ML17212A448

301 Exam Administrative Items

ML17212A448
Person / Time
Site:	Farley
Issue date:	07/31/2017
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
Download: ML17212A448 (36)

Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility:

A44I,77 Developed by: itten:

Facility L<cRC D

-180 1.

Examination administration date confirmed (Cia; 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) 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-401 N-1/2, ES-401 -3, ES-401 N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; C.3.d) 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-3d -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 (Cii; C.2.g; ES-202)

-21 11.

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

-21 12.

Examinations reviewed with facility licensee (Cl.); 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) 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; ; 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)

Date of Examination:

II Operating Facility NRC D Target Task Description (Reference)

Date*

[-1201

{-85}

-7

• Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter.

They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

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

ES-201 Page 25 of 28

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: FARLEY Date ot ExamInation 04/03/17 Initials Item Ta5k Description

1 a.

Verify that the outline(s) fit(s) the appropriate model In accordance with ES-401 or ES-401N f2,.1Z b.

Assess whether the outline was systematically and randomly prepared In accordance with T

Section D.1 of ES-401 or ES4O1N and whether all K/A categories are appropriately sampled.

c.

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

N

d. Assess whether the justitlcation5 for deselected or rejected K/A statements are appropriate b

2.

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number at normal evolution5, 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 mix of applicants In accordance with the expected crew composition and rotation schedule c

without compromising exam Integrity, and ensure that each apptlcant can be tested using at 22, A

least one new or significantly modified scenario, that no scenarios are duplicated from the Ij T

applicants audit lest(s), and that scenarios wifi not be repeated on subsequent days.

c.

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

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 e

L (3) no tasks are duplicated tram the applicants audit test(s) t (

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

the form.

b.

Verify that the administrative outline meets the criteria specified on Form ES-aOl.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 1R.

r4 applicants and ensure that no Items are duplicated on subsequent days.

I 4.

a.

Assess whether plant-specific priorities (Including PRA and IPE Insights) are covered in the appropriate exam sectIons.

8 G

E b.

Assess whether the 10 CFR 55.41/43 and 55.45 sampling Is appropriate J

c.

Ensure that K/A Importance ratlng5 (except tot plant-specific priorities) are at least 2 5 j

R d.

Check for duplication and overlap among exam sections.

j C

e.

Check the entire exam tot balance of coverage.

f.

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

• J ij Printed NaI(4/iqatLji......_

Date

a. Author Stanely Jackson /

Mi\\

3-?fr j 7

b. Facility Reviewer ()

BiPy Thornton /

-it-3 zs - 7

c. NRC Chief Examiner (#)

A]Fs4fa.iJ L.ic, tr) 1). L&y)/3

.ØrV17 3 Iv I

d. NRC Supervisor

( 1i C..c.

3i4ot2t7 Note:

1. Independent NRC reviewer InWal Items In Cotumn c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines.

Outline supplied by the NRC

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: PARLEY Date of Examination: 04/03/17 Operating Test Number:FA2OI7-301 Initials

1. General Criteria a

b c#

a.

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

b.

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

f c.

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

d.

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

rC) e.

It appears that the operating test will differentiate between competent and tess-than-competent applicants at the designated license level, a

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 far completion) and specific designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that lnciude

detailed expected actions with exact criteria and nomenclature

system response and other examiner cues

/.

statements describing important observations to be made by the applicant

criteria for successful completion of the task

identification of critical steps and their associated performance standards

restrictions on the sequence of steps, If applicable b.

Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g.. item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201.2.

3. Simulator Criteria

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

=

Pn rne I Signature Date a.

Author Stanley Jackson /

b.

Facility Reviewer()

Billy Thornton!

&2 c:i4t.-_

3 w c.

NRCChiefExaminer(#) Ad(7A..

L;1)7 yhi/17

!tarh7 d.

NRC Supervisor GQct.

/

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-30f Simulator Scenario Quality Checklist Form ES-301-4 Facility:

12tRIEL, Date of Exam: A) ZolY Scenario Numbers:

I I 7._I 4/5)4 Operating Test No.:OI7)e(

QUALITATIVE ATTRIBUTES Initials

a b*

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.

1

-w-2.

The scenarios consist mostly of related events.

3.

Each event description 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.

5.

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

Li 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.

7.

The simulator modeling is not altered.

j_ 7 8.

The scenarios have been validated.

Pursuant to 10 CFR 55.4 6(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained white running the planned scenarios.

10 9.

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

scenarios have been altered in accordance with Section D.5 of ES-301.

/6 10.

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

.t

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

LI) 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).

F),

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

11214/5/6 1.

Malfunctions after EOP entry (1-2) 2/312! 2! 1 S

2.

Abnormal events (2-4) 4 /4 / 4 / 5 / 5 kS 3.

Majortranslents(12) 1 /2/2/212 r

4.

EOPs entered/requiring substantive actions (12) 1 / 1 /0/ 1 /0 5.

EOP contingencies requiring substantive actions (0-2) 0 / 0 I 1 / 1 $ 1 6.

EOP based Critical tasks(23) 3/2/5/4/6

• • _j NOTE:

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

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

2

$ - potential EOP Contingency

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 04/03/17 Operating Test No.: FA2017-301 A

E Scenarios 1

2 5

6 T

M L

N CREW CREW POSITION CREW POSITION CREW POSITION 0

I I

T POSmON

I C

S A

B S

A B

S A

B S

A B

A M

R T

0 R

T 0

R 1

0 R

i o

L u

T P

0 C

P 0

C P

0 C

P 0

C P

M(*)

E R

I U

Spencer RX 1

1 1

1 0

SRO-I 1111

/c 2456 4

4 2

SRO-U TS 2

0 2

2 Hershman RX

3

2 J

1 0

SRO-I NOR 3556442 SRO-U MAJ 67 78 79 2

2 1

TS 135 245

0 22 Myers RX 1

1 0

SRO-l NOR 1

1 1

1 I/C 2456 1235 15 13 4

4 2

SRO-U MA]

15 135 0

2 2

Burgess RX 1

4 1

1 0

SRO-I NOR 1

1 1

1 I/C 2456 1235 1

5 13 4

4 2

SRO-U MAJ TS 135 0

2 2

Instructions:

1.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SRO5 (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-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.

(*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 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 ATC 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 manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 04/03/17 Operating Test No.: FA2O1 7-301 A

E Scenarios 1

2 5

6 T

M L

N CREW CREW POSITION CREW POSITION CREW POSITION 0

I I

T POSm0N

T C

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 o

L u

T 0

C P

0 C

P 0

C P

0 C

P M(*)

E R

IU Johnson RX 1

1 1

1 0

SRO-I

/c 257 1245 9

4 4

2 SRO-U MAJ 2

2 1

TS 245 3

0 2

2 Ruble RX 1

1 2

110 NOR 3

1 SRO-l I/C 257 3456 1245 14 4

4 2

LJ 8

68 SRO-U MAJ 7

78 5

2 2

1 D

TS 245 245 6

0 2

2 Scarvey RX 1

1 2

1 J

0 SRO-I NOR 3

1 1

1 1

257 3456 1245 14 4

4 2

SRO-U TS

245 245 6

0 2

2 Gawne-RX 4

1 1

1 0

NOR

1 32 111 RO I/C 237 468 2468 10 4

4 2

MAJ 67 78 79 6

2 2

1 TS

°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-I) 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-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 04/03/17 Operating Test No.: FA2017-301 A

E Scenarios 1

2 5

6 T

M L

N CREW CREW POSITION CREW POSITION CREW POSITION I

I T

POSmON

T C

S A

B S

A B

S A

B S

A B

A M

R T

0 R

T 0

R 1

0 R

T o

L u

T P

0 C

P 0

C P

0 C

P 0

C P

M(*)

E

R IU J1Q RX 1

1 110 RO NOR 111 I/C 487 158 35 8

4 4

2 MAJ 7

67 78 2

2 1

TS

0022 Peachey RX 1

1 0

RO NOR 132111 I/C 237 468 2468 10 4

4 2

MAJ 67 78 79 6

2 2

1 TS 0022 Smith RX 1

1 1

1 0

RO NOR 4

111 I/C 467 158 35 8

4 4

2.

MAJ 7

67 78 2

2 1

TS 0022 Nesbia RX

4

1 1

1 0

RO NOR

13 21 ii I/C 237 468 2468 10 4

4 2

MA]

67 78 79 6

2 2

1 TS 0022 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 ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.

(*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 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 ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-l applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

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 (IIC) 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 ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.

(*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 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.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 04/03/17 Operating Test No.: FA2O17-3ij A

E Scenarios 1

2 5

6 T

M L

N CREW CREW POSITION CREW POSITION CREW POSITION o

I I

T POSmON

T C

S A

B S

A B

S A

B S

A B

A M

A R

T 0

R T

0 R

T 0

R T

o L

u P

0 C

P 0

C P

0 C

P 0

C P

M(*)

E R

IU RX Chavers RO TS

.4.

NOR

4

3111 I/C

467 158 35 4

4 2

MAJ 67 78 2

2 1

110 0

0 2

6

ç Instructions:

4.

For licensees that use the ATC 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-I in manipulating plant controls.

L p

ES-301 Competencies Checklist Form ES-301-6 fFacility: FARLEY Date of Examination: 04/03/17 Operating Test No.: FA2017-301 APPLICANTS RO BOP RD El RO El SRO-I El SRO-I El SRO-I SRO-I El SRO-U El SRO-U El SRO-U L

SRO-U El Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1245124512451 234 Interpret/Diagnose 25 23 23 23 46 I 5 46 46 24 I 2 23 23 7

67 57 57 67 78 78 56 35 45 45 Events and Conditions 8

8 7

8 7

67 67 67 8

8 8

Comply With and 12 23 23 13 13 13 14 i4 23 12 23 23 57 46 57 57 46 56 56 67 4535 45 45 Use Procedures (1) 7 8

8 7

78 78 8

67 67 68 67 8

Operate Control i 2 23 23 I 3 I 3 1 5 i 4 1 4 57 46 57 57 46 67 56 67 Boards (2) 7 8

7 Communicate 12 23 23 13 13 13 14 14 1212 i2 12 57 46 57 57 46 56 56 67 34 34 34 34 and Interact 7

7 7$

78 56 56 56 56 7

78 7$

7$

Demonstrate 12 12 12 12 34 34 34 34II.

Supervisory Ability (3) 5 6 5 6 5 6 56 II 7

78 78 Comply With and 4 5 13 263 24 UseTech.Specs.(3)

Notes:

(1)

Includes Technical Specification compliance for an RO.

(2)

Optional tot 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.)

Interpret/Diagnose Events and Conditions Comply With and Use Procedures (1)

V Operate Control I 3 Boards (2)

V Communicate I 3 and Interact V

Demonstrate Supervisory Ability (3)

Comply With 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.

Instructions:

Check the applicants license type and enter one or mote 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 factots as described on forms ES-303-7 and ES-303-3.)

ES-301 Competencies Checklist Form ES-301-6 Facility: FARLEY Date of Examination: 04/03/17 Operating Test No.: FA2017-301 APPLICANTS Competencies RO L1 BOP RO D

RO SRO-l D

SRO-I D

SRO-I E1 SRO-l E

SRO-U D

SRO-U D

SRO-U I1 SRO-U L1 SCENARIO 6

L..

I fi

ES4OI, Rev. 10 PWR Examination Outline Form ES4OI-2 Facility: f RL E >

Date of Exam:

,4,PR/c

?o/

RO K/A Category Points SRO-Only Points Tier Group

KKKKKKAAAAG A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total

= =

=

I

=

I AbnorrnalPlantE 2

N/A 2

2 N/A 19 2

2 4

Evolutions f Tier Totals 4

4 5

5 5

4 27 5

5 10

= =

=

=

1 233222 23333 28 3

2 5

2 IiJiiiEioiiio i1 1

3 Systems Tier Totals 3

4 4

3 3

3 3

4 3

4 41 38 3

8

3. Generic Knowledge and Abilities I

3 J4 10 1

2 f

3 4

7 Categories

2 2 L__

- 2 L 2 L 1

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 K/A category shall not be less than two). (One Tier 3 Radiation Control K/A 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 on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section 0.1.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 fIR) 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 I and 2 from the shaded systems and K/A categories.

7.

• The generic fG) 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.I.b of ES-401 for the applicable KAs.

8.

On the following pages, enter the K/A 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.

Forlier3, select topics from Section 2ofthe K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES4OI-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..

2.8 2.9 3.1 4.2 2.6 2.8 DEED ELItE DEED DEED DEED DEED LIED!

DEED tiLlED DEED ELIDE DEED ELIDE EED EED DEED DEED EDD DEED DEED ES-401, REV 70 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

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

RO SRO Decay power as a function of time LPI System 009EK3.20 Small Break LOCA / 3 3.5 4.3 011 EA2.08 Large Break LOCA / 3 3.4 3.9 015AA2.10 RCP Malfunctions / 4 3.7 3.7 OO7EKJ.05 Reactor Trip

- Stabilization

- Recovery 3.3 3.8 LI E

/1 008AA1.05 Pressurizer Vapor Space Accident / 3 3.4 3.3 LI LI LI DE DDE DDE DE LIED DEE DE EE 022AK1.03 Loss of Rx Coolant Makeup / 2 3

3.4 Tech-Spec leakage limits Conditions necessary for recovery when accident reaches stable phase When to secure RCPs on loss of cooling or seal injection Relationship between charging flow and PZR level 025AA1.23 Loss of RHR System /4 026AG2.2.36 Loss of Component Cooling Water /8 027AK2.03 Pressurizer Pressure Control System Malfunction / 3 029EK2.06 ATWS/

RHR heat exchangers 1

2.9 3.1 038EK1.02 Steam Gen. Tube Rupture / 3 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Controllers and positioners 3.2 DDLIEDLIDEEE Breakers, relays, and disconnects.

Leak rate vs. pressure drop Page 1 of 2 05/05/2016 1:24 PM

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

The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers RPS ES-407, REV 10 KA NAME / SAFETY FUNCTION:

040AG2.4.35 Steam Line Rupture

- Excessive Heat Transfer / 4 054AK3.04 Loss of Main Feedwater /4 056AA2.42 Loss of OH-site Power / 6 057AG2.4.20 Loss of Vital AC Inst. Bus/6 062AK3.0l Loss of Nuclear Svc Water / 4 065AA1.05 Loss of Instrument Air / 8 FORM ES-407-2 TOPIC:

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Actions contained in EOPs for loss of MFW Occurrence of a reactor trip TJG1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.8 4.0 4.4 4.6 4.1 4.1 3.8 4.3 3.2 3.5 3

3.3 3.9 4.2 WEO5EK2.2 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

Page 2 of 2 05/05/2016 1:24PM

ES-401, REV 70 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 059AA1.02 Accidental Liquid RadWaste Rel. / 9 074EK3.04 mad. Core Cooling / 4 WEO2EK1.1 SI Termination/3 WE13EA2.2 Steam Generator Over-pressure / 4 wel4EG2.l.19 Loss of CTMT Integrity / 5 24.4 3.2 3.9 WE16EK2.2 High Containment Radiation / 9 2.6 3.0 Facilitys heat removal systems, inch]ding primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

KA NAME I SAFETY FUNCflON:

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

nO SRO OO3AA1.04 Dropped Control Rod / 1 3.4 3.3 Control rod drive safety rod out limit bypass switch or key 024AK3.02 Emergency Boration / 1 036AA2.0l Fuel Handling Accident! 8 Actions contained in EOP for emergency boration ARM system indications ARM system 3.3 3.4 3.9 4.2 DEEDED 323.8 3.0 3.4 Tripping RCPs 3.9 3.8 EEEEEEEEEE Components, capacity, and function of emergency systems.

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Ability to use plant computer to evaluate system or component status.

Page 1 of 1 05/05/2016 1:24PM

DDE DEID DDE DD DEL DEE DEID EEL EiE DEE ES-401, REV 70 T2G7 PWR EXAMINATION OUTLINE FORM ES-407-2 KA NAME / SAFETY FUNCTION:

IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO 003G2.4.31 Reactor Coolant Pump 4.2 4.1 Knowledge of annunciators alarms, indications or response procedures 003K5.02 Reactor Coolant Pump 2.8 3.2 Effects of RCP coastdown on RCS parameters 004K5.35 Chemical and Volume Control 2.5 2.9 Heat exchanger principles and the effects of flow, temperature and other parameters 005K2.03 Residual Heat Removal 2.7 2.8 RCS pressure boundary motor-operated valves Emergency Core Cooling 4.2 4.3 006A3.08 007K4.0l Pressurizer Relief/Quench Tank 2.6 008A3.l0 Component Cooling Water 2.9 008G2.2.3 Component Cooling Water 3.8 3.9 D

E LI D

E E

E D

D D

E LI D

E LI D

E EID ED ED ED ED ED LIE ED ED EI DDD DEED DEED DEED DED DEED E1ED DED E LI LI LI DEED Automatic transfer of ECCS flowpaths Quench tank cooling 01 0K2.04 Pressurizer Pressure Control 01 2A1.01 Reactor Protection 012A2.05 Reactor Protection 2.7 2.9 2.9 3.4 CCW pump instruments and their respective sensors, including flow, pressure, oil level and discharge temperature (multi-unit license) Knowledge of the design, procedural and operational differences between units.

Indicator for code safety position Trip setpoint adjustment

Faulty or erratic operation of detectors and function generators 3.1 3.2 LIEDLIEEEDELI Page 1 of 3 05/05/20 16 1:24 PM

ES-407, REV 70 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 061 K6.02 Auxiliary/Emergency Feedwater 062A4.04 AC Electrical Distribution 062K1.02 AC Electrical Distribution 063K1.03 DC Electrical Distribution 2.6 2.7 4.1 4.4 2.9 3.5 KA NAME / SAFETY FUNCTION:

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

RO SRO 01 3K2.01 Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control 013K6.01 Engineered Safety Features Actuation 2.7 3.1 Sensors and detectors 022A1.02 Containment Cooling 3.6 3.8 Containment pressure 026A4.0l Containment Spray 4.5 4.3 CSS controls 039A2.03 Main and Reheat Steam 3.4 3.7 H

Indications and alatms tot main steam and area radiation monitors (during SGTR) 039K3.05 Main and Reheat Steam 3.6 3.7 J H j RCS 059G2.2.44 Main Feedwater 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 2.6 2.7 H

Pumps Local operation of breakers ED/G Battery charger and battery Page 2 of 3 05/05/2016 1:24PM

ES-407, REV 10 KA NAME / SAFETY FUNCTION:

064A4 01 Emergency Diesel Generator 073A2.02 Process Radiation Monitoring 076K3.03 Service Water 3.5 3.9 078K4.02 Instrument Air 3.2 3.5 103A3.01 Containment 3.9 4.2 103K3.03 Containment 3.7

4.1 TOPIC

Local and remote operation of the ED/G Detector failure Reactor building closed cooling water Cross-over to other air systems Containment isolation Loss of containment integrity under refueling operations.

FORM ES-401-2 T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RD SAD 4.0 4.3 2.7 3.2 Page 3 of 3 05/05/2016 1:24PM

ES-407, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

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

RO SAC Reactor Coolant 3.6 3.9 PZR and makeup tank level 002A1.02 014K1.02 Rod Posdion hidation 3.0 3

NIS 01 6A2.01 Non-nuclear Instrumentation 3.0 3.1 j

Detector failure 027K2.01 Contnment Iodine Removal 3.1 3.4 j

Fans 034G2.4.2 Fuel Handling Equipment 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

035K6.01 Steam Generator 3.2 3.6 MSlVs 071 K5.04 Waste Gas Disposal 2.5 3.1 j

Relationship of hydrogen/oxygen concentrations to flammability 072K3.02 Area Radiation Monitoring 3.1 3.5 Fuel handling operations 079A4.01 Station Air 2.727 H

H H H H H

Cross-tie valves whIAS 086K4.01 Fire Protection 3.1 3.7 H H H H H H H H H Adequate supply of water for FPS Page 1 of 1 05/05/2016 1:24 PM

ES-401,_REV 10 KA NAME / SAFETY FUNCTION:

IR T3 PWR EXAMINATION OUTLINE Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

Ability to make accurate, clear and concise verbal reports.

Knowledge of system purpose and or function.

Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Ability to recognize system parameters that are entry-level conditions for Technical Specifications Ability to control radiation releases.

Ability to use radiation monitoring systems Knowledge of EOP entry conditions and immediate action steps.

Knowledge of operator response to toss of all annunciators.

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

G2. 1.27 Conduct of operations G2.1.5 Conduct of operations RO SRO G2.1.17 Conduct of operations 3.9 4.0 fl D D FORM ES-401-2 3.94 2.9 3.9 DEEDED 4.6 4.1 DEEDED 3.9 4.6 DEEDED G2.2.2 Equipment Control G2.2.42 Equipment Control G2.3.1 1 Radiation Control EEDE DDE EI EDDE EDEE 3.8 4.3 DEDEEEDEDEI G25RaaUonControl 2929DDEEDDEDEE G2.4.1 Emergency Procedures/Plans 4.6 4.8 D E D D E E D E E D G2.4.32 Emergency Procedures/Plans 3.6 4.0 E D D E D D D D D E 54.7 G2.4.4 Emergency Procedures/Plans Page 1 of 1 05/05/2016 1:24 PM

ES-407, REV 10 SRO TJG1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:

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

RO SAC 008AG2.1.7 Pressurizer Vapor Space Accident /3 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

025AA2.04 Loss of RHR System /4 3.3 3.6 Location and isolability of leaks 056AG2.2.22 Loss of Off-site Power / 6 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

065AA2.02 Loss of Instrument Air / 8 242.6 Relationship of flow readings to system operation weO4EG2.4.3 LOCA OutsJe Containment / 3 2.7 4.1 D D Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

WEO5EA2.2 Inadequate Heat Transfer

- Loss of 3.7 4.3 Adherence to appropriate procedures and operation Secondary Heat Sink / 4 within the limitations in the facilitys license and amendments.

Page 1 of 1 05/05/2016 1:24 PM

ES-401, REV 10 KA NAME I SAFETY FUNCTION:

001 AA2.02 Continuous Rod Withdrawal / 1 028AG2.2.25 Pressurizer Level Malfunction / 2 3.2 4.2 060AG2.2.37 Accidental Gaseous Radwaste Rel. / 9 3.6 4.6 061AA2.02 ARM System Alarms / 7 2.9 3.2 SRO TJG2 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 4.2 4.2 Position of emergency boration valve FORM ES-401-2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Ability to determine operability and/or availability of safety related equipment Normal radiation intensity for each ARM system channel Page 1 of 1 05/05/2016 1:24 PM

FORM ES-401-2 G

TOPIC:

Knowledge of the emergency action level thresholds and classifications.

Knowledge of the parameters and logic used to assess the status of safety functions LI Loss of ventilation during battery charging LossofSWS Necessary plant conditions for work in containment ES-401, REV 10 KA NAME I SAFETY FUNCTION:

012G2.4.41 Reactor Protection 039G2.4.21 Main and Reheat Steam 063A2.02 DC Electrical Distribution 076A2.Ol Service Water 1 03A2.02 Containment SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 RO SRO 2.9 4.6 O4.6 2.3 3.1 3.5 3.7 2.2 3.2 Page 1 of 1 05/05/2016 1:24PM

ES-407, REV 70 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

028A2.03 Hydrogen Recombiner and Purge Control 034K5.02 Fuel Handling Equipment 3.4 4.0 2.6 The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment Limiting of load KA NAME I SAFETY FUNCTION:

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

RO SRO 001 G2.1.23 Control Rod Drive 4.3 4.4 Page 1 of 1 05/05/2016 7:24 PM

ES-401, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

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

RD SRO G2.l.35 Conduct of operations 2.2 3.9 Knowledge of the fuel handling responsibilities of SROs G2.l.40 Conduct of operations 2.8 3.9

/

Knowledge of refueling administrative requirements G2.2.17 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance activities during power operations.

G2.2.19 Equipment Control 2.3 3.4 Knowledge of maintenance work order requirements.

G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems 02.4.20 Emergency Procedures/Plans 3.84.3 Li Li Li Li Li Knowledge of operational implications of EOP warnings, cautions and notes.

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

Page 1 of 1 05/05/2016 1:24 PM

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Farley Date of Exam: April 2017 Exam Level:

RO SRO 3

]

Item Description Initials a

b c

1.

Clean answer sheets copied before grading 2.

Answer key changes and question deletions justified and documented N)11 3.

Applicants scores checked for addition errors

(reviewers spot check> 25% of examinations) 55 ZyC 4.

Grading for all borderline cases (80 +/-2% overall and 70 or 80,

as applicable, +/-4% on the SRO-only) reviewed in detail SS 5.

All other failing examinations checked to ensure that grades

are justified iJ JP 6.

Performance on missed questions checked for training

deficiencies and wording problems; evaluate validity of V

questions missed by half or more of the applicants Printed Name/Signature Date a.

Grader 5LW1-IA SH/H/cJI%tL ()JtA&L QS/oI/2oI b.

Facility Reviewer(*)

c.

NRC Chief Examiner (*)

3/(

d.

NRC Supervisor (*)

f/)zi7

(*)

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

Southern Nuclear Operatia Farley Nuclear Plant Post Office Drawer 470 Ashford,AL 36312 Tel 334.814.4511 Fax 334.814.4575 March 1, 2017 FNP-201 7-0008 -TRN Mrs. Catherine Haney Regional Administrator, Region II United States Nuclear Regulatory Commission 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Attention: Mr. David Lanyi

Dear Mr. Lanyi,

Enclosed for your review are the preliminary uncertified license applications and medical certifications for the license candidates currently enrolled in the Operator License Training program at J.M. Farley Nuclear Plant.

Should you have any questions regarding these applications or medical certificates, please contact Mr.

Vince Richter, Operations Lead Instructor at 334-814-4689.

Sincerely, Vince Richter Operations Lead Instructor

- Farley CVR/SCD

Southern Nuclear September 16, 2015 Mrs. Catherine Haney Regional Administrator, Region II United States Nuclear Regulatory Commission 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Attention: Mr. David Lanyi

Dear Mr. Lanyi,

Southern Nuclear Operating Company, Inc.

Farley Nuclear Plant Post Office Drawer 470 Ashtord, AL 36312 Tel 334.8144511 Fax 334.814.4575 FNP-20 1 7-0009-TRN Farley Nuclear Plant formally requests the NRC administer an operating test and a written examination beginning April 3, 2017 to candidates whose final Personal Qualification Statement-Licensee and Certification of Medical Examination by Facility licensee forms are included with this submittal.

If you should have any questions regarding this matter, please contact Mr. Vince Richter, Operations Lead Instructor, at 334-814-4579.

BRIscd I

.201?

Sincerely, Training Director farley

Southern Nuclear FNP-201 7-0001 0-TRN Operating Company, Inc.

Post Office Drawer 470 Ashlord, Alabama 36312 SOUTHERN Tel 334.B99 5156 COMPANY Fax 334.8144661 03/20/17 Mr. David Lanyi U.S. Nuclear Regulatory Commission, Region 11 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. Lanyi, The final submittal for the Opetating Exam portion of the 2017 farley Nuclear Plant Licensing Exam is attached. All documents have been submitted via file Transfer Protocol. Physical copies are available at your request. All exam materials must be withheld from public disclosure until after the examination is complete.

The following documents have been submitted:

15-201-2, Examination Outline Quality Checklist ES-201-3, Examination Security Agreement ES -301-1, Administrative Topics Outline ES-301-2, Control Roomlln-Plant Systems Outline ES-301-3, Operating Test Quality Checklist ES-301-4, Simulator Scenario Quality Checklist ES-301-5, Transient and Events Checklist ES-301-6, Competencies Checklist ES-D-l, Scenario Outlines (Previously submitted on 31717)

ES-D-2, Scenario Required Actions (Previously submitted on 3/17/17)

Control Room/in-Plant Systems JPMs with references (Previously submitted on 3/17/17)

Administrative Topic JPMs with references (Previously submitted on 3/17/i?)

Contact Billy Thornton, Stanley Jackson, or Jeremy Jefcoat, at 334-814-4758 with any questions.

(,3BIIIS Thornton Operations Lead Cnstructor Exam Development cc:

File

Southern Nuclear FNP-201 7-0001 9-TRN Operating Company. Inc.

Post Office Drawer 470 Ashtord, Alabama 36312 SOUTHERN Tel 334.899.5156 COMPANY Fax 334.814.4661 April 20, 2017 Mr. David Lanyi U.S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. Lanyi, NRC Initial written examination fA2017-301 was administered on April 18, 2017. form ES-201-3, Exam Security Agreement, will be completed as soon as possible and delivered electronically. There were no substantive applicant comments during post exam review.

The following documents are enclosed:

Original exam cover sheet for each applicant.

Original answer sheet (SCANTRON) for each applicant.

One copy of the answer sheet for each applicant.

Original questions asked by applicants during the exam.

Test item statistics (RO and SRO).

Exam Score Summary (RO and SRO).

Exam Seating Chart.

RO composite exam with changes.

SRO composite exam with changes.

Exam key with changes.

Copy of partially completed ES-20l-3, Exam Security Agreement.

Contact Billy Thornton, Stan Jackson or Jeremy Jefcoat, J

Brian Reed Training Director cc: file