ML17212B168

Exam Admin Items (Immediate Release) - ADAMS 2D

ML17212B168
Person / Time
Site:	Browns Ferry
Issue date:	07/31/2017
From:	NRC/RGN-II
To:
References
Download: ML17212B168 (57)

Text

ES-201 Examination Preparation Checklist Form ES-201 -1 FaciIity: gOA)M.S Date of Examination: At j Zl l Developed by: Written: Facility NRC /1 Operating Facility NRC Target Task Description (Reference) Exarrs Date Initials

-180 1. Examination administration date confirmed (Cia; C.2.a and b) I019_ It,

-150 2. NRC examiners and facility contact assigned (C.1 .d; C.2.e) /0 f/,

-150 3. Facility contact briefed on security and other requirements (C.2.c) 1 -//

-150 4. Corporate notification letter sent (C.2.d) 10 -.7-J6 i.

[-120] 5. Reference material due (C.1.e; C.3.c; Attachment 3) /O3)I/

{-90} 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, ES-401-i/2, ES-401N-112, ES-401-3, ES-401N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; C.3.d) (0 3/,fl,, ?K

(-85] 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e) /( il,6

{-60} 8. Proposed examinations (including written, walk-through JPM5, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, ES-401N-6, and any Form ES-201-2, ES-201-3, ES-3d-i, orES-301-2 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

-45 9. Written exam and operating test reviews completed. (C.3.f) - /1 i7

-30 10. Preliminary license applications (NRC Form 398s) due (Cli: C.2.gS-2)

-21 ii. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-21 12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g)  ?/oi7 3- 21-i

-14 13. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)

-14 14. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h) 7j

-7 15. Facility licensee management queried regarding the licensees views on the examination. (C.2j) 3to /7

-7 16. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications I eligibility; and examination approval and waiver letters sent (C.2.i; ;9/

Attachment 5; ES-202, C.2.e; ES-204)

-7 17. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k) 4. 24- iT

-7 18. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i) #fO IT 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 onlyJ {Does not apply} to examinations prepared by the NRC.

ES-201, Page 25 of 28

ES-201 Examination Outline Quality Checklist Form ES-201 -2 Facility: Browns Ferry Nuclear Station Date of Examination: 4/10/2017

. Initials Item Task Description b c#

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES4CI N. ,4 ?ii.

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

.. Section D.1 of ES-401 or ES-401N and whether all K/A categories are appropriately sampled.

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. 4 ,4 73L N

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. 4

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

-J S transients.

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

u mix of applicants in accordance with the expected crew composition and rotation schedule NJ ,

L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the 7 T applicants audit test(s), and that scenarios will not be repeated on subsequent days.

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

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

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

A (2) task repetition from the last two NRC examinations is within the limits specified on the form L (3) no tasks are duplicated from the applicants audit test(s) fr1 K (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 T the form.

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

o (1) the tasks are distributed among the topics as specified on the form 4

U (2) at least one task is new or significantly modified G (3) no more than one task is repeated from the last two NRC licensing examinations H

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. ,L I

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are coveted in the appropriate exam sections. f 4 G ft E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

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

R d. Check for duplication and overlap among exam sections. .4 1L L e. Check the entire exam for balance of coverage. l

f. Assess whether the exam fits the appropriate job level (RO or SRO). 4 ;c Date

a. Author Michael Barton / c4/V 5-29,7

b. Facility Reviewer f) Keith Nichols / 5-. /7 -

c. NRC Chief Examiner (#) IL° 4-4-17

d. NRC Supervisor E1_tt.i._k. (iAfLii-

/ iu.4%f LIf.Ct/

Note: # Independent NRC reviewer initial items in Column crn; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines.

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

Date of Examination: 4 1& 17-Initials Item Task Description b*

a c#

I a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401 N. ØJfc M 4/4.

ed in accordance with

b. Assess whether the outline was systematically and randomly prepar D. 1 of ES-401 or ES-401 N and whether all K/A categories are appropriately sampled.

Section T

or generic topics. tiA t,4 Assess whether the outline over-emphasizes any systems, evolutions, c.

N K/A statements are appropriate. Nk NM

d. Assess whether the justifications for deselected or rejected cover the required number of

2. a. Using Form ES-301-5, verify that the proposed scenario sets AJA A.M normal evolutions, instrument and component failures, technical specifications, and major S transients.

to test the projected number and M b. Assess whether there are enough scenario sets (and spares) ance with the expect ed crew composition and rotation schedule u mix of applicants in accord FsS,4 iJ4 can be tested using at L without compromising exam integrity, and ensure that each applicant are duplicated from the A least one new or significantly modified scenario, that no scenarios d on subsequent days.

T applicants audit test(s), and that scenarios will not be repeate

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and ,Jk Appendix D. I quantitative criteria specified on Form ES-301-4 and described in on Form ES-301-2:

3. a. Verify that the systems walk-through outline meets the criteria specified outline(s) contain(s) the required number of control room and in-plant tasks distributed (1) the W among the safety functions as specified on the form A (2) task repetition from the last two NRC examinations is within the limits specified on the form ,4i I

L (3) no tasks are duplicated from the applicants audit test(s) specified on the form K (4) the number of new or modified tasks meets or exceeds the minimums the numbe r of alternate path, low-power, emergency, and RCA tasks meet the criteria on (5)

I the form.

H on Form ES-301-1:

b. Verify that the administrative outline meets the criteria specified R

(1) the tasks are distributed among the topics as specified on the form (. . 2 (2) at least one task is new or significantly modified 74 U licensing examinations G (3) no more than one task is repeated from the last two NRC H number and mix of

c. Determine if there are enough different outlines to test the projected no items are duplicated on subseq uent days.

applicants and ensure that insights) are covered in the

4. a. Assess whether plant-specific priorities (including PRA and IPE appropriate exam sections.

is appropriate.

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling priorities) are at least 2.5. / , t1

c. Ensure that K/A importance ratings (except for plant-specific R d. Check for duplication and overlap among exam sections.

A L e. Check the entire exam for balance of coverage. $4 (RO or SRO).

f. Assess whether the exam fits the appropriate job level Printed NemeSure.-/ 7 Date 4i?-f7

a. Author Mirirtci Ek/-- g/-T

b. Facility Reviewer

(*) K.;$ tV/ .o)r ,/a

c. NRC Chief Examiner (#) WW(t40 LI/I )i7

d. NRC Supervisor vu chief examiner concurrence required.

Note: # Independent NRC reviewer initial items in Column c; Not applicable for NRC-prepared examination outlines.

cTPt1 ote

- ( 13 FrzM E5- 7-Di -2 doames ES-201, Page 26 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 04-10-17 through 04-24-17 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).

Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 04-10-17 through 04-24-17. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

1. Pre-Examlnation for the week(s) of 04-10-17 through 04-24-17 as of I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled persons who have not been authorized by the the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these examination administratio n, except as specifically noted below and authorized by the NRC (e.g., acting licensing examinations from this date until completion of provide direct or indirect feedback).

as a simulator booth operator or communicator is acceptable if the individual does not select the training content or and understand that violation in the facility licensees procedures)

Furthermore, I am aware of the physical security measures and requirements (as documented or the facility licensee. I will of the examinations and/or an enforcement action against me of the conditions of this agreement may result in cancellation may have been compromised.

security immediately report to facility management or the NRC chief examiner any indications or suggestions that examination

2. Post-Examination the NRC licensing examinations administered during the To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning of examination administration, I did not week(s) of 04-10-17 through 04-24-17. From the date thatl entered into this security agreement until the completion these licensing examinations , except as specifically noted below instruct, evaluate, or provide performance feedback to those applicants who were administered and authorized by the NRC.

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

1. Pre-Examj nation I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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 schedule to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).

Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation I

of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. will examiner any indications or suggestions that examination security may have been compromised .

immediately report to facility management or the NRC chief

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 04-10-17 through 04-24-17. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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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 04-10-17 through 04-24-17 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).

Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 04-10-17 through 04-24-17. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201 a 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 04-10-17 through 04-24-17 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).

Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 04-10-17 through 04-24-17. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201 Examination Security Agreement Form E-2O1-3

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).

Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 04-10-17 through 04-24-17. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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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 04-10-17 through 04-24-17 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).

Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 04-10-17 through 04-24-17. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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Form ES-201-3

[5-2 C) I Examination Security Agreement

1. P re-ExamInation I acknowledqe that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 as of to any persons who have not been authorized by the the date of my signature. I agree that I will not knowingly divulge any information about these examinations 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 it the individual does not select the training content or provide director indirect feedback).

Furthermore. I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation andlor an enforcement action against me or the facility licensee. I will of the conditions of this agreement may result in cancellation of the examinations irimediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised

2. Post-Examination during the To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered administratio n, I did not week(s) of 04-10-17 thro9_Q424I7. From the date that I entered into this security agreement until the completion of examination licensing examinations , except as specifically noted below instinct, evaluate, or provide performance feedback to those applicants who were administered these and authorized by the NRC.

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-1 7 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).

Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 04-10-17 through 04-24-17. 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.

PRINT NAME JOB TITLE / RESPONSIBILITY SIGNATURE(1) DATE SIGNATURE (2) DA E NOTE NOTES

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Browns Ferry Nuclear Station Date of Examination: 4/10/2017 Operating Test Number: 17-03

. . Initials

1. General Criteria b c#

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

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.) 4 $1C

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.

4

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 criteria (e.g., item ,4 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- /( 4 3ol4andacopyisattached. ZI..

Prin,Na e / S n ture Date

a. Author Michael Barton / J2i7 Z//

b. Facility Reviewer(*) Keith Nichols / /'

c. NRC Chief Examiner(#) tt 44%

d. NRC Supervisor (c_ LI/ 5/, 7 NOTE: The facility signature is not applicable for NRC-developed tests.

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

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Date of Examination: 4 -/- /7 Operating Test Number: t7 03

. Initials

1. General Criteria b* c#

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

/, y

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.)  % T*t

d. Overlap with the written examination and between different parts of the operating test is within t%i3 4 acceptable limits.

e. It appears that the operating test will differentiate between competent and less-than-competent A .//j,(

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:

4 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 flit 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 ,4J1 ES-301-4 and a copy is attached.

j4 S4}/

Printed Name Si atur Date

a. Author Mi i 17

b. Facility Reviewer(*) /(Jj6 AL .-

c. NRC Chief Examiner (#) 4 1d1

d. NRC supervisor (

f ii (i 7 NOTE:

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

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

-301-3 tD Jfl,Y7 (-tL

-, 1-ES-301, Page 24 of 27

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: BFNS Date of Exam: 4/10/17 Scenario Numbers: 2 I 3 ( 5! 6 Operating Test No.: 17-03 QUALITATIVE ATTRIBUTES Initials b c#

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

2. The scenarios consist mostly of related events. / ?L

3. Each event description consists of a the point in the scenario when it is to be initiated J a

a the malfunction(s) or conditions that are entered to initiate the event the symptoms/cues that will be visible to the crew f,% ,%

. the expected operator actions (by shift position)

. the event termination point (if applicable) -

4. The events ate valid with regard to physics and thermodynamics. ./ PC

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

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

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

Cues are given.

4 ,(

7. The simulator modeling is not altered. 4  %

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

deficiencies or deviations from the referenced plant have been evaluated to ensure that functional (,t fidelity is maintained while wnning the planned scenarios.

9. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301.

,ç/

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

/ I

11. The scenario set provides the opportunity for each applicant to be evaluated in each of the applicable rating factors. (Competency Rating factors as described on forms ES-303-1 and ES.303-3.)

12. Each applicant will be significantly involved in the minimum number of transients and events specified ,/

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

13. The level of difficulty is appropriate to support licensing decisions for each crew position. /4 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes --

213/516

1. Malfunctions after EOP entry (1-2) 1 I 2 I 2 / 2 4

2. Abnormal events (2-4) 2 / 2 / 3 / 2 ( C

3. Major transients (12) 1 / 1 / 1 / 2 si

4. EOPs entered/requiring substantive actions (12) 2 / 2 / 2 / 2 )

5. EOP contingencies requiring substantive actions (0-2) 1 I 0 / 1 / 1

. (.

6. EOP based Critical tasks (23) 2 I 2 I 2 / 2 NOTE: The facility signature is not applicable for NRC-developed tests.

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Browns F4PP Date of Exam: April 10, 2017 Operating Test No.: ILT 1703 Scenarios P E 2 3 6 5 T M CREW CREW CREW CREW 0 c POSITION POSITION POSITION POSITION T A T S A B S A B S A B S A B A M R T 0 R T 0 R T 0 R T 0 L U E 0 C P 0 C P 0 C P 0 C P R I U r RX 2 2 5 3 1 NOR 1 1 1 SRO-I

1. 1 Bennett ,

12 4 I/C 46 5,8 6,8,9 r MAJ 7 7 7 3 2 TS 35 2 2 RX 2 5 2 1 NOR 1 1 1 SRO-I

1. 2 Ultlsap I/C 4,6 8 4 MAJ 7 7 2 2 TS 3,5 2 2 RX 2 .________ 5 2 1 SRO-t NOR 1 1 1

1. 3 Rose I/C 4,6 8 4 MAJ 7 7 2 2 TS 3,5 2 2 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 (BOPY 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 semen in the SOP 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 Appendie 0. (( Reactivity and normal evolutions maybe replaced with additional instrument or Component maffunctions on a 1-for-i basis.

3 Whenever practical, both instrument and component malfunctions should be included, oniy those that require veritable actions that provide insight to the applicants competence count toward the minimum requirements specifed for the applicants license level in the right-hand columns,

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Browns FXPP Date_of_Exam: April_10,_2017 Operating Test_No.:_ILT_1703 Scenarios P E 2 3 6 5 T M CREW CREW CREW CREW 0 c POSITION POSITION POSITION POSITION T I A T S A B S A B S A B S A B A M R T 0 R T 0 R T 0 R T 0 L U E 0 C P 0 C P 0 C P 0 C P R I U RX 2 2 2 1 NOR 1 1 1 SRO-I

1. 4 Spears I/C 4, 5 3.4,6,8 10 4 8

MAJ 7 7 7 3 2 TS 2,4 2 2 r RX 2 2 2 1 NOR 1 2 1 SRO-I

1. 5 Yarbrough I/C 4, 5 3,4,6,8 10 4 MA] 7 7 7 3 2 TS 2,4 2 2 pJ( 0 0 NOR 1 1 1 SRO-U

1. 1 Alsup I/C C 3,4 3.4.6,8 6 2 MAJ 5 7 2 1 TS 2,4 2 2 RX 2 1 0 NOR 1 1 2 1 SRO-U

1. 2 Cobb 3 6, 8, 7 2 I/C 359 7 7 2 1 TS 4,6 2 2 e RX 2 1 0 NOR 1 1 2 1 SRO-U

1. 3 Humphries 3 6, 8, 7 2 I/C 3,5,9 r MAJ 7 7 2 1 TS 4.6 2 2 RX 2 1 0 NOR 1 1 2 1 SRO-U 3, 6, 8,

1. 4 KnIght ic 359 . 7 2 MAJ 7 7 2 1 IS 4,6 2 2 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/Cl malfunctions and one maior 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 0. () Reactivity and normal evolutions may be replaced with additional instrument or Component malfunctions on a 1-for-i basis.

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

ES3O1 Transient and Event Checklist Form ES-301-5 Facility: Browns F!1PP Date_of_Exam: April_10,_2017 Operating Test_No.:_ILT_1703 Scenarios P E 2 3 6 5 T M CREW CREW CREW CREW 0 c POSITION POSITION POSITION POSITION T I A T S A B S A B S A B S A B A M R T 0 R T 0 R T 0 R T 0 L U e 0 C P 0 C P 0 C P 0 C P R I U RX 0 0 NOR 1 1 2 1 SRO-U

1. 5 Lambert 6 2 I/C 4,6,7,8 3,9 MAJ . 5,9 7 3 1 TS  : 2,3 2 2 RX 0 0 NOR 1 1 2 1 SRO-U .

1. 6 Maye I/C 4,6,7,8 3,9 6 2 MAJ 111 59 7 3 1 TS i!.

2,3 2 2 RX 0 0 NOR 1 1 2 1 SRO-U

1. 7 Stephenson I/C 4,6,7,8 3,9 6 2 MAJ 5,9 7 3 1 TS 2,3 2 2 Check the applicant level and enter the operating tent number and Form ES-D-i 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 SRO5 must serve in both the SRO and the ATC positions, including at least two instrument or component (I/Cl 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 0.5 d) but must be significant per Section C.2.a of Appendix 0. rt Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.

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

ES-301 Competencies Checklist Form ES-301 -6 Facility: BEN Date of Examination: 4/10/2017 Operating Test No.: 17-03 APPLI CANTS RD El RO El RD El RD El SRO-l 1 RZ SRD-l 2 Ri SRD-l 3 [ SRO-I 4 [1 SRO-U El SRO-U El SRO-U El SRO-U El Competencies SCENARIO SCENARIO SCENARIO SCENARIO i+/-

2,1,3, 2,4,5, 2,38, 2,1,3, 2,4, 3,1,5, 2,1,3, 2,4, 3,1, 2,3, 2,1,3, 2,3,8,

+1 inerpreu iagnose I

4,9,7, 7 6 4,9,7, 5,7 7,6 4,9,7, 5,7 5,7, 4,5, 4,5,6, 6 5,6 5,6 5,6 6 8,7, 8,9,7 Events and Conditions 2,1,3, 2,4,5, 2,3,8, 2,1,3, 2,4, 3,1,5, 2,1,3, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, I !9I+k anu ,4 C ompy k 497 7 6 4,9,7, 5,7 7,6 4,9,7, 5,7 5,7, 4,5, 4,5,6, 6 6 87,87 UseProcedures(1)

N/A 2,3,8, N/A 2,4, 3.1,5. N/A 2,4, 3.1, 2,3, 2.1,3, 2.3,8, l 4 C perace ontro 6 5.7 7,6 5,7 5.7, 4,5, 4,5,6, 6 6 8,7, 8,9,7 Boards (2) 2.1,3, 1-10 2.3,8, 2.1,3, 1- 3,1.5, 2,1,3. 1- 3,1, 2,3, 2,1,3. 2.3,8,

+

C ommunlcate .

4,9.7, 6 4.97. 10 7,6 4,9,7. 10 5.7, 4,5, 4,5,6, 6 5.6 5,6 5,6 6 8,7. 8.9,7 and Interact 2,1,7 2,1,7 2,1,7 1,2,6 Demonstrate Supervisory Ability (3) 5,6 4 4 5,6 4 4 5,6 4 4 5,6 3,5 4 Comply With and Use Tech. Specs. (3) = = = = = = = = = = =

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303- I and ES-303-3.)

Facility: BEN Date of Examination: 4/10/2017 Operating Test No.: 17-03 APPLICANTS RO El RO El RO El RO El SRO-I El SRO-I El SRO-I El SRO-I El SRO-U 4 SRO-U 5 El SRO-U 6 El SRO-U 7 El Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1234123412341234 21,3, 2,4,5, 2,3,8, 2,1, 245, 3,1,5, 2,1, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, I

I rnerpre1, iagnose 4,9,7, 7 6 3,4, 7 7,6 3,4, 5,7 5,7, 4,5, 4,5,6, 6 5,6 9j 9,7, 6 8,7, 8,9,7 Events and Conditions I Ai+k ,4 2,1,3, 2,4,5, 2,3,8, 21, 2,4,5, 3,1,5, 2,1, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, C ompy IL I anu 4,9,7, 7 6 3,4, 7 7,6 3,4, 5,7 5,7, 4,5, 4,5,6, 6 5,6 6 8,7, 89,7 Use Procedures (1) .

N/A 2,3,8, N/A 2,4,5, 3,1,5, N/A 2,4, 3,1, 2,3, 2,1,3, 2,3,8, O perace onLrolI 6 7 7.6 5,7 5,7, 4,5, 45,6, 6 Boards(2) 2,1,3, 1-10 2,3,8, 2,1, 1-10 3,1,5, 2,1, 1- 3,1, 2,3, 2,1,3, 2,3,8, C ommunicaLe .

4,9,7, 6 3,4, 7,6 3,4, 10 5,7, 4.5, 4,5,6, 6 5,6 9 9,7, 6 8,7, 8,9,7 and Interact 2,1,7 2, 2, 1,2,6 Demonstrate Supervisory Ability (3) 5.6 4 4 5,6 4 4 5.6 4 4 5.6 3.5 4 C amply With and Use Tech. Specs. (3) = = = =

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Forv as3o-c

Facility: BFN Date of Examination: 4/10/2017 Operating Test No.: 17-03]

APPLICANTS RO El RO El RO El RO El SRO-I 5 SRO-I El SRO-I El SRO-I El SRO-U El SRO-U 1 El SRO-U 2 El SRO-U 3 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1234123412341234 I 4 4/ 2,1,3, 2,45. 2,3,8, 2,1, 2,4,5, 3,1,5. 2,1, 2,4, 3,1, 2,3, 2,1.3. 2.3,8, InLerpreu iagnose 4,9,7. 7 6 3,4, 7 7.6 3,4. 5,7 5,7, 4.5, 4,5,6. 6 5.6 9J 9,7, 6 8,7, 8.9,7 Events and Conditions I AI+ki an 2,1,3, 2,4,5, 2,3,8, 2,1, 2,4,5, 3,1,5, 2,1, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, C ompy ,.

4,9,7, 7 6 3,4, 7 7,6 3,4, 5,7 5,7, 4,5, 4,5,6, 6 5,6 9j 9,7, 6 8,7, 8,9,7 Use Procedures (1)

I N/A 2,3,8, N/A 2,4,5, 3,1,5, N/A 2,4, 3,1, 2,3, 2,1,3, 2,3,8, O perace ontroi 4 6 7 7,6 5,7 5,7, 4,5, 4,5,6, 6 68,7,87 Boards(2) 2,1,3, 1-/0 2,3,8, 2,1. 1-10 3,1,5. 2,1, 1- 3,1, 2,3, 2,1,3, 2,3,8, C ommunica1e .

4,9,7, 6 3.4. 7.6 3,4, 10 5.7, 4,5, 4,5,6, 6 5.6 9J 9 6 8,7, 8,9,7 and Interact 2,1,7 2, 7,1, 1.2.6 Demonstrate Supervisory Ability (3) 5,6 4 4 5,6 4 4 5,6 4 4 5,6 3,5 4 Comply VVith and Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RD.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Foryw S4Q

EXAM SmnPLE IAN ouijtY Form ES-201-2 ES-201 Examination Outline Quality Checklist Facility:

t3Ro,jAJ5

/,j*y Date of Examination:

,%nRit Initials Task Description Item

1. a. Verifythatthe outline(s)fit(s)the appropriate model, in accordance with ES-401 or ES-40 1N.

7 7.

and randomly prepared in accordance with :t R b. Assess whether the outline was systematically all K/A categories are appropriately sampled. /

1 or ES-40 1N and whethe r Section D.1 of ES-40 es any systems, evolutions, or generic topics.

c. Assess whether the outline over-emphasiz lected or rejected K/A statements are approp riate. 4 Z_

d. Assess whether the justifications for dese r of ed scenario sets cover the required numbe

2. a. Using Form ES-301-5, verify that the propos s, technic al specifi cations , and major nt failure normal evolutions, instrument and compone S transients.

number and ario sets (and spares) to test the projected M b. Assess whether there are enough scen crew compo sition and rotation schedule ce with the expect ed mix of applicants in accordan using at u ensure that each applicant can be tested L without compromising exam integrity, and scen arios are duplic ated from the io, that no A least one new or significantly modified scenar repe ated on subsequent days.

and that scen arios will not be T applicants audit test(s),

tive and r the outline(s) conform(s) with the qualita

c. To the extent possible, assess whethe and desc ribed in Appen dix D.

ES-30 1-4 quantitative criteria specified on Form 1-2:

meets the criteria specified on Form ES-30

3. a. Verify thatthe systems walk-through outline l room and in-plan t tasks distrib uted number of contro (1) the outline(s) contain(s) the required form ns as specifi ed on the among the safety functio the form W examinations is within the limits specified on A (2) task repetition from the last two NRC test( s) nts audit L (3) no tasks are duplicated from the applica or exceeds the minimums specified on the form (4) the number of new or modified tasks meets on K emergency, and RCA tasks meet the criteria (5) the number of alternate path, low-power, I the form.

1-1:

H s the criteria specified on Form ES-30 R b. Verity that the administrative outline meet as specifi ed on the form (1) the tasks are distrib uted amo ng the topics modified (2) at least one task is new or significantly u the last two NRC licensing examinations (3) no more than one task is repe ated from G mix of outlines to test the projected number and H c. Determine if there are enough different subs eque nt days.

ated on applicants and ensure that no items are duplic (including PRA and IPE insights) are covere d in the ,.i :9iL.

4. a. Assess whether plant-specific priorities fIf ft appropriate exam sections.

and 55.45 sampling is appropriate.

b. Assess whether the 10 CFR 55.41/43 E

at least 2.5. 4 N/4 1K_

(except for plant-specific priorities) are

c. Ensure that K/A importance ratings exam sections.

R d. Check for duplication and overlap among coverage.

7 /L;in 2_

L e. Check the entire exam for balance of job level (RO or SRO).

f. Assess whether the exam fits the appropriate am&S/L a Author 4c//4& PrN 4

(*) A Facility Reviewer 4-/5/

b.

c. NRC Chief Examiner (#) RL41JO CAak1-L,2 7 1W:&4O 3çflc,

d. NRC Supervisor ce required.

in Column c; chief examiner concurren Note: # Independent NRC reviewer initial items ation outlines.

Not applicable for NRC-prepared examin

ES-401, Rev. 10 BWR Examination Outline FE4OI-1 Facility ØgO4.IAJ PEI> Date of Exam: 14P,Q/L c RO K/A Category Points SRO-Only Points Tier Group K K KJKKKAAAAG A2 G* Total 1 2 3f4 5 6 1 2 3 4

• Total 1 3 3 4 4 3 20 4 3 7 1.

Emergency&

Abnormal Plant 2

12 I

1 N/A 1 1 N/A 1

7 2 1 3 10 Evolutions I

Tier Totals 4 5 5 f II 5 4 I

4 27 6 4 232232323 26 3 2 5 I 1 22

2. 0 2 1 3 2 1 1 1 1 2 1 1 1 1 1 12 Plant Systems Tier Totals 3 3 3 4 3 4 4 3 4 3 4 38 5 3 8

3. GenericKnowledgeandAbilities I 2 3 4 10 1 2 jT 3 I

4 7 Categories I I I 2Jj1j 2 J 3 J 2 - 3 -

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

,Øf., in each K/A category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the K/A is replaced by a K/A from another Tier 3 Category.)

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

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

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do

,yl1r not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution 7VvG in the group before selecting a second topic for any system or evolution.

,r31 5. Absent a plant-specific priority, only those K/As having an importance rating fIR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

,I. 6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.

7. *The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance 73i.. ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note

1. I 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 K/A numbers, descriptions, IRs, 17? and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnorm ant Evolutions Tier 1/Group 1 EIAPE # / Name I Safety Function K K K A A G* K/A Topic(s) IR #

1231 2 295001 Partial or Complete Loss of Forced RA2 02.

Core Flow Circulation / 1 & 4 -

fl- AAI. £ - 2.l. 2 295003 Partial or Complete Loss of AC I 6 R Al. o I 295004 Partial or Total Loss of DC Pwr I 6 R - k 3 .04 5 AA2.. 03 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1

- AA I. 0 R Ag3.o 295016 Control Room Abandonment /7 295018 Partial or Total Loss of CCW / 8 R AK 0

. - S A AZ. 02 295019 Partial or Total Loss of Inst. Air / 8 S A K3. 3 S AA% .02.

A K L .o 295021 Loss of Shutdown Cooling / 4 P. AJ< . Q.

295023 Refueling Acc / 8 g, - EAt. f 295024 High Drywell Pressure/5 R - 2.4. 50 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water R

Temp. / 5 295027 High Containment Temperature / 5 R

EA . 0 ..

295028 High Drywell Temperature / 5 2 .4-. I t 2. 2.44 295o3oLowSuppression Pool WtrLvl/5 295031 Reactor Low Water Level / 2 1<1. o S 2. 4. I 295037 SCRAM Condition Present and R E J41.

Reactor Power Above APRM Downscale or Unknown / 1 R - E 1(2.0 g 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site I 8 R R - 2. 4. 30 700000GeneratorVoltageand ElectricGrid ft s AAZo7 Disturbances / 6 K/A Category Totals: 1J14fj Group Point Total: = 20/7 sRo 4:;

ES-401, Page 34 of 50

ES-401, REV 10 TJG1 BWR EXAMINATION OUTLINE FORM ES-407-1 NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA AC SRO 295001 AA2.02 Partial or Complete Loss of Forced 3.1 3.2 Neutron monitoring LI LI LI LI LI LI LIL LI LILI Core Flow Circulation / 1 & 4 295003AA1.01 Partial or Complete Loss of AC /6 3.7 3.8 A.C. electrical distribution system LI LI LI LI LI LI LI LI LID 295005AK3.04 Main Turbine Generator Trip / 3 3.2 3.2 Main generator trip LI LI LI LI LI DLI LI DLI 295006AA1.06 SCRAM / 1 3.5 3.6 CRD hydraulic system LI LI LI LI LI LI ]LI LI DLI 295016AK3.02 Control Room Abandonment/7 3.7 3.8 Turbine trip LI LI LI LI LI DLI LI LILI 295018AK2.02 Partial or Total Loss of CCW / 8 3.4 3.6 Plant operations LI LI LI LI LI DLI LI LID 295019AK3.03 Partial or Total Loss of Inst. Air / 8 3.2 3.2 Service air isolations: Plant-Specific LI LI ] LI LI LI DLI LI LID 295021AK1.01 Loss of Shutdown Cooling / 4 3.6 3.8 Decay heat LI LI LI LI LI DLI LI LID 295023AK202 Refueling Ace Cooling Mode / 8 2.9 3.2 Fuel pool cooling and cleanup system LI LI LI LI LI DLI LI LID 295024EA1.14 High Drywell Pressure/5 3.4 3.5 Drywell ventilation system LI LI LI LI LI LI EiD LI LID 295025G2.4.50 High Reactor Pressure / 3 4.2 4.0 Ability to verify system alarm setpoints and operate LI LI LI LI LI LI DLI LI LI controls identified in the alarm response manual.

Page 1 of 2 04/13/2016 9:32 AM

ES-407, REV 10 T1GJ BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295026EA2.02 Suppression Pool High Water Temp. / 3.8 3.9 Suppression pooi level DDDDDDDDDD 5

295028EA2.02 High Drywell Temperature / 5 3.8 Reactor pressure 295030G2.4.1 Low Suppression Pool Wtr Lvi / 5 4 4.8 Knowledge of EOP entry conditions and immediate action steps.

295037EK1.02 SCRAM Condition Present and Power 414.3 Reactor water level effects on reactor power Above APRM Downscale or Unknown

/1 295038EK2.08 High Off-site Release Rate I 9 2.6 3.1 SPDS/ERIS/CR1DS/GDS: Plant-Specific 600000G2.4.35 Plant Fire On Site / 8 3.8 4.0 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 295004AA1.O1 Partial or Total Loss of DC Pwr / 6 a33.4 D.C. electrical distribution systems 295031EK1.03 Reactor Low Water Level / 2 3.7 4.1 Water level effects on reactor power 700000AK3.02 Generator Voltage and Electric Grid 3.6 3.9 Actions contained in abnormal operating procedures for Distrurbancecs voltage and grid disturbances Page 2 of 2 04/13/2016 9:32 AM

ES-401, REV 10 (T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295003G2132 Partial or Complete Loss of AC /6 3.8 4.0 Ability to explain and apply all system limits and precautions.

5005AP03 MatrrTuriT G&iera or rip / 3 -&-13:t Ti-valve-position.

Z9p24AZo3 thy JetIPw 29501 8AA2.02 Partial or Total Loss of CCW / 8 3.1 3.2 Cooling water temperature D D D D D D D [ D D D 29501 9AA2.02 Partial or Total Loss of Inst. Air / 8 3.63.7 Status of safety-related instrument air system loads (see AK2.1 AK2.19) 295030G2.2.44 Low Suppression Pool Wtr Lvl / 5 4.2 Ability to interpret control room indications to verify the 44D status and operation of a system, and understand how operator actions and directives affect plant and system conditions 295031G2.431 ReactorLowWaterLevel/2 4.2 4.1 Knowledge of annunciators alarms, indications or D D D D D D D D D El response procedures 700000AA2.07 Generator Voltage and Electric Grid 3.6 4.0 Operational status of engineered safety features D DDE DDE D ED Distrurbancecs Page 1 of 1 04/13/2016 9:32AM

ES4OI 3 Form ES-401-f ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions Tier 1/Group 2) SRO)

E/APE # / Name / Safety Function K K K A A G* KIA Topic(s) IR #

12312

• S C 2. 4.

g 295002 Loss of Main Condenser Vac / 3 R

295007 High Reactor Pressure / 3

- 2.. 1. 32.

295008 High Reactor Water Level / 2 2 95009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperatute / 5 P.

295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cant. Isolation / 5 & 7 f P..- Aj4I.° 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr LvI / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area

. a R-6A.oi Radiation Levels/9 S - BA2..03 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High R P..

l43. Op.

Differential Pressure / 5 03 295036 Secondary Containment High S Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: I Group Point Total: 7/3 ES-401, Page 35 of 50

ES-401, REV 70 T1G2 BWR EXAMINATION OUTLINE FORM ES-407-1 NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA RO Sf0 295007AK2.03 High Reactor Pressure / 3 3.1 3.2 RHR/LPCI: Plant-Specific El El El El El El El El El L]

295008G2.1.32 High Reactor Water Level / 2 3.8 4.0 Ability to explain and apply all system limits and El El El El El El El Li El El precautions.

29501 3AK0l High Suppression Pool Temp./5 3.6 3.7 Suppression pool cooling El [l El El El El El El El El El 295015AA1.04 lncompleteSCRAM/l El El El El Rod control and information system: Plant-Specific...

El El El El El El 295022AK1 02 Loss of CRD Pumps / 1 3.6 Reactivity control El El El El El El El El El El 295033EA2.01 High Secondary Contaiment Area 3.8 3.9 Area radiation levels El El El El El El El [ El El El Radiation Levels I 9 295035EK3.02 Secondary Containment High 3.3 El El El El El El El El Secondary containment ventilation response El El Differential Pressure / 5 Page 1 of 1 04/13/2016 9:32 AM

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ES-401 4 Form ES-401-1 ES-401 BWR Examination Oflie F orm ES 4 0 1 -1

= Plant Systems-]ier 2/Gp 1 System #1 Name K K K K K K A A A A G* K/A Topic(s)

R 203000 RHR/LPCI: Injection Mode 1 R..o 205000 Shutdown Cooling S SA 2O6000HPCI 207000 Isolation (Emrgency)

Condenser 2O9001LPCS 209002 HPCS R-3P3 Sc...4.4j 211000SLC R R-G2..4.4 212000 RPS R- J3.O c

2150031RM R R 1(2.01 215004 Source Range Monitor 215005APRM/LPRM R-I4.D3 S Pi2..15 217000RCIC c2.4.%

218000 ADS R A2.D$

223002 PCIS/Nuclear Steam Supply Shutoff 239002SRVs t5o4-259002 Reactor Water Level g A I. 03 Control R - JLI.o3 261000 SGTS A3.o 262001 AC Electrical Distribution R AJ.D.-

262002 UPS (AC/DC) 263000 DC Electrical A I. I Distribution I.4. D.

R ICI.V4 5- A2.D2.

264000 EDG5 300000 lnstwment Air 400000 Component Cooling Water K/A Category Point Totals: 2I i 13 2 3 Group Point Total: 26/5 3 a ES-401, Page 36 of 50

ES-401, REV 10 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 2o3000A2.02 3.5 3.5 - Pump trips RHR/LPCI: Injection Mode El El El El El El El El El El 205000K2O1 Shutdown Cooling 3.1 3.1 Pump motors El F El El El El El El El El El 206000A3.02 HPCI 3.8 3.8 System Flow: BWR-2,3,4 El El El El El El El El [ El El 2O6OOO4 HPCI -&4 3*4DElElElElElElDElEl 4z 4,3 209001G2.1.23 LPCS 4.3 4.4 Ability to perform specific system and integrated plant El El El El El El El El El El procedures during all modes of plant operation.

21 1000K3.03 SLC 2.6 2.7 El El El El El El El El Core plate differential pressure indication El El 212000G2.4.46 RPS 4.2 4.2 Ability to verify that the alarms are consistent with the El El El El El El El El El El plant conditions.

212000K3.06 RPS 4.0 4.1 Scram air header solenoid operated valves El El El El El El El El El El 215003A4.02 IRM 2.9 2.8 El CRT display indications: Plant-Specific El El El El El El El El El 215003K4.02 IRM 4.0 4.0 El El El El El El El Reactor SCRAM signals El El El 215004K2.O1 Source Range Monitor 2.6 2.8 SRM channels/detectors El El El El El El El El El El Page 1 of 3 04/13/2016 9:32AM

ES-401, REV 10 2G1 BWR EXAMINATION OUTLINE FORM ES-401-7 NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA RO SRO 21 5005A4.04 APRM / LPRM 3.2 3.2 LPRM back panel switches, meters and indicating lights DDDDDDDD 217000K4.03 RCIC 2.9 3.0 Prevents pump over heating 218000G2.4.35 ADS Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 223002A2.08 PCIS/Nuclear Steam Supply Shutoff 2.7 3.1 Surveillance testing 239002A3.07 SRVs 3.8 3.9 DL1E1L1DL Reactor water level 239002K5.04 SRVs 3.3 3.5 Tail pipe temperature monitoring 259O02M0e Reactor Water Level Control 3t  ! k)L tr) IIG/L ;-d1 I?

Aio1- -34 3, 261000K1 .03 SGTS 2.9 3.1 Suppression pool 262001A3.01 AC Electrical Distribution 3.1 3.2 Breaker tripping 262002A1 .02 UPS (AC/DC) a52.9 Motor generator outputs 263000A1.01 DC Electrical Distribution 5 2.8DDDDD DDE Battery charging/discharging rate Page 2 of 3 04/13/2016 9:32 AM

çLO FORM ES-401-7 ES-407, REV 10 T2G1 BWR EXAMINATION OUTLINE NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA P0 SRO 263000K4.02 3.1 3.5 Breaker interlocks,permissives, bypasses and cross ties:

DC Electrical Distribution Plant Specific 264000K1.04 EDGs 3.2 3.3 Emergency generator cooling water system 300000K5.O1 Instrument Air 2.5 2.5 Ah compressors 4000001<6.05 Component Cooling Water ao3.1 Pumps (A.f)

Page 3 of 3 04/13/2016 9:32AM

(T2G7 BWR EXAMINATION OUTLINE FORM ES-407-7 ES-401,_REV 10 KA NAME I SAFETY FUNCTION: IA Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

AC SRO 206000A2.08 HPCI 3.9 4.2 THigh suppression pooi temperature: BWR-2,3,4 211OOOG,4,43-. SLC classtficattons. r f/%* L4-e 4-Ls 11-e.

215003G2.447 lAM 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

3.8 3.8 jj Steam line break 217000A2.15 RCIC 264OOOAe EDGs 34&1 A27 ;z;;;:

.36 3,(;7 6, 7Of/

,1\2,o7 Page 1 of 1 04/13/2016 9:32 AM

ES-401 5 Form ES-401-1 ES-401 BWR Examination OuSin Form ES-401-1

Plant Stems -Tier 2/Grop 2

System # / Name K K K K K K A A A A G* K/A Topic(s) IR #

201001 CRD Hydraulic 201002 RMCS 201003 Conttol Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 3 -A3.3 -2.4,sO 215001 Traversing In-Core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode Al. 0+

230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment R-AdQ 239001 Main and Reheat Steam 239003 MSIV_Leakage_Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux. .

256000 Reactor Condensate 259001 Reactor_Feedwater 268000 Radwaste AO!

271000 Offgas 272000 Radiation Monitoring c

- 46.2 .Df-286000 Fire_Protection 288000 Plant Ventilation 0+

290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals: PD I I [t I 2. [ I j I I [ If Group Point Total: 12)3 I

ES-401, Page 37 of 50

ES-407, REV 70 T2G2 BWR EXAMINATION OUTLINE FORM ES-407-7 IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA NAME/SAFETY FUNCTION:

RO SRO 201006K5.07 RWM 2.8 2.9 Latch groups: P-Spec(Not-SWR6)

EDDD ELIDED 202001 K4.07 Recirculation 2.8 2.9 Motor generator set trips: Plant-Specific DDDE ELIDED CVFb -Fv-p.)

202002K2.02 Recirculation Flow Control 2.6 2.6 Hydraulic power unit: Plant-Specific EEL1D ELIDED LI (VFI) 215001A3.03 Traversing In-core Probe 2.5 2.6 Valve operation: Not-BWR1 ELIDED DDD1D 226007 K3.02 RHR/LPCI: CTMT Spray Mode 3.5 3.5 Containmentldrywell/suppression chamber temperature ED LIE DDDED E 230000A1.o4 RHR/LPCI: Torus/Pool Spray Mode 3.2 3.3 System flow ELIDED DDED LI 239001 K6.06 Main and Reheat Steam 3.8 3.9 MSIV isolation signal ELIDED ED ED LI 245000K6.04 Main Turbine Gen. / Aux. 2.6 2.7 Hydrogen cooling ELIDED DDED 268000G2.1.32 Radwaste 8 Ability to explain and apply all system limits and ELIDED precautions.

271000A2.01 Otfgas 3.1 3.3 Low condenser vacuum ELIDED DE1DD 288000A4.02 Plant Ventilation 2.8 2.8 Area temperature DEELIELIDLILID Page 1 of 2 04/13/2016 9:32 AM

T2G2 BWR EXAMINATION OUTLINE FORM ES-407-1 ES-401, REV 70 NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA HO SRO 290001 Ki .04 Secondary CTMT 3.7 3.9 SBGT Page 2 of 2 04/13/2016 9:32AM

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ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401 -3 Facility: ROLL) li5 PEI4.I Date of Exam: /4PR L 9_C)i 7 Category K/A # Topic RO SRO-Only iR # IR #

2.1.5 t  %

2.1. Ad .1 1- inJer re md &, 9toh ed:. 3.9 1 2.1.

Conduct of 2.1. 17 4tc.L4.rt-, Leac) CXh6.Q1TYfS .0 Operations 2.1. %2 3 .

2.1.

Subtotal 2.2. 4r (iti c- ..

2.2.43 Prv-ces5 4o k- 3 w)4te iLjt

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Control 2.2. 6 -

a 2.2.3S c c/Lkdot ;tc&1j La 45 Subtotal 2.3.12 Aa1S4djprrcptespe4zi7iitq-/v L0. dds .Z 2.3. P5 RiL nwii*rf IcrLc

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23 16 Ri). m1l*rsn.f S4e*ix 3. /

Subtotal 2.4,f proet&feC 3.4..

2.4. ST t.hf a.cttwriiy 4cr?f -i1a 3.t

4. 2.4.3Y p.o rf.p4Jrhe6- E-pla.ei 3..?

Emergency Procedures / 2.4.

Plan 2.4.2 ceA-vt., ka4 A -A-dw 2.4.40 Subtotal -

Tier3PointTotal (7)

ES-401, Page 43 of 50

T3 BWR EXAMINATION OUTLINE FORM ES-401-3 ES-407, REV 70 NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA PC SRO G2.1 .25 Conduct of operations 3.9 4.2 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

G2.1.3 Conduct of operations 3.7 3.9 j Knowledge of shift or short term relief turnover practices.

DDE 62.2.4 Equipment Control 3.6 3.6 j (multi-unit) Ability to explain the variations in control LID DEE board layouts, systems, instrumentation and procedural actions between units at a facility.

G2.2.43 Eqpment Control 3.0 3.3 Knowledge of the process used to track inoperable alarms ED DDE 62.2.44 Equipment Control 4.2 4.4 Ability to interpret control room indications to verify the LIDD ED DDE status and operation of a system, and understand how operator actions and directives affect plant and system conditions 62.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties 2.9 3.1 Knowledge of radiation monitoring systems(eAe1.1 a4d- tIk)

G2.3.15 Radiation Control as G2.4.27 Emergency Procedures/Plans 3.4 3.9 Knowledge of fire in the plant procedures.

G2.4.37 Emergency Procedures/Plans 3.0 4.1 Knowledge of the lines of authority during implamentation of an emergency plan.

62.4.39 Emergency Procedures/Plans 3.9 3.8 Knowledge of the ROs responsibilities in emergency plan implementation.

Page 1 of 1 04/13/2016 9:32AM

ES-407, REV 10 (T3 BWR EXAMINATION OUTLINE FORM ES-407-3 KA NAME / SAFETY FUNCTION: JR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.17 Conductof operations 3.9 4.0 Abthtyto make accurate, clear and concise verbal reports.

G2.1.26 Conduofopemtions 3.4 3.6 [] -

Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

Ga2.38 Equipment Control 3.6 Knowledge of conditions and limitations in the facility El El El El El El El El El El license.

G2.2.5 Equipment Control 2.2 3.2 Knowledge of the process for making design or operating El El El El El El El El El El changes to the facility G2.3.15 Radiation Control 2.9 3.1 -

Knowledge of radiation monitoring systems (r.ç, p(a.t wkk El El El El El El El El El El Emergency Procedures/Plans 45 4S El El El El El El ElElEl ccn1itiQn 4-

) ie,,ud G2A.40 Emergency Procedures/Plans 2.7 4.5 Knowledge of the SROs responsibilities in emergency El El El El El El El El El El plan implementation.

Page 1 of 1 04/13/2016 9:32 AM

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Date of Exam: Exam Level: RO SRO Item Description Initials a b c

1. Clean answer sheets copied before grading

2. Answer key changes and question deletions justified and fr_

documented

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

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

5. All other failing examinations checked to ensure that grades are justified

6. Performance on missed questions checked for training p1 deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants 1

(V 7 Printed Name/Signature Date

a. Grader lAc,JA 7.i9)Jl2Y t *17

//7

b. Facility Reviewer(*)

c. NRC Chief Examiner (*) RL4Mb

d. NRC Supervisor(*)

t(t7

(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-403, Page 6 of 6

hlU Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 6, 2017 10 CFR4O(b)(3) 10 CFR 55.5 10 CFR 55.49 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1 257 Attention: Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Submittal of Initial Operator Licensing Examination

Reference:

Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant Notification of Licensed Operator Initial Examination 05000259/2017301, 05000260/2017301, and 05000296/2017301, dated October 27, 2016 In accordance with the referenced letter and NUREG-1 021, Operator Licensing Examination Standards for Power Reactors, the Tennessee Valley Authority is providing the written test and supporting reference materials for the upcoming license examination.

The Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Initial Operator Licensing Examination is scheduled for the week of April 10, 2017. In order to meet the examination schedule, the NRC requested that BFN furnish this examination material by February 6, 2017.

See the attached enclosure for the Reactor Operators and Senior Reactor Operators examinations.

I,.

Ms. Catherine Haney Page 2 February 6, 2017 In accordance with Title 10 of the Federal Code of Regulations (10 CFR) 55.49, and NUREG-1 021, appropriate measures have been taken to ensure examination integrity and security. Accordingly, it is requested that this letter and the enclosed documents will be withheld from public disclosure until the examinations are completed.

There are no commitments contained in this submittal. Should you have any questions regarding this matter, please contact Mr. Michael Barton, at (256) 729-2783.

Enclosure:

Written Examination and Supporting Reference Materials Operator License Examination Scheduled for the Week of April 24, 2017

Ms. Catherine Haney Page 3 February 6, 2017 MWO: RWC bcc: (wlo Enclosure)

M. A. Barton A. S. Bergeron G. A. Boerschig D. L. Hughes W. L. Parker G.E.Pry J. W. Shea C. L. Vaughn EDMS

Withhold the Enclosure from Public Disclosure in Accordance with NUREG-f 021 Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1,2, and 3 Written Examination and Supporting Reference Materials Operator License Examination Scheduled for the Week of April 24, 2017 This enclosure contains the following information:

1. A notebook containing the following:

• ES-201-1, Examination Preparation Checklist

• ES-201-2, Examination Outline Quality Checklist

• ES-201-3, Examination Security Agreement

• ES-301-J, Administrative Topic Outline

• ES-301-2, Control Room/In-Plant Systems Outline

• ES-301-3, Operating Test Quality Checklist

• ES-301-4, Simulator Scenario Quality Checklist

• ES-301-5, Transient and Event Checklist

• ES-301-6, Competencies Checklist

• ES-401-4, Record of Rejected K/As

• ES-40J-6, Written Examination Quality Checklist

• ES-DI, Scenario Outline

• ES-D2, Required Operator Actions

• Written Examination with References

2. Compact disk containing the examination and references

sI I 1i Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Match 10, 2017 10 CFR 55.5 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 Attention: Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos, DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Preliminary Senior Reactor Operator (SRO) Licensee Application Information

Reference:

Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant Notification of Licensed Operator Initial Examination 05000259/2017301, 05000260/2017301, 05000296/2017301, dated October 27, 2016 In accordance with the above referenced NRC letter dated October 27, 2016, the Tennessee Valley Authority (WA) is providing preliminary Senior Reactor Operator (SRO) Licensee application information that is to be submitted 30 days prior to the SRO examination date of April 10, 2017.

The enclosure contains the preliminary (signed) personal qualification statement form (NRC Form 398) and certification of medical examination form (NRC Form 396), for the SRO candidates.

The enclosure to the letter is considered by the WA to be of a personal nature and, as such, is to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).

Ms. Catherine Haney Page 2 March 10, 2017 There are no new regulatory commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Christopher L. Vaughn, at (256) 729-3439.

Respectfully, Vice President

Enclosure:

Preliminary Senior Reactor Operator (SRO) Licensee Application Information

Jdim Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 March 23, 2017 10 CFR 55.5 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1 257 Attention: Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Final Senior Reactor Operator (SRO) Licensee Application Information

Reference:

Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant Notification of Licensed Operator Initial Examination 05000259/2017301, 05000260/2017301, 05000296/2017301, dated October 27, 2016 In accordance with the above referenced NRC letter dated October 27, 2016, the Tennessee Valley Authority (TVA) is providing finalized Senior Reactor Operator (SRO) Licensee application information that is to be submitted 14 days prior to the SRO examination date of April 10, 2017.

The enclosure contains the final (signed) personal qualification statement form (NRC Form 398) and certification of medical examination form (NRC Form 396), for the SRO candidates.

The enclosure to the letter is considered by the WA to be of a personal nature and, as such, is to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).

MAR 2 4 .U ii

Ms. Catherine Haney Page 2 March 23, 2017 There are no new regulatory commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Christopher L. Vaughn, at (256) 729-3439.

Respectfully,

Enclosure:

Final Senior Reactor Operator (SRO) Licensee Application Information

-J

Tennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000 April 4, 2017 10 CFR 55.5 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 Attention: Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Updated final Senior Reactor Operator (SRO) Licensee Application Information

References:

1. Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant Notification of Licensed Operator Initial Examination 05000259/2017301, 0500026012017301, 05000296/2017301, dated October 27, 2016

2. Letter from the Tennessee Valley Authority to the Nudear Regulatory Commission, Final Senior Reactor Operator (SRO) Licensee Application Information, dated March 23, 2017 In accordance with the above referenced NRC letter dated October 27, 2016 (Reference 1), the Tennessee Valley Authority (WA) provided finalized Senior Reactor Operator (SRO) Licensee application information that was to be submitted 14 days prior to the SRO examination date of April 10, 2017 (Reference 2).

However, due to an administrative error, the personal qualification statement forms (NRC Form 398) were unsigned by the applicants.

The enclosure contains the final (signed) personal qualification statement form (NRC Form 398) and certification of medical examination form (NRC Form 396), for the SRO candidates.

Ms. Catherine Haney Page 2 April 4, 2017 The enclosure to the letter is considered by the TVA to be of a personal nature and, as such, is to be withheld from public disclosure in accordance with 10 CFR 2.390fa)(6).

There are no new regulatory commitments in this letter. Should you have any questions regarding this mailer, please contact Mr. Christopher L. Vaughn, at (256) 729-3439.

Enclosure:

Final Senior Reactor Operator (SRO) Licensee Application Information

Ms. Catherine Haney Page 3 April 4, 2017 MWO: RWC bcc: (wlo Enclosure)

A. S. Bergeron R. A. Evans D. L. Hughes W. L. Parker G.E.Pry J.W. Shea M. C. Tharpe C. L. Vaughn EDMS

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 May 1,2017 10 CFR 55.5 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1 257 Attention: Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Senior Reactor Operator Initial License Written Examinations Post Examination Response The Tennessee Valley Authority (WA) administered the final NRC Written Examination for the Browns Ferry Nuclear Plant Senior Reactor Operator Initial License Training (ILT) on April 10, 2017. The supporting documentation specified by Section ES-501 of NUREG 1021, Revision 10, Operator Licensing Examination Standards for Power Reactors, for Initial Post-Examination Activities is enclosed. The enclosures content listing is provided at the end of this letter.

The NRC Form ES-201-3, will be forwarded to the NRC as soon as it is completed.

The enclosures to this letter are considered by WA to be of a personal nature and, as such, are requested to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).

There are no commitments contained within this letter.

Ms. Catherine Haney Page 2 May 1,2017 Should you have any questions regarding this matter, please contact Mr. Michael Barton, at (256) 729-2783.

Enclosures:

Enclosure 1 - Form ES-403-1, Written Examination Grading Quality Checklist Enclosure 2 Graded Written Examinations (Each Applicants Original Answer and Examination Cover Sheets) and a Clean Copy of Each Applicants Answer Sheet Enclosure 3 Questions Asked By and Answers Given to the Applicants During the Written Examination Enclosure 4 Examination Seating Chart Enclosure 5 Results of Written Examination Performance Analysis that was Performed Enclosure 6 Master Examination Answer Key, Annotated to Indicate any Changes Made While Administering and Grading the Exam i nations Enclosure 7 Facility Comments made in accordance with ES-501 Attachment 1 Enclosure 8 Correction to Nuclear Regulatory Commission Letter dated April 17, 2017 List of Applicants

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Ms. Catherine Haney Page 3 May 1,2017 MWO:MNK Enclosures bcc: (wlo Enclosure)

M. A. Barton G. A. Boerschig A. S. Bergeron D. L. Hughes J. W. Shea C. L. Vaughn EDMS