep/aced question with Bank question.

AL 11/18/09 1214/09 Gerry accepted changes and approved SAT.

2 H X U 055EA2.02 Question appears to match KIA.

Question appears to be SRO only. Distractors A and 5/80 E B do not appear to be plausible. With the conditions in the stem why would anyone even consider reflux cooling? Try changing some of the stem conditions, and have the applicant determine if natural circ cooling is in progress or not, and then have the procedure actions as written. (this can easily be fixed)

NEW

• Question Enhancement made 11118109 AL

• Revised question to have applicant evaluate whether or not natural circulation is in progress or not. Used Gerry's suggestion to ask where the RCS is depressurized to (180# - #230) and why we stop at this pressure (to prevent N2 from accumulator to RCS - blocking SG U-tubes thus stopping natural circulation). The question was also tied to actions directed by EPP-001.

1214/09 Many discussions on weather EOP Step basis is SRO only or Not. This is a gray area and chief examiner accepted changes and approved SAT.

3 F S 057AG2.2.38 Question appears to match KIA, and appears to be SRO only. SAT (had a discussion on 6/81 references and determined that a reference is not I needed on this question.

NEW

2 H S 033AG2.4.30 Question appears to match KIA, and appears to be SRO only. SAT 7/82 NEW 2 F X U 061AA2.02 Question appears to match KIA. Appears to be SRO only. Distractors C and D are not really 8/83 S plausible. Need to change this indication to something closer to the actual indications (do you have a radiation monitor that you use for RCS leak detection that displays CPM?

NEW

• 11/6/09 Gerry suggested enhancement to make question SA T: change the rad monitor to the Containment leak detection rad monitor 3502 readings. The rad monitor readouts will be different but Ger/}

Gerry said he is OK with this.

11117109AL

• Enhancement performed per direction:

Changed distractor C and D readings to the normal reading for RM-3502A, CNMT Leak Detection Rad Monitor. (4.8E-06 J.lCi/ml) 1214/09 Gerry accepted changes and approved SAT.

2 F X E WE10EA2.2 Question does not meet the KIA. If you covered up the initial conditions of the question and left 9/84 just the stem, it would not affect the question at all. The answer would be the same whether you were in EPP-006 or in a normal cooldown procedure.

NEW

• 11106109 Gerry suggested enhancement:

change to EPP-006 11116109AL

• Changed per suggested enhancement to EPP-006

• Based on feedback from week of 30NOV09, modified stem to eliminate subset issue utilizing MAXIMUM as part of discriminating question.

Changed both CSIPs to Two CSIPs and added maximum to the stem to resolve subset issue. Added lAW EEP-006. SAT 12108/2009

2 H X E 003G2.4.41 Question appears to match KIA. Question appears to be SRO only. Need to see the format of the 10/85 EALs. The way the answers are written the applicant need only look at EAL 2-1-2 and 2-1-3 etc. Is this what was intended? This could be cueing.

NEW

• 11116109 AL: Our flow chart requires the applicant to process the information from the beginning of the chart to each EAL classification. We do not just look at each EAL like some other stations EAL's may be designed.

• Plausibility quality is met for the other distracters to allow for adequate discrimination.

Upon further review, question really did not meet the KIA, because the classification was not based on a loss of the RCP system.

Stem was re-written to include a problem with the RCP seals (leakage) to place the plant in a condition that warranted a declaration. SAT 12108/2009.

2 H ? E 005G2.4.34 Question appears to match the KIA.

May not be SRO. Please explain why you think it is 11/86 S SRO. It seems like notes, cautions, precaution and limitations and systems knowledge could answer this question. These are all items ROs are expected to know. The ONL ONLY Y running CCW pump is a cue. Use damage to the B CCW pump.

NEW

• 11116109 AL: SRO Justification is that AOP-004 provides specific directions for establishing 'B' Train RHR cooling because this is the preferred train. ONL Y a note is provided on page 81 about allowance for ~ I RHR train to be used. It would not be expected for an RO to know this.

Additionally a failure has occurred the candidate must use knowledge of the procedure and P&Ls of OP-145 to determine the success path.

• Changed distracter A and C to 'a ' CCW pump 1214/09 Gerry accepted changes and approved SAT. Again there was much discussion concerning weather this was SRO only or not. Chief examiner allowed question due to the depth in the procedure of the note.

2 H X S 008A2.05 Question appears to meet the KJA.

Question is not SRO only. The question can be 12/87 answered using only systems knowledge and procedure entry requirements. Need to make question SRO only. Also an individual with good test taking skills could determine the malfunction from systems knowledge, and use the fact that the OP procedure is used twice to lower power and select the question for this reason (they know that power must be lowered.

NEW Could not write an SRO question on this topic.

• KIA was rep/aced by Gerry Laska on 11/9/09

• New KIA is 008A4.10 11118/09 AL - RESPONSE to NEW KIA

• Replaced question with modified 2009A NRC SRO question Question kind of matches KIA. Conditions that require operation of two coolers is the KIA, the licensee placed two coolers in operation, and the applicant had to answer based on two coolers being used. CE accepted borderline KIA match.

1214/09 Gerry accepted changes and approved SAT.

13/88 H 2 X U 059A2.04 Question appears to match K/A. Does not appear be SRO only. This was used on the 2008 Harris exam as an RO question.

The question is listed as a bank question, but no reference is made to it being on the 2008 NRC exam. We could change CETCs to slowly rising and the correct answer would be 0 and the question would be modified. (Unless you already have that version in your bank. Still need to discuss how to make SRO only. UNSAT BANK

• This question addresses application of conditions in an attachment that would be addressed by an SRO only.

• The question requires assessing plant conditions and then prescribing a procedure or section of a procedure to mitigate, recover, or with which to proceed thus making this question a SRO ONL Y question.

• Gerry will discuss with Malcolm when he get's back. If he is OK with this he will change to 'Enhance'.

• Modified condition in stem to indicate dry SG conditions, which changed the answer per Gerry's request.

After conferring with numerous examiners, asked licensee to replace question because it was not SRO only.

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x S 033A2.01 Question does not really match the KIA.

15/90 The second part of the KIA: based on those F 2 predictions, use procedures to correct, control or mitigate the consequences of th()se malfunctions or operations ... There are not any procedure actions required in the question. Furthermore the basis portion of the question is really not operationally valid. Increasing the boron concentration is the action that is needed to be performed. Need to work on this question. NEW

• This question was written on the premise that Tech Specs are plant documents which direct actions to be implemented if limitations are not met. Harris does not have operations procedures that would address a credible event that would result in a loss of SOM.

• If Tech Secs are not considered to be a procedure, recommend substituting a new KA.

• Gerry's comment is that the 'B' part of the KIA statement needs to match the SRO level. He believes we need to use procedures and doesn't think that the Tech Spec is a procedure. Talk to Gerry about this one more time.

Exam team had a long discussion on tech specs versus procedures, and the exam team accepted the tech spec requirements as procedure actions. 1214/09 Gerry accepted changes and approved SAT rating.

F 2 S 068G2.1.7 Question kind of matches K/A. Appears 16/91 to be SRO only. SAT NEW F 2 X S 071 G2.1.31 Question appears to match the K/A.

17/92 Question appears to have SRO only knowledge.

Distractors A and B are not plausible. Why would you operate N2 to PRT valves on a (assumption on my part) remote shutdown panel? I could not find this AEP in your lesson material. This is similar to a question that was asked on the 2009A exam, except is involved a RCDT valve. Verify 144 shut is all distractors this should be moved up above the individual distractors. Need to discuss other options.

NEW Made the following enhancements:

• AEP-1 (Aux Equipment Panel 1) is a safety related panel located in the MCR where normally operated components are controlled by the operators. This panel contains multiple Phase '~" components including the RCDT valve referenced above.

It also contains other TS related equipment.

• We agreed that "Verify 1RC-144 shut" can be moved to the stem and modified question.

11/06/09 Reviewed with Gerry and determined question to be SAT

H 2 X S G2.1.28 Question appears to match KIA. Does not 18/93 appear to be SRO only. I understand that he 140 of number is in the basis of technical specifications, but it is also the upper limit of temperature allowed in mode 6. Knowing the operational modes is considered RO knowledge.

• after the following discussion and enhancements:

• Question is measuring SRO knowledge of surveillance requirements. This question does not evaluate knowledge of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> tech spec applications.

• The first part of the questions evaluates knowledge of section 4 of Tech Specs.

Reviewed changes with Gerry and determined question to be SAT11106/09 H X E G2.1.44 Question kind of matches the KIA. Question appears to SRO only knowledge. Distractors A, and D 19/94 S do not appear to be plausible unless they are mentioned in some other TS, or basis. Try using cold legs on two distractors, and Hot legs on the other two.

11117109AL

• Enhanced question per suggestion: Changed A and D to Core Alterations in the vicinity of the Reactor Vessel cold legs 1214/09 Gerry accepted changes and approved SAT.

F 2 S G2.2.20 Question appears to match KIA. Appears 20/95 to be SRO only. Not sure all the information on the top of the page is required unless it is there to make distractors plausible. Otherwise SAT.

NEW 11116109AL

• Required information for distractor plausibility H 2 S G2.2.35 Question appears to match KIA. Appears 21/96 to be SRO only SAT.

BANK F 2 X E G2.3.4 Question appears to match KIA. Appears to 22/97 be SRO only. In order to make the ReO more S plausible, suggest adding who is the lowest level individual (or something similar) that can authorize this limit.

NEW 11117109AL

• Enhanced question per suggestion: Added lowest level of authority to stem.

stem.

H 2 X X U G2.4.16 Question appears to match KIA. Not SRO.

23/98 Knowing the entry conditions to procedures such S as loss of all AC is considered RO knowledge.

Therefore the applicant need only know that a loss of All AC has occurred and the choices would be limited to A and C. The second part of the questions deals with using an AOP at the same time that the operator is using an EOP. The way the distractors are worded I don't think anyone would pick the 2nd part of distractor C " as necessary under all conditions of EOP use" That makes this distractor not plausible. If distractor C is not plausible, the applicant can answer the question with only RO knowledge.

NEW Replaced question - Gerry reviewed new question and considered replacement SAT11/06/09

H 2 X X U G2.4.20 Question does not really meet the KIA.

24/99 This is an AOP note or caution and the KIA asks for an EOP. We do sometimes make allowances if there are not many EOPs with important notes or cautions, but this is totally generic and there are may EOPs note a cautions to choose from. What led you to choose a question off of the last exam?

Question is not SRO only. The actions in TS 3.7.1.2 for this condition are immediate, and this is RO knowledge. The responses in distracter Band D for technical specification actions are not entirely correct. The TS action statement does not say "stay in mode 3". It states to immediately initiate corrective actions to restore at least one pump to service. This question could be very easily appealed.

NEW Replaced question with one meeting the KIA, and was at the SRO Only level, EPP-017 Caution. 12104/09

H 2 x WE13EG2.1.7 Question appears to match K/A.

E IWE13EG2.1.7 25/100 Borderline SRO. Distractors A and C are not really plausible. Why would anyone pick A S/G ONLY, S 'plausible.

with the other two available? What exactly are we asking in the stem? It is not very clear. Are you asking the applicants what SG PORV would be used to lower steam in A SG be used to lower steam in A SG or are you asking what SGs PORVs you would use to control RCS Temperature in general? The stem is very confusing. This question needs work.

NEW 11118109AL

• The decision point for transition to FRP-H.2 is based on SG 'A '. FRP-H.2 directs depressurizing the affected SG unless it has been overfilled (step 4). In step 6, the procedure directs controlling RCS temperature using the unaffected SGs.

• Enhancement for question clarification:

Changed stem to "which PORVS would be used to mitigate the SG over pressurization ?"

• Enhancement: Changed A and C to ALL SGs". This would not be a correct response.

Chief Examiner accepted changes and approved SAT. 1214/09 5 Unsat questions after review.

ES-401, Rev. 9 Harris 2009-302 RO Written Examination Review Worksheet Final Form ES-401-9

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

LOD I~---T--~---r--~--____~~----~--r-~

Q# LOK (F/H) LOD Stem

~~

(1-5) ,I Cues T/F Stem Icuesl T/F I Credo cred'l Partial Partial I Job-JOb-I Minutia Minutia I #1 Back- 0=

1. 1 I Back-I 0= I SROSRO IU/EI 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 (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 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.

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.

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 1 F X X E 007EK3.01 Question appears to match the KIA.

Listing the step is teaching. Remove "Step 3 directs the operator to ....

Leave the initial conditions and:

Change to: Which ONE of the following temperature indications would the operators use to control and stabilize temperature and why?

BANK

• Changes made as suggested. Changed stem to: Which ONE of the following temperature indications would the operators use to control and stabilize temperature between 555°F anc ana 559°F AND why? JLC 11-16-09 Question SAT 12109/2009

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- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 2 H X E 008AK1.01 Question appears to match KIA.

Pressurizer level rising will be due to the Safety injection in progress, not due to the steam space break. If a safety Injection was not in progress the initial response of level would be rising due to the steam space break. I am not sure what you are trying to ask. Need to have the original question to verify that it is modified.

MOD

• Original question is provided in the ResponSe

Response

Form Field of LXR Test.

• Changed stem to eliminate SI flow. Also provided Core Exit temperature reading to ensure only one correct answer. 11-16-09 JLC Question SAT 12109/2009 H 2 S 009EK1.02 Question appears to match KIA. Not much discriminating value. SAT 3

BANK H 2 S 011 EG2.4.4 Question appears to match KIA. SAT 4 NEW

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

Q# LOK LOD (FIH) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- Q= SRO utEi Explanation Focus Dist. Link units ward KIA Only S H 2 X E 015AK1.02 Question appears to match KIA.

Distractor D needs to be re-ordered. Initiate a plant 5

shutdown ... Secure the pump ... shut the valve. In the stem third bullet, crew has entered AOP-18.0 ...

Which ONE of the following describes the correct sequence of actions that operators will perform lAW AOP-18.0.

NEW

• Changes made as suggested.

• Stem changed to: Which ONE of the following describes the correct sequence of actions that operators will perform lAW AOP-018, Reactor Coolant Pump Abnormal Conditions? 11-16-09 JLC Question SAT 12109/2009

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- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S H 2 X E 022AA1.03 Question Kind of matches KIA. The question better fits a pressurizer level control 6

malfunction KIA. However, Make up is lost due to FCV-122 closing. Will Discuss. When does level transmitter 460 ever control FCV-122? I don't believe this is plausible. The applicant would need the pressurizer level control selector switch to make this determination. Therefore the switch position should be in the stem and then distractor A should read 461 is controlling level. Or at least state that the system is in the normal line etc.

NEW?

• Plausible since 3 level instruments feed into PRZ level control. Applicant must recall from memory which instrument is utilized for varying FCV-122 position.

• Modified stem to identify which channels are selected for control. 4591460 is normally selected. This would still have the applicant determining appropriate response to the failure. JLC 11-16-09 Question is SAT 12109/2009

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 #/ Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S H 2 E 025AK2.03 Question kind of matches the KIA. Will get another examiner to verify. Are only the A and B 7

CCW pumps running? May want to add this to the stem.

NEW

• No change. A and B CCW pumps are the ONL Y pumps that would normally be operating.

• When CCW is aligned to support RHR Operations (both trains of RHR in service),

two CCW pumps are in service. C CCW pump is a swing pump and could not be aligned to service in this situation.

Question SAT 12109/2009 8 H S 027AK3.04 Question appears to match the KIA. SAT BANK H 2  ? E 029EA2.02 Question kind of matches the KIA. Will get another examiner to verify. (an ATWS is in 9 progress) Not very discriminating.

BANK

• Need Gerry to get back to us on this one to find out what the resolution is.

After Discussions, Question was allowed as is SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO UlEI Explanation Focus Dist. Link units ward KIA Only S H 2 X E 038EG2.4.4 Question appears to match the KIA. If an operator does actuate an SI using the initiation 10 switch, will all of the appropriate actions/lineups occur? If so, what is wrong with answer C?

• Answer C is not IA W EPP-009 foldout criteria.

• See section 6. 17 SI Reinitiation in the EOP User's Guide which defines that switches should NOT be used to reinitiate 81 flow.

Question is SAT 12109/2009 H 2 S 040AA2.04 Question appears to match the KIA.

Need to explain how the negative rate works.

11 Otherwise SAT NEW

• High steamline pressure negative rate. Two of three steamline pressure instruments on any SG decrease greater than 100 psi (can be a step change or 2 psi/sec). A 190 pSig drop in P corresponds to greater than 6 psig a second. JLC 11-16-09 Discussed during meeting SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f 8ack- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S H 2 E 056AA1.01 Question appears to match KIA. Does the instrument bus have a supply from a battery, or 12 will it be lost if you loose the AC buses? You know your plant better than I do, but most plants would still have the instrument bus energized for about two hours. If the instrument bus is still energized, there is not a correct answer. Please Check. Otherwise SAT.

NEW

• No change

• Not all of our SG PORVs are powered from Instrument buses. A & B SG PORV Servos receives power directly from Safety Bus (not through an Instrument Bus). C PORV receives power from Instrument Bus Sill (A Train) which is current powered from battery based on plant conditions.JLC 11-16-09 Discussed during meeting SAT 12109/2009 13 H 2 X E 057 AF2.2.38 Question appears to match KIA. Not really sure that distractor D is plausible. Can a better distractor be developed?

NEW

• Changed 0 distractor to one inoperable diesel. Now reads: Engineering determined that the 'B' EDG fuel oil transfer pump is inoperable JLC 11-17-09 SAT 12109/2009

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- Q= SAO U/EI Explanation Focus Dist. Link units ward KIA Only S H 2 S 058AA1.03 Question appears to match KIA. SAT 14 BANK 15 H 2 X X U 062AA2.03 Question appears to match KIA.

Distractors A and D are not plausible. I do not know of any plant that cannot isolate coolers or fan units.

This does not have very much discriminating value.

The stem needs some improving, try Which ONR of the following identifies (1) the possible location of ...

Any header leak could also cause these conditions.

Are any of these actions listed in AOP 022?

NEW

• Changed the second part of the answer to 12-4-09AL

'shut all' or 'individual'. 12-4-09 AL SAT 12109/2009

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

0# LOK LOD (FIH) (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 16 H 2 X E 065AK3.03 Question kind of matches KIA in a backwards method. Again not very discriminating.

Securing the charging pump is only immediate action in the procedure that is listed. So if you tell them in the stem the applicant need only remember the IDA.

Usually this question is asked: The air line to HCV-142 is broken etc. Which one of the following describes the effect this will have on the plant, and what actions are required to mitigate the event.

NEW

• Modified question to eliminate RCP concern and IA concern. Modified per NRC suggestion to identify broken line and ask for plant response when isolated. 11-16-09 JLC Still need to change distractors c and d to an action that would be appropriate to a lowering ReS pressure 12107/2009.

Made changes as requested Sat 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO UlEi Explanation Focus Dist. Link units ward KIA Only S 17 H 2 X S WE04EK2.1 Question kind of matches KIA.

Distractors A and B do not appear to be plausible. If the valves indicate partially open, then they already have some kind of control power, so the control power switch would not have to be turned on.

NEW

• HNP's indication is separate from motive power. Multiple safety injection valves require closure of the breaker or operation of a switch to apply control power (at the MCB) to allow operation of the component.

• Explained to Gerry and question is SA T. JLC 11-6-09 SAT 12109/2009

~

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

Q# LOK LOD (FIH) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 18 H 2 X X U WEOSEK2.2 Question kind of matches KIA. Will get another examiner to review. Distractors Band C do not appear to be plausible. Why would Tc or Th be lowering in a loss of heat sink? This question should be more operationally driven, what is the indication listed in the procedure that defines a loss of heat sink?

BANK

• Need to revise second part of question to I

get rid of implausible distracters B & c.

Could use indication for loss of Heat Sink for stem and ask about indications for loss of Heat Sink.

• This same KA/question was used on the Harris 2007 NRC RO examination.

• Replaced question. 11-20-09 JLC New question SAT 12109/2009 19 H 2 S 001 AA2.04 Question appears to match KIA.

Question not very discriminating.

BANK

• Modified stem by adding instrument failure to have student determine direction of rod withdrawal.JLC 11-18-09 I

• Added "Initial" prior to effects.

SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO utE! Explanation Focus Dist. Link units ward KIA Only S 20 H 2 S 003AK3.0S Question appears to match KIA. SAT NEW 21 H 2 X E 00SAG2.1.20 Question appears to match KIA. Not much discriminating value. Explain distractor analysis, is G 15 an adjacent thermocouple? If so this may be okay.

BANK

• Yes, G-15 is an adjacent thermocouple .

SAT 12109/2009 22 F 2 X E 024AK1.04 Question does not really meet the KIA.

where is the operational implications? I understand that you are asking what is operable or not operable, but the question should be a boration should be started using the .... Question can be easily fixed.

NEW I

• Modified stem to "Emergency Boration shoula shoulc be implemented using which ONE of the following source(s) available to perform the Emergency Boration? 11-18-09 JLC Made changes as requested. SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues TIF Credo Partial Job- Minutia #/ Back- Q= SAO U/EI Explanation Focus Dist. Link units ward KIA Only S 23 H 2 X S 076AG2.1.25 Question does not meet KIA. If the plant was performing a rapid ramp down for any other reason the answer would be the same. The ability to interpret reference material NEW

• Original KIA 076AG2.1.25 was replaced with KIA 076AG2.1.28, by chief examiner via telecom with Archie Lucky on 11/9/09 Bank question used as replacement.

JLC 11-19-09 BANK New question SAT 12109/2009 24 H 2 X X S WE03EK1.1 Question kind of matches KIA. Very similar to RO question 10. 80th are in EOP-9.0, and involve SI reinitiation criteria. I realize in this version we are testing subcooling and not pressurizer level, but they are very similar and I think are double jeopardy. Not sure that starting the 8 CSIP with normal charging in service is plausible. Starting the pump will do little to change subcooling with 122 at 100%.

BANK

• Question 10 and 24 are too similar for Gerry.

We have agreed to rep/ace the question with one asking 'what do you use to coo/down in EPP-009 and at what rate'.

• Question rep/aced with modified question from 2009a Exam. JLC 11-19-09 Replacement question SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 25 F 2 X X U WE06EK3.3 Question does not meet the KIA. This KIA is asking for knowledge of the reasons for the following responses as they apply to "Degraded Core Cooling." This question test inadequate core cooling. Need to write the question to test FRP-C.2.

BANK

• Need to replaceirevise question with an EOP FRP-C.2 with focus on RCP restart / continue to run RCP. Must be addressed in FRP-C.2 vs. C.1 (degraded vs. loss).

• Question revised to address RCP operation per FRP-C.2. JLC 11-19-09 Replacement Question SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues TtF Credo Partial Job- Minutia #t Back- 0= SAO utE! Explanation Focus Dist. Link units ward KIA Only S 26 F 2 X X 8 WE1SEK2.1 Question does not meet the KIA. If you covered up the lower two bullets in the stem, you could ask the question, have the same answer and not mention anything about containment flooding.

Where does the 19 feet come from, if one crew was faster than another, this number would be different.

NEW

• Audit Exam SRO question #27 asks what the source of extra water is in the Containment during FRP-J.2 Having a question on the NRC written would be overlap between the Audit and NRC exam.

• Gerry provided new KIA W02 EK2.1

• Replaced question with a bank question that matches the KIA.

Replacement Question SAT 12109/2009 27 F 2 X E WE16EA1.1 Question appears to match KIA. Not sure that the 8-1 fans are plausible distractors. Will discuss. Which radiation monitor gives the auto stop signal?

BANK

• The Containment Ventilation Isolation radiation monitors provide the auto stop signal.

Question SAT 12109/2009 I

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

0# LOK LOD (FIH) (1-S) Stem Cues T/F Credo Partial Job- Minutia #1 Back- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 28 F 2 X E 003K2.02 Question appears to match KIA.

Distractor C and D are not plausible. Why would a 6.9KV pump be powered from a 480V bus, or a safety related piece of equipment be powered from S and Gen Service Bus? This question could be asked by a loss of off site power and a specific diese not starting etc and asking what pumps would be available, and if they would start on an LOSP or SI sequencer or something like that. Needs more work.

BANK

• Changed distracter 0 to 480V bus similar to distracter C. Got rid of the General Service Bus that Gerry considered to be implausible.

By making the change to ONL Y 1 distracter the question rated question as an 'Enhance'.

With new distracter for '0' answer the question is now SA T.

• Changed during meeting. 11-6-09 JLC meeting. 11-6-09JLC Made changes, Question SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues TIF Credo Partial Job- Minutia #/ Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 29 F 2 X X E 004A1.11 Question kind of matches KIA. It appears to me that when LT -115 fails Iowan auto make up S will occur. (Unless there is something there to block this) This would make choice A as the correct answer. I looked into the lesson plan and it confirmed that when LT-115 gets to 20% an auto make up will occur. I don't think that this is what you meant by asking this question. I realize that you are asking what/how does the procedure direct the operator to make up, but as written A is correct.

BANK

• Gerry suggested changing the stems first bullet to ensure we are providing information that ensures we are past step 5 of the procedure. This will have the control in

'STOP' and therefore make the automatic makeup in distracters ~' and 'C' wrong.

With this change the question is now SA T.

I

• Modified stem to indicate all actions in AOP-003 are complete, awaiting repairs. This put the plant well beyond the step that places makeup in manual control.

• Changed during meeting on 11-6-09. JLC Replacement Question SAT 12109/2009

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

0# LOK LOD (F/H) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 30 F 2 X E 004K2.05 Question appears to match KIA. If there are not any MCCs on the RAB 236 level, then distractors A, and B are not plausible. Will discuss.

NEW

• MGG 1A22-SA and 1B22-SA are on the 236 elevation and supply containment ventilation.

There are power distribution panels located on the RAB 236 level.

Question SAT 12109/2009 31 F 2 X U 005A1 .02 Question appears to match KIA. If 1 1RH RH 30 does not have an automatic mode, then S distractors band C are not plausible. Why would anyone think if I went to lower on one controller, that flow would increase. The 2008 version of this question was very different and involved a failure of an air supply. Flow remains the same would be a better distractor. Another option is to state that the controller output failed low or high, or that power was lost to the controller.

MODIFIED

• Gerry suggested: Add name of each indicator and change second indicator to FI-605A. Need to make these changes and then the question will be SA T.

• Added names to stem, changed second indicator to FI-605A. JLG 11-17-09 After changes, Question SAT 12109/2009

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 #/ Back- Q= SRO utEi Explanation Focus Dist. Link units ward KIA Only S 32 H 2 X E 005K5.03 Question kind of matches KIA. Distractor D is not plausible. If the plant is not going to refuel, why would RHR boron concentration have to be at the refueling boron concentration? Need to develop another distractor.

MODIFIED

• Modified distractor to utilize PRZ boron concentration and eliminated refueling concentration. JLC 11-17-09 Question SAT 12109/2009 33 H 2 X E 006K6.13 Question appears to match KIA. Distractor A is not plausible. Add approximately to distractor B.

(decrease to approximately half the previous value)

This allows for pump differences if they were in parallel operation (cross connected).

BANK

• Modified distracter A and B to include

'approximately'.

• 'Modified distracters A and B to measure awareness of flow path following completion of EPP-010. JLC 11-19-09 After changes, Question SAT 12109/2009

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 U/EI Explanation Focus Dist. Link units ward KIA Only S 34 H 2 X S 007A1.01 Question appears to match KIA. In review of the procedure, please ensure that the flow from the RCDT pumps do not go to the RCDT (recirc) or it could be considered correct. What is the normal level at 100% power for the PRT? Otherwise SAT NEW

• The RCDT recirc isolation is closed when draining the PRT, therefore the recirc line would not fill the RCDT when using the RCDT pumps to reduce PRT level. The question specifically asks where the water would be transported to lAW OP-1 00, therefore the RCDT would not be a correct answer.

• PRT level is normally maintained between 69

-74% lAW OP-100.

Question SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 35 F 2 S 008K4.02 Question appears to match KIA. Add transfer to A and B like it states in the procedure.

CCW Drain Tank Transfer pump and CCW holdup tank transfer pump. Does the word" Verify" at Harris mean "Make it happen"? If so C could be correct. If not it will be okay. Are these actions lAW AOP-14, or the ARP? The procedure should be referenced in the Stem. Which ONE of the following automatic actions must be verified lAW ...

BANK

• Added 'Transfer' to distractor A and B.

• Verify means make it happen.

• Opening DW-15 requires manual operation, no automatic function; therefore 'C'is not correct. Stem asks for automatic actions.

• Added procedural reference to the stem. JLC 11-18-09 Question SAT 12109/2009 36 H 2 S 010A3.01 Question appears to match KIA. SAT BANK

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO UIE! Explanation Focus Dist. Link units ward KIA Only S 37 H 2 X S 010K3.03 Question does not meet KIA. The question is testing P-11, a permissive, but on an ESF Actuation Signal. Suggestion: If PT-444 failed high, and the PORV opened along with the spray valves the RCS pressure would continue to lower until an ESF actuation occurred.

NEW

• ESFAS is Engineered Safety Function Actuation System. P-11 is part of the Engineered Safety Function Actuation System. P-11 allows block of SI and is covered in TS 3.3.2. 10. Engineered Safety Features Actuation System Interlocks

• a. Pressurizer Pressure. P-IIINot P-II

• After discussion with Gerry, the question was determined to be SA T without changes during meeting on 11-6-09. JLC Question SAT 12109/2009 38 H 2 S 012A2.04 Question appears to match the KIA.

Distractors C and D have reasons in them, and the stem does not ask for reasons. Change C to read

'With N35 in bypass, the reactor trip breakers will remain closed." Change D to read 'With N35 blocked in SSPS, the reactor trip breaker will remain closed." Otherwise SAT NEW

• Modified distracters C and D as described above. JLC 11-18-09 Question SAT 12109/2009

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

Q# LOK LOD (F/H) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- Q= SRO utE! Explanation Focus Dist. Link units ward KIA Only S 39 H 2 X U 013K2.01 Question appears to match KIA. Band 0 distractors are not plausible. Why would a loss of a power supply cause an "energize" to actuate relay to change state? Replace the first parts of these distractors.

NEW

• Replaced question. 11-18-09 AGREE 39 - REPLACE question due to the double jeopardy concern with question #40.

Replacement Question SAT 12109/2009 40 H 2 X 8 013K6.01 Question appears to match KIA. This is the same power supply as question #39. Double jeopardy. Please use another Bus, or malfunction.

Furthermore, distractor C is not plausible when would an 81 not occur and a C8A8 occur? Either question # 39 or this question needs to be replaced.

BANK AGREE 39 will be replaced to alleviate double jeopardy concern.

• Told Gerry that question 39 will be replaced and the double jeopardy concern is now gone. Gerry also agreed that distracter 'C' is plausible and no changes need to be made to the question.

Question 40 is SAT. JLC 11-6-09 Question SAT 12109/2009

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 Partial Job- Minutia #1 Back- 0= SRO UlEI Explanation Focus Dist. Link units ward KIA Only S 41 H 2 X E 022A3.01 Question appears to match KIA.

Distractors Band C are not plausible, and why would S some one perform distractor D. This does not make sense to secure all of one trains' fans, and start the other trains. This question needs some work BANK

• Gerry agreed to the fol/owing explanations:

Oistracter 'B': On an UV signal (sequencer program A) fan should start 1 per unit in fast. This makes 'B' plausible.

Oistracter 'C': The normal operating alignment is aI/

fans in a Train running in fast with the other train secured. This distracter would restore to the normal alignment and is plausible.

I Oistracter '0': This takes the normal alignment and combines it with slow which the system can still perform. This makes this distracter plausible.

• Gerry said to add LOSP to stem and the I

question. It has been included and the question is now SA T. JLC 11-6-09 Long discussion on how these fans worked.

After discussion was determined to be SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 42 F 2 S 026K3.01 Question appears to match the KIA. The stem asks for the required containment fan coolers is this lAW EPP-12? If so the statement should be "Based on plant conditions, which one of the following identifies the minimum number of Containment Fan Coolers required to be in operations lAW EPP-12. Otherwise SAT NEW

• Modified stem as requested during meeting.

11-6-09JLC Question SAT 12109/2009 43 H 2 S 039A4.04 Question appears to match KIA. Need to state that these are SG Narrow Range levels. I some one believed them to be wide range levels the answer would be different. Otherwise SAT BANK

• Modified stem to indicate SG NR levels. 11-6 09JLC Question SAT 12109/2009 44 H 2 S 059A3.06 Question appears to match KIA. SAT NEW

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

Q# LOK LOD (FIH) (1-5) Stem Cues TfF Credo Partial Job- Minutia #/ Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 45 H 2 X E 059A4.12 Question appears to match KIA. Question is very confusing in format and what information is being asked for. Why would anyone think that both signals will be generated and that the MFRVs will remain open? Not much discriminating value as written. This would be better for the applicants if you just asked what will give a Feed water Isolation Signal. (Give initial conditions in the stem and then ask FWIS should have occurred or not etc.

NEW

• The first part tests knowledge of P-4 (Reactor (Reactol Trip). P-4 is 111 Train specific (NOT 212).

However, plausibility comes from other functions.

• Stem modified to eliminate confusion.

Question changed to allow discrimination of which whether FWIVs and FRVs will close based on the P-4 signal and FWI signal response. 11-25-09 JLC Question SAT 12109/2009 46 H 2 S 061A2.03 Question appears to meet KIA. Very similar to SRO question #24, in that the same DC bus failure occurs. Again, for the SROs this is double jeopardy. With the difficulties that occurred with the SRO question, I suggest to change SRO #

24 and leave this one alone. It would be a SAT question.

NEW

• SRO question 24 will be replaced. 11-6-09 Question SAT 12109/2009

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- 0= SRO utE! Explanation Focus Dist. Link units ward KIA Only S 47 F 2 S 062A2.03 Question kind of matches KIA.

Understand that improper sequencing is prevented by interlock. Will allow testing of what interlock prevents improper sequencing. SAT BANK 48 H 2 X E 062G2.2.36 Question appears to match KIA. The second parts of Band D are not very plausible.

Could you find another action to replace this one?

NEW

• Could substitute OST-1024, ON-SITE POWER DISTRIBUTION VERIFICA TlON WEEKL Y INTERVAL MODES 1 - 6. This would test individual knowledge of surveillance requirement, what is in the OSTs and which satisfies the required action.

• Modified question to include OST-1024 in distracters. 11-16-09 JLC After changes, Question SAT 12109/2009 49 F 2 S 063G2.2.22 Question appears to match KIA. Not very discriminating. SAT New

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

Q# LOK LOD (FIH) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 50 H 2 S 063K1.03 Question appears to match KIA. It appears that the distractor analysis is incorrect. It states that 1A2-SA is the supply to the battery charger, but the correct answer states 1A3-SA as the correct supply.

One of these is wrong, please fix. Otherwise, SAT NEW

• Corrected distractor analysis statements based on reference materials. Question is correct as written. 11-6-09 JLC Question SAT 12109/2009 51 H 2 S 064K6.08 Question appears to match KIA. SAT with reference.

MODIFIED from Harris 2009A NRC exam.

52 F 2 S 073K5.01 Question appears to match KIA. Sat NEW 53 H 2 S 076K1.01 Question appears to match the KIA. SAT NEW

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 54 H 2 X E 078G2.4.47 Question appears to match KIA. To increase plausibility change IA pressure @ 1020 to 83 psig, and 1030 to 75 psig (low pressure alarm setpoint. Question will then be SAT NEW

• Change made as described during meeting.

11-6-09JLC After changes, Question SAT 12109/2009 55 F 2 S 103A4.01 Question appears to match KIA. SAT NEW 56 F 2 S 001 K2.05 Question appears to match KIA. SAT NEW 57 H 2 S 011 K5.09 Question appears to match KIA. SAT NEW

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

Q# LOK LOD (FIH) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f 8ack- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 58 H 2 X U 014G2.4.21 Question does not meet the KIA.

Multiple rods stuck out is not testing rod position indication. This is a good question and we need to find a way to incorporate RPI into the indications in S the stem. Also need to change distractors A and B to shutdown (vice subcritical) procedure states to check reactor shutdown.

NEW

• Made slight change to stem to state that

'multiple rod bottom lights are NOT lit' and question is now SA T Completed during meeting. 11-6-09 JLC After discussion and changes, Question is SAT 12109/2009 59 H 2 S 015A1.03 Question appears to match KIA. SAT BANK

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- 0= SRO U/EI Explanation Focus Dist. Link units ward KJA Only S 60 H 2 X E 016A4.01 Question appears to match KIA. As question is written second part does not appear to be relevant. If IGAs placed rods in manual (which I think they did) the second part is not relevant. Need to fix this portion of the question.

NEW

• Drafted Change

• Modified stem to evaluate rod control status itif placed in AUTO. 11-17-09 JLC After discussion and changes, Question is SAT 12109/2009 61 F 2 E 017A3.02 Question appears to match KIA. Do any other monitoring stations outside of the control room use CRT monitor and keyboard? Dose the procedure have the operators perform another action in PIC room RAB 305"? If not these distractors are not plausible. Please explain.

BANK

• The plausibility for the 305' elevation comes from the B Train Cabinet being located in the 305' Main Termination Cabinet (MTC) Room but the procedure specifies ~' Train Cabinet.

The plausibility for CRT monitor and keyboard comes from the normal controls in MCR. We do have other CRTs and keyboards outside the MCR though. DEH has a CRT monitor and keyboard on 305'.

Both trains of Hydrogen Analyzers have a keyboard and LCD in their cabinets located on 305'.

Question is SAT 12109/2009

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

Q# LOK LOD (F/H) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 62 H 2 S 028A2.02 Question appears to match KIA. SAT NEW 63 F 2 E 035K6.01 Question appears to match KIA. Distractor D does not appear to be plausible. Need to fix distractor.

BANK

• Changed C and 0 distractor to 'stays the same'. 11-18-09 JLC After changes, Question SAT 12109/2009 64 H 2 X E 041 K4.09 Question appears to match KIA. In order for the Steam dump atmospheric valves to open it appears that you must be in the Tave mode. When you are cooling down I believe that the steam dumps are in the steam pressure mode. So why would I anyone think that the Atmospheric steam dumps would work? Will discuss

• Revised distracter C to all 6 condenser and atmospheric dump valves can be opened.

Plausible if candidate does not understand operation of steam dumps when in steam i pressure mode of operation with a cooldown in progress. These valves would be available if still in Tavg mode. Modified A to ONLY three condenser.... 11-18-09 JLC I

After changes, Question SAT 12109/2009

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 65 F 2 S 056K1.03 Question appears to match KIA. Need to discuss what trips what. Otherwise SAT.

NEW

• Note provided with reference on original submittal. JLC 11-6-09 66 F 2 X E G2.1.20 Question appears to match KIA. Change the Containment pressure in the stem to allow the use of adverse #'s. (D would then be correct) and change the word preferred (this word is subjective, and I did not see it anywhere in the procedure) use the valves the procedure directs the operator to close first, or something similar.

BANK (will be modified after the change)

• Modified stem to indicate adverse conditions .

Correct answer changed to 'D'. Changed stem to indicate which valves would be closed first lAW PATH-1. Modified plausibility statements to identify that the FCVs are RND steps. 11-17-09 JLC After changes, Question SAT 12109/2009

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 utE! Explanation Focus Dist. Link units ward KIA Only S 67 F 2 S G2.1.38 Question appears to match KIA. SAT What is the definition of an Event Procedure?

BANK

• From OPS-NGGC-1000: Event Procedures

- Abnormal Procedures, Abnormal Operating procedures or Emergency Operating Procedures.

Question SAT 12109/2009 68 F 2 S G2.2.13 Question appears to match KIA. SAT BANK 2004 Harris NRC exam.

69 F 2 S G2.2.35 Question appears to match KIA. SAT NEW

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO utE! Explanation Focus Dist. Link units ward KIA Only S 70 F 2 X E G2.3.11 Question kind of matches KIA. In a review of attachment 7 of AOP-S.O even though the leak is in the WPB portion of SW, the attachment directs the running train of ESW to be placed Standby. This answer would be considered correct. Need to either make it totally correct, or make it totally wrong.

BANK

• Discuss with Gerry. The leak would be from NSW, not ESW. See plausibility statements.

• Modified distracters A and C to indicate re-alignment of ESW trains such that the alternate train is placed in service and the running train is placed in standby. JLC 11-19 09 After changes, Question SAT 12109/2009 71 F 2 X U G2.3.S Question kind of matches KIA. Very little discriminating value. A and B distractors are not S plausible. Why would valves that exhaust to atmosphere be left open? This question needs some work.

• Gerry said to split out answers out to ~' Train dampers ONL Y close, ~'& 'B' Train dampers close. Make the question train specific then i will be SA T. (changes need to be made).

• Actual fix was utilizing E-13 emergency exhaust fans rather than the normal exhaust dampers. 11-18-09 After changes, Question SAT 12109/2009

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

Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 72 F 2 S G2.3.7 Question appears to match KIA. Distractor B needs to read: Entry into a Locked High Radiation Area to hang a clearance. Otherwise SAT NEW

• Modified '8' to include 'to'. 11-6-09 JLC Question SAT 12109/2009 73 F 2 S G2.4.2 Question appears to match KIA. SAT BANK 74 H 2 X S G2.4.39 Question does not appear to match KIA.

This is a normal operating procedure evolution and the answer would be the same if this had been performed after maintenance or just after a high radiation alarm. The question needs to deal with a part of the emergency plan that the RO is responsible for.

NEW Need to discuss RO responsibilities may need new KIA

• Gerry provided new KIA G.2.4.23 New Question is SAT 12109/2009

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

Q# LOK LOD (F/H) (1-5) Stem Cues TfF Credo Partial Job- Minutia #f Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 75 H 2 X U G.4.4 Question appears to meet KIA. Distractors C and D are not plausible. Why would an operator go to path 1 to trip or verify the turbine tripped. Try using another AOP (Turbine trip below P-9 orsomething similar).

NEW

• Changed distracters C and D to utilize AOP-006. 11-17-09 JLC After changes Question is SAT 12109/2009 8 Unsat questions.

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: I-/flRKIS ~[()r-3od..- Date of Exam: !;;(jtlza,9ExamLevel:ROIZI Exam Level: RO IZI SRO [gJ SROrg]

Initials Item Descri tion Description a b r/OY

1. Clean answer sheets copied before grading ~/II! N,~ ~

2. Answer key changes and question deletions justified and documented ~~-?Jl ~

3. Applicants' scores checked for addition errors reviewers sspot (reviewers ot check> 25% of examinations examinations) ?J//)fJJ1 I y

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, a licable, +/-4% on the SRO-onl as applicable, SRO-only) reviewed in detail 1J//K4l1 J "

5. All other failing examinations checked to ensure that grades

'ustified are justified 1JIt(;fI1 Jj ()

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity uestions missed by of questions b half or more of the applicants a licants ~m 1J1('

Printed Name/Signature Date

a. Grader m£EKs/~a--

(f/JcHllfL. mEEKS I

~a-- /~o4,?

b. Facility Reviewer(*) ~:4

)lIA /1 /) /) ;J  ! I ()t.f/zOj[)

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c. NRC Chief Examiner (*) G~W.LA5k:A (O<//~/i)

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d. NRC Supervisor (*) AAww.TWip~ / o(l(J~/1.d! t>

(*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two inde endent NRC reviews are re independent uired.

required.