ML18240A432

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301 Exam Administrative Items 2D - Normal Release
ML18240A432
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/28/2018
From:
Southern Nuclear Company
To:
NRC/RGN-II
References
52-025/17-01, 52-026/17-01 52-025/OL-17-01, 52-026/OL-17-01
Download: ML18240A432 (36)
v • d • e


Text

ES-201 Examination Preparation Checklist Form ES-201-7 Facility: V3ii C U..-- 3.- Date of Examin)ion:

Developed by: Written: Facility NRC // Operating Facility NRC Target . Chief Task Description (Reference) Examiners ae Initials

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

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

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

-150 4. Corporate notification letter sent (C.2.d)

[-1201 5. Reference material due (C.1.e; C.3.c; Attachment 3)

(-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-401-1/2, ES-401N-1/2, ES-401-3, ES-401N-3, ES-401 -4, and ES-401 N-4, as applicable (C. 1 .e and f; C.3.d)

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

{-60} 8. Proposed examinations (including written, walk-through JPMs, 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-301-1, or ES-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)

-30 10. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202) S

-21 11. 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)

-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)

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

-7 16. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

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

-7 18. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

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

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

  • VJrM-ES-207 Examination Outline Quality Checklist Form ES-201-2 Facility: Date of Examination:

\/ .j__ çjj Lü Initials Item Task Description =

1. a. Verity that the outline(s) fit(s) the appropriate model, In accordance with ES-401 or ES-401N.
b. Assess whether the outline was systematically and randomly prepared in accordance with T Section D.1 of ES-401 or ES-401N and whether all KJA categories are appropriately sampled. ft.

N

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. Z
d. Assess whether the justitications for deselected or rejected K/A statements are appropriate. j
2. a. Using Form ES-301 -5, verify that the proposed scenario sets cover the required number of normal evolutions, Instrument and component failures, technical specifIcations, and major S transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number and u mix of applicants in accordance with the expected crew composition and rotation schedule L wIthout compromising exam Integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301 -4 and described in Appendix D.
3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

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

K (4) the number of new or modilled 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 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.
4. a. Assess whether plant-specific priorities (Including PRA and IPE insights) are coveted in the appropriate exam sections. r /3 G

E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling Is appropriate. t1

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. j4y_

R d. Check for duplication and overlap among exam sections.

L e. Check the entire exam for balance of coverage.

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

-,a PrinteName/Signature DaIe

a. Author c-t7L.r I
b. Facility Reviewer (*) N14 C. NRC Chief Examiner (#) fri. (ti Note: # Independent NRC reviewer initial items in Column ac; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines.

r (*j*\ 0 ) !4

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: VogUe AP-1000 Date of Examination: 2? Februanj 2017 Item Initials Task Description a b c#

a. Verify that the outline(s) fit(s) the appropnate modet, in accordance with ES-401 or ES-401 N.

w

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

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

T /

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

N

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

i 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 without compromising exam integrity, and ensure that each applicant can be tested using at A

L least one new or significantly modified scenario, that no scenarios are duplicated from the 7,2 T applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix 0.
3. a. Verity 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)

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

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

a (1) the tasks are distributed among the topics as specified on the form u

(3 (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

)

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

appropriate exam sections.

E b. Assess whether the 10 CFR 55.41/43 and 55,45 sampling is appropriate.

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

A d. Check for duplication and overlap among exam sections. 3 L a. Check the entire exam for balance of coverage.

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

Printed Name/Signature ,i I Date

a. Author E 1 --- I ..., ..______

iFV U. NRC Supervisor l Note: Independent NRC reviewer initial items in Column c; chief examiner concurrence reqciired.

Not applicable for NRC-prepared examination outlines.

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 17 OCT 2016 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 knowIede, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATU (1) DATE SIGNATUR(2) DATE NOTE

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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 17 OCT 2016 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 knowjd , I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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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 17 OCT 2016 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 f% . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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NOTES:

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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 17 OCT 2016 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 knowIede, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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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 17 OCT 2016 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 knowled9e, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of,JI. From the date that I entered into this security agreement until the completion of examination administratio I did not n,

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

PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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

1. Pta-Examination I acknowledge that I have acquired speciahzed knowledge about the NRC licensing examinations scheduled for the week(s) of 17 OCT 2016 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 indMdual 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 andlor an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
2. Post-Examination To the best of my knowl?de. I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of i J From the date that I entered into this security agreement until the completion of examination administration. I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE (1) DATE SIG TURE (2) DATE NOTE 1t.., xel OP+S T,1 NOTES:

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of (1 _Tltas 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 knowlede, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of,?- From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance teedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE! RESPONSIBILITY DATE SI ATURE(2) DATE NOTE

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ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Voae Unft 3 Date of Examination: 02127/2017 Operating Test Number:

Initials

1. General Criteria a b c#

(2

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). 4.

tests

b. There is no rtay-to-day repetition between this and other operating during this examination.

to be administered I

a. The operating test shall not duplicate items tram the applicants audit test(s). (see Section D.1.a.) 1 ;
d. Overtop with the written examination and between different parts of the operating test is within acceptable limits. 1 It appears that the operating test will differentiate between competent and less-than-competent e.

applicants at the designated license level.

2. Walk-Through Criteria -- -- --
a. Each JPM includes the following, as applicable:
  • initial conditions
  • inibating cues
  • references and toots, including associated procedures
  • reasonabte ancf validated time limits (average time allowed fnr completion) and specific designation if deemed to be time*critical by f ho facility Icensee
  • operationally important specific performance criteria that nclude:

detaited expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the appticant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, it 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 a,,

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 I Signature Date

a. Author //frtfAd
b. Facility Reviewer(l Q_huX iktC
c. NRC Chief Examiner (if) iej fri. LD.\ 2,.iLi2
d. NRC Supervisor (vu(Jiru / Qt NOTE; The facility signature is net appicable tot NRC-developed tests.

ft Independent NRC reviewer initiai items in Column c: chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Voatle Unit 3 Date of Exam: 02/27/2017 Scenario Numbers: 1 /2 / 3 / 4 Operating Test No,:

QUALITATIVE ATTRIBUTES lrufials a b* 4

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events,
2. The scenarios consist mostly of related events. ,4 i
3. Each event descnption consists of

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

. the malfunction(s) or conditions that are entered to initiate the event

  • the symptoms/cues that will be visible to the crew

. the expected operator actions (by shift position)

. the event termination point (if applicable)

4. The events are valid with regard to physics and thermodynamics.

._A _

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

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

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

Cues are given.

7. The simulator modeling is not altered. 4- F
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 evalciated to ensure that functional fidelity is maintained while running the planned sceiranos.
9. Every operator will be evaluated using at least one new or significantly modified scenario. Al I other j scenarios have been altered in accordance with Section D.5 of ES-301.
10. All individual operator competencies can be evaluated, as verified using Form ES-SO 1-6 (submit the ,4, ,

form along with the simulator scenarios). t 1 1. 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). 4 a...
13. The level of difficulty is appropriate to support licensing decisions for each crew position.

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

1. Malfunctions after EOP entry (1-2) 3/4/3/3
2. Abnormal events (2-4) 4/4/5/3 4
3. Major transients (12) 1 / 1 / I / 1 4, FOPs entered/requiring substantive actions (12) 1 I 1 / 1 / 1
5. EOP contingencies requiring substantive actions (0-2) 1 / 1 / 0/ 1 if
6. EOP based Critical tasks (23) 2 / 2/2 %1 _

NOTE: The facility signature is not applicable tot NRC-developed tests.

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Voqtle Unit 3 Date of Exam: March 2017 Operating Test No.: ILT-2 A E Scenarios 1 2 3 4 T M L N CREW CREW CREW CREW POSITION T N I T POSmON POSmON pOSmON C A S A B S A B S A B S A B M A T L R T 0 R T 0 R T 0 R T U 0 C P 0 C P 0 C P 0 C P M(*)

T E R I U NOR 063 4 1 ii o-I/C 12 12 12 35 28 4 4 2 SRO-U 35 34 46 68 78 89 89 9 D 9 10 10 10 11 MAJ 6 7 7 7 4 2 21 TS 14 25 35 26 8 0 22 RX 1 3 0 1 3 1 10 RO NOR 0 0 0 4 1 1 11 SRO-l I/C 3 7 4 8 1 8 6 8 14 4 4 2 8 9 9 9 SRO-U MAJ 6 7 77 4 2 21 TS 0 0 0 0 0 0 22 NOR 0631 3 1 ii o-i I/C 12 12 24 35 14 4 42 SRO-U 59 3 6 10 D MAJ 6 7 7 7 4 2 21 TS 0 0 0 0 0 0 22 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 (SRO-l) 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 SRO-l additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the AIC 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. f) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one 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.
4. For licensees that use the AIC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-l in manipulatina plant controls,

ES-301 Corn petencies Checklist Form ES-301 -6 Facility: Voqtle Unit 3 Date of Examination: March 2017 Operating Test No.:

APPLICANTS RD El RO/ATC RO/BOP RD El SRO-I El SRO-I [] SRO-I SRO-I SRO-U SRO-U El SRO-U E SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1234 12341 234 1234 Interpret/Diagnose

. 1-9 i-lI 1-10 -10 1.3. 3,4. 1.7- ..H2.ft 1-3,

-,, 2-7 L 3.

,.7.

Events and Conditions

(,-$ 7-1 0 (-

It)

Comply Vvith and L 2. 1-3. 1.3.

t 1 I 7- I 4

-9 1-Il I-it) I-it 5,A, 5-7. 2-7 5.7.

Use Procedures (1) (-8 7-10 10 6-9 9 ii 10 Operate Control 1.2. 1-3. 1.3.

1 4 1 7 I 4

-9 I-Il 1-10 1-10 5t-. 5-7. 2-7 5.7.

Boards (2)

(-8 7-10 10 6-9 Communicate j 3 1,2. -3. 1.3.

4 1 7- I 4 1-9 i-Il 1-10 i-iO 5,6. -7. 2-7 5.7.

and Interact 6-8 7-10 10 6-9 ii 0 Demonstrate -

-9 I-Il I-it) 1-10 N/A

. N/A N/A N/A N/A N/A N/A NA Supeisory Ability (3)

Comply With and 1,4 2,5 3. 5 2.0 N/A N/A N/A N/A N/A N/A N/A N,\

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- 1 and ES-303-3 (Note: Based on the scenarios chosen and the crew makeup, ATC and BOP (UO) positions will be filled by RO or SRO-l candidates. Form completed for control room positions NOT individual candidates.)

ES-401N, Rev. 10 PWR Examination Outline Form ES-401N-2 Facility: Vogtle Dateof Exam: Otobor2018 Zori RO K/A Category Points SRO-Only Points Tier Group K KFK K A A A AG A2 G* Total 1 2 5 6 1 2 3 4 Total

1. 1 i 313 2 3 3 18 3 3 6 2 1 2 1 9 2 2 4 Abnormal Plant NIA N/A Evolutions TierTotals 5 4J5 3 5 4 27 5 5 10 I I 1 33 243 32232 28 2 3 5 2 1 1 1 1 1 1 1 0 1 1 1 10 1 2 3 p2ant Systems Tier Totals 4 4 3 4 4 2 3 4 3 38 5 8
3. GenericKnowledgeandAbilities 1 21 3 14 10 1 2 1 Categories 2

L 2 3 .

L 2 2 2

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO only outlines (i.e., except for one category in Tier 3 of the SRO-only, the Tier Totals in each KIA 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.

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 n the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As 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 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. Refer to section D.1 .b of ES-401 for the applicable KAs.
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 SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES4OIN, REV 10 TIGI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO A-301AA2.02 Rapid Power Reduction 3 3.1 LILILILILILILILIE]LI Reactor Coolant System boron addition volume and rate A-31 3AA1.03 Uncontrolled Cooldown - 3.5 LI LI LI LI LI LI LI LI LI LI SGPORVs - -

A-323AK108 Loss of 6.9KV, 4160 Volt, or 480 3.2 LI LI LI LI LI LI LI LI LI LI Main Control Room Emergency Habitability System Volt Bus Power A-336AG2.l.14 Malfunction of Protection and 4 3.3 LI LI LI LI LI LI LI LI LI LI Ability to use integrated control systems to operate plant Safety Monitoring System systems or components.

A-337AK3.06 Passive Residual Heat Removal 2.7 LI LI LI LI LI LI LI LI LI LI Trending Passive Residual Heat Removal System inlet Heat Exchanger Leak temperatures and pressures A-342AG2.4.36 Reactor Coolant Pump Malfunctions 4.1 4.3 LI LI LI LI LI LI LI LI LI LI Ability to prioritize and interpret the significance of each annunciator or alarm.

A-343AK2 02 Loss of Normal Residual Heat 3.5 LI LI LI LI LI LI LI LI LI LI Transferring Reactor Coolant System heat load to the Removal Passive Residual Heat Removal System heat exchanger E-1 EK1 .01 Loss of Reactor or Secondary 4.3 LI LI LI LI LI LI LI LI LI LI Automatic Depressurization System Coolant E-2EK3.04 Faulted Steam Generator Isolation 3.4 LI LI LI LI LI LI LI LI LI LI Checking Passive Residual Heat Removal System is available prior to isolating the startup feedwater lines to the faulted steam generators ECA-1.1EA1.02 Loss of CoolantAccident Outside 3.6 LI LI LI LI LI LI LI LI LI LI Diverse Actuation System -____________

Containment ES-0.1EK2.l0 Reactor Trip Response 3.3 LI LI LI LI LI LI LI LI LI LI Inability to stabilize Reactor Coolant System at no load Tcold temperature Page 1 of2 01/11/2016 7:41 AM

ES4OIN, REV 10 TIGI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO ES-l.1EK1.12 Passive Safety System Termination 2.8 Pressurizer Pressure Control System ES-1.3EA1.14 ADS Stage 1-3 Actuation Response 3.6 0 ADS Stage4 ES-i .4EA2.O1 ADS Stage 4 Actuation Response 3.6 3.8 ADS Stage 4 proper alignment FR-C.1EG2.4.1 Response to Inadequate Core 4.6 4.8 Knowdge of Emergency/Abnormal Operating Procedure Cooling entry conditions.

FR-H.1EK3.14 Response to Loss of Heat Sink 4.4 Automatic Depressurization System Actuation FR-S.1 EK2.03 - Response to Nuclear Power 4.1 Failure to recognize the need and failure to manually trip Generation ATWS the reactor through the Protection and Safety Monitoring System, given anticipated transient without scram (PRA related)

SDP-1 EA2.03 Response to Loss of RCS 3.6 3.6 Core exit temperature Inventory During Shutdown Page 2 of 2 01/11/2016 7:41AM

ES-401N, REV 10 TIG2 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTIO IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO A-304AK2.08 Steam Generator Tube Leak 3.2 Using Passive Residual Heat Removal System for Reactor Coolant System cooldown A-311AK3.02 Rod Control System Malfunctions 3.3 Checking On-Une Power Distribution Monitoring System is operable A-320AK1 .09 Loss of Circulating Water 2.6 Circulating Water trash screens A-327AA2.0l Startup Feedwater System 2.8 3.5 Steam generator level Malfunctions A-328AK1 .03 Malfunction of Feedwater Heaters 2.6 DDE Main and Startup Feedwater System and Extraction Steam A-333AA1.0l Main Turbine Malfunctions 3.4 DEEDED Main turbine load and trip controls FR-Z.l EK3.06 Response to High Containment 3.4 EEEEEEEEEE Main Steam Isolation Actuation Pressure FR-Z.2EG2.4.25 Response to Containment Flooding 3.6 4 Knowledge of operator response to a loss of all annunciators.

FR-Z.4EA2.0l Low Containment Pressure 2.8 3 EEEEEEEEEE Containment pressure Page 1 of 1 01/11/2016 7:41 AM

ES-401N, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES4OIN-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO ADSA4.04 Automatic Depressurization System 4.1 D Reactor Coding System pressure ADSK6.01 Automatic Depressurization System 4.2 Diverse Actuation System CASA1.01 CompressedAirSystem 2.6 Instrumentaircompressorpackageparameters CCSK4.02 Component Cooling Water System 3 Normal Reactor Coolant System cooldown CNSK1.20 ContainmentSystem 3.3 SteamGeneratorSystem CNSK3.Ol Containment System 4 Containment integrity CVSK2.04 Chemical and Volume Control 3.7 Containment isolation valves System DASA2.05 Diverse Actuation System 3.4 3.3 J Containment isolation ECSG2.2.17 AC Electrical Distribution Systems 4 4.7 Knowledge of limiting conditions for operations and safety limits.

ESASK6.23 Engineered Safeguards Actuation 3.6 P-12, Pressurizer Level System RNSA4.05 Main and Startup Feedwater System 3.3 Main feedwater control valve Page 1 of 3 01/11/2016 7:41 AM

ES-401N, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO IDSK2.09 Class 1E and Non 1E DC and UPS 2.5 Non class 1E instrument bus inverters (OE-related)

Systems IDSK4.06 Class 1E and Non JE DC and UPS 2.6 System ground detection Systems MSSA3.05 Main Steam System 3.5 D Steam Line Isolation Actuation PCSA2.13 PassiveContainmentCooling 3.8 4.1 Lossofcoolantaccident System PCSd PassiveContainmentCooling CL.O1 System Ffr- i kkhf LAO PPCSG2.4.39 Pressurizer Pressure Control 4.2 4 Ability to verify system alarm setpoints and operate controls System identified in the Alarm Response Procedure.

PRHRA1.03 Passive Residual Heat Removal 3.5 Passive Residual Heat Removal System heat exchanger System temperature PXSK3.02 Passive Core Cooling System 3.2 Normal Residual Heat Removal System RCPK5.04 Reactor Codant Pump System 3.2 Reactor coolant pump start effect on reactivity/boron (CE related)

RCSA1.17 Reactor CodantSystem 3.9 Reactor Coolant System Automatic Depressurization System discharge temperature RCSK1 .18 Reactor Coolant System 3.6 Normal Residual Heat Removal System Page 2 of 3 01/11/2016 7:41 AM

ES4OIN, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO RNSA4.07 Normal Residual Heat Removal 3.5 Post loss of coolant accident containment makeup System RNSK6.04 Normal Residual Heat Removal 2.7 DDE EDDiED Pump fl rate instrument System RTSK2.02 Reactor Trip System 3.6 EEEEEEE Reactor Thp System Instrumentation SGSK5.14 Steam Generator System 2.6 D EEEE ED LI DLI Chemistry and corrosion control SWSK1 .03 Service Water System 2.7 EDDEEDDEED Circulating Water System ZOSA3.01 Onsite Standby Power System 3.2 D EDDEEEDDE Standby Diesel Generator starting and loading Page 3 of 3 01/11/2016 7:41AM

ES-401N, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES4OIN-2 KA NAME / SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO

CDSK4.07 Condensate System 2.6 Feedwater heater automatic isolation and bypass DRCSG2.228 Digital Rod Control System 3.9 4.6 DEED EEED Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

FHSK5.06 Fuel Handling System 2.7 3.0 Loss of Containment Air Filtration System llSK1O1 Incore Instrumentation System of ° NISA3.03 Nuclear Instrumentation System 3.6 P-l 7, Negative Flux Rate Alert PLCSA1 .08 Pressurizer Level Control System 3.1 DEED D1EEED Code safety tailpipe temperature RMSK2.01 Radiation Monitoring System 3.1 Radiation monitors that provide Engineered Safeguards Actuation System Actuations VFSK6.01 Containment Air Filtration System 2.5 DDDDEEEEDE Compressed Air System VLSA4.02 Containment Hydrogen Control 3.6 EEEDEEEEDD Containment hydrogen igniter System WGSK3.01 Gaseous Radwaste System 2.6 Plant Gas Systems Page 1 of 1 01/11/2016 7:41 AM

ES4OIN, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES4OIN-3 KA NAME / SAFETY FUNCTIO IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO G.2.3.9 Radiation Control 2.9 3.1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.

02.1.5 Conduct of operations 2.9 3.9 DEDDEEDDED - Ability to use procedures related to shift staffing, such as minimum crew complement, or overtime limitations.

G2.1.8 Conduct of operations 3.4 4.1 Ability to coordinate personnel activities outside the control room.

G2.2.15 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.

Equipment Control to-oquipm L fSl Ct. pfe/f -ø4 c/ nj fit- c4jci 5jt, Le.1 X 022.24 Equipment Control 3.9 4.5 Knowledge of less than or equal to one hour Technical Specification action statements. (This K/A does not include Action Statements of one hour or less that follow the expiration of a completion time for a Technical Specification condition for which an A G2.3.4 Radiation Control 3.5 3.6 DDE DDDD Ability to comply with radiation work permit requirements during normal or abnormal conditions.

G2.4.16 Emergency Procedures/Plans 4 4.6 D D D D D D D D D Knowledge of the parameters and logic used to assess the status of Emergency Operating Procedures Critical Safety Functions or Shutdown Critical Safety Functions.

02.4.38 Emergency Procedures/Plans 4.24.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material 02.4.8 Emergency Procedures/Plans 3.8 4.2 E E D D D LI LI LI Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

Page 1 of 1 01/11/2016 7:41 AM

ES-401N, REV 10 SRO TIGI PWR EXAMINATION OUTLINE FORM ES4OIN-2 KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO A-323AG2.2.21 Loss of 6.9KV, 4160 Volt, or 480 Volt 3.1 4.2 Ability to analyze the effect of maintenance activities, such Bus Power as degraded power sources, on the status of limiting conditions for operations.

A-329AG2.1.14 Loss of InstrumentAir 4 3.3 j Abilityto use integrated control systems to operate plant systems or components.

A-336AA2.02 Malfunction of Protection and Safety 4 3.7 j Diverse Actuation System indications Monitoring System E-1 EA2.04 Loss of Reactor or Secondary Coolant 3.4 3.4 Passive Residual Heat Removal System flow FR-C.l EG2.2.19 Response to Inadequate Core Cooling 0 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

FR-H.1EA2.02 Responseto Loss of Heat Sink 3.8 3.7 Reactor Coolant System pressure and/or temperature Page 1 of 1 01/11/2016 7:41 AM

ES-401N, REV 10 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES40IN-2 NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO A-308AA2.02 Loss of Control Room Air 2.3 2.8 Nuclear Island Nonradioactive Ventilation System flow Conditioning A-318AG2.2.22 Condensate System Malfunctions 0 4.6 Lj D Ability to determine operability or availability of safety related equipment.

ES-i .2EA2.07 Post Loss of Coolant Accident 3.2 3.7 Containment pressure Cool Down and Depressurization FR-C.32-44.d Response to Saturated Core 4.1 .l6%vv{cd f flpfai Cooling 3,b cedri sym8ls, n]icenO rfl fit5 tk-f14,. Ievcj i%e . we Page 1 of 1 01/11/2016 7:41AM

ES-401N, REV 10 SRO T2GI PWR EXAMINATION OUTLINE FORM ES4OIN-2 KA NAME / SAFETY FUNCTIO IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO CASA2.06 Compressed Air System 3 2.7 Loss of instrument air supply pressure CNSA2.03 Containment System 3.7 3.6 Normal Residual Heat Removal System containment isolation ESASG2.4.3 Engineered Safeguards Actuabon 3.7 3.9 Ability to identify post-accident instrumentation.

System FWSG2.l.21 Main and Startup Feedwater 4.3 4.4 Ability to perform general and/or normal operating System procedures during any plant condition.

RTS61 Reactor Trip System 4G-t E Kvl1je ul r iei c2.fl 3.1 q,r )(t c-i Ope(f-y PJJWeJ çt-e Lt Wik ctyø.cy Op Page 1 of 1 01/11/2016 7:41 AM

ES-401N, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO FPSG2.4.39 Fire Protection System 4.2 4 Ability to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.

SDCSA2.08 Steam Dump Control System 2.7 2.9 Main steam header pressure VESG2.4.24 Main Control Room HVAC 4.2 4.1 J Knowledge of annunciator alarms, indications, or response procedures.

Page 1 of 1 01/11/2016 7:42 AM

ES4OIN, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401N-3 KA NAME/SAFETYFUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO

_&2&8.LV Radiation Control Knowdc

2. 3.3 FhfJ +o P0 ir+.

G2.1 .30 Conduct of operations 3 Knowledge of the fuel-handling responsibilities of SROs.

G2.2.1l Equipment Control 3.9 4.3 7 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, or tag-outs.

G2.2.27 Equipment Control 3.5 3.9 D , Ability to obtain and/or interpret station electrical and mechanical drawings.

G2.3.5 Radiation Control 3.8 4.3 Ability to control radiation releases.

G2.4.39 Emergency Procedures/Plans 4.24 AbUity to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.

G2.4.6 Emergency Procedures/Plans 3.7 4.7 j Knowledge of Emergency/Abnormal Operating Procedures major action categories.

Page 1 of 1 01)11/2016 7:42AM

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

1. Clean answer sheets copied before grading
2. Answer key changes and question deletions justified and documented Ø
3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations) W &]
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail
5. All other failing examinations checked to ensure that grades are justified /1/k rJ4r (J]gf.
6. Performance on missed questions checked for training ,._

deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Date Printed Name/Signature

a. Grader ]4so 2 /%__- O/O(/o/7

/Z7 //

b. Facility Reviewer(*)
c. NRC Chief Examiner(*)
d. NRCSupervisor(*) cM/sN tI3)fl

(*) 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

Southern Nucear Southern Nucear 0peratng Comoany. nc.

9034 Rver Road John C. Austin. Ill Wayneboro. GA 30830 Training Director 706 826 6800 tel Plant Vogtle 3&4 706 826 1992 fax Jqaustetscuthernco.corn October 18, 2016 ND-i 6-2222 US, Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1 257 VOGTLE ELECTRIC GENERATING PLANT UNITS 3&4 NRC OPERATING EXAMINATION OUTLINES

Dear Mr. Bacon,

Attached please find the Vogtle 3 & 4 Operating Examination outline submittal and supporting documentation. The examination is being administered beginning the week of February 27, 2017. This examination package is being submitted in accordance with NUREG-1021, Revision 10. Reference materials have been submitted separately. The examination materials submitted must be withheld from public disclosure until after the examinations are complete.

Specific items provided include:

  • ES-201-2 (Examination Outline Quality Checklist)
  • ES-201-3 (Examination Security Agreement)
  • ES-301-1 (Administrative Topics Outline)
  • ES-301-2 (Control Room/In-Plant Systems Outline)

If you have any questions, please contact Chuck Howard at 706-848-7869.

Lead Instructor Exam Development Vogtle 3&4

Southern Nuclear P ai John G. ustin, Ill r A Training Director Plant Vogtle 3&4 33 7%

nw December 27, 2016 ND-i 6-2643 U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 ATTN: Mr. Bacon VOGTLE ELECTRIC GENERATING PLANT UNITS 3&4 NRC OPERATING AND WRITTEN EXAMINATIONS

Dear Mr. Bacon,

Provided by secure transmittal via FTP site please find the Vogtle 3 & 4 Operating and Written Examinations and supporting documentation. The examination is being administered beginning the week of February 27, 2017. This exam package is being submitted in accordance with NUREG-1021 Revision 10. The exam materials contained in this transmittal MUST be withheld from public disclosure until after the examinations are complete.

Specific items provided include:

  • ES-201-2 (Examination Outline Quality Checklist)
  • ES-201-3 (Examination Security Agreement)
  • ES-301-1 (Administrative Topics Outline)
  • ES-301-2 (Control Room/In-Plant Systems Outline)
  • ES-301-3 (Operating Test Quality Checklist) a ES-301-4 (Simulator Scenario Quality Checklist)
  • ES-D-2 (Required Operator Actions)

i- 2 ND-I 6-2643

£iher .).

If you have any questions, please contact Chuck Howard at 7O6$48-7$69.

Sincerely, C1uck Howard Lead Instructor Exam Development Vogtle 3&4

Southern Nuclear dent, Vogtle 3&4 WaynesboriGA 30830 (706) 848-7717 tel (706) 496-6149 cell kdlilie. southernco.ccm March 21, 2017 ND-i 7-0471 U.S. Nuclear Regulatory Commission, Region Ii 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257, ATTN: Mr. Daniel Bacon VOGTLE ELECTRIC GENERATING PLANT UNITS 3&4 POST EXAMINATION PACKAGE

Dear Mr. Bacon,

Attached please find the Vogtle 3 & 4 RO/SRO Initial License Exam Post Examination material and supporting documentation. The operating test was administered during the weeks of February 27 and March 6, 2017, and the written exam was administered on March 15, 2017.

This post-exam package is being submitted in accordance with NUREG-1021, Revision 10, Section ES-501 (Initial Post-Examination Activities).

Specific items provided include:

  • ES-20 1-3 (Examination Security Agreement)
  • Each applicants original answer sheet
  • One copy of each applicants original answer sheet
  • Master written examination with answer key, annotated with changes made while administering the exam
  • Written examination pertormance analysis
  • Questions asked by the candidates during the exam, with responses
  • Condition reports written for procedure revision suggestions, etc.
  • Applicant seating chart The Vogtle 3 & 4 facility has no post examination comments for this examination.

If you have any questions, please contact Chuck Howard at 706-848-7869.

Sincerely, Karen D. Fili Site Vice President

Southern Nuclear Karen 0. Fill Site Vice President, Vogtle 3&4 7825 River

\Vnyneshtro, GA 30830 706 ) 84 8-77)7 tel (706 4t-6l49 ccli kdlil iGsoUtbenlco.coiTt April 14, 2017 ND-i 7-0635 U.S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257, AUN: Mr. Daniel Bacon VOGTLE ELECTRIC GENERATING PLANT UNITS 3&4 POST EXAMINATION PACKAGE REDACTED -

Dear Mr. Bacon,

This letter provides information related to the Vogtle 3 & 4 Initial License Exam (ILT-2) operating test that was administered during the weeks of February 27 and March 6, 2017, and the written exam that was administered on March 15, 2017.

Enclosed is Westinghouse letter SVP_SVO_004793, which contains the following:

1) AFFIDAVIT CAW-17-4551
2) PROPRIETARY INFORMATION NOTICE and COPYRIGHT NOTICE
3) Southern Nuclear Company (SNC), Letter for Transmittal to the NRC
4) V3&4 NRC ILT-2 Admin Job Performance Measures (JPMs) (Proprietary)
5) V3&4 NRC ILT-2 Admin JPMs (Non-Proprietary)
6) V3&4 NRC ILT-2 In-Plant JPMs (Proprietary)
7) V3&4 NRC ILT-2 In-Plant JPMs (Non-Proprietary)
8) V3&4 NRC ILT-2 Sim JPMs (Proprietary)
9) V3&4 NRC ILT-2 Sim JPMs (Non-Proprietary)

JO) V3&4 NRC ILT-2 Simulator Scenarios (Proprietary)

11) UV3&4 NRC ILT-2 Simulator Scenarios (Non-Proprietary)
12) V3&4 NRC ILT-2 Written Exam (Proprietary)
13) V3&4 NRC ILT-2 Written Exam (Non-Proprietary)

Also enclosed is the Westinghouse Application for Withholding Proprietary Information from Public Disclosure CAW-17-4551, accompanying Affidavit, Proprietary Information Notice, and Copyright Notice.

As Items 4, 6, 8, 10, and 12 contain information proprietary to Westinghouse Electric Company LLC, it is supported by an Affidavit signed by Westinghouse, the owner of the information. The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commissions regulations.

ND-I 7-0635 Page 2 Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commissions regulations.

Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-17-4551 and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive, Building 3 Suite 310, Cranberry Township, Pennsylvania 16066.

This letter contains no regulatory commitments. Should you have any questions, please contact John C. Howard at 706-848-7869.

Sincerel Karen D. Fili Site Vice President, VEGP 3&4 KDF/MC/amw

Enclosure:

Westinghouse letter SVP SVO 004793, CAW-17-4551 (Transmittal of V3&4 NRC ILT-2 Admin JPMs, V3&4 ILT-2 In-Plant JPMs, V3&4 NRC ILT-2 Sim JPMs, V3&4 NRC ILT-2 Simulator Scenarios, and V3&4 NRC ILT-2 Written Exam) cc:

Southern Nuclear Orerating ComDany Mr. J. G. Austin (w/o enclosures)

Document Services RTYPE: VND.LI.L00 (w/o enclosures)

File AR.01 .02.06 fw/o enclosures)

Southern Nuclear Operating Company Vogtle Electric Generating Plant (VEGP) Units 3 and 4 ND-I 7-0635 Enclosure Westinghouse letter SVP_SVO_004793, CAW-17455f (Transmittal of V3&4 NRC ILT-2 Admin JPMs, V3&4 ILT-2 In-Plant JPMs, V3&4 NRC ILT-2 Sim JPMs, V3&4 NRC ILT-2 Simulator Scenarios, and V3&4 NRC ILT-2 Written Exam)

(This Enclosure consists of 1907 pages, including this cover page)

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