ML100830101

Initial Exam 2009-302 Final Administrative Documents

ML100830101
Person / Time
Site:	Watts Bar
Issue date:	02/11/2010
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-390/09-302
Download: ML100830101 (43)

Text

ES-201, Rev. 9E Examination Preparation Checklist Form ES-201-1 Facility:

Watts Barr Date of Examination:

11130 Examinations Developed by:

Facility Written / Operating Test Target Chief Date

• Task Description (Reference)

Examiner's Initials

-180

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

~ri

-120

2.

NRC examiners and facility contact assigned (C.1.d; C.2.e)

L"t

-120

3.

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

£J-

-120

4.

Corporate notification letter sent (C.2.d)

~;J--

[-90]

[S. Reference material due (C.l.e; C.3.c; Attachment 2)]

L.ci

{-7S}

6.

Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-S, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, as ~J applicable (C.l.e and f; C.3.d)

{ -70}

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

{ -4S}

8.

Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4,

~ci ES-301-S, ES-301-6, and ES-401-6), and reference materials due (C.l.e, f, g and h; C.3.d)

-30

9.

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

£.£

-14

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

-14 1l. Examination approved by NRC supervisor for facility licensee review

£;L (C.2.h; C.3.f)

-14

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

Lot

-7

13. Written examinations and operating tests approved by NRC supervisor L/

(C.2.i; C.3.h)

-7

14. Final applications reviewed; 1 or 2 (if> 1 0) applications audited to confirm

~t qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 4; ES-202, C.2.e; ES-204)

-7 IS. Proctoring/written exam administration guidelines reviewed with facility licensee 4~

(C.3.k)

-7

16. Approved scenarios, job performance measures, and questions distributed to J(r/-

NRC examiners (C.3.i)

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

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

ES-201, Rev. 9E Examination Preparation Checklist Fonn ES-201-1 Facility:

Watts Barr Date of Examination:

11/30 Examinations Developed by:

Facility Written / Operating Test Target Chief Date

• Task Description (Reference)

Examiner's Initials

-180

l.

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

£ri

-120

2.

NRC examiners and facility contact assigned (C.l.d; C.2.e)

£~t

-120

3.

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

£J-

-120

4.

Corporate notification letter sent (C.2.d)

~ :J-.-

[ -90]

[5. Reference material due (C.l.e; C.3.c; Attachment 2)]

L-~

{-75 }

6.

Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, as

~cf applicable (C.l.e and f; C.3.d)

{ -70}

(7. Examination outline(s) reviewed by NRC and feedback provided to facility

~c1 licensee (C.2.h; C.3.e)}

{-45 }

8.

Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, Lei ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.l.e, f, g and h; C.3.d)

-30

9.

Preliminary license applications (NRC Form 398's) due (C.Ll; C.2.g; ES-202) £f

-14

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

-14 1l. Examination approved by NRC supervisor for facility licensee review

£~

(C.2.h; C.3.f)

-14

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

L;l

-7

13. Written examinations and operating tests approved by NRC supervisor

£/

(C.2.i; C.3.h)

-7

14. Final applications reviewed; 1 or 2 (if> 1 0) applications audited to confirm

~t qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 4; ES-202, C.2.e; ES-204)

-7

15. Proctoring/written exam administration guidelines reviewed with facility licensee ~;t (C.3.k)

-7

16. Approved scenarios, job performance measures, and questions distributed to

~i NRC examiners (C.3.i)

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

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

ES-201 Examination Outline Quality Checklist Facility: Watts Bar Date of Examination:

11/30/2009 Item

. 1.

W R

I T

T E

N

2.

S I

M U

L A

T o R

3.

W

/

T

4.

G E

N E

R A

L Task Description

a.

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

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

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

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

a.

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

b.

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

c.

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

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

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

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

c.

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

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

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

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

d. Check for duplication and overlap among exam sections.

e. Check the entire exam for balance of coverage.

f.

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

a. Author C\\

Print~d..Narllei/SignafllJre Darrell Henslev 1 J\\lJuu ltV

~nAJlli.u

b. Facility Reviewer (*)

Steve R. Smith 1-t[12Sk...,R a

c. NRC Chief Examiner (#)

Form ES-201-2 Initials a

b*

c#

I I

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Watts Bar Date of Examination:

11/30/2009 Item

1.

W R

I T

T E

N

2.

S I

M U

L A

T o R

3.

W

/

T

4.

G E

N E

R A

L Task Description

a.

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

b.

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

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

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

a.

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

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

c.

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

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

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

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

c.

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

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

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

c.

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

d. Check for duplication and overlap among exam sections.

e. Check the entire exam for balance of coverage.

f.

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

Initials a

b*

c#

a. Author Darrell Henslev 1.{\\\\AuG 1111

~iL1..Vnu

" (3. Q C\\

Printed.NarJia/Signa!bJre

~.Ei Steve R. Smith 1~175"",,,,!R

([ -"

tI 'A

£d£Llul iJe:l J: TA"/.-J~ :t:.-,{l.

~

41..tU_.u:T.\\lIrMn A.NAJ,4 '(7 L' 11/""1#1'

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Supervisor Note:

/1~~=n"~~'~==== _____________ ~1

1. Independent NRC reviewer initial items in C~umn

\\'t:;"~~hief examiner concurrence required.

• Not applicable for NRC-prepared examination outlines

W

().:~s ~o.r ES-201 Examination Security Agreement Form ES-201-3

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled forthe week(s) of N<!/II, A'}

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

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of ~<:av* n~t C,=rom the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28

~~~ (

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

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of N($V, O~

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

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of ('\\ov-JJ.H C'.from the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

ES-201, Page 27 of 28

W~~3 ~0Jt ES-201 Examination Security Agreement Form ES-201-3

1.

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

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Nov~ l')e.c, ~<JFrom the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28 p~~ J-.

ES-201 Examination Security Agreement Form ES-20 1-3

1.

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

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of No'll ~ l')e.c, ~<JFrom the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

DATE NOTE ES-201, Page 27 of 28

N~fu '6~

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

. 1.

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

2;pbst~Examinatron To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered

. duringtheweek(s) of Noy.. l>t(,0 tFrom the date that I entered into this security agreement until the completion of examination administration, I did not

. instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1)

DATE SIGNATURE (2)

DATE NOTE

)141".,..., VI IV,,",IL.Nrs7

'q;;:..... -;~ &=

iI/OICA ES-201, Page 26 of 27 r~~3 ES-201 Examination Security Agreement Form ES-201-3

. 1.

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

2.

P.ost-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) ofNo~~l>t(,o'.Fr6m the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1)

DATE SIGNATURE (2)

DATE NOTE

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ES-20 1, Page 26 of 27

ES-301 Administrative Topics Outline Form ES-301-1 hrJd-.1 Facility: Watts Bar Date of Examination: 11/30/2009 Examination Level: RO fZI SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements. 3.8/4.2 JPM:

Determine License Status.

G2.1.25 Ability to interpret reference materials, such as Conduct of Operations N,R graphs, curves, tables, etc. 3.9/4.2 JPM:

Perform RCS DeborationCalculation.

G 2.2.12 Knowledge of surveillance procedures. 3.7/4.1 Equipment Control N,R JPM:

Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three.

G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions. 3.2/3.7 JPM:

Determine Potential Dose for Valve Alignment.

Emergency Procedures 1 N/A Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

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

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

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

ES 301, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 hrJd-./

Facility: Watts Bar Date of Examination: 11/30/2009 Examination Level: RO fZI SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements. 3.8/4.2 JPM:

Determine License Status.

G 2.1.25 Ability to interpret reference materials, such as Conduct of Operations N,R graphs, curves, tables, etc. 3.9/4.2 JPM:

Perform RCS Deboration Calculation.

G 2.2.12 Knowledge of surveillance procedures. 3.7/4.1 Equipment Control N,R JPM:

Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three.

(

G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions. 3.2/3.7 JPM:

Determine Potential Dose for Valve Alignment.

Emergency Procedures /

N/A Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

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

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

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

ES 301, Page 22 of 27

('

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: 11/30/2009 Examination Level: ROO SRO ~

Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements. 3.8/4.2 JPM:

Determine License Status.

G 2.1.25 Ability to interpret reference materials, such as Conduct of Operations D,R graphs, curves, tables, etc. 3.9/4.2 JPM:

Review of Estimated Critical Position Calculation.

G 2.2.12 Knowledge of surveillance procedures. 3.71 4.1 Equipment Control N,R JPM:

Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three."

G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions. 3;2/3.7

. JPM:

Determine Potential Dose for Valve Alignment.

G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. 2.5/3.3 Emergency Procedures I M,R G 2.4.41 Knowledge of the emergency action level Plan thresholds and classifications. 2.9/4.6 JPM:

Classify the Event and Determine PAR.

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 (~3for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (? 1)

(P)revious 2 exams (~ 1; randomly selected)

ES 301, Page 22 of 27

(

{

(

(

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Exam ination: 11/30/2009 Examination Level: RO 0 SRO [8]

Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements. 3.8/4.2 JPM:

Determine License Status.

G 2.1.25 Ability to interpret reference materials, such as Conduct of Operations D,R graphs, curves, tables, etc. 3.9/4.2 JPM:

Review of Estimated Critical Position Calculation.

G 2.2.12 Knowledge of surveillance procedures. 3.7/

4.1 Equipment Control N,R JPM:

Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three."

G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions. 3.2/3.7 JPM:

Determine Potential Dose for Valve Alignment.

G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. 2.5/3.3 Emergency Procedures /

M,R G 2.4.41 Knowledge of the emergency action level Plan thresholds and classifications. 2.9/4.6 JPM:

Classify the Event and Determine PAR.

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

• Type Codes & Criteria:

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

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

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

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 FI"al Facility: Watts Bar Date of Examination: Nov-Dec 2009 Exam Level: RO IXI SRO-IIXI SRO-U IXI Operating Test Number: 1 (Bo/ded JPMs are SRO-U.)

(Italicized JPM is RO only.)

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

a. Exercise Control Rods per 1-SI-85-2.

N 1

b. Perform FR-1.1,"High Pressurizer Level."

A,M,L 2

c. Align RHR for Hot Leg Recirculation.

A,D,EN 3

d. Place Standby Main Feedwater Pump in service for Periodic Operation A,N 4S with Main Feedwater Pumps.

e. Align CRDM Coolers.

N 5

f. Reinstate Source Range following a Reactor Trip.

A,M 7

g. Transfer 6.9 KV RCP Board 1 D from Alternate to Normal per 501-202.01.

M 6

h. Swap CCS Pumps (place 18 in service, remove 1A from service). (RO Only)

A,N 8

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Isolate The RCP Seal Injection And Thermal Barrier Per ECA-O.O.

D,E,L,R 2

j. Align High Pressure Fire Protection (HPFP) to Centrifugal Charging Pump D,EN,R 8

1 A-A Lube Oil Coolers.

k. Align the Upper Containment Monitor to Lower Containment Locally.

D,R 7

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

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

~9/ ~8 / ~ 4 (E)mergency or abnormal in-plant

~ 1 /

~1 / ~ 1 (EN)gineered safety feature

/

/ ~ 1 (L)ow-Power / Shutdown

~ 1 /

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

~2/ ~2 / ~1 (P)revious 2 exams

~3

~ 3 /

~ 2 (randomly selected)

(R)CA

~ 1 /

~1 / ~1 (S)imulator ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 FI"aL Facility: Watts Bar Date of Examination: Nov-Dec 2009 Exam Level: RO lXI SRO-I lXI SRO-U lXI Operating Test Number: 1 (Bolded JPMs are SRO-U.)

(Italicized JPM is RO only.)

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

a. Exercise Control Rods per 1-SI-85-2.

N 1

b. Perform FR-1.1,"High Pressurizer Level."

A,M,L 2

c. Align RHR for Hot Leg Recirculation.

A,D,EN 3

d. Place Standby Main Feedwater Pump in service for Periodic Operation A,N 4S with Main Feedwater Pumps.

e. Align CRDM Coolers.

N 5

f. Reinstate Source Range following a Reactor Trip.

A,M 7

g. Transfer 6.9 KV RCP Board 1 D from Alternate to Normal per 501-202.01.

M 6

h. Swap CCS Pumps (place 18 in service, remove 1A from service).(RO Only)

A,N 8

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Isolate The RCP Seal Injection And Thermal Barrier Per ECA-O.O.

D,E,L,R 2

j. Align High Pressure Fire Protection (HPFP) to Centrifugal Charging Pump D,EN,R 8

1 A-A Lube Oil Coolers.

k. Align the Upper Containment Monitor to Lower Containment Locally.

D,R 7

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

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

~9/ ~8 / ~ 4 (E)mergency or abnormal in-plant

.::: 1 /

> 1 /.::: 1 (EN)gineered safety feature

/

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

.::: 1 /

.:::1

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

.:::2/.:::2 /.::: 1 (P)revious 2 exams

~3

~ 3 /

~ 2 (randomly selected)

(R)CA

.::: 1 /

.:::1

/.::: 1 (S)imulator ES-301, Page 23 of 27

ES-301 Operating Test Quality Checklist Form ES-301-3 F:rl2./

Facility:

Watts Bar Date of Examination: Nov 2009 Operating Test Number: 1 Initials

1. General Criteria a

b*

c#

a.

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

~

$R:$ ~j sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).

b.

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

~

~:r Ld-during this examination.

c.

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

~

~I(.s 2l

d.

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

~

~

2;t acceptable limits.

e.

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

~

'S~ /.;c-L applicants at the designated license level.

2. Walk-Through Criteria

a.

Each JPM includes the following, as applicable:

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

~

operationally important specific performance criteria that include:

.. ~

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant

~

criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b.

Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance

~

i'"

criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified

~. II on those forms and Form ES-201-2.

3. Simulator Criteria The associated simulator operating tests (scenario sets) have been reviewed in accordance with ili... '" Lei Form ES-301-4 and a copy is attached.

~

Printed Name 1 Signature Date

a.

Author Darrell D. Henslev 1 fJalt H 10 (O tk U2D&l 11/12/09 Facility Reviewer(*)

Steve R. Sm;th / ~

~/~,(J.a

b.

11/12/09

c.

NRC Chief Examiner (#) f~ftnr1 ~eCl" ~Tr IL~ L L~,

NL/9/.20D?

JJ).U,IJ,'-)'il:7.V{Co1~.j!/ *1i';,~J;jj{u,~/

I

,7

d.

NRC Supervisor It~/jz'l;fl1

/

["'v./

\\)

~-,

NOTE:

The facility signature is not applicable for NRCcdeveloped tests.

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

(

ES-301 Operating Test Quality Checklist Facility:

Watts Bar Date of Examination: Nov 2009 Operating Test Number: 1

1. General Criteria

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).

b.

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

c.

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

d.

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

e.

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

a.

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

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

detaited 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 com pletion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b.

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

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

Printed Name / Signature

a.

Author

b.

Facility Reviewer(*)

c.

NRC Chief Examiner (#)

d.

NRC Supervisor NOTE:

The facility signature is not applicable for NRCcdeveloped tests.

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

Form ES-301-3 Initials a

b*

c#

Date 11/12/09 11/12/09

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 hl1a../

Facilty: Watts Bar Date of Exam: 12109 Scenario Numbers: 1/2/3 Operating Test No.:

1 QUALITATIVE ATTRIBUTES Initials a

b*

c#

1.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out

~ lj of service, but itdoes not cue the operators into expected events.

S~5

2.

The scenarios consist mostly of related events;

~

S~ ~t

3.

Each event description consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event I~

the symptoms/cues that will be visible to the crew S~ 4;j the expected operator actions (by shift position) the event termination point (if applicable)

4.

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario

~ 1;/

without a credible preceding incident such as a seismic event.

Sfs

5.

The events are valid with regard to physics and thermodynamics.

I~ 1fl:s ~f

6.

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

f~ LJ 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.

H/A NIl.

I Cues are given.

~4

8.

The simulator modeling is not altered.

I~

5~ Lt

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 IO.fY SfI:s ~I to ensure that functional fidelity is maintained while running the planned scenarios.

10.

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

I~ 1~:5~

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

11.

All individual operator competencies can be evaluated, as verified using Form ES-301-6

~

1Rs Ii (submit the form along with the simulator scenarios),

12.

Each applicant will be significantly involved in the minimum number of transients and events I~

1'~

~I specified on Form ES-301-5 (submit the form with the simulator scenarios).

13.

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

W 1f!S Target Quantitative Attributes (Per Scenario; See Section D.S.d)

Actual Attributes

i.

Total malfunctions (5-8) 6/6/7

~

5tu,t;

2.

Malfunctions after EOP entry (1-2) 2/1/2 r\\)f4... "j~ I~

3.

Abnormal events (2-4) 4/4/4

~

"SI<< ld

4.

Major transients (1-2) 1/2/2

{'j}-. ~i< LtA

5.

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

~

11k W

6.

EOP contingencies requiring substantive actions (0-2) 1 11 11

~~

7.

Critical tasks (2-3) 3/214

(

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 hl1a-1 II r

Date of Exam: 12109 Scenario Numbers: 1/2/3 Operating Test No.:

1 QUALITATIVE ATTRIBUTES Initials a

b*

c#

1.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out Ut-

11) of service, but it does not cue the operators into expected events.

S~S

2.

The scenarios consist mostly of related events.

~

S~ ~

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 tt-the symptoms/cues that will be visible to the crew S~ -1/

the expected operator actions (by shift position) the event termination point (if applicable)

4.

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario

~ d without a credible preceding incident such as a seismic event.

S~

5.

The events are valid with regard to physics and thermodynamics.

~

1Rs /~

6.

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

~

S'~ ltj 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.

HIA N{A ~

Cues are given.

8.

The simulator modeling is not altered.

~

5~ -kl

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 lOt"" Sib ~~

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

10.

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

~

1~~ J/--

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

11.

All individual operator competencies can be evaluated, as verified using Form ES-301-6 IJJr "SR$ ~j (submit the form along with the simulator scenarios),

12.

Each applicant will be significantly involved in the minimum number of transients and events

~

i'~ ltJ specified on Form ES-301-5 (submit the form with the simulator scenarios).

13.

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

W 11?S l-tf Target Quantitative Attributes (Per Scenario; See Section D.S.d)

Actual Attributes

1.

Total malfunctions (5-8) 6/6/7

~

i-Sa-l £rJ

2.

Malfunctions after EOP entry (1-2) 2/1/2 I~

~JU P,

3.

Abnormal events (2-4) 4/4/4

~

-SRI d

4.

Major transients (1-2) 1/2/2 1tC'J}- ~Il<,t~

5.

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

~

~R{ U

6.

EOP contingencies requiring substantive actions (0-2) 1 11 11 tOf.6.- -SR~ ~/

7.

Critical tasks (2-3) 3/2/4

~A-"i5 ~

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Watts Bar Date of Exam:

Nov. 2009 Operating Test No.: 1 A

E Scenarios - for CREW ONE P

V P

E Scenario 1 Scenario 2 T

M 0

I L

N I

T C

CREW CREW CREW POSITION POSITION POSITION CREW T

N A

I POSITION L

M A

T S

A B

S A

B S

A B

S A

B U

N Y

R T

0 R

T 0

R T

0 R

T 0

T P

0 C

P 0

C P

0 C

P 0

C P

E RO RX 0

SRO-I NOR 2

IIC 5

SRO-U MAJ 3

TS 2

RO RX NOR SRO-J I/C 6

SRO-U MAJ 3

TS 2

RO RX NOR SRO-I I/C 6

SRO-U MAJ 3

TS RO RX NOR SRO-I I/C SRO-U MAJ TS 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 I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

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

3.

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

ES-301 Transient and Event Checklist ri a wi Form ES-301-5 I

Facility: Watts Bar Date of Exam:

Nov. 2009 Operating Test No.: 1 I

A E

Scenarios - for CREW ONE P

V T

M Scenario 1 Scenario 2 P

E 0

I L

N T

N I

T CREW CREW CREW CREW A

I C

POSITION POSITION POSITION POSITION L

M A

T S

A B

S A

B S

A B

S A

B U

N Y

R T

0 R

T 0

R T

0 R

T 0

M(*

T P

0 C

P 0

C P

0 C

P 0

C P

R I

U E

RO RX 0

1 1 0 SRO-I NOR 5

1 2

1 1 1 IIC 123 35 5

4 4 2 SRO-U MAJ 6

67 3

2 2 1 TS 23 2

0 2 2 RO RX 5

1 1

1 0 NOR 1

1 1

1 1 SRO-/

IIC 2.4 2345 6

4 4 2 SRO-U MAJ 6

67 3

2 2 1 TS 24 2

0 2 2 RO RX 1

1 1

1 0 NOR 5

1 1

1 1

(

SRO-I IIC 1378 24 6

4 4 2 SRO-U MAJ 6

67 3

2 2 1 TS 0

2 2 RO RX 1

1 0 NOR 1

1 1 SRO-I IIC 4

4 2 SRO-U MAJ 2

2 1 TS 0

2 2 Instructions:

1.

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

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

2.

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

3.

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Watts Bar Date of Exam:

Nov. 2009 Operating Test No.: 1 A

E Scenarios - for CREW TWO P

V T

M Scenario 1 Scenario 2 P

E 0

I L

N CREW CREW CREW CREW T

N I

T A

I C

POSITION POSITION POSITION POSITION L

M A

T S

A B

S A

B S

A B

S A

B U

N y

R T

0 R

T 0

R T

0 R

T 0

M(*:

T P

0 C

P 0

C P

0 C

P 0

C P

E R

U RO RX I"'v, i;'

1

~f~?{

i?;~

~i SRO-I NOR 5

IfJ;~( ;; :{;

VI':;!f,'

1;;1&,;

IIC 123 I/~f~~i."".... ;;' i."

24

~;;~I

1.11 SRO-U MAJ 6

~~;

!/;~ n 67

~~7,)

TS 23

~;;; ;., ;,", 1X RO RX 5

I I:~'

1

'.pi;:!

NOR i:;,

1 IY1~

,11,';

1 SRO-I I/C 24 2345 liLt; 6 I;~r' 4 :~~;,

SRO-U MAJ i\\

6 67 f';~;;,>

3 12~

~i, TS 24 2 I)~~ 2 irl~

RO RX 1

0 NOR 1

1 SRO-I I/C 4

4 2 SRO-U MAJ 2

2 1

TS 0

2 2 RO RX 1

0 NOR 1

1 SRO-I I/C 4

4 2 SRO-U MAJ 2

1 TS 0

2 Instructions:

1.

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

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

2.

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

3.

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

ES-301 Transient and Event Checklist Form ES-301-S I

Facility: Watts Bar Date of Exam:

Nov. 2009 Operating Test No.: 1 I

A E

Scenarios - for CREW TWO P

V T

M Scenario 1 Scenario 2 P

E 0

I L

N CREW CREW CREW CREW T

N I

T A

I C

POSITION POSITION POSITION POSITION L

M A

T S

A B

S A

B S

A B

S A

B U

N Y

R T

0 R

T 0

R T

0 R

T 0

M(*

T P

0 C

P 0

C P

0 C

P 0

C P

E R

I U

RO RX 1

1 1

1 0 SRO-/

NOR 5

1 1

1 1 I/C 123 24 5

4 4 2 SRO-U MAJ 6

67 3

2 2 1 TS 23 2

0 2 2 RO RX 5

1 1

1 0 NOR 1

1 1

1 1 SRO-/

I/C 24 2345 6

4 4 2 SRO-U MAJ 6

67 3

2 2 1 TS 24 2

0 2 2 RO RX 1

1 0 NOR 1

1 1

(

(

SRO-I I/C 4

4 2 SRO-U MAJ 2

2 1 TS 0

2 2 RO RX 1

1 0 NOR 1

1 1 SRO-I I/C 4

4 2 SRO-U MAJ 2

2 1 TS 0

2 2 Instructions:

1.

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

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

2.

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

3.

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

ES-301, Rev. 9 Competencies Checklist Form ES-301-6

11'22/

Facility:

Watts Bar Date of Examination: Nov 2009 Operating Test No.: 1 APPLICANTS RO X

RO RO SRO-I SRO-I X SRO~I SRO-U SRO-U SRO-U X Competencies SCENARIO SCENARIO SCENARIO 1

2 1

2 1

2 Interpret/Diagnose Events 246 24 23467 3456 13 3456 and Conditions Comply With and 25 246 ALL ALL 13 ALL Use Procedures (1) 56 Operate Control 245 124 245 124

(>'i'

~r Boards (2)

Communicate 1345 ALL ALL ALL ALL ALL and Interact 6

Demonstrate Supervisory

~'ff '}

1456 1356 14 1356 Ability (3) 56 Comply With and

.... ~

~i' 23 24 23 24 Use Tech. Specs. (3)

~>

Notes:

(1 )Includes Technical Specification compliance for an RO.

(2)Optional for an SRO-U.

(3)Only applicable to SROs.

Instructions:

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

ES-301, Rev. 9 Competencies Checklist Form ES-301-6 rlr72/

Facility:

Watts Bar Date of Examination: Nov 2009 Operating Test No.: 1 APPLICANTS RO X

RO RO SRO-I SRO-I X SRO~I SRO-U SRO-U SRO-U X Competencies SCENARIO SCENARIO SCENARIO 1

2 1

2 1

2 Interpret/Diagnose Events 246 24 23467 3456 13 3456 and Conditions Comply With and 25 246 ALL ALL 13 ALL Use Procedures (1) 56 Operate Control 245 124 245 124 Boards (2)

Communicate 1345 ALL ALL ALL ALL ALL and Interact 6

Demonstrate Supervisory 1456 1356 14 1356 Ability (3) 56 Comply With and 23 24 23 24 Use Tech. Specs. (3)

Notes:

(1 )Includes Technical Specification compliance for an RO.

(2)Optional for an SRO-U.

(3)Only applicable to SROs.

Instructions:

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

E8-401. Rev. 9 PWR examination Outline Form E8-401-2 Facility:

Watts Bar Date of Exam: Nov 2009 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 1

1 2

2 1

2 9

2 2

4 Abnormal Plant N/A N/A Evolutions nerTotais 4

4 5

5 4

5 27 5

5 10 1

3 2

3 3

2 2

2 3

2 3

3 28 3

2 5

2.

2 1

0 1

1 1

1 1

1 1

1 1

10 2

1 3

Plant Systems Tier Totals 4

2 4

4. 3 3

3 4

3 4

4 38 5

3 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

categories 3

2 2

3 1

2 2

2

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., excapt for one category in Tier 3 of the SRO-only outline, the "ner 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 r~vislons. 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 aesociated 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. Refar to E8-401, 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 KlAs 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) K/Asln Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must ba relevant to tha applicable evolution or system.

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' Importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category In the table above; If fuel handling eqUipment is sampled in other than Category A2 or G* on the SRQ.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. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

E8-401. Rev. 9 PWR examination Outline Form E8-401-2 Facility:

Watts Bar Date of Exam: Nov 2009 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 1

1 2

2 1

2 9

2 2

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

4 5

5 4

5 27 5

5 10 1

3 2

3 3

2 2

2 3

2 3

3 28 3

2 5

2.

Plant 2

1 0

1 1

1 1

1 1

1 1

1 10 2

1 3

Systems Tier Totals 4

2 4

4 3

3 3

4 3

4 4

38 5

3 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

2 2

3 1

2 2

2

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (I.e., except for one category In Tier 3 of the SRO-only outline, the "Tier Totals*

In each KIA category shall not be less than two).

2.

The point total for each group and tier In the proposed outilne 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 r!'vlslons. 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 outilne; 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 outiine 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 KlAs having an importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SROtoplcs.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.

8.

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

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

9.

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

ES401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EG2.4.21 Reactor Trip - Stabilization - Recovery 4.0 4.6 0 0 0 0 0 0 0 0 0 0 Ii']

11 009EA2.20 Small Break LOCA 13 2.6 2.9 0 0 0 0 0 0 o "Ii'] 0 0 0 011EK1.01 Large Break LOCA 13 4.1 4.4

~ 0 0 0 0 0 0 0 0 0 0 015AK1.03 RCP Malfunctions I 4 3

4

~OOOOOOOOOO 022AA 1.02 Loss of Rx Coolant Makeup 12 3

2.9 OOOOOO~OOOO 025AK2.05 Loss of RHR System 14 2.6 2.6 0 ~ 0 0 0 0 0 0 0 0 0 026AK3.02 Loss of Component Cooling Water IS 3.6 3.9 0 0 ~ 0 0 0 0 0 0 0 0 027AK2.03 Pressurizer Pressure Control System 2.6 2.S 0 ~ 0 0 0 0 O~ 0 0 0 0 Malfunction 13 029EK1.05 ATWS/1 2.S 3.2

~ 0 0 0 0 0 0 0"0 0 0 038EA2.11 Steam Gen. Tube Rupture/3 3.7 3.9 0 0 0 0 0 0 0 Ii'] 0 0 0 O4OAA 1.23 Steam Line Rupture - Excessive Heat 3.6 3.5 0 0 0 0 0 0 ~ 0 0 0 0 Transfer/4 Page 1 of2 FORM ES-401-2 TOPIC:

Knowledge of the parameters and logic used to assess the status of safety functions Containment vent damper position Indicator Natural circulation and cooling, including reflux boiling.

The basis for operating at a reduced power level when one RCP is out of service CVCS charging low flow alarm, sensor and indicator Reactor building sump The automatic actions (alignments) within"the CCWS resulting from the actuation of the ESFAS Controllers and positioners definition of negative temperature coefficient as applied to large PWR coolant systems Local radiation reading on main steam lines All pressure gauges per steam generator (for pressure drop) 2111/2009 7:17 AM E5-401, REV 9 T1 G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 007EG2.4.21 Reactor Trip - Stabilization - Recovery 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~

11 009EA2.20 Small Break LOCA 13 2.6 2.9 0 0 0 0 0 0 0 ~ 0 0 0 011 EK1.01 Large Break LOCA I 3 4.1 4.4

~ 0 0 0 0 0 0 0 0 0 0 01SAK1.03 RCP Malfunctions I 4 3

4

~OOOOOOOOOO 022AA1.D2 Loss of Rx Coolant Makeup I 2 3

2.9 0 0 0 0 0 0 ~ 0 0 0 0 025AK2.05 Loss of RHR System 14 2.6 2.6 0 ~ 0 0 0 0 0 0 0 0 0 026AK3.02 Loss of Component Cooling Water 18 3.6 3.9 OO~OOOOOOOO 027AK2.03 Pressurizer Pressure Control System Malfunction 13 2.6 2.8 O~OOOOOOODO 029EK1.0S ATWS/1 2.8 3.2

~ 0 0 0 0 0 0 0'0 0 0 038EA2.11 Steam Gen. Tube Rupture 13 3.7 3.9 OOOOOOO~OOO 040AA 1.23 Steam Une Rupture - Excessive Heat 3.6 3.S 0 0 0 0 0 0 ~ 0 0 D 0 Transfer 14 Page 1 of 2 FORM ES-401-2 TOPIC:

Knowledge of the parameters and logic used to assess the status of safety functions Containment vent damper position indicator Natural circulation and cooling. including reflux boiling.

The basis for operating at a reduced power level when one RCP is out of service CVCS charging low flow alarm. sensor and indicator Reactor building sump The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS Controllers and positioners definition of negative temperature coefficient as applied to large PWR CCiolant systems Local radiation reading on main steam lines All pressure gauges per steam generator (for pressure drop) 2111/2009 7:17 AM

E8-401, REV 9 KA NAME I SAFETY FUNCTION:

054AK3.03 Loss of Main Feedwater /4 055EA2.06 Station Blackout / 6 057 AG2.1.23 Loss of Vital AC Inst. Bus / 6 058AG2.4.34 Loss of DC Power /6 065AK3.04 077AK2.03 Loss of Instrument Air /8 Generator Voltage and Electric Grid Disturbances / 6 WE04EA 1.3 LOCA Outside Containment / 3 T1G1 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G AO SAO 3.8 4.1 D D ~ D D D D D D D D 3.7 4.1 D D D D D D D ~ D D D 4.3 4.4 D D D D D D D D D D ~

4.2 4.1 D D D D D D D D D D ~

3 3.2 D D ~ D D D D D D D D 3.0 3.1 D ~ D D D D D D D D D 3.8 4.0 D D D D D D ~ D D D D Page 20f2 FORM ES-401-2 TOPIC:

Manual control of AFW flow control valves Faults and lockouts that must be cleared prior to re-energizing buses Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Knowledge of AO tasks performed outside the main control room during an emergency and the resultant operational effects Cross-over to backup air supplies Sensors, detectors, Indicators Desired operating results during abnormal and emergency situations.

2111/2009 7:17 AM E8-401, REV 9 KA NAME / SAFETY FUNCTION:

054AK3.03 Loss of Main Feedwater / 4 055EA2.06 Station Blackout / 6 057 AG2.1.23 Loss of Vital AC Ins!. Bus / 6 058AG2.4.34 Loss of DC Power / 6 065AK3.04 Loss of Instrument Air / 8 077AK2.03 Generator Voltage and Electric Grid Disturbances / 6 WE04EA 1.3 LOCA Outside Containment / 3 T1 G1 PWR EXAMINATION OUTLINE IA K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 3.8 4.1 D D ~ D D D D D D D D 3.7 4.1 D D D D D D D ~ D D D 4.3 4.4 D D D D D D D D D D ~

4.2 4.1 D D D D D D D D D D ~

3 3.2 D D ~ D D D D D D D D 3.0 3.1 D ~ D D D D D D D. D D 3.8 4.0 D D D D D D ~ D D D D Page 2 of 2 FORM ES-401-2 TOPIC:

Manual control of AFW flow control valves Faults and lockouts that must be cleared prior to re-energizing buses Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Cross-over to backup air supplies Sensors, detectors, indicators Desired operating results during abnormal and emergency situations.

211112009 7:17 AM

E5-401, REV 9 KA NAME I SAFETY FUNCTION:

024AA2.02 Emergency Boration 11 028AK3.05 Pressurizer Level Malfunction I 2 036AG2.4.2 Fuel Handling Accident I 8 OS9AK3.01

_ Accidental Liquid RaclWaste ReI. I 9 067AK1.0l Plant Fire On-site 19 8 069AA 1.01 Loss of CTMT Integrity 1 5 WEOl EA 1.3 Rediagnosis 13 W613EG2.1.31 Steam Generator Over"pressure I 4 WE15EK2.2 Containment Rooding IS T1G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.9 4.4 0 0 0 0 0 0 0 ~ 0 0 0 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 4.5 4.6 0 0 0 0 0 0 0 0 0 0 ~

3.S 3.9 0 0 ~ 0 0 DO 0 0 0 0 2.9 3.9

~ 0 0 0 0 0 0 0 0 0 0 3.5 3.7 0 0 0 0 0 0 ~ 0 0 0 0 3.4 3.8 0 0 0 0 0 0 ~ tJ 0 0 0 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~

2.7 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM E$-401-2 TOPIC:

When use of manual boration valve is needed Actions contained in EOP for PZR level malfunction Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Termination of a release of radioactive liquid Fire classifications by type Isolation valves, dampers and electropneumatic devices.

Desired operating resuHs during abnormal and emergency situations.

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

Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these syStems to the operation of the facility.

2111/2009 7:17 AM ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G AO SAO 024AA2.02 Emergency Boration / 1 3.9 4.4 0 0 0 0 0 0 0 ~ 0 0 0 028AK3.0S Pressurizer Level Malfunction / 2 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 036AG2.4.2 Fuel Handling Accident / 8 4.S 4.6 0 0 0 0 0 0 0 0 0 0 ~

OS9AK3.01 Accidental Liquid RadWaste ReI. / 9 3.S 3.9 0 0 ~ 0 0 0 0 0 0 0 0 067AK1.01 Plant Fire On-site / 9 8 2.9 3.9

~ 0 0 0 0 0 0 0 0 0 0 069AA 1.01 Loss of CTMT Integrity / S 3.S 3.7 0 0 0 0 0 0 ~ 0 0 0 0 WE01 EA 1.3 Rediagnosis / 3 3.4 3.8 0 0 0 0 0 0 ~ t:J 0 0 0 we13EG2.1.31 Steam Generator Over-pressure / 4 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~

WE1SEK2.2 Containment Flooding / S 2.7 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:

When use of manual boration valve is needed Actions contained in EOP for PZA level malfunction Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Termination of a release of radioactive liquid Fire classifications by type Isolation valves, dampers and electropneumatic devices.

Desired operating results during abnormal and emergency situations.

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

Facility's heat removal systems, Including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

2111/2009 7: 17 AM

E8-401, REV 9 KA NAME / SAFETY FUNCTION:

003A1.09 Reactor Coolant Pump 004K5.36 Chemical and Volume Control 005G2.1.23 Residual Heat Removal 005K6.03 Residual Heat Removal 006K5.09*

Emergency Core Cooling 007A4.01 Pressurizer Relief/Quench Tank 007A4.09 Pressurizer Relief/Quench Tank 008K1.05 Component Cooling Water 010A4.03 PresSurizer Pressure Control 012A3.03 Reactor Protection 012G2.1.30 Reactor Protection T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 2.8 0 0 0 0 0 0 ~ 0 0 0 0 2.5 2.8 OODO~OOOOOO 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~

2.5 2.6 DOOOO~ODOOO 3.3 3.6 0 0 0 0 ~ 0 0 0 0 0 0 2.7 2.7 0 0 0 0 0 0 0 0 0 ~ 0 2.5 2.7 0 0 0 0 0 0 0 0 0 ~ 0 3.0 3.1

~ 0 0 0 0 0 0 0 0 0 0 4.0 3.8 0 00 0 DODO 0 ~ 0 3A 3.5 OOOOOOOO~OO 4.4 4.0 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of3 FORM ES-401-2 TOPIC:

Seal flow and DIP Solubility of boron in water; temperature effect Ability to perform specific system and integrated plant procedures during all modes of plant operation.

RHR heat exchanger Thermodynamics of water and steam, including subcooled margin, superheat and saturation PRT spray supply valve Relationships between PZR levet and changing levels of the PRT and bleed holdup tank SourCes of makeup water PORV and block valves Power supply Ability to locate and operate components, including local controls.

211112009 7:17 AM Es-401, REV 9 KA NAME / SAFETY FUNCTION:

003A1.09 Reactor Coolant Pump 004KS.36 Chemical and Volume Control 005G2.1.23 Residual Heat Removal 005K6.03 Residual Heat Removal 006KS.09 Emergency Core Cooling 007A4.01 Pressurizer Relief/Quench Tank 007A4.09 Pressurizer Relief/Quench Tank OOBK1.0S Component Cooling Water 010A4.03 PresSurizer Pressure Control 012A3.03 Reactor Protection 012G2.1.30 Reactor Protection T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 2.8 D D D D D D ~ D D D D 2.5 2.8 D DOD ~ 0 0 0 DOD 4.3 4.4 0 D D D D D DOD D ~

2.5 2.6 D D D D D ~ D D D D D 3.3 3.6 D D D D ~ D D D D D D 2.7 2.7 D D D D D D D D D Ii'I D 2.S 2.7 D D D D D D D D D Ii'I D 3.0 3.1 Ii'I D D D D D D D D D D 4.0 3.8 0 D D D D D D D D Ii'I D 3.4 3.S D D D D D D D D ~ D D 4.4 4.0 D D DOD 0 D D D D ~

Page 1 of 3 FORM ES-401-2 TOPIC:

Seal flow and D/P Solubility of boron in water; temperature effect Ability to perfoml specific system and integrated plant procedures during all modes of plant operation.

RHR heat exchanger Thermodynamics of water and steam, including subcooled margin, superheat and saturation PRT spray supply valve Relationships between PZR level and changing levels of the PRT and bleed holdup tank Sources of makeup water PORV and block valves Power supply Ability to locate and operate components, including local controls.

2111/2009 7:17 AM

E8-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G AO SRO 013K6.01.

Engineered Safety Features Actuation 2.7 3.1 0 0 0 0 0 ~ 0 0 0 0 0 022K2.02 Containment Cooling 2.5 2.4 0 ~ 0 0 0 0 0 0 0 0 0 026K4.0B Containment Spray 4.1 4.3 0 0 0 ~ 0 0 0 0 0 0 0 039Kl.02 Main and Reheat Steam 3.3 3.3

~OOOOOOOOOO 059K3.04 Main Feedwater 3.6 3.B 0 0 ~ 0 0 0 0 0 0 0 0 059K4.02 Main Feedwater 3.3 3.5 OOO~OOODOOO 061A2.0B Auxiliary/Emergency Feedwater 2.7 *2.9 0 0 0 0 0 0 0 ~ 0 0 0 062A2.09 AC Electrical Distnbution 2.7 3.0 0 0 0 0 0 0 0 ~ 0 0 0 062A2.10 AC Electrical Distribution 3.0 3.3 0 0 [J 0 0 0 0 ~ 0 0 0 063K3.01 DC Electrical Distribution 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 063K4.01 DC Electrical Distribution 2.7 3.0 0 0 0 ~ 0 0 0 0 0 0 0 Page20f3 FORM ES-401-2 TOPIC:

Sensors and detectors Chillers Automatic swapover to containment sump suction for recirculation phase after LOCA (AWST low-low level alarm)

Atmospheric relief dump valves RCS Automatic turbine/reactor trip runback Flow rates expected from various combinations of AFW pump discharge valves Consequences of exceeding current limitations Effects of switching power supplies on instruments and controls ED/G ManuaVautomatic transfers of control 2111/2009 7:17 AM 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 013K6.01 Engineered Safety Features Actuation 2.7 3.1 DDDDD~DDDDD Sensors and detectors 022K2.02 Containment Cooling 2.5 2.4 D~DDDDDDDDD Chillers 026K4.0B Containment Spray 4.1 4.3 DDD~DDDDDDD Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm) 039K1.02 Main and Reheat Steam 3.3 3.3

~DDDDDDDDDD Atmospheric relief dump valves 059K3.04 Main Feedwater 3.6 3.B DD~DDDDDDDD RCS 059K4.02 Main Feedwater 3.3 3.5 DDD~DDDDDDD Automatic turbine/reactor trip run back 061A2.0B Auxiliary/Emergency Feedwater 2.7 2.9 DDDDDDD~DDD Flow rates expected from various combinations of AFW pump discharge valves 062A2.09 AC Electrical Distribution 2.7 3.0 DDDDDDD~DDD Consequences of exceeding current limitations 062A2.10 AC Electrical Distribution 3.0 3.3 DDDDDDD~DDD Effects of switching power supplies on instruments and controls 063K3.01 DC Electrical Distribution 3.7 4.1 DD~DDDDDDDD ED/G 063K4.01 DC Electrical Distribution 2.7 3.0 DDD~DDDDDDD ManuaVautomatic transfers of control Page 2 of3 2111/2009 7:17 AM

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

064A1.04 Emergency Diesel Generator 064K1.03 Emergency Diesel Generator 073K3.01 Process Radiation Monitoring 076K2.01 Service Water 078A3.01 Instrument Air 103G2.4.30 Containment T2G1.PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G AO SAO 2.8 2.9 0 0 0 0 0 0 ~ 0 0 0 0 3.6 4.0

~ 0 0 0 0 0 0 0 0 0 0 3.6 4.2 0 0 ~ 0 0 0 0 0 0 0 0 2.7 2.7 0 ~ 0 0 0 0 0 0 0 0 0 3.1 3.2 0 0 0 0 0 0 0 0 ~ 0 0 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~

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

Crankcase temperature and pressure Diesel fuel oil supply system Radioactive effluent releases Service water Air pressure Knowledge of events related to system operations/status*

that must be reported to Intemal orginizations or outside agencies.

2111/2009 7:17 AM Es-401, REV 9 KA NAME I SAFETY FUNCTION:

064A1.04 Emergency Diesel Generator 064K1.03 Emergency Diesel Generator 073K3.01 Process Radiation Monitoring 076K2.01 Service Water 078A3.01 Instrument Air 103G2.4.30 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 2.9 0 0 0 0 0 0 ~ 0 0 0 0 3.6 4.0

~ 0 0 0 0 0 0 0 0 0 0 3.6 4.2 0 0 ~ 0 0 0 0 0 0 0 0 2.7 2.7 0 ~ 0 0 0 0 0 0 0 0 0 3.1 3.2 0 0 0 0 0 0 0 0 ~ 0 0 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~

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

Crankcase temperature and pressure Diesel fuel oil supply system Radioactive effluent releases Service water Air pressure Knowledge of events related to system operations/status that must be reported to Internal orginizations or outside agencies.

2111/2009 7:17 AM

ES401, REV 9 KA NAME I SAFETY FUNCTION:

oolA1.13 Control Rod Drive oo2A4.05 Reactor Coolant 016G2.2.38 Non-nuclear Instrumentation 027K1.01 Containment Iodine Removal 033A3.01 Spent Fuel Pool Cooling 0351<6.01 Steam Generator 045K4.46 Main turbine Generator 055K3.01 Condenser Air Removal 071A2.02 Waste Gas Disposal 086K5.04 Fire Protection T2G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 4.0 4.2 0 0 0 0 0 0 ~ 0 0 0 0 2.8 2.7 0 0 0 0 0 0 0 0 0 ~ 0 3.6 4.5 0 0 0 0 0 0 0 0 0 0 ~

3.4 3.7

~ 0 0 0 0 0 0 0 0 0 0 2.5 2.7 0 0 0 0 0 0 0 0 ~ 0 D 3.2 3.6 0 0 0 0 0 ~ 0 0 0 0 0 2.5 2.8 OOO~OODOOOO 2.5 2.7 0 O.~ 0 0 0 0 0 0 0 0 3.3 3.6 OOOOOOO~OOO 2.9 3.5 0 0 0 0 ~ 0 0 0 0 0 0 Page 1 of 1 FORM E5-.401-2 TOPIC:

"Prepower dependent insertion limit" and pOwer dependent insertion limit, determined with metroscope The HPI system when it is used to refill the refueling cavity Knowledge of conditions and limitations in the facility license.

ess Temperature control valves MSIVs Defeat of reactor trip by overspeed trip test lever Main condenser Use of waste gas release monitors, radiation, gas flow rate and totalizer Haiards to*personnel as a result of fire type and methods of protection 211112009 7:17 AM ES401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:

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

RO SRO 001A1.13 Control Rod Drive 4.0 4.2 DDDDDD~DDDD

'Prepower dependent insertion limit' and power dependent insertion limit, determined with metroscope 002A4.05 Reactor Coolant 2.8 2.7 DDDDDDDDD~D The HPI system when it is used to refill the refueling cavity 016G2.2.38 Non-nuclear Instrumentation 3.6 4.5 DDDDDDDDDD~

Knowledge of conditions and limitations in the facility license.

027K1.01 Containment Iodine Removal 3.4 3.7

~DDDDDDDDDD CSS 033A3.01 Spent Fuel Pool Cooling 2.5 2.7 DDDDDDDD~DD Temperature control valves 035K6.01 Steam Generator 3.2 3.6 DDDDD~DDDDD MSIVs 045K4.46 Main Turbine Generator 2.5 2.8 DDD~DDDDDDD Defeat of reactor trip by overspeed trip test lever 055K3.01 Condenser Air Removal 2.5 2.7 o D.~ 0 0 0 0 0 0 0 0 Main condenser 071A2.02 Waste Gas Disposal 3.3 3.6 DDDDDDD~DDD Use of waste gas release monitors, radiation, gas flow rate and totalizer 086K5.04 Rre Protection 2.9 3.5 DDDD~DDDDDD Hazards to.personnel as a result of fire type and methods of protection Page 1 of 1 2111/2009 7:17 AM

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

G2.1.29 Conduct of operations G2.1.30 Conduct of operations G2.1.6 Conduct of operations G2.2.41 Equipment Control G2.2.42 Equipment Control G2.3.13 Radiation Control G2.3.6 Radiation Control G2.4.12 Emergency Procedures/Plans G2.4.21 Emergency Procedures/Plans G2.4.39 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.0 0 0 0 0 0 0 0 0 0 0 ~

4.4 4.0 0 0 0 0 0 0 0 0 0 0 ~

3.8 4.8 OOOOOOOOOO~

3.5 3.9 0 0 0 0 0 0 0 0 0 0 ~

3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~

3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~

2.0 3.8 0 0 0 0 0 0 0 0 0 0 ~

4.0 4.3 0 0 0 0 0 0 0 0 0 0 ~

4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~

3.9 3.8 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1

3 FORM ES-401~ ~

TOPIC:

Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

Ability to locate and operate components, including local controls.

Ability to manage the control room crew during plant transients.

Ability to obtain and interpret station electrical and mechanical drawings

. Ability to recognize system parameters that are entry-level conditions for Technical Specifications Knowledge of radiological safety procedures pertaining to licensed operator duties Ability to aprove release permits Knowledge of general operating crew responsibilities during emergency operations.

Knowledge of the parameters and logic used to assess the status of safety functions Knowledge of the RO's responsibilities in emergency plan implementation.

2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.29 Conduct of operations G2.1.30 Conduct of operations G2.1.6 Conduct of operations G2.2A1 Equipment Control G2.2.42 Equipment Control G2.3.13 Radiation Control G2.3.6 Radiation Control G2.4.12 Emergency Procedures/Plans G2.4.21 Emergency Procedures/Plans G2.4.39 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.0 DDDDDDDDDD~

4.4 4.0 DDDDDDDDDD~

3.8 4.8 DDDDDDDDDD~

3.5 3.9 DDDDDDDDDD~

3.9 4.6 DDDDDDDDDD~

3.4 3.8 DDDDDDDDDD~

2.0 3.8 DDDDDDDDDD~

4.0 4.3 DDDDDDDDDD~

4.0 4.6 DDDDDDDDDD~

3.9 3.8 DDDDDDDDDD~

Page 1 of 1 3

FORM ES-401~ ~

TOPIC:

Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

Ability to locate and operate components, including local controls.

Ability to manage the control room crew during plant transients.

Ability to obtain and interpret station electrical and mechanical drawings

. Ability to recognize system parameters that are entry-level conditions for Technical Specifications Knowledge of radiological safety procedures pertaining to licensed operator duties Ability to aprove release permits Knowledge of general operating crew responsibilities during emergency operations.

Knowledge of the parameters and logic used to assess the status of safety functions Knowledge of the RO's responsibilities in emergency plan implementation.

2111/2009 7:17 AM

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

022AA2.03 Loss ot'Ax Coolant Makeup 12 029EG2.2.22 ATWS/1 038EG2.2.4 Steam Gen. Tube Rupture 13 058AA2.02 Loss of DC Power IS 077AA2.07 Generator Voltage and Electric Grid Disturbances IS

\\NeOSEG2.4.3 Inadequate Heat Transfer - Loss of Secondal)' Heat Sink I 4 SRO T1G1 PWR EXAMINATION OUTLINE IR K1 K2K3 i<4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.6 0 0 0 0 0 0 0 ~ 0 0 0 4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~

3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~

3.3 3.S 0 0 0 0 0 0 0 ~ 0 0 0 3.S 4.0 0 0 0 0 0 0 0 ~ 0 0 0 3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM E5-401-2 TOPIC:

Failures of flow control valve or controller Knowledge of limiting conditions for operations and safety limits.

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

12SV dc bus voltage, low/criticallow, alarm Operational status of engineered safety features Ability to identify post-accident instrumentation.

2/11/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

022AA2.03 Loss of Ax Coolant Makeup / 2 029EG2.2.22 ATWS /1 038EG2.2.4 Steam Gen. Tube Aupture / 3 058AA2.02 Loss of DC Power / 6 077AA2.07 Generator Voltage and Electric Grid Disturbances / 6 We05EG2.4.3 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 SRO T1 G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 3.1 3.6 D D D D D D D ~ D D D 4.0 4.7 D D DOD D D D D D ~

3.6 3.6 D D D D D D D D D D ~

3.3 3.6 D D D DOD D ~ DOD 3.6 4.0 D D D D D D D ~ D D D 3.7 3.9 D D D D D D D D D D ~

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

Failures of flow control valve or controller Knowledge of limiting conditions for operations and safety limits.

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

125V dc bus voltage, low/critical low, alarm Operational status of engineered safety features Ability to identify post-accident instrumentation.

2111/2009 7:17 AM

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

033AG2.2.40 Loss of Intermediate Range NI/7 067AA2.12 Plant Fire On-site I 9 8 we06EG2.1.23 Degraded Core Cooling 14 WE09EA2.1 Natural eirc. I 4 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.4 4.7 0 0 0 0 0 0 0 0 0 0 ~

2.9 3.9* 0 0 0 0 0 0 0 ~ 0 0 0 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~

3.1 3.8 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:

Ability to apply technical specifications for a system.

Location of vital equipment within fire zone Ability to perform specific system and integrated plant procedures during all modes of plant operation.

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

2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

033AG2.2.40 Loss of Intermediate Range NI/7 067AA2.12 Plant Fire On-site I 9 8 we06EG2.1.23 Degraded Core Cooling I 4 WE09EA2.1 Natural eirc. I 4 SRO T1 G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SAO 3.4 4.7 0 0 0 0 0 0 0 0 0 0 ~

2.9 3.9* 0 0 0 0 0 0 0 ~ 0 0 0 4.3 4.4 0 0 0 0 DOD 0 0 0 ~

3.1 3.8 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:

Ability to apply technical specifications for a system.

Location of vital equipment within fire zone Ability to perform specific system and integrated plant procedures during all modes of plant operation.

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

2111/2009 7:17 AM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 008G2.2.25 Component Cooling Water 3.2*4.2 00000 DO 0 0 0 ~

010A2.02 Pressurizer Pressure Control 3.9 3.9 0 0 0 0 0 0 0 ~ 0 0 0 026A2.03 Containment Spray 4.1 4.4 0 0 0 0 0 0 0 ~ 0 0 0 063G2.4.20 DC Electrical Distribution 3.8 4.3 OOOOOOOOOO~

103A2 03 Containment 3.5 3.8 OOOOOOO~OOO Page 1 of 1 FORM ES-401-2 TOPIC:

Knowledge of the bases In Technical Specifications for limiting conditions for operations and safety limits.

Spray valve failures Failure of ESF Knowledge of operational implications of EOP warnings.

cautions and notes.

Phase A and B isolation 2111/2009 7:17 AM 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:

AO SAO OOBG2.2.25 Component Cooling Water 3.2 4.2 DDDDDDDDDD~

Knowledge of the bases iri Technical Specifications for limiting conditions for operations and safety limits.

010A2.02 Pressurizer Pressure Control 3.9 3.9 DDDOOOO~OOO Spray valve failures 026A2.03 Containment Spray 4.1 4.4 DDDDDDD~DDD Failure of ESF 063G2.4.20 DC Electrical Distribution 3.B 4.3 DDDDDDDDDD~

Knowledge of operational implications of EOP warnings, cautions and notes.

103A2 03 Containment 3.5 3.B DDDDDDD~DDD Phase A and 8 isolation Page 1 of 1 2111/2009 7:17 AM

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

028A2.01 068A2.03 071G2.4.9 Hydrogen Recombiner and Purge Control Uquid Radwaste Waste Gas Disposal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.6 0 0 0 0 0 0 0 ~ 0 0 0 2.5 2.6 0 0 0 0 0 0 0 ~ 0 0 0 3.8 4.2 0 0 0 0 0 0 0 0 0 0 ~

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

Hydrogen recombiner power setting, determined by using plant data book Insufficient sampling frequency of the boric acid in the evaporator bottoms Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

2111/2009 7:17 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

028A2.01 068A2.03 071G2.4.9 Hydrogen flecombiner and Purge Control Uquid Radwaste Waste Gas Disposal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 KS A1 A2 A3 A4 G RO SRO 3.4 3.S 0 0 0 0 0 0 0 ~ 0 0 0 2.5 2.S 0 0 0 0 0 0 0 ~ 0 0 0 3.8 4.2 0 0 0 0 0 0 0 0 0 0 ~

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

Hydrogen recombiner power setting. determined by using plant data book Insufficient sampling frequency of the boric acid in the evaporator bottoms Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

2111/2009 7:17 AM

E5-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.41 Conduct of operations G2.2.22 Equipment Control G2.2.37 Equipment Control G2.3.6 Radiation Control G2.3.7 Radiation Control G2.4.18 Emergency Procedures/Plans G2.4.3 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 2.8 3.7 0 0 0 0 0 0 0 0 0 0 ~

4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~

3.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

2.0 3.8 0 0 0 0 0 0 0 0 0 0 ~

3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~

3.3 4.0 0 0 0 0 0 0 0 0 0 0 ~

3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 TOPIC:

Knowledge of the refueling processes J

FORM ES-401~ 4-Knowledge of limiting conditions for operations and safety limits.

Ability to determine operability and/or availability of safety related equipment Ability to aprove release perm its Ability to comply with radiation work permit reqUirements during normal or abnormal conditions Knowledge of the specific bases for EOPs.

Ability to identify post-accident instrumentation.

2111/2009 7:17 AM E$-401, REV 9 KA NAME I SAFETY FUNCTION:

G2.1.41 Conduct of operations G2.2.22 Equipment Control G2.2.37 Equipment Control G2.3.6 Radiation Control G2.3.7 Radiation Control G2.4.18 Emergency Procedures/Plans G2.4.3 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IA K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.8 3.7 0 0 0 0 0 0 0 0 0 0 ~

4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~

3.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

2.0 3.8 0 0 0 0 0 0 0 0 0 0 ~

3.S 3.6 0 0 0 0 0 0 0 0 0 0 ~

3.3 4.0 0 0 0 0 0 0 0 0 0 0 ~

3.7 3.9 0 0 DOD 0 0 0 0 0 ~

Page 1 of 1 TOPIC:

J FORM ES-401~ 4-Knowledge of the refueling processes Knowledge of limiting conditions for operations and safety limits.

Ability to determine operability and/or availability of safety related equipment Ability to aprove release permits Ability to comply with radiation work permit reqUirements during normal or abnormal conditions Knowledge of the specific bases for EOPs.

Ability to identify post-aCCident instrumentation.

2111120097:17AM

(

ES-401 Tier/

Group 1/1 2/2 2/2 3

Randomly SelectedK/A 015 AK1.03 027 K1.01 033 A3.01 G 2.3.6 Record of Rejected KI As Watts Bar Nov. 2009 RO exam Reason for Rejection Reactor Coolant Pump (RCP) Malfunctions Form ES-401-4 Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow):

AK1.03 The basis for operating at a reduced power level when one RCP is out of service.

Replaced because Watts Bar procedures do not allow this operating configuration.

Replaced by Chief Examiner on 08/04/09 with KA AK1.02 Containment Iodine Removal System (CIRS)

Knowledge of the physical connections and/or cause effect relationships between the CIRS and the following systems: CSS Replaced - Watts Bar CSS has no interface with the iodine removal function.

Replaced by Chief Examiner on 08/04/09 with KA K5.01 Spent Fuel Pool Cooling System (SFPCS)

Ability to monitor automatic operation of the Spent Fuel Pool* Cooling System including:

Temperature control valves Replaced because Watts Bar design is using manual valves only; there are no automatic temperature control valves for SFP cooling.

Replaced by Chief Examiner on 08/04/09 with KA A2.03 Ability to approve release permits.

Replaced - per alignment with Chief Examiner, it is not feasible to write an operationally valid question for an RO to approve release permits..

Replaced by Chief Examiner on 08/04/09 with KA G2.3.4

(

(

ES-401 Tier/

Group 1/1 2/2 2/2 3

Randomly Selected KIA 015 AK1.03 027 K1.01 033 A3.01 G 2.3.6 Record of Rejected KI As Watts Bar Nov. 2009 RO exam Reason for Rejection Reactor Coolant Pump (RCP) Malfunctions Form ES-401-4 Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow):

AK1.03 The basis for operating at a reduced power level when one RCP is out of service.

Replaced because Watts Bar procedures do not allow this operating configuration.

Replaced by Chief Examiner on 08/04/09 with KA AK1.02 Containment Iodine Removal System (CIRS)

Knowledge of the physical connections and/or cause effect relationships between the CIRS and the following systems: CSS Replaced - Watts Bar CSS has no interface with the iodine removal function.

Replaced by Chief Examiner on 08/04/09 with KA K5.01 Spent Fuel Pool Cooling System (SFPCS)

Ability to monitor automatic operation of the Spent Fuel Pool Cooling System including:

Temperature control valves Replaced because Watts Bar design is using manual valves only; there are no automatic temperature control valves for SFP cooling.

Replaced by Chief Examiner on 08/04/09 with KA A2.03 Ability to approve release permits.

Replaced - per alignment with Chief Examiner, it is not feasible to write an operationally valid question for an RO to approve release permits.

Replaced by Chief Examiner on 08/04/09 with KA G2.3.4

ES-401 Tier 1 Group 1/1 2/2 212 Record of Rejected KlAs Watts Bar 2009 SRO exam Form ES-401-4 Randomly Reason for Rejection Selected KIA 038 EG 2.2.4 Steam Generator Tube Rupture (multi-unit license) Ability to explain the variations in control boardlcontrol room layouts, systems, instrumentation, and procedural actions between units at a facility.

Replaced because WBN is currently a single unit site and does not have multi-unit licenses.

Replaced by Chief Examiner on 08/04/09 with KA G2.2.44 068 A2.03 Liquid Radwaste System (LRS)

Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Insufficient sampling frequency of the boric acid in the.

evaporator bottoms Replaced because WBN does not use boric acid evaporators.

Replaced by Chief Examiner on 08/04/09 with KA A2.04

~

071 G 2.4.9 Waste Gas Disposal System (WGDS)

Knowledge of low powerlshutdownimplications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

Replaced - per alignment with Chief Examiner, not feasible to write an operationally valid question to match the KIA.

Replaced by Chief Examiner on 08/04/09 with KA G2.4.8 ES-401

(

Tier /

Group 1/1 2/2 2/2 I

Record of Rejected KlAs Watts Bar 2009 SRO exam Form ES-401-4 Randomly Reason for Rejection Selected KIA 038 EG 2.2.4 Steam Generator Tube Rupture (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

Replaced because WBN is currently a single unit site and does not have multi-unit licenses.

Replaced by Chief Examiner on 08/04/09 with KA G2.2.44 068 A2.03 Liquid Radwaste System (LRS)

Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Insufficient sampling frequency of the boric acid in the evaporator bottoms Replaced because WBN does not use boric acid evaporators.

Replaced by Chief Examiner on 08/04/09 with KA A2.04 c

071 G 2.4.9 Waste Gas Disposal System (WGDS)

Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

Replaced - per alignment with Chief Examiner, not feasible to write an operationally valid question to match the KIA.

Replaced by Chief Examiner on 08/04/09 with KA G2.4.8

ES-401 Written Examination Quality Checklist Form ES-401-6 Fly I

Watts Bar Date of Exam:

Nov/Dec 2009 Exam Leyel: RO X SRO X Item Description

1.

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

2.

a.

b.

NRC KlAs are referenced for all questions.

Facility learning objectives are referenced as available..

3.

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

4.

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

5.

Question duplication from the license screening/audit exarn was controlled as indicated below

6.

(check the item that applies) and appears appropriate:

_ the audit exam was systematically and randomly developed; or

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

_ the examinations were developed independently; or

)!;. the licensee certifies that there is no duplication; or

_ other (explain)

Bank Modified New a

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

20%/8%

25% 128%

55%/64% ~

7.

Between 50 and 60 percent of the questions on the RO exam are written at the comprehension/

analysis level; the SRO exam may exceed 60 percent if the randomly selected KlAs support the higher cognitive levels; enter the actual RO /

SRO question distribution(s) at right.

Memory CIA 47%/36%

53/64%

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 tierto which they are assigned; deviations are justified.

10.

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

11.

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

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor Note:

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

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

Initial b*

Date

(

ES-401 Written Examination Quality Checklist Form ES-401-6 Final Facility:

Watts Bar Date of Exam:

NovlDec 2009 Exam Leyel: RO X SRO X Item Description

1.

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

2.

a.

b.

NRC KlAs are referenced for all questions.

Facility learning objectives are referenced as available..

3.

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

4.

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

5.

6.

7.

8.

9.

10.

11.

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

_ the audit exam was systematically and randomly developed; or

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

_ the examinations were developed independently; or

~

the licensee certifies that there is no duplication; or

_ other (explain)

Bank use meets limits (no more than 75 percent Bank Modified from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only 20% 18%

25% 128%

question distribution(s) at right.

Between 50 and 60 percent of the questions Memory on the RO exam are written at the com prehension/

analysis level; the SRO exam may exceed 60 47%/36%

percent if the random Iy selected KI As support the higher cognitive levels; enter the actual RO /

SRO question distribution(s) at right.

New 55%/64%

CIA 53164%

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

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

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

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

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor

,~

Note:

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

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

Initial a

b*

c#

iSllA-

,l/.

_r:t--

1 ~

~

~j.

~j

~

~i--

• -ti Lf

,~

Date

Watts Bar Nuclear Plant 2009-302 ES-401 Written Examination Review Worksheet Form ES-401-9 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 (Le., clues, specific determiners, phrasing, length, etc).

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

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

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

4.

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

The question is not linked to the job requirements (Le., the question has a valid KIA but, as written, is not operational in content).

The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., it is not required to be known from memory).

The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

The question requires reverse logic or application compared to the job requirements.

5.

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

6.

Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

7.

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

8.

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

2/11/2010 1 of 12 Watts Bar Nuclear Plant 2009-302 ES-401 Written Examination Review Worksheet Form ES-401-9 Instructions

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

1.

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

2.

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

3.

Check the appropriate box if a psychometric flaw is identified:

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

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

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

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

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

4.

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

The question is not linked to the job requirements (Le., the question has a valid KIA but, as written, is not operational in content).

The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., it is not required to be known from memory).

The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

The question requires reverse logic or application compared to the job requirements.

5.

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

6.

Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section 0.2.f.

7.

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

8.

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

2/11/2010 1 of 12

Watts Bar Nuclear Plant 2009-302 ES-401 2

Form ES-401-9

4. Job Content Flaws

8.

5. Other

3. Psychometric Flaws

1. I 2.

LOK LOD Q# I (F/H)

(1-5)

6.

I

7.

B/M/N I U/E/S Explanation H

2 M

(OK) 2 I H

3 X

X N

Stem uses valves and the distractors use dampers. Identify correct term. The distractors use Green in one and Red in three. Use green in a second distractor. (MODIFIED DISTRACTORS AS REQUESTED) (OK) 3 F

2 X

M S/E No need to provided assumption (REMOVED ASSUMPTION) (OK) 4 F

2 M

S (OK) 5 H

2

.x N

S/E Consider changing the stem to read as a two part question (1 & 2).

WOOTF identifies how (1).... And (2) (MODIFIED STEM AND DISTRACTOR -

6 H

3 N

S (OK) 7 F

2 N

S (OK) 8 F

2 X

M E

Distractor 0 is not plausible. What is "continue to throttle?"

Open/Close? Fully open/Fully close? (MODIFIED STEM AND DISTRACTORS) (OK) 9 H

3 N

S (OK) 10 H

2 N

S (OK) 11 I H

I 3

I I I I I I I I I I I I N

S (OK)

I U/E I Missing words in stem and distractors (grammar). Based on the H

3 X

X N

12 information provided, I am not sure there is a correct answer. Look at actions identified in steps 8 & 9. What conclusion would the applicant come too based on the information provided? (CHANGES WORDS IN BOTH STEM AND DISTRACTORS) (OK) 2/11/2010 2 of 12 Watts Bar Nuclear Plant 2009-302 ES-401 2

Form ES-401-9

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

8.

~~~~

(F/H)

(1-5)

Stem Goee TIF Geed_ P,rtl,' Job-MI""tI,

'1 Back-Q-

SRO B/MIN U/EIS Explanation Focus Dlst.

Link Units ward KIA Only

W""'"

1111111'1"'"

'"j'",'

IIEE~

J~i:III;I;'

~~!~:::~~~!;:J~!~!~:~~~~~~;~~

jil 1

H 2

M S

(OK) 2 H

3 X

X N

E Stem uses valves and the distractors use dampers. Identify correct term. The distractors use Green in one and Red in three. Use green in a second distractor. (MODIFIED DISTRACTORS AS REQUESTED) (OK) 3 F

2 X

M S/E No need to provided assumption (REMOVED ASSUMPTION) (OK) 4 F

2 M

S (OK) 5 H

2 X

N S/E Consider changing the stem to read as a two part question (1 & 2).

WOOTF identifies how (1).... And (2) (MODIFIED STEM AND DISTRACTOR - MINOR) (OK) 6 H

3 N

S (OK) 7 F

2 N

S (OK) 8 F

2 X

M E

Distractor D is not plausible. What is "continue to throttle?"

Open/Close? Fully open/Fully close? (MODIFIED STEM AND DisTRACTUH::l) *(OK) 9 H

3 N

S (OK) 10 H

2 N

S (OK) 11 H

3 N

S (OK) 12 H

3 X

X N

U/E Missing words in stem and distractors (grammar). Based on the information provided, I am not sure there is a correct answer. Look at actions identified in steps 8 & 9. What conclusion would the applicant come too based on the information provided? (CHANGES WORDS IN BOTH STEM AND DISTRACTORS) (OK) 2/11/2010 2 of 12

1. I 2.

Q# I LOK LOD (F/H)

(1-5) 14 H

2 15 H

3 16 F

2 17 I F I 3 18 I H I 3 19 I H

I 3

20 I H 2

21 I H 3

22 I F

2 23 F

2 24 F

3 25 H

3 2/11/2010

3. Psychometric Flaws X

X X

X X

Watts Bar Nuclear Plant 2009-302

4. Job Content Flaws

6.

I

7.

U/E/S M

S B

S B

S/E N

S M

S B

E B

S X

N U

N S/E N

S N

S N

S?

8.

Explanation (OK)

(OK)

Question is difficult to read. Consider writing stem to ask two part question and revise distractors to reflect two part answer.

CHANGED D (OK)

(OK)

Stem is not clear. Check grammar. Need additional information to show plausibility of distractors valve lineups. Explain why closing selected valves would be plausible. <<CHANGES MADE TO I DISTRACTORISTEM) (OK)

T/f"Il<"\\

(;llcmfl~ (;Ufl~LltUU:i t:lIlry IIltU Ult: cvr~! \\.:>nvuL..U I'IV I nr\\VC DCC AU KA MATCHES ---MODIFIED STEM - LOTS OF DISCUSION (

THIS QUESTION) (OK)

Consider rewriting stem. Unit? is a 100% power with a LRRIP.. when the following alarm(s) are received (DETERMINE THAT KIA DID NOT MATCH 11/3) 11/4 WROTE NEW (OK)

(OK)

The conditions in the stem (RCS pressure at 1630 psig and PZR Level at 11 %) do not seem consistent with an inadvertent SI. Would you expect to have low RCS pressure and low PZR level with an inadvertent SI? (MADE CHANGES TO THE STEM AND DISTRACTORS) (OK) 3 of 12 Watts Bar Nuclear Plant 2009-302

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

8.

Q# LOKL~j (F/H)

(1-5)

Stem Cues T/F C~ed. Partial J?b-Minutia

1. 1 Back-~

B/WN U~

E'plaoa""

Focus Dlst.

Link units ward KIA Only I

'rII

"!:~I

~::,:~

.j~;I,

.,~"11' _0

~,~0'

'~"Jl:'r'~~~~~~~~]~~:::I~!~]~~I[:~~~~~((I~))~~~~ill~~~~r:~~~~~~

'.N~@:;f A, I!'

13 13 3

N U

If a SBO has occurred, then why would distractors A and B be credible? If the 161 KV system is the normal offsite.supply, then by the definition of an SBO you have already told the applicant that the 6~~r~A6~~;~~ /~~)available. (CHANGED STEM AND 14 H

2 M

S (OK) 15 H

3 B

S (OK) 16 F

2 X

B S/E Question is difficult to read. Consider writing stem to ask two part question and revise distractors to reflect two part answer.

(CHANGED DIST£lACT~ (OK) 17 F

3 N

S (OK) 18 H

3 M

S (OK) 19 H

3 X

B E

Stem is not clear. Check grammar. Need additional information to show plausibility of distractors valve lineups. Explain why closing selected valves would be plausible. ((CHANGES MADE TO DISTRACTORISTEM) (OK) 20 H

2 B

S (OK) 21 H

3 X

X N

U Explain why you consider this a KIA match. Does actuation of the alarms constitute entry into the EOPs? (SHOULD NOT HAVE BEEN AU KA MATCHES ---MODIFIED STEM - LOTS OF DISCUSION ON THIS QUI ",' lVI'll (OK) 22 F

2 X

N S/E Consider rewriting stem. Unit? is a 100% power with a LRRIP.. when the following alarm(s) are received (DETERMINE THAT KIA DID NOT MATCH 11/3) 11/4 WROTE NEW QUESTION) (OK).....

23 F

2 N

S (OK) 24 F

3 N

S (OK) 25 H

3 X

N S?

The conditions in the stem (RCS pressure at 1630 psig and PZR Level at 11 %) do not seem consistent with an inadvertent SI. Would you expect to have low RCS pressure and low PZR level with an inadvertent SI? (MADE CHANGES TO THE STEM AND DISTRACTORS) (OK) 2/11/2010 3 of 12

1. I 2.

Q# I LOK LOD (F/H)

(1-5) 26 I H

3 27 I H I 3

28 29 30 I F I 2

31 H

2 32 H

2 33 I F

34 I F

2 2/11/2010

3. Psychometric Flaws I X I X I X I I

X I

X I X I X

X I I

I I

I Watts Bar Nuclear Plant 2009-302

4. Job Content Flaws

5. Other

6.

I 7.

8.

u/E/S Explanation N

U I Wrong procedure number in stem (FR-H.2 -vs-FR-H.3).

According to ES-O.1, 1-HS-3-45, MFW Mode Switch only gets placed in "LONG CYCLE RECIRC" position if AFW flow is established to the SGs. Don't understand why applicants would think the second part of choices C and 0 would be plausible since AFW flow would already be established with MFW in Long Cycle Recirc.

Unable to locate a procedural action/step which states "Supply AFW into the steam space." Is this an RO question - action (s) very specific and located deep into procedure? (MADE SHANGES TO THE STEM AS SUGGESTED) (OK)

I M I U I Improve stem. Appears to be confusing. There also appear to be two correct answers B & D. (STEM DID NOT HAVE TWO CORRECT ANSERS. MADE CHANGES TO (OK)

Consider rewording 2nd half of 'C' and '0'. As written it appears confusing. Consider: "Letdown temperature will NOT change because the failure results in blocking the input to the valve controller. (MADE MINOR CHANGES) (OK)

I M I E I Consider rewording the stem and revising distractors to better match KIA. In the stem consider asking the applicant to provide the procedure and add procedures to the distractors. (REWORDED STEM AND N.

(OK)

N Explain why "Subcooling remain constanf' is plausible after stopping a pump. (SHOUND NOT HAVE BEEN A U CHANGED STEMl (OK)

N E I LOD. Distractor 0 is the only distractor that does not have O-L-2 panel identified. Consider rewriting the question such that the applicant is given a set of condition and must take actions or identify the actions that should be taken and where the actions are (MADE MINOR CHANGES TO THE DISTRACTORS I

I I

I I

I I

(OK)

N S

II"\\V\\

4 of 12 Watts Bar Nuclear Plant 2009-302

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

8.

Q#

LOK LOD (F/H)

(1-5) St,m e"~

emd. Partial Job-Minutia

1. /

Back-Q=

SRO B/M/N u/E/S Explanation Focus Dlst.

Link units ward KIA Only I"Wf~~~1

• 1

S

);

~~;JII.:l Ji:!.,

26 H

3 X

X N

U Wrong procedure number in stem (FR-H.2 -vs-FR-H.3).

According to ES-O.1, 1-HS-3-45, MFW Mode Switch only gets placed in "LONG CYCLE RECIRC" position if AFW flow is established to the SGs. Don't understand why applicants would think the second part of choices C and D would be plausible since AFW flow would already be established with MFW in Long Cycle Recirc.

Unable to locate a procedural action/step which states "Supply AFW into the steam space." Is this an RO question - action (s) very specific and located deep into procedure? (MADE SHANGES TO THE STEM AS SUGGESTED) (OK) 27 H

3 X

X M

U Improve stem. Appears to be confusing. There also appear to be two correct answers B & D. (STEM DID NOT HAVE TWO CORRECT ANSERS. MADE CHANGES TO DISTRACTOR) *OK) 28 F

3 M

S (OK) 29 H

3 X

X N

S/E Consider rewording 2nd half of 'C' and 'D'. As written it appears confusing. Consider: "Letdown temperature will NOT change because the failure results in blocking the input to the valve controller. (MADE MINOR CHANGES) (OK) 30 F

2 X

X M

E Consider rewording the stem and revising distractors to better match KIA. In the stem consider asking the applicant to provide the procedure and add procedures to the distractors. (REWORDED STEM AND DISTRAC-I UH::;) (OK) 31 H

2 N

S (OK) 32 H

2 X

N U

Explain why "Subcooling remain constant" is plausible after stopping a pump. (SHOUND NOT HAVE BEEN A U CHANGED STEM) lQ15l 33 F

1 X

N E

LOD. Distractor D is the only distractor that does not have O-L-2 panel identified. Consider rewriting the question such that the applicant is given a set of condition and must take actions or identify the actions that should be taken and where the actions are performed. (MADE MINOR CHANGES TO THE DISTRACTORS (OK) 34 F

2 N

S (OK) 2/11/2010 4 of 12

Watts Bar Nuclear Plant 2009-302 Explanation

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

I

7.

8.

1. I 2.

LOK LOD Q# I (F/H)

(1-5)

U/E/S 35 I F

2 I X I X I X I N

E lis there an alarm received? If an alarm is received, what actions will the operator be directed to take. At what level will the alarm come in? Will it come in before the auto action occurs?..... Consider identifying the alarm in the stem. The fact that "on low level in Surge Tank" in choices "A" and "B" is not included, could possibly cue the applicant to exclude them. Consider moving "on low level in Surge Tank" into the stem after the first fill-in-the-blank and remove from choices "c" and "0". (MINOR CHANG 36 F

2 N

S (OK) 37 F

2 N

S (OK) 38 F

2 X

N E

The stem is confusing. Consider asking the applicant what could cause the alarm. How and where would you go to determine what caused the alarm? (CHANGED AS 39 I H I 3

N S

(OK) 40 I F I 2 N

S (OK) 41 I F I 2 X

M E

o not plausible. The word operated instead of opened or closed has the potential to make all 4 answers incorrect. If FCV-72-40 were partially open for whatever reason, can I close it with the suction valve from the RWST open? (CHANGED DISTRACTOR, MINOR CHANGE TO STEM) (OK) 42 I H

2 X I I M I U I With RCS temp comparable to about 370 psig, Stm Line Low Pressure causing an isolation (when it hasn't already) is not plausible. This x2 is unsat.

Will an open PORV reduce pressure at 100/50 sec when at 370 psig?

Rec: Make RCS pressure - 1900 psig? (MADE CHANGES TO PRESSURE AND TEMP) (OK) 43 I H

2 X I I M I u I Tc and power changing in the same direction is not plausible x2 is unsat.

Rec; Does COLR have a power that your not allowed above without a negative CXTmod (like 80% or so). If so, make this question immediately after a refueling outage to add the potential of being overmoderated OR maybe after stabilizing, power will be: Pzr level will be: Power will be:..... {SHOULD NOT HAVE BEEN A U - ONLY MINOR CHANGES NEEDED) (OK) 2/11/2010 5 of 12 Watts Bar Nuclear Plant 2009-302

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

W LOK LODs (F/H),(1-5) stem, C T/,F Credo P rf I Job-M' f

1. /

Back-Q=

Focus ues Dist.

a la Link InU la units ward KIA

. ;l1!J!!!II¥o/;li~j,III,."+!!~::::ilm:: A::::'!I~::,!iI~r,I, l'i;j;~!~Vq 35 F

2 x

x x

36 F

2 37 F

2 38 F

2 x

39 H

3 40 F

2 41 F

2 x

42 H

2 x

43 H

2 x

2/11/2010 SRO B/M/N U/E/S Only N

E N

S N

S N

E N

S N

S M

E M

U M

U

8.

Explanation

'4.l!"I~!!!'11!i1P0111~~~;~~,~~i;~;~~!'II~~!~;~:~~~~~~~5~~~~j,,~~~;1 Is there an alarm received? If an alarm is received, what actions will the operator be directed to take. At what level will the alarm come in? Will it come in before the auto action occurs?...... Consider identifying the alarm in the stem. The fact that "on low level in Surge Tank" in choices "A" and "B" is not included, could possibly cue the applicant to exclude them. Consider moving "on low level in Surge Tank" into the stem after the first fill-in-the-blank and remove from choices "c" and "0". (MINOR CHANGES) (OK)

(OK)

(OK)

The stem is confusing. Consider asking the applicant what could cause the alarm. How and where would you go to determine what caused the alarm? (CHANGED AS SUGGESTED) (OK)

(OK)

(OK) o not plausible. The word operated instead of opened or closed has the potential to make all 4 answers incorrect. If FCV-72-40 were partially open for whatever reason, can I close it with the suction valve from the RWST open? (CHANGED DISTRACTOR, MINOR CHANGE TO STEM) (OK)

With RCS temp comparable to about 370 psig, Stm Line Low Pressure causing an isolation (when it hasn't already) is not plausible. This x2 is unsat.

Will an open PORV reduce pressure at 100/50 sec when at 370 psig?

Rec: Make RCS pressure - 1900 psig? (MADE CHANGES TO PRESSURE AND TEMP) (OK)

Tc and power changing in the same direction is not plausible x2 is unsat.

Rec; Does COLR have a power that your not allowed above without a negative CXTmod (like 80% or so). If so, make this question immediately after a refueling outage to add the potential of being overmoderated OR maybe after stabilizing, power will be: Pzr level will be: Power will be:..... (SHOULD NOT HAVE BEEN A U - ONLY MINOR CHANGES NEEDED) (OK) 5 of 12

Q#

45 I 46 I 47 I 48 49 50 I 51 I 52 I 53 I

1.

LOK (FtH)

H F

H H

F F

F F

F 2/11/2010

2.

LOD (1-5) 2 2

2 2

2 2

2 2

2

3. Psychometric Flaws X

I X I Watts Bar Nuclear Plant 2009-302

4. Job Content Flaws

5. Other

6.

7.

8.

UtE/S Explanation N

S i::Ulllt:1U al 0/70 Guru lilt:;! IVlrvv IJUlllfJ aUlU IUIIUi:1l.1l\\ I;:' i:11111t:lU al OU/O, (PROVIDED PROOF) (0)

X N

UtE What procedure is being used to correct, control or mitigate per the KIA?

Do I need SG levels? What levels does AFW maintain in this condition? (MINOR CHANGES) (OK)

N I UtE I B & D not plausible. My choices are electrical trouble or a fire. It would not make sense to start more fans on either. Need better 2nd half for B & D. (MADE MINOR CHANGES TO STEM) (OK)

I X I N

U I What procedure is being used to correct, control or mitigate per the KIA?

Rec: State what procedure is used to mitigate this event.

The procedure provided: SOI-211.04 states 0-FCV-67-152 MAY reposition. It needs to have a component that will reposition or not reposition, i.e. no gray space. (ONLY MINOR CHANGES REQUIRED - SHOULD NOT HAVE BEEN IDENTIFIED AS UNSAT)

(OK)

(OK)

Why would I think that a loss of power to DC Batt Bd 2 (A & B) would cause DC TB Dist Bd 1 to switch? X2 = unsat. (MADE MINOR CHANGES MADE TO DISTRACTOR) (OK)

I X I B

U lit doesn't predict or monitor anything. It asks a trip setpt.

Rec: Give some condition that will lead to some type of trip.

(CHANGED WORDING IN STEM AND B I UtE I Explain how manual is plausible.

Rec: Ask about the pump and level or a leak and makeup capacity.

Something more along the line of cause and effect.(DECIDED TO USE A BACKUP QUESTION) (OK)

I X I I M I U I The KA asks for the effect of a malfunction on a Rad Release.

The question states the effect and asks how to restore.

Rec: Drop the last two bullets and ask about valve repositioning.

(REWROTE QUESTI N

E I Should state: an ERCW pump that can be selected to start.

(REWORDED STEM) (OK) 6 of 12 Q#

45 46 47 48 49 50 51 52 53

1.

LOK (F/H)

H F

H H

F F

F F

F 2/11/2010

2.

LOD (1-5) 2 2

2 2

2 2

2 2

Watts Bar Nuclear Plant 2009-302

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

U/E/S X

N U/E X

N U/E X

N U

B S

X M

U/E X

B U

X B

U/E X

M U

N E

8.

Explanation What procedure is being used to correct, control or mitigate per the KIA?

Do I need SG levels? What levels does AFW maintain in this condition?

B & 0 not plausible. My choices are electrical trouble or a fire. It would not make sense to start more fans on either. Need better 2 nd half for B & D.

MINOR CHANGES TO What procedure is being used to correct, control or mitigate per the KIA?

Rec: State what procedure is used to mitigate this event.

The procedure provided: SOI-211.04 states 0-FCV-67-152 MAY reposition. It needs to have a component that will reposition or not reposition, I.e. no gray space. (ONLY MINOR CHANGES REQUIRED - SHOULD NOT HAVE BEEN IDENTIFIED AS UNSAT)

(OK)

Why would I think that a loss of power to DC Batt Bd 2 (A & B) would cause DC TB Dist Bd 1 to switch? X2 = unsat. (MADE MINOR CHANGES MADE TO It doesn't predict or monitor anything. It asks a trip setpt.

Rec: Give some condition that will lead to some type of trip.

o WORDING IN STEM AND 01 Explain how manual is plausible.

Rec: Ask about the pump and level or a leak and makeup capacity.

Something more along the line of cause and effect. (DECIDED TO USE A BACKUP QU The KA asks for the effect of a malfunction on a Rad Release.

The question states the effect and asks how to restore.

Rec: Drop the last two bullets and ask about valve repositioning.

ROTE QUESTION Should state: an ERCW pump that can be selected to start.

(REWORDED STEM) (OK) 6 of 12

1. I 2.

Q# I LOK LOD (F/H)

(1-5) 2 55 F

2 56 H

3 57 I H I 2

58 I F I 3

59 I F

60 I H

61 H

2 62 I H

I 2

H 2

63 64 H

2 65 F

2 2111/2010

3. Psychometric Flaws I

I I

I X I I I X I I X

Watts Bar Nuclear Plant 2009-302

4. Job Content Flaws

5. Other

6.

I

7.

u/E/S N

S N

E I

N I E

X I I

N I E

U U

S I

I I I I I I S

M U

S/E X

N U

8.

Explanation I

No reference for rod insertion limit?

Change "drops" to lowers or decreases.... (MADE CHANGES AS DISCUSSED) (OK)

I Should state lAW AOI 29.

Should state the level (something less than 748') (MADE MINOR CHANGES TO THE STEM) (OK).

I Make sure that "spent fuel shuffles being conducted in the Spent Fuel Pit". Is the same as the TS applicability "during movement of irradiated fuel assemblies" RO's are typically not required to know information below the line unless < 1 HR TS.

Is this an RO objective?

C should be "either" instead of "both". (LICENSEE STATED THAT THIS IS AN RO QU Distractors C and D DISTRACTORS C&

As w~-..... ~.~ ~~

INFC WOl HAV (OK)

(OK)

KIA mismatch. KIA ask for hazards to personnel as a result of fire type and methods of protection. (CONVENSED US THAT THE QUESTION DID MATCH THE KIA) (KIA) 7 of 12

1.

LOK Q#

(F/H) 55 F

56 H

57 H

58 F

59 F

60 H

61 H

62 H

63 H

64 H

65 F

2/11/2010

3. Psychometric Flaws

3 3

2 3

X 2

2 X

2 2

2 X

2 X

2 Watts Bar Nuclear Plant 2009-302

4. Job Content Flaws

5. Other

6.

7.

8.

U/E/S N

S (OK)

N E

No reference for rod insertion limit?

Change "drops" to lowers or decreases.... (MADE CHANGES AS DISCUSSE N

E Should state lAW AOI 29.

Should state the level (something less than 748') (MADE MINOR CHANGES TO THE STEM N

E Make sure that "spent fuel shuffles being conducted in the Spent Fuel Pit". Is the same as the TS applicability "during movement of irradiated fuel assemblies" RO's are typically not required to know information below the line unless < 1 HR TS.

Is this an RO objective?

C should be "either" instead of "both". (LICENSEE STATED THAT THIS IS AN RO QU M

U N

U S

S (OK)

M U

Will the alarm result in a decrease in condenser vacuum? Potentially no correct answers. If no operator actions are taken, would the 1 B pump not trip? If it trips, distractor A is correct. Is there sufficient information in the stem?

MINOR CHAN S/E type of malfunction? Do you need to identify a malfunction?

ED INSTRUNMENT MALFUNCTION) (OK)

X N

U KIA mismatch. KIA ask for hazards to personnel as a result of fire type and methods of protection. (CONVENSED US THAT THE QUESTION DID MATCH THE KIA) (KIA) 7 of 12

1.

LOK Q# I (F/H) 67 I F

68 69 70 71 72 I F

73 F

74 F

75 F

2/11/2010 I

I

2.

LOD (1-5) 2 2

2 2

I X

3. Psychometric Flaws I

I X

I X

Watts Bar Nuclear Plant 2009-302

4. Job Content Flaws

5. Other

6.

7.

8.

U/E/S Explanation B

M The stem does not match all of the distractors. The stem ask the applicant to identify two components. TD AFW speed is not a component. (MODIFIED - REMOVE SPEED AS A COMPONENT)

(OK)

(OK)

Is there a correct answer? I could not locate a CC in your procedure.

The second half of the distractors is week. Rewrite.(4 TVA GUYS STATED THAT IS "CC" AND "AC" IS USED AT THE PLANT - WILL PROVIDE INFORMATION AT M

S (OK)

N S/E Consider rewording the stem to read:

... which ONE of the following describes:

(1) why the sump pumps will be operated locally and (2) if.....

Remove "Operated locally" form A-D. (Explain why 1st part of C&D is E CHANGES TO THE QUESTION) (OK)

I X I B I U/E I Weak KIA match. Write the question to show that the applicant has a knowledge/understanding of the various limits. There is no evident what limit the applicant has to have knowledge of to answer this question. For the given condition, would you expect anyone else to make decisions about authorizing/giving final decision to allow additional exposure to perform the job. (REWROTE QUESTION)

JK)

B S/E LOD. Consider revising question. (REVISED QUESTION) (OK)

B S

(OK)

N S

(OK) 8 of 12 Watts Bar Nuclear Plant 2009-302

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

8.

Q#

1. /

Back-B/M/N U/E/S Explanation 67 F

2 X

M The stem does not match all of the distractors. The stem ask the applicant to identify two components. TD AFW speed is not a component. (MODIFIED - REMOVE SPEED AS A COMPONENT) 68 H

2 B

S 69 F

2 N

U/E Is there a correct answer? I could not locate a CC in your procedure.

The second half of the distractors is week. Rewrite.(4 TVA GUYS STATED THAT IS "CC" AND "AC" IS USED AT THE PLANT - WILL PROVIDE INFORMATION AT S 70 H

2 M

S (OK) 71 H

2 X

X N

S/E Consider rewording the stem to read:

... which ONE of the following describes:

(1) why the sump pumps will be operated locally and (2) if.....

Remove "Operated locally" form A-D. (Explain why 1 st part of C&D is CHANGES TO THE 72 F

2 X

B U/E Weak KIA match. Write the question to show that the applicant has a knowledge/understanding of the various limits. There is no evident what limit the applicant has to have knowledge of to answer this question. For the given condition, would you expect anyone else to make decisions about authorizing/giving final decision to allow additional exposure to perform the job. (REWROTE QUESTION) 73 F

B S/E LOD. Consider revising question. (REVISED QUESTION) (OK) 74 F

2 B

S (OK) 75 F

2 N

S (OK) 2/11/2010 8 of 12

Watts Bar Nuclear Plant 2009-302

1. I 2.

LOK LOD Q# I (FtH)

(1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

I

7.

8.

Explanation u/EtS Consider rewriting the stem. Identify the annunciators that are lit and 76 I H

I I

X I

I N

I E

I have the applicant determine how the system should respond and have them identify what procedure to select. You can also ask why the procedure is selected. REWORDED STEM IN OFFICE (OK) 77 X

X N

E I Check grammar in the stem and the distractors. (had existed for but...) (MADE TO STEM -MUCH MOR E READIBLE) (OK)

Check grammar in the stem. Distractor A is not plausible and 78 X

X B

UtE I distractor 0 C may be a correct answer. (CHANGED DISTRACTOR C) (OK)

Consider rewriting the stem. If stem is rewritten, write distractors to match. Example:

"In accordance with Technical Specification BASES, based on the given plant conditions which ONE of the following identifies (1 L WhX the 125V DC Vital Battern Channel" In 79 I F

I I

X I

I I

INOPERAB E, ND (2) how long Battery ! is deSi?ned to be 2

M E

I able to maintain greater than the minimum termina voltage for the given plant conditions?"

Delete the "Declare Battery Channel II INOPERABLE because of... " statements from all distractors; the WOOTF already states that the battery is inoperable.

ED INFORMATION IN STEM AND DISTRACTORS) (OK)

Check grammar in the stem. (CORRECTED GRAMMAR) (OK)

Stem is confusing. Explain KIA match.

Not SRO-Ievel knowledge; first part of question is systems knowled~, second part of question can be eliminated by knowing CA-O.O entry conditions (major EOP entry conditions RO-Ievel knowledge).

81 I I

I I

Four non-plausible distractors; it is common knowledge that F

2 X

I X I X I N I E I narrow range S/G levels go offscale low on every trip from 100% power; it is common knowled~e that narrow range S/G level instrumentation is used throug out the EOPs/post-accident conditions.

Question is UNSAT based on above discussions.

(REWROTE STEM - EXPLAINED KIA MATCH) (OK) 2/11/2010 9 of 12 Watts Bar Nuclear Plant 2009-302

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

8.

Q#

LOK LOD (F/H)

(1-5)

Q= SRO B/M/N U/E/S Explanation KIA Only Consider rewriting the stem. Identify the annunciators that are lit and 76 H

X N

E have the applicant determine how the system should respond and have them identify what procedure to select. You can also ask why the procedure is selected. REWORDED STEM IN OFFICE (OK) 77 X

X N

E Check grammar in the stem and the distractors. (had existed for but...) (MADE TO STEM -MUCH MOR E READIBLE) (OK)

Check grammar in the stem. Distractor A is not plausible and 78 X

X B

U/E distractor 0 C may be a correct answer. (CHANGED DISTRACTOR C) (OK)

Consider rewriting the stem. If stem is rewritten, write distractors to match. Example:

"In accordance with Technical Specification BASES, based on the given plant conditions which ONE of the following identifies (1l why the 125V DC Vital Batte?! Channel II in INOPERAB E, AND (2) how long Battery! is desi~ned to be 79 F

2 X

M E

able to maintain greater than the minimum termina voltage for the given plant conditions?"

Delete the "Declare Battery Channell! INOPERABLE because of... " statements from all distractors; the WOOTF already states that the battery is inoperable.

(CHANGED INFORMATION IN STEM AND DISTRACTORS) (OK) 80 H

3 N

S Check grammar in the stem. (CORRECTED GRAMMAR) (OK)

Stem is confusing. Explain KIA match.

Not SRO-Ievel knowledge; first part of question is systems knowled1f' second part of question can be eliminated by knowing CA-O.O entry conditions (major EOP entry conditions RO-Ievel knowledge).

Four non-plausible distractors; it is common knowledge that 81 F

2 X

X X

N E

narrow range S/G levels go offscale low on every trip from 100% power; it is common knowled~e that narrow range S/G level instrumentation is used throug out the EOPs/post-accident conditions.

Question is UNSAT based on above discussions.

(REWROTE STEM - EXPLAINED KIA MATCH) (OK) 2/11/2010 9 of 12

Watts Bar Nuclear Plant 2009-302 Explanation

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

I

7.

8.

1. I 2.

LOK LOD Q# I (F/H)

(1-5)

U/EIS Explain why performing a risk assessment is plausible as used in 82 I H

3 I

X I

N I S/E I distractors C and D. (CHANGED WORDING IN THE STEM AND THE DISTRACTORS ) (OK)

Stem says that there is an impact. The answer Band distractor 0 83 I F

2 X I I X I

N I u/E I state "no impact." Rewrite stem to match distractor/answer. Make sure A and C are not correct. (RE WORDED STEM AND CORRECTED DISTRACTOR ) (OK).

85 I F

2 X I N

U I Distractors A is also correct based on 20.f.RNO of ES-O.2 (WROTE NEW QUESTION) (OK).

Reword the stem such that it ask for the bases as identified in the KIA. Based on the current plant conditions, which LCO should be 86 I X

X I X I N

U I entered, identify the actions that should be taken and the bases for taking the actions. Make sure that there is a direct tie to bases.

(QUESTION WAS DETERMINED TO BE SAT, ONLY MINOR l...(Q!Sh There appear to be two correct answers. Both A and B. If your can not established pressure control with the PORV, you are required to 87 I H

2 X I U I implement ECA-3.3 (MADE MINOR CHANGES TO THE QUESTION - AND DECIDED THAT QUESTION SHOULD NOT BE liQ!:Q Stem needs to be re worded (check gramma). Consider using the following distractors:

A. PDT-30-43 is required to be placed in the TRIPPED position; Subsequent testing of PDT-30-44 will still allow a valid automatic Containment Spray actuation to occur B. PDT-30-43 is required to be placed in the TRIPPED position; 88 I H

X I I X E

Subsequent testing of PDT-30-44 will prevent a valid automatic I Containment Spray actuation from occurring.

C. PDT-30-43 is required to be placed in the BYPASS position; Subsequent testing of PDT-30-44 will still allow a valid automatic Containment Spray actuation to occur D. PDT-30-43 is required to be placed in the BYPASS position; Subsequent testing of PDT-30-44 will prevent a valid automatic Containment Spray actuation from occurring. (MADE MODIFICATIONS) (OK) 2/11/2010 10 of 12

1.

LOK Q#

(F/H) 82 H

83 F

85 F

86 87 H

88 H

2/11/2010 3

2 X

2 X

2 X

Watts Bar Nuclear Plant 2009-302

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

B/M/N U/E/S N

S/E N

U/E X

N U

X X

N U

X U

X E

8.

Explanation Explain why performing a risk assessment is plausible as used in distractors C and D. (CHANGED WORDING IN THE STEM AND THE DISTRACTORS ) (OK)

Stem says that there is an impact. The answer Band distractor D state "no impact." Rewrite stem to match distractor/answer. Make sure A and C are not correct. (RE WORDED STEM AND CORRECTED DISTRACTOR ) (OK).

Distractors A is also correct based on 20.f.RNO of ES-O.2 (WROTE NEW QUESTION) (OK).

Reword the stem such that it ask for the bases as identified in the KIA. Based on the current plant conditions, which LCO should be entered, identify the actions that should be taken and the bases for taking the actions. Make sure that there is a direct tie to bases.

(QUESTION WAS DETERMINED TO BE SAT, ONLY MINOR CHANGES WERE MADE) (OK).

There appear to be two correct answers. Both A and B. If your can not established pressure control with the PORV, you are required to implement ECA-3.3 (MADE MINOR CHANGES TO THE QUESTION - AND DECIDED THAT QUESTION SHOULD NOT BE Stem needs to be re worded (check gramma). Consider using the following distractors:

A. PDT-30-43 is required to be placed in the TRIPPED position; Subsequent testing of PDT-30-44 will still allow a valid automatic Containment Spray actuation to occur B. PDT-30-43 is required to be placed in the TRIPPED position; Subsequent testing of PDT-30-44 will prevent a valid automatic Containment Spray actuation from occurring.

C. PDT-30-43 is required to be placed in the BYPASS position; Subsequent testing of PDT-30-44 will still allow a valid automatic Containment Spray actuation to occur D. PDT-30-43 is required to be placed in the BYPASS position; Subsequent testing of PDT-30-44 will prevent a valid automatic Containment Spray actuation from occurring. (MADE MODIFICATIONS) (OK) 10 of 12

Watts Bar Nuclear Plant 2009-302

1. I 2.

LOK LOD Q# I (F/H)

(1-S)

3. Psychometric Flaws

4. Job Content Flaws

s. Other U/E/S

6.

I

7.

8.

Explanation 89 X

B U

DIRECTION OF THE SRO. MADE MINOR CHANGES TO THE STEM l (OK)

It appears that the question can be answered with system knowledge only and the fact that the RO would know that LCO 3.6.12 is not applicable for the current mode. Suggest testing the applicant 90 I H

2 I X I N

U I knowledge of which surveillance test is allowed to be conducted ["B" Phase test] and any associated action statements that are required to conduct the surveillance test. [Le., link question to Tech Specs versus procedure selection.] (WROTE NEW QUESTIONS) (OK) 92 F

1 X

X N

U ILU GUrrl:ll.;L, GUlIlrUI, UI rIlIUYCUI:I U 11:1 GU"<:>I:I'-IU"'"(;".....,

IIVI,...UL; CHANGES TO DISTRACTORS) (OK) SHOULD NOT HAVE BE A U. TAKE A LOOK AT THIS QUESTION Distractors poorly written. Unnecessary words. Consider re-writing the stem. Ask for status of the release and what procedure should be implemented based on the given conditions. Please identify the 93 I H

2 X I X I N I U/E I alarm number. Need to determine if there are any automatic actions associated with the condition. There may be two correct answers, C and D. (MADE CHANGES TO DISTRACTORS; DID NOT HAVE TWO CORRECT ANSWERS) SHOULD NOT HAVE BEEN A u/E (OK)

It appears that this question can be answered with system knowledge only. If a support system of the operating train is declared 94 I H

2 I X I M I U I inoperable, would you not expect the RO to know that work in progress should be stopped to evaluate conditions? (CONVENSED US THAT THIS WAS AN SRO ONLY QUESTION. SHOULD NOT HAVE BEEN IDENTIFIED AS UNSATl (OK)

(OK) 96 I H

3 I

X I

I M I E/S I Question is OK. Consider rewording the stem (IMPROVED THE STEM) (OK) 2/11/2010 11 of 12 Watts Bar Nuclear Plant 2009-302

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

8.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F emd. P rt 'iliJi.~)U/~

Explanation Focus Dist.

a la Link Inu la units ward KIA Only I>

r

""lidFoJ""dd;j:"

'J:~Cd:"i:

lilt J~"ij~"

i:,~.. " Ii I owilli:

Not SRO only question. Appears that question can be answered with system only knowledge. (DECIDET TO ACCEPT QUESTION 89 F

2 X

8 U

8ASED ON THE FACT THAT ACTIONS ARE ONLY TAKEN AT THE DIRECTION OF THE SRO. MADE MINOR CHANGES TO THE STEM l10K)

It appears that the question can be answered with system knowledge only and the fact that the RO would know that LCO 3.6.12 is not applicable for the current mode. Suggest testing the applicant 90 H

2 X

N U

knowledge of which surveillance test is allowed to be conducted ["8" Phase test] and any associated action statements that are required to conduct the surveillance test. [Le., link question to Tech Specs versus procedure selection.] (WROTE NEW QUESTIONS) (OK) 91 H

2 N

S (MADE MINOR CHANGES TO THE STEM) (OK)

LOD. Could not locate information which indicated that release would auto terminate. Can not see how this is a KIA matcl,. Explain 92 F

1 X

X N

U how making a notification meets the requirement of using procedures to correct, control, or mitigate the consequences..... ? (MADE CHANGES TO DISTRACTORS l (OK) SHOULD NOT HAVE BEEN A U. TAKE A LOOK AT THIS QUESTION Distractors poorly written. Unnecessary words. Consider re-writing the stem. Ask for status of the release and what procedure should be implemented based on the given conditions. Please identify the 93 H

2 X

X N

U/E alarm number. Need to determine if there are any automatic actions associated with the condition. There may be two correct answers, C and D. (MADE CHANGES TO DISTRACTORS; DID NOT HAVE TWO CORRECT ANSWERS) SHOULD NOT HAVE BEEN A U/E (OK)

It appears that this question can be answered with system knowledge only. If a support system of the operating train is declared 94 H

2 X

M U

inoperable, would you not expect the RO to know that work in progress should be stopped to evaluate conditions? (CONVENSED US THAT THIS WAS AN SRO ONLY QUESTION. SHOULD NOT HAVE BEEN IDENTIFIED AS UNSATl (OK) 95 H

2 M

S

(~

96 H

3 X

M E/S Question is OK. Consider rewording the stem (IMPROVED THE STEM) (OK) 2/11/2010 11 of 12

Watts Bar Nuclear Plant 2009-302 1, I 2, LOK LOD Q# I (F/H)

(1-5) 3, Psychometric Flaws 4, Job Content Flaws 5, Other 6,

I 7,

8, U/E/S Explanation Who is responsible lor performing this procedure? I am not sure this 97 I H

2 I

oX I

X I X I M

I UlE I is SRO only, What must be done if O-RM is inoperable - is this not common knowledge? (CONVENSED US THAT IS SRO - SHOULD BE AN "E") (OK)

Parts of distractors C and D do not appear to be plausible, It appears that the stem is cueing that correct answer should have include a 98 I H

2 I

oX I

I oX I

N U

I time requirement. On two distractors have time limitations, Who is responsible for performing (CHANGED STEM AND DISTRACTORS)

(OK)

In stem (1) identify maximum rate of depressurization, Reword distractors to match stem, This appears to be three part question, 99 I I

oX I

X M I E

I Distractors should reflect questions asked, Use 15% instead of 10%,

(MADE MINOR CHANGES TO THE STEM AND CHANGED NUMBERS IN DISTRACTORS) (OK) 2/11/2010 12 of 12

1.

2.

LOK LOD Q#

(F/H)

(1-5) 97 H

2 98 H

2 99 100 F

2/11/2010

3. Psychometric Flaws X

X X

X Watts Bar Nuclear Plant 2009-302

4. Job Content Flaws

5. Other

6.

7.

U/E/S X

M U/E N

U M

E N

S/E

8.

Explanation Who is responsible for performing this procedure? I am not sure this is SRO only. What must be done if O-RM is inoperable - is this not common knowledge? (CONVENSED US THAT IS SRO - SHOULD BE AN '"E") (OK)

Parts of distractors C and D do not appear to be plausible. It appears that the stem is cueing that correct answer should have include a time requirement. On two distractors have time limitations. Who is responsible for performing (CHANGED STEM AND DISTRACTORS)

(OK)

In stem (1) identify maximum rate of depressurization. Reword distractors to match stem. This appears to be three part question.

Distractors should reflect questions asked. Use 15% instead of 10%.

(MADE MINOR CHANGES TO THE STEM AND CHANGED NUMBERS IN DISTRACTORS) (OK)

Re-write stem. Stem is confusing (ENHANCED STEM) (OK) 12 of 12

ES-403 Written Examination Grading Quality Checklist Form ES-403-1 Facility: We:J.,!fs Bd" ('"

Date of Exam: 12.//7/.2M?Exam Level: Rq7J'SROV1 Initials Item Description a

b c

1.

Clean answer sheets copied before grading 10 JlIA L~

2.

Answer key changes and question deletions justified

(

"'/A and documented NjA

3.

Applicants' scores checked for addition errors Cj5 11-(reviewers spot check> 25% of examinations)

(

\\

?

4.

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

5.

All other failing examinations checked to ensure that grades P5

( III are justified

6.

Performance on missed questions checked for training

~

deficiencies and wording problems; evaluate validity t /ci of questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader f{t.,,,en..J ClIo"'" If.-iaW LXIV

b. Facility Reviewer(*)

)//~

c. NRC Chief Examiner (*) ~'/."A L.-:,. iff

/ /~ht)Ll)

I

d. NRC Supervisor (*)

/..U.UAlJJ-.Wu,IJ("a /~"""

.'/"'/Z4'"

/ 'f..-/

(*)

The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-403, Page 6 of 6 ES-403 Written Examination Grading Quality Checklist Form ES-403-1 raGIIIlY*

W~.Jfs Ba-r' Date of Exam: /2//7/2~Exam Level: RO[2J SRo0 Initials Item Description a

b c

1.

Clean answer sheets copied before grading 1C15

1. /4 L~

2.

Answer key changes and question deletions justified

(

and documented

"'/A NjA

3.

Applicants' scores checked for addition errors Cj5

( lil (reviewers spot check> 25% of examinations)

\\

4.

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

5.

All other failing examinations checked to ensure that grades 05

)

1;1-are justified

(

6.

Performance on missed questions checked for training

~

deficiencies and wording problems; evaluate validity t /ci of questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader

~"~m.sCM? Ii-~

/-r--fD

b. Facility Reviewer(*)

JI/A

c. NRC Chief Examiner (*) dJ..kz~::!::,. W

//~h~Lb 7 ;

d. NRC Supervisor (*)

tlJ.iMlJ.L v.\\Alit>a~~ lJ.1 /{J;J;;;Jf/f/. '"

tllft*!2(1L~

/ 'f..--/

(*)

The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-403, Page 6 of 6