ML16049A502

Initial Exam 2015-301 Final Administrative Documents

ML16049A502
Person / Time
Site:	Farley
Issue date:	02/18/2016
From:	Division of Reactor Safety II
To:	Southern Nuclear Operating Co
References
Download: ML16049A502 (45)

Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Farley Date of Examination: Oct., 2015 Developed by: Written: Facility NRC II Operating Facility NRC Target . . Chief Task Description (Reference)

Date Examiners Initials

-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 (C2.d)

[-120] 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-i, ES-401-112, ES-401N-112, ES-401-3, ES-401N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; Cad)

(-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)

-21 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-21 12. Examinations reviewed with facility licensee (Ci.]; C.2.f and h; C.3.g)

-14 13. Final license applications due and Form ES-201-4 prepared (C.1 .1; 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 I 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.

ES-201 Examination Outline Quality Checklist Eprm ES-201-2 Facility: FAR LEY Date of ExaminatIon 10/5/15 Item Task Descnpticn Initiats 1 a. Venfy that the outline(s) fit(s) the appropriate model, In accordance with ES-401 or ES-401N ,* jZ.

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

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

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

$ [ c.

Z..

2. a. Using Form ES-301-5, verily 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 lest(s), and lhat 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 cntena specified on Form ES-301-4 and described in Appendix D.

3. a. Verily that the systems walk-through outline meets the criteria specified ocr 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 repelilion 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 cI new or modified tasks meets or exceeds the nininiums 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 (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 priontles (Including PRA and IPE insights) are covered In the appropriate exam sections b Assesswhetherthe ID CFR 55.41143 and 5545 sampling Isappropnate c Ensure that K/A Importance ratings (except for plant-specific priorities) are at least 2.5 R d. Check for duplication and overlap among exam sections L e. Check the entire exam for balance of covera9e -

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

PnnteNa4ture Date a Author Stanley Jackson 9)22)15

b. Facility Reviewer () Billy Thornton / 9)22/15 c, NRC Chief Examiner (#) .3)o.,c) / LL 9 )?.j/,.,(

d NRC Supervisor

/ --

Note # Independent NRC reviewer initial Items in Column c, chief examiner concurrence required.

Not applicable for NRC-prepared examination outines.

Outline provided by NRC.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO X SRO Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a

Title:

Monitor CSFST. Given a set of conditions, R, D the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, D

Title:

Determine maximum RHR flowrate and time to saturation for a loss of RHR event. Given a set Conduct of Operations of conditionsthe applicant will : Determine maximum RHR flowrate and time to saturation for RO a loss of RHR event.

G2.1.25 - 3.9 / 4.2 A.2

Title:

Perform a QPTR. Given a set of conditions, R, M determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio.

RO G2.2.12 - 3.7 /4.1 A.3

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control R, D conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 NONE SELECTED Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO SRO x Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a R, D

Title:

Monitor CSFST. Given a set of conditions, the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, M

Title:

Determine Active License Status. Given a set of conditions, the applicant will have to Conduct of Operations determine the status of 3 individuals license.

SRO G2.1.4 - 3.3 / 3.8 A.2 R, D

Title:

Perform a QPTR. Given a set of conditions, determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio. Determine what Tech Specs actions, if any, are required.

SRO G2.2.12 - 3.7 / 4.1 G2.2.40 - 3.4 / 4.7 G2.2.42 - 3.9 / 4.6 A.3 R, D

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 A.4 R, M

Title:

Classify an emergency event.

Emergency Plan G2.4.40 - 2.7 / 4.5 G2.4.41 - 2.9 / 4.6 SRO NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: FARLEY Date of Examination: 10/05/15 Exam Level: RO X SRO-I X SRO-U X Operating Test No.: FA2015-301 Control Room Systems: 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. CRO-074: Fill the 1A SIS Accumulator: the 1A Accumulator low and will D, S 2 be filled using SOP-8.0, Safety Injection - Accumulators.

006A1.13 - 3.5 / 3.7 006A4.02 - 4.0 / 3.8

b. CRO-333: Perform the required actions for Cold Leg Recirculation. A, D, EN, L, S 3 During the performance of the procedure, a valve will not close requiring an (SRO-U) alternate path.

011EA1.11 - 4.2 / 4.2 011EA1.13 - 4.1 / 4.2

c. 343G: Restore Service water to normal in response to a spurious Safety D, L, S 4S Injection - Applicant will restore Service Water using ESP-1.1, SI Termination.

062AA1.02 - 3.2 / 3.3 076A4.02 - 2.6 / 2.6

d. CRO-043B: Start the 1A RCP - After starting the 1A RCP, a high bearing A, D, S 4P temp alarm will be received requiring the 1A RCP to be secured.

003A1.02 - 2.9 / 2.9 003A2.03 - 2.7 / 3.1

e. CRO-406B (MOD): Verify Phase B Containment Isolation and A, M, S 5 Containment Spray Initiation. Containment pressure will be above 27psig (SRO-U) and Phase B / Containment Spray will not have actuated. Requires manual actions to start Containment spray and isolate valves.

WE14EA1.1 - 3.7 / 3.7 103A3.01 - 3.9 / 4.2

f. CRO-NEW: Perform Corrective Actions to a trip of the On Service CCW A, N, L, S 8 pump. The plant is in Mode 3 and the loss of the On Service train of CCW occurs while shifting Heat Exchangers.

008A2.01 - 3.3 / 3.6 026AA1.02 - 3.2 / 3.3

g. CRO-033 (MOD): Perform STP-5.0, Full Length Control Rod Operability A, M, S 1 Test. Applicant will insert Control Bank D 10 steps and when the rods are (SRO-U) withdrawn, they will continue to move when the Rod Control Switch is released. When rods are placed in AUTO, they will continue to move requiring a trip.

001A2.11 - 4.4 / 4.7 001A3.02 - 3.7 / 3.6 001AA1.05 - 4.3 / 4.2

h. CRO-039A: Adjust Setpoint of the N-16 Primary to Secondary Leak D, S 7 Detection System (R-70B). Applicant will change the R-70B setpoint to 75 (RO ONLY) gpd.

073A4.02 - 3.7 / 3.7

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

i. CRO- 607A (UNIT 1) : Perform the required actions to minimize DC loads. D, E, L 6 ECP-0.0 is in progress and the applicant is required to minimize DC loads in (SRO-U) the Non-Rad Aux Building.

055EA1.04 - 3.5 / 3.9

j. SO-444 (UNIT 1): Restore Compressed Air Systems After an Auto D 8 Isolation. Unit 1 has an extra valve that is operated by this JPM.

065AA1.03 - 2.9 / 3.1

k. SO-368A: Align RCDT Discharge to the WHT - Applicant is required to D, R 9 reduce RCT level from 50% to 10% per SOP-50.0, Liquid Waste Processing. (SRO-U) 068K1.07 - 2.7 / 2.9

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

• Type Codes Criteria for RO / SRO-I / SRO-U A)lternate path 4-6 / 4-6 / 2-3 5/5/3 (C)ontrol room (D)irect from bank 9/8/4 8/7/3 (E)mergency or abnormal in-plant 1/1/1 1/1/1 (EN)gineered safety feature 1 / 1 / 1 (control room system) 1 / 1 / 1 (L)ow-Power / Shutdown 1/1/1 4/4/2 (N)ew or (M)odified from bank including 1(A) 2/2/1 3/3/2 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0/0/0 (R)CA 1/1/1 1/ 1/ 1 (S)imulator 8/7/3

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: FARLEY Date of ExamInation; 10/5/15 Operating Test Number: FA2015.301 1 General CriterIa Initials 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 distnbution).

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

c. The operating test shall not duplicate Items from the applicanls 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.

a. It appears that the operating test Will differentiate between competent and lass-than-competent lhtl.

applicants at the designated license level.

1:31

2. Walk-Through CrIteria -.

a. Each JPM includes the following, as applicable:

• initial conditions

• Initialing cues

• references and tools, Including associated procedures

- reasonable and validated time limits (average time allowed for completion) and specific designation it deemed 10 be time-critical by the facility licensee

• operationally Important specific performance criteria that Include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria ror successful completion of tile 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 outJines (Forms ES-301-1 and 2) have not caused the test to deviale 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.

Pd t ame I Signature Date

a. Author Stanley Jackson/ - 9/22/15

b. Facility Revlewer() 8ilv Thornton 9/22/15

c. NRC Chle(Examiner(#) ic) L.o.y ,/(

d. NRCSupervisor Ccç\ I y

NOTE:

• The tacitly signature Is not applicable for NRC-developed tests.

1. Independent NRC reviewer initial items In Column c, chief examiner concurrence required. -

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: FARLEY Date of Exam: 10/05115 Scenario Numbers: 2 I 3 I 4 / 51 6 Operating Test No.: FA2O1S-301 QUALITATIVE ATTRIBUTES Initials a b c#

1. The Initial conditions are realistic, In that some equipment and/or Instrumentation may be out of service, but it does not cue the operators Into expected events.

2. The scenarios consist mostly of related events.

3. Each event desaiption 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 syrriptomslcues that will be vIsible to the crew

. the expected operator actions (by shift position)

. the event termination point (II 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.

6. If lime compression techniques are used, the scenario summary dearly so Indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. A çt Cues are given. . f I J

7. The simulator modeling Is not altered.

8. The scenarios have been valIdat. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional A L

fidelity Is maintained while running the planned scenarios.

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

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

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

1 2. Each applicant will be significantly Involved In the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

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

Target Quantitative Attributes (Per Scenario; See SectIon D.5.d) Actual Attributes 213/4/5/6

1. Maifunctlons after EOP entry (1-2)

2. Abnormal events (2-4) 3 / 1 /212 / 2 iL X.

5/5/5/4/4 *1:___ j ,L

3. Major transients (12) 2/2(1 I 2 / 1 Z.

4. EOPs entered/requiring substantive actions (12)

5. EOP contingencies requiring substantive actions (0-2) 1 1 1 I1 10/0 1 I 0/0/ 1 / 1 4-j_ 4_

j fj2 s<)t

6. EOP based Critical tasks (23) 2 I 2 /2 /2 /2 -

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

1. Independent NRC reviewer Initial Items In Column c; chief

• examiner concurrence required.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 10/5/15 Operating Test No.: FA2015-301 A E Scenarios P V 2 5 3 4 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U JOHNSON RX 1 6 1 3 1 1 0 SRO-I NOR 1 1 2 1 1 1 I/C 123 478 245 15 4 4 2 567 67 8

MAJ 78 89 7 5 2 2 1 TS 35 6 346 6 0 2 2 RX 1 6 1 3 1 1 0 KOENIG NOR 1 1 2 1 1 1 I/C 123 478 245 15 4 4 2 SRO-I 567 67 8

MAJ 78 89 7 5 2 2 1 TS 35 6 346 6 0 2 2 RO RX 1 1 0 X

NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2

Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (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-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 10/5/15 Operating Test No.: FA2015-301 A E Scenarios P V 2 5 3 4 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U Darrah RX 1 1 1 1 0 RO NOR 1 1 1 1 1 I/C 35 457 5 4 4 2 MAJ 89 7 3 2 2 1 TS 0 0 2 2 Day RX 3 1 1 1 0 NOR 4 1 2 1 1 1 RO I/C 236 25 267 10 4 4 2 78 MAJ 78 78 7 5 2 2 1 TS 0 0 2 2 Elliot RX 4 1 1 1 0 RO NOR 1 1 2 1 1 1 I/C 157 467 35 8 4 4 2 MAJ 78 78 89 6 2 2 1 TS 0 0 2 2 Patterson RX 3 1 1 1 0 RO NOR 4 1 2 1 1 1 I/C 236 78 25 267 10 4 4 2 MAJ 78 78 7 5 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (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-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 10/5/15 Operating Test No.: FA2015-301 A E Scenarios P V 2 5 3 4 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U Pollard RX 4 1 1 1 0 RO NOR 1 1 1 1 1 I/C 157 467 6 4 4 2 MAJ 78 78 4 2 2 1 TS 0 0 2 2 Reznikov RX 3 1 1 1 0 RO NOR 4 1 2 1 1 1 I/C 236 78 25 267 10 4 4 2 MAJ 78 78 7 5 2 2 1 TS 0 0 2 2 Sauls RX 4 1 1 1 0 RO NOR 1 1 2 1 1 1 I/C 157 467 35 8 4 4 2 MAJ 78 78 89 6 2 2 1 TS 0 0 2 2 RO RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (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-I in manipulating plant controls.

ES-301 Competencies Checklist Form ES-301-6 Facility: FARLEY Date of Examination: 10/5/15 Operating Test No.:FA2015-301 APPLICANTS RO BOP RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 2 5 3 4 2 5 3 4 2 5 3 4 2 5 3 4 Interpret/Diagnose 14 23 46 13 23 46 13 12 12 23 12 23 57 57 78 45 67 78 58 67 34 45 34 45 Events and Conditions 8 8 9 7 8 9 56 67 56 67 78 8 78 9

Comply With and 14 23 46 14 23 13 13 12 34 24 34 24 57 57 78 57 46 46 58 67 56 56 56 56 Use Procedures (1) 8 8 9 78 78 9 78 78 89 7 Operate Control 14 23 46 14 23 13 13 12 57 57 78 57 46 46 58 67 Boards (2) 8 8 9 78 78 9 Communicate 12 23 45 14 23 13 12 12 12 12 12 12 45 57 67 57 46 46 34 46 34 34 34 34 and Interact 67 8 89 78 78 57 7 56 56 56 56 8 89 78 78 78 7 9

Demonstrate 12 12 12 12 34 34 34 34 Supervisory Ability (3) 56 56 56 56 78 78 78 7 9

Comply With and 35 24 26 34 5 6 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.

ES-301 Competencies Checklist Form ES-301-6 Facility: FARLEY Date of Examination: 10/5/15 Operating Test No.:FA2015-301 APPLICANTS RO BOP RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 6 6 6 Interpret/Diagnose 25 13 12 Events and Conditions 67 47 34 56 7

Comply With and 25 13 34 Use Procedures (1) 67 47 56 7

Operate Control 25 13 Boards (2) 67 47 Communicate 24 13 12 and Interact 56 45 34 7 7 56 7

Demonstrate 12 Supervisory Ability (3) 34 56 7

Comply With and 34 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.

ES-401 PWR Examination Outline Form ES-401-2 Facility: Farley Date of Exam: October, 2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

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

Abnormal 2 2 1 1 N/A 2 1 N/A 2 9 2 2 4 Plant Evolutions Tier Totals 5 4 4 5 4 5 27 5 5 10 1 3 3 2 3 2 3 3 2 3 2 2 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 2 3 2 3 1 2 2 2 7 Note: 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 outline, 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 with justification; operationally important, site-specific systems/evolutions 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 1 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 K/As.

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 a category 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 K/A 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.

G* Generic K/As

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000007 (BW/E02&E10; CE/E02) Reactor X 007EA2.03; Ability to determine or interpret the 4.4 Trip - Stabilization - Recovery / 1 following as they apply to a reactor trip: Reactor trip breaker position.

000008 Pressurizer Vapor Space X 008G.2.1.32; Ability to explain and apply system 3.8 Accident / 3 limits and precautions.

009EA1.17; Ability to operate and monitor the 000009 Small Break LOCA / 3 X following as they apply to a small break LOCA: PRT 3.4 011EK3.05; Knowledge of the reasons for the 000011 Large Break LOCA / 3 X following responses as they apply to the Large Break 4.0 LOCA: Injection into cold leg.

015AA2.08; Ability to determine and interpret the 000015/17 RCP Malfunctions / 4 X following as they apply to the Reactor Coolant Pump 3.4 Malfunctions (Loss of RC Flow): When to secure RCPs on high bearing temperature.

022AA2.02; Ability to determine and interpret the 000022 Loss of Rx Coolant Makeup / 2 X following as they apply to the Loss of Reactor 3.2 Coolant Makeup: Charging pump problems.

025AG2.4.2; Knowledge of system set points, 000025 Loss of RHR System / 4 X interlocks and automatic actions associated with EOP 4.5 entry conditions.

000026 Loss of Component Cooling X 026AG2.4.46; Ability to verify that the alarms are 4.2 Water / 8 consistent with the plant conditions.

027AK2.03; Knowledge of the interrelations between 000027 Pressurizer Pressure Control X the Pressurizer Pressure Control Malfunctions and the 2.6 System Malfunction / 3 following: Controllers and positioners.

029EK2.06; Knowledge of the interrelations between 000029 ATWS / 1 X the following and the following an ATWS: Breakers, 2.9 relays, and disconnects.

038EK1.02; Knowledge of the operational 000038 Steam Gen. Tube Rupture / 3 X implications of the following concepts as they apply 3.2 to the SGTR: Leak rate vs. pressure drop.

WE12EK1.3; Knowledge of the operational 000040 (BW/E05; CE/E05; W/E12) X implications of the following concepts as they apply 3.4 Steam Line Rupture - Excessive Heat to the (Uncontrolled Depressurization of all Steam Transfer / 4 Generators) Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

054AA1.04 ; Ability to operate and / or monitor the 000054 (CE/E06) Loss of Main X following as they apply to the Loss of Main 4.4 Feedwater / 4 Feedwater (MFW): HPI, under total feedwater loss conditions.

055EK3.02; Knowledge of the reasons for the 000055 Station Blackout / 6 X following responses as they apply to the Station 4.3 Blackout: Actions contained in EOP for loss of offsite and onsite power.

056AG2.2.44; Ability to interpret control room 000056 Loss of Off-site Power / 6 X indications to verify the status and operation of a 4.4 system, and understand how operator actions and directives affect plant and system conditions.

057AA2.16; Ability to determine and interpret the 000057 Loss of Vital AC Inst. Bus / 6 X following as they apply to the Loss of Vital AC 3.0 Instrument Bus: Normal and abnormal PZR level for various modes of plant operation.

058AA1.02; Ability to operate and / or monitor the 000058 Loss of DC Power / 6 X following as they apply to the Loss of DC Power: 3.1 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector.

062AK3.01; Knowledge of the reasons for the 000062 Loss of Nuclear Svc Water / 4 X following responses as they apply to the Loss of 3.2 Nuclear Service Water: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers.

065AA2.06; Ability to determine and interpret the 000065 Loss of Instrument Air / 8 X following as they apply to the Loss of Instrument Air: 4.2 When to trip reactor if instrument air pressure is de-creasing.

WE04EG2.2.4; (multi-unit license) Ability to explain W/E04 LOCA Outside Containment / 3 X the variations in control board/control room layouts, 3.6 systems, instrumentation, and procedural actions between units at a facility.

4.4 WE04EG2.1.2; Knowledge of operator X responsibilities during all modes of plant operation.

WE11EK1.3; Knowledge of the operational W/E11 Loss of Emergency Coolant X implications of the following concepts as they apply 3.6 Recirc. / 4 to the (Loss of Emergency Coolant Recirculation):

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation).

WE05EA2.1; Ability to determine and interpret the BW/E04; W/E05 Inadequate Heat X following as they apply to the (Loss of Secondary 4.4 Transfer - Loss of Secondary Heat Sink / 4 Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

077AK2.01; Knowledge of the interrelations between 000077 Generator Voltage and Electric X Generator Voltage and Electric Grid Disturbances and 3.1 Grid Disturbances / 6 the following: Motors.

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000001 Continuous Rod Withdrawal / 1 X 001AG2.1.32; Ability to explain and apply 3.8 system limits and precautions.

003AG2.1.23; Ability to perform specific 000003 Dropped Control Rod / 1 X 4.4 system and integrated plant procedures during all modes of plant operation.

000005 Inoperable/Stuck Control Rod / 1 024AA2.05; Ability to determine and 000024 Emergency Boration / 1 X 3.9 interpret the following as they apply to the Emergency Boration: Amount of boron to add to achieve required SDM.

000028 Pressurizer Level Malfunction / 2 X 028AG2.1.25; Ability to interpret 4.2 reference materials, such as graphs, curves, tables, etc.

000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 037AK1.02; Knowledge of the operational 000037 Steam Generator Tube Leak / 3 X 3.5 implications of the following concepts as they apply to Steam Generator Tube Leak:

Leak rate vs. pressure drop.

000051 Loss of Condenser Vacuum / 4 X 051G2.2.38; Knowledge of conditions 3.6 and limitations in the facility license.

000059 Accidental Liquid RadWaste Rel. / 9 060AK2.01; Knowledge of the 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.6 interrelations between the Accidental Gaseous Radwaste Release and the following: ARM system, including the normal radiation-level indications and the operability status.

000061 ARM System Alarms / 7 067AA1.06; Ability to operate and / or 000067 Plant Fire On-site / 8 X 3.5 monitor the following as they apply to the Plant Fire on Site: Fire alarm.

068AK3.03; Knowledge of the reasons for 000068 (BW/A06) Control Room Evac. / 8 X 3.7 the following responses as they apply to the Control Room Evacuation: Transfer of AFW flow control valves and pumps to local control.

000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 076AA2.03; Ability to determine and 000076 High Reactor Coolant Activity / 9 X 2.5 interpret the following as they apply to the High Reactor Coolant Activity: RCS radioactivity level meter.

W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4

WE15EK1.2; Knowledge of the W/E15 Containment Flooding / 5 X 2.7 operational implications of the following concepts as they apply to the (Containment Flooding): Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

W/E16 High Containment Radiation / 9 WE10EA2.2; Ability to determine and BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X 3.9 interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

WE08EA1.1; Ability to operate and / or CE/A11; W/E08 RCS Overcooling - PTS / 4 X 3.8 monitor the following as they apply to the (Pressurized Thermal Shock):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

K/A Category Point Totals: 2 1 1 2 1/2 2/2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 003A2.03; Ability to (a) predict the 003 Reactor Coolant Pump X impacts of the following malfunctions or 2.7 operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.

003G2.4.45; Ability to prioritize and X interpret the significance of each 4.3 annunciator or alarm.

004A2.24; Ability to (a) predict the 004 Chemical and Volume X impacts of the following malfunctions or 2.8 Control operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Isolation of both letdown filters at one time: down-stream relief lifts.

004A1.05; Ability to predict and/or 2.9 monitor changes in parameters (to X

prevent exceeding design limits) associated with operating the CVCS controls including: S/G pressure and level.

005A1.03; Ability to predict and/or 005 Residual Heat Removal X monitor changes in parameters (to 2.5 prevent exceeding design limits) associated with operating the RHRS controls including: Closed cooling water flow rate and temperature.

005K3.06; Knowledge of the effect that a X loss or malfunction of the RHRS will 3.1 have on the following: CSS.

006K5.07; Knowledge of the operational 006 Emergency Core Cooling X implications of the following concepts as 2.7 they apply to ECCS: Expected temperature levels in various locations of the RCS due to various plant conditions.

X 006K6.05; Knowledge of the effect of a 3.0 loss or malfunction on the following will have on the ECCS: HPI/LPI cooling water.

007G2.2.44; Ability to interpret control 007 Pressurizer Relief/Quench X room indications to verify the status and 4.2 Tank operation of a system, and understand how operator actions and directives affect plant and system conditions.

X 007A2.03; Ability to (a) predict the 3.9 impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Overpressurization of the PZR.

008 Component Cooling Water X 008K2.02; Knowledge of bus power 3.0 supplies to the following: CCW pump, including emergency backup.

010K6.04; Knowledge of the effect of a 010 Pressurizer Pressure Control X loss or malfunction of the following will 2.9 have on the PZR PCS: PRT.

X 010G2.2.44; Ability to interpret control 4.4 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

012K4.09; Knowledge of RPS design 012 Reactor Protection X feature(s) and/or interlock(s) which 2.8 provide for the following: Separation of control and protection circuits.

013 Engineered Safety Features X 013A4.01; Ability to manually operate 4.5 Actuation and/or monitor in the control room:

ESFAS-initiated equipment which fails to actuate.

022K4.01; Knowledge of PRTS design 022 Containment Cooling X feature(s) and/or interlock(s) which 2.6 provide for the following: Quench tank cooling.

025 Ice Condenser 026A1.03; Ability to predict and/or 026 Containment Spray X monitor changes in parameters (to 3.5 prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level.

4.4 026A2.03; Ability to (a) predict the X impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of ESF.

039K5.08; Knowledge of the operational 039 Main and Reheat Steam X implications of the following concepts as 3.6 they apply to the MRSS: Effect of steam removal on reactivity.

059 Main Feedwater X 059A3.03; Ability to monitor automatic 2.5 operation of the MFW, including:

Feedwater pump suction flow pressure.

061 Auxiliary/Emergency X 061K2.03; Knowledge of bus power 4.0 Feedwater supplies to the following: AFW diesel driven pump.

062A3.01; Ability to monitor automatic 062 AC Electrical Distribution X operation of the ac distribution system, 3.0 including: Vital ac bus amperage.

062K2.01; Knowledge of bus power X 3.3 supplies to the following: Major system loads.

063K3.01; Knowledge of the effect that a 063 DC Electrical Distribution X loss or malfunction of the DC electrical 3.7 system will have on the following: ED/G.

064K6.07; Knowledge of the effect of a 064 Emergency Diesel Generator X loss or malfunction of the following will 2.7 have on the ED/G system: Air receivers.

073K1.01; Knowledge of the physical 073 Process Radiation X connections and/or cause effect 3.4 Monitoring relationships between the RPS and the following systems: 120V vital/instrument power system.

X 073A2.01; Ability to (a) predict the 3.6 impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation.

076 Service Water X 076A3.02; Ability to monitor automatic 3.7 operation of the SWS, including:

Emergency heat loads.

X 076A4.04; Ability to manually operate 3.5 and/or monitor in the control room:

Emergency heat loads.

078G2.4.34; Knowledge of RO tasks 078 Instrument Air X performed outside the main control room 4.2 during an emergency and the resultant operational effects.

078K1.05; Knowledge of the physical X connections and/or cause-effect 3.4 relationships between the IAS and the following systems: MSIV air.

103K1.08; Knowledge of the physical 103 Containment X connections and/or cause/effect 3.6 relationships between the containment system and the following systems: SIS, including action of safety injection reset.

X 103K4.01; Knowledge of containment 3.0 system design feature(s) and/or interlock(s) which provide for the following: Vacuum breaker protection.

K/A Category Point Totals: 3 3 2 3 2 3 3 2/3 3 2 2/2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 001K5.47; Knowledge of the following 001 Control Rod Drive X operational implications as they apply to 2.9 the CRDS: Factors affecting SUR: eff ,

l/.

002 Reactor Coolant 011 Pressurizer Level Control X 011K2.02; Knowledge of bus power 3.1 supplies to the following: PZR heaters.

014K1.01; Knowledge of the physical 014 Rod Position Indication X connections and/or cause/effect 3.2 relationships between the RPIS and the following systems: CRDS.

015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017K6.01; Knowledge of the effect of a 017 In-core Temperature Monitor X loss or malfunction of the following ITM 2.7 system components: Sensors and detectors.

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029A3.01; Ability to monitor automatic 029 Containment Purge X operation of the Containment Purge 3.8 System including: CPS isolation.

033 Spent Fuel Pool Cooling X 034G2.4.30; Knowledge of events related 034 Fuel Handling Equipment to system operation/status that must be 4.1 reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

035 Steam Generator X 035A1.02; Ability to predict and/or 3.5 monitor changes in parameters (to prevent exceeding design limits) associated with operating the S/GS controls including: S/G pressure.

041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator X 045A2.17; Ability to (a) predict the 2.7 impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Malfunction of electrohydraulic control.

055 Condenser Air Removal X 055K3.01; Knowledge of the effect that a 2.5 loss or malfunction of the CARS will have on the following: Main condenser.

056 Condensate X 056G2.1.28; Knowledge of the purpose 4.1 and function of major system components and controls.

068 Liquid Radwaste X 068K4.01; Knowledge of design 3.4 feature(s) and/or interlock(s) which provide for the following: Safety and environmental precautions for handling hot, acidic, and radioactive liquids.

071 Waste Gas Disposal 072 Area Radiation Monitoring X 072A2.03; Ability to (a) predict the 2.9 impacts of the following malfunctions or operations on the ARM system- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Blown power-supply fuses.

075 Circulating Water 079 Station Air X 079A2.01; Ability to (a) predict the 3.2 impacts of the following malfunctions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Cross-connection with IAS.

086 Fire Protection K/A Category Point Totals: 1 1 1 1 1 1 1 1/2 1 0 1/1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Farley Date of Exam: October, 2015 Category K/A # Topic RO SRO-Only IR # IR #

2.1.18 Ability to make accurate, clear, and concise logs, records, status 3.6 boards, and reports.

1. 2.1.8 Ability to coordinate personnel activities outside the control 3.4 Conduct room.

of Operations 2.1.41 Knowledge of the refueling process. 3.7 Subtotal 2 1 2.2.21 Knowledge of pre- and post-maintenance operability 2.9 requirements.

2.2.22 Knowledge of limiting conditions for operations and safety 4.0

2. limits.

Equipment 2.2.35 Ability to determine Technical Specification Mode of 3.6 Control Operation.

2.2.13 Knowledge of tagging and clearance procedures. 4.3 2.2.40 Ability to apply Technical Specifications for a system. 4.7 Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 emergency conditions.

2.3.15 Knowledge of radiation monitoring systems, such as fixed 2.9

3. radiation monitors and alarms, portable survey instruments, Radiation personnel monitoring equipment, etc.

Control 2.3.12 Knowledge of radiological safety principles pertaining to 3.7 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.14 Knowledge of radiation or contamination hazards that may 3.8 arise during normal, abnormal, or emergency conditions or activities.

Subtotal 2 2 2.4.18 Knowledge of the specific bases for EOPs. 3.3 2.4.27 Knowledge of fire in the plant procedures. 3.4

4. 2.4.43 Knowledge of emergency communications systems and 3.2 Emergency techniques.

Procedures / Plan 2.4.30 Knowledge of events related to system operation/status that 4.1 must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

2.4.35 Knowledge of local auxiliary operator tasks during an 4.0 emergency and the resultant operational effects.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 011EA2.01 Oversampled. Changed to 007EA2.03.

1/1 025AA2.05 Oversampled. Changed to WE5EA2.1.

1/2 028AK1.01 Oversampled. Changed to 037AK1.02.

1/2 068AA2.11 Oversampled. Changed to 024AA2.05.

1/2 WE09G2.2.38 Oversampled. Changed to 051G2.2.38.

2/1 005A1.05 Oversampled. Changed to 004A1.05.

2/1 022K4.04 Oversampled. Changed to 103K4.01.

2/1 061K2.02 Oversampled. Changed to 062K2.01 2/1 073K3.01 Oversampled. Changed to 005K3.06.

3 G2.3.14 Oversampled. Changed to G2.2.22

E5-401 Wntteri Examination Quality Checklist Form ES-401-.6 Factiuty:FARLEY DateofExarn: 10/5/15 Examlevei: RD SRO tnitjal tern Description 1 Questions and answers are technically accurate and applicable to the facility.

2. a. NRC KJAs are referenced for all questions.

b. Facility teaming objectives are referenced as available.

4

3. SRO questions are appropriate in accordance with SectIon D.2.d of ES-4i)1 The sampling process was random and systematIc (If more than 4 RD or 2 SRO questions f

ware repeated from the last two NRC licensing exams, consult the NRR/NRO DL program

5. Question duplication from the licensee screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate The audit exam was systematically and randomly developed; or the audit exam was completed before the iicense exam was started; or the examinations were developed Independently; or the licensee certifies that there is no duplication; or other (explain)

6. Bank use meets limits (no more than 75 percent from the bank, at least 10 percent new, and the rest new or Bank Modified New modified enter the actual RD / SRO-onty question

7. Between 50 and 60 percent of the questions on the RD 301 3 1 3112 32/10 ZY exam are written at the comprehension.! analysis level; the Memory C/A

• SRO exam may exceed 60 percent if the randomiy selected K/As support the higher cognitive levels. enter the actual RD I SRO_question distribution(s) at rIght.

31/ 5 441 20 14- ](

8. References/handouts provided do not give away answers or aid i the ailmination of dislractors.

9. Question content conforms to specific K/A statements In the previously approved examination j.

outline and Is_appropriate_for the tler to which_they_are_assigned:_deviations are_justified.

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

11. The exam contains the required number of one-paint, multiple choice Items: the total Is correct and agrees with the value an the cover sheeL Printed Name I S gnature Date

a. Author Stanley Jackson /

b. FacIlity Reviewer () SHIy Thornton 9/22115 c.

i NRC Chief ExamIner (if)

NRC Regional Supervisor 2)OdO

/ a?  :::_

6

{ A)

Note: The facility reviewers initials or signature are not appcabte for NRC-developed examinations.

if independent NRC reviewer initials items In Column c; chief examiner concurrence required.

ES-401 Written Examination Review Worksheet - Farley 2015-301 Form ES-401-9

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only 001AG2.1.32.

K/A is met.

Reverse the question order. Then this would NOT pre-dispose the applicants on whether to trip or go to 1 F 2 X N E AUTO. Drl 7/13/15 Reversed the FIB order as requested. BT 7/23/15 Revised question attached.

Revised question is SAT. drl 8/11/15 001K5.47.

2 F 2 N S K/A is met drl 7/13/15 003A2.03.

3 H 3 N S K/A is met. drl 7/13/15 004A2.24.

4 H 3 N S K/A is met. drl 7/13/15 004K4.12.

5 F 2 B S K/A is met drl 7/13/15 05A1.03.

6 F 2 N S K/A is met drl 7/13/15 Instructions (Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts:

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

2. Enter the level of difficulty (LOD) of each question a 1(easy) to 5 ( difficult); (questions with a difficulty between 2 and 4 are acceptable)

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

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

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

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

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

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

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

• Job Link: The question is not linked to the job requirements (i.e., the question has a valid K/A, but as written, is not operational in content).

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

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

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

5. Check questions that are sampled for conformance with the approved K/A and those K/As that are designated SRO-only (K/A and license level mismatches are unacceptable)

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

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

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

ES-401 2 Form ES-401-9

1. 2. 6. Source 7. Status Q 3. Psychometric Flaws 4. Job Content Flaws 5. Other 8. Explanation LO LOD (B/ M / N) (U /E /S)

K (1-5)

Stem Cred. Job- #/ Back Q- SRO (F/ Cues T/F Partial Minutia Focus Dist Link Units ward K/A Only H) 005K6.03.

K/A is kind of met.

Is it possible to supply fire water to the CCW system per AOP-9.0 via a charging pump and thus cool the seals? Looking at the procedures, it appears that this might be the case. If so, then the second question needs altered. Drl 7/13/15 We understand your comment on the K/A match. We could modify the second FIB to ask if that RHR train 7 F 3 X M E/U could / could not be used for recirculation during a LOCA. That would be a direct K/A match.

BT 7/23/15 Revised Question attached Revised question is SAT. drl 8/11/15 After further evaluation, we found that an additional bullet was required in the stem stating that The A Train is the ON SERVICE Train. This was discussed with CE and he concurred.

BT 9/18/15 Revised Question is SAT. drl 9/23/15 006K5.07.

8 H 2 B S K/A is met. drl 7/13/15 006K6.05.

9 F 2 N S K/A is met drl 7/13/15 007G2.2.44.

K/A is not really met. The second part of the question is asking how operator actions and directives affect the plant. Something more on the line of what is the effect of what happened.

First FIB meets ability to interpret control room indications. Second FIB is understanding how operator actions affect plant conditions. Both are related. BT 7/23/15 10 F 2 X X B U Second question distractor does not seem very plausible. Where else in the plant do you control the atmosphere for corrosion concerns? Drl 7/13/15 We use N2 atmosphere for corrosion control of SGs during wet layup conditions, use N2 atmosphere for corrosion control of FW Heaters during shutdown, we use H2 in the RCS to minimize corrosion products.

BT 7/23/15 Revised question is SAT. drl 8/11/15 008G2.1.32.

K/A is not met. The question needs to demonstrate knowledge to explain and apply system limits and precautions associated with a vapor space accident.

Although the indicated level may rise due to this leak, uncovering the core is a real threat. Knowing the LP Reactor Trip set point does not meet the K/A.

11 F 2 X N U The stated basis for meeting the K/A does not match the question, but does hint at a possibly better K/A match. Drl 7/13/15 Question revised based upon comments.

BT 7/23/15 Revised question attached.

Revised question is SAT. drl 8/11/15 008K2.02.

12 H 3 M S K/A is met. drl 7/14/15 009EA1.17.

13 F 2 N S K/A is met. drl 7/14/15 011EK3.05.

14 F 2 N S K/A is met drl 7/14/15 011K2.02.

15 H 3 N S K/A is met. drl 7/14/15 012K4.09.

16 F 2 N S K/A is met. drl 7/14/15 013A4.01.

17 H 3 N S K/A is met. drl 7/15/15 013K2.01.

18 F 2 B S K/A is met. drl 7/15/15 014K1.01.

19 F 3 N S K/A is met. drl 7/15/15 015AA2.08.

K/A is met.

Could we put a procedural reference in the question IAW ARP-1.10 only the drl 7/15/15 There are two ARPs that would need to be referenced, one provides info for Motor Bearing temp limits, the other provides Motor Stator Temp limits.

20 H 3 B E We could be cueing if we provided per ARP-XX.

BT 7/23/15 As long as there are no other references that would conflict with the answer given, this would be SAT. drl 8/11/15 We can find no other reference to cause conflict with the correct answer. BT 9/18/15 Question is SAT. drl 9/23/15 017K6.01.

K/A is met.

A, C, and D are too connected. By disconnecting a CETC you are failing it high. Therefore would an applicant consider C?

A better way to ask this might be to ask it like this:

Which of the following conditions would cause the CETC monitor to generate an alarm?

1. Any CETC input is disconnected.

2. Only 10 valid CETCs

3. Any CETC temperature at 650 °F 21 F 3 X B E A. 1 ONLY.

B. 1 and 3 ONLY.

C. 2 ONLY.

D. 1, 2, and 3.

Drl 7/15/15 Question modified as requested, but also modified stem to clarify that we are only asking about a CETC monitor alarm rather than any alarm (MCB,etc.).

cause a Core Exit Thermocouple (CETC) monitor alarm.

BT 7/23/15

Revised Question Attached Revised question is SAT. drl 8/11/15 022AA2.02.

K/A is met.

Could we change the FCV-122 to failed closed? I believe this would still only be a single correct answer and slightly more plausible. Drl 7/15/15 22 H 2 M E Modified as requested, but used terminology FCV-122 closing since FCV-122 fails open.

BT 7/23/15 Revised Question Attached Revised question is SAT. drl 8/11/15 022K3.01.

K/A is not met.

K/A requires demonstration of knowledge of effects on systems in containment when CCS is lost not just how the CCS responds.

23 H 3 M U Perhaps if you also ask why the fans shift to slow speed, this would cleanly match the K/A. Drl 7/15/15 Modified as requested.BT 7/27/15 Revised Question Attached.

Revised question is SAT. drl 8/11/15 025AG2.4.2.

K/A is met, but backwards.

The applicant should understand the setpoints to determine that nothing happens. This is not wrong, but could be confusing to applicants that are unsure.

Lets discuss this to make sure it is worded the way it should be o test the desired knowledge.

What was the initial pressure? What was the cause of the pressure drop? Do those questions matter?

24 H 3 N E Is there anything else that could be inferred to have happened that would have been an AOP entry condition? drl 7/15/15 To reduce confusion and clarify, modified question.

Removed the HG5 bullet in the stem and changed the second FIB to IF MOV-8701A Closes, then AOP-12 entry (IS or is NOT) required. BT 7/27/15 Revised question attached.

Revised question is SAT. drl 8/11/15 026A1.03.

25 F 2 B S K/A is met. drl 7/15/15 027AK2.03.

26 H 2 N S K/A is met. drl 7/15/15 029A3.01.

K/A is met.

27 H 3 N S Seems like a poor design to leave the fans running deadheaded. Drl 7/15/15 029EK2.06.

K/A is met.

The Part 2 distractor is not plausible. If you know the 28 F <2 X B U RTBs are in parallel, why would you ever consider that a RTBB would do anything else?

LOD is very low for the first part. This is GFES knowledge.

Perhaps you can change it to ask what the status of each breaker is after a valid A or B train actuation. drl 7/15/15 Changed question in response to comment BT 7/27/15 Revised Question Attached Revised question is SAT. drl 8/11/15 035A1.02.

K/A is met.

Wording is a bit awkward. Could we remove due to increased steam demand from the 2B SG from the question and still have a valid question? drl 7/15/15 29 H 3 B E We put that info in the stem due to validator FB. If RCS temperature is lowered using steam dumps in auto, you will get steam flow from C loop, and eventually you could lower 2B SG pressure as RCS cooled down. The extra wording makes answer choice D completely incorrect.

BT 7/23/15 Original question is SAT. drl 8/11/15 038EK1.02.

K/A is met.

GFE Question. drl 7/15/15 This meets the K/A and is operationally valid 30 H 2 B S/E (requires use of plant instrumentation), in that the student has to determine which pressures and temperatures to use to determine the correct answers.BT 7/23/15 After further review, the question is SAT. drl 8/14/15 039K5.08.

31 H 3 B S K/A is met. drl 7/15/15 045A2.17.

32 H 3 B S K/A is met. drl 7/15/15 051G2.2.38.

33 H 3 N S K/A is met. drl 7/15/15 054AA1.04 34 H 3 B S K/A is met. drl 7/15/15 055EK3.02.

K/A is met.

A is not very plausible. How does depressurizing the secondary side minimize the DP. Instead consider something on the lines of minimizing the RCS as a heat source. drl 7/15/15 A is plausible because D/P across the SG U-Tubes is reduced during the procedure but it isnt a reason 35 H 3 B E pressure is reduced.

In ECP-0.0 one additional reason SG Pressure is reduced to 260 psig is to dump accumulators. During SG depressurization the RCS pressure drops due to RCS temperature dropping. Pressure must drop to at least 650psig in order for accumulators to inject.

Initially :

D/P = 2235 psig (RCS) - 1000 psig (SG)=1235 psig

After Secondary Depressurization:

D/P = 650 psig (RCS) - 260 psig (S/G) = 390 psig BT 7/23/15 After further review, the question is SAT. drl 8/14/15 055K3.01.

36 H 2 B S K/A is met. drl 7/15/15 056AG2.4.1.

K/A is kind of met.

The first questions distractors are barely plausible since you tell them that all AC is lost. The second question is not very logical (and kind of minutia) since you are in Mode 4.

Consider changing the stem state that both units are in Mode 5 following a hurricane onsite. Then state that all offsite power is lost and the EDGs fail to start.

There is a report of a fire in the 1B EDG oil system and another report that the 2B EDG air system has 37 H 3 N E ruptured.

Then the first question could remain the same, but the answer would be the AOP. The second question is would ask what that procedure would immediately require them to do. Either restore one of the EDGs or start the SBO EDG. Here the answer should be the SBO EDG. drl 7/15/15 Changed per recommendations.

BT 7/27/15 Revised Question Attached Not quite changed per recommendation, but revised question is still SAT. drl 8/14/15 056G2.1.28.

38 F 2 B S K/A is met. drl 7/15/15 057AA2.16.

K/A is met.

Is LCV-1115A being in AUTO unusual? If his is the normal position for the controller, then this is teaching and needs to be removed from the stem. drl 7/15/15 39 H 3 N E Removed the bullet for LCV-115A being in AUTO.

That is its normal position.

BT 7/23/15 Revised Question attached.

Revised question is SAT. drl 8/14/15 058AA1.02.

40 H 3 B S K/A is met. drl 7/15/15 059A3.03.

41 H 2 B S K/A is met. drl 7/16/15 060AK2.01.

42 H 3 B S K/A is met. drl 7/16/15 061A1.01.

43 H 3 N S K/A is met. drl 7/16/15 062A3.01.

K/A is met.

On a loss of feed event, how quickly would the setpoint for the MDFW pumps to start be reached?

44 H 3 N E Based on the conditions given, I dont think youd reach low level to start the pumps in less than 10 seconds AND since you had a LOSP, there is no auto start on loss of the MFPs. This could cue the applicants towards 0 amps.

An easy fix would be to use the SW pumps (as long as they have amp indication) and make A the answer. This would also remove some overlap from the previous question. drl 7/16/15 The MDAFW pumps are started by the LOSP Sequencer. It is not based on reaching a normal AFW auto start setpoint.

BT 7/23/15 After further review, the question is SAT. drl 8/14/15 062AK3.01.

45 H 3 N S K/A is mostly met. drl 7/16/15 062K2.01.

46 F 2 N S K/A is met. drl 7/16/15 063K3.01.

47 H 3 M S K/A is met. drl 7/16/15 064K6.07.

K/A is kind of met.

Second question distractor is not plausible. For an item that will cause inoperability, youd expect it to have some kind of annunciation in the CR. If you can show me examples where Im wrong, then this will be SAT.

A better K/A match would have the second question ask how many start attempts, by design, would be left if the pressure was at the alarm setpoint before the EDG could not start.

48 F 2 B U This would also raise it to a higher level question. drl 7/16/15 Second FIB changed per recommendation.

BT 7/27/15 Revised question attached In order to get rid of a subset issue, make the second question state that per FSAR section xx, there is enough air pressure drl 8/14/15 Changed the word minimum to maximum in the second question statement per phone communication with CE 8/21/15. BT 9/18/15 Revised question is SAT. drl 9/23/15 067AA1.06.

49 H 2 B S K/A is met. drl 7/16/15 068K3.03.

50 H 3 N S K/A is met. drl 7/16/15 068K4.01.

K/A is met.

How many questions are in the bank that match this K/A? drl 7/16/15 51 H 2 B E There are 4 questions in the bank (questions from other facilities and one from the previous NRC exam). This question was randomly selected per NUREG guidance. BT 7/27/15 This question is SAT.drl 8/14/15 073K1.01.

52 H 3 B S K/A is met. drl 7/16/15 076A3.02.

53 H 3 M S K/A is met. drl 7/16/15 076A4.04.

54 H 2 X X N E K/A is met.

• It seems that the MOC switch could never

be wrong. Although the sequencer appears to be a decent distractor, the MOC switch appears too good.

• Is there a reason you state that the charging pump is running AND the supply breaker is closed. Would that not raise eyebrows if the pump was running with the breaker open or tripped?

• Is changing the first question to Cooler is designed to / is NOT designed to be running? Since other ESF coolers run on a thermostat, I think that might work. We would need to add a room temperature to the question to enhance the distractors.

• We probably dont need the 4th bullet about the lack of damage. Normal should be assumed and we dont want to key the applicants.

drl 7/16/15 changed per recommendation BT 7/27/15 Revised question attached The revised question is SAT. drl 8/14/15 076AA2.03.

K/A is met.

This is OK as long as Operations agrees that the applicants should know that the Hi Alarm is 1x104 55 F 2 N E cpm above background. drl 7/16/15 David Reed (OPS Rep) Reviewed and approved the Current Version of question.

BT 7/28/15 The question is SAT. drl 8/14/15 077AK2.01.

56 H 2 M S K/A is met. GFES type question. drl 7/16/15 078G2.4.34.

57 H 2 B S K/A is met. drl 7/16/15 078K1.05.

58 H 3 N S K/A is met. drl 7/16/15 103K1.08.

K/A is met.

Im not sure why resetting Phase A SI would be plausible for resetting Phase A Containment Isolation especially when you tell them that Phase B Reset switches exist. drl 7/16/15 Removed MLB-1, 2, and 3 lights from the stem 59 H 3 X B E/U This removes reference to Phase A as a separate signal in the stem. This should improve plausibility.

Also, Phase B is a totally separate signal but Phase A occurs upon each SI. So, it is plausible that resetting SI would reset the associated Phase A.

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 103K4.06.

60 H 3 B S K/A is met. drl 7/16/15 G2.1.18.

61 F 2 N S K/A is met. drl 7/16/15

G2.1.8.

K/A is kind of met.

Reducing hydrogen pressure does not seem logical just because you SI. What would this have to do with the SI?

Why not pull something out of the manual EDG start procedure? Ask about something that the RO and non-licensed operator need to coordinate.

There isnt really any procedural direction that would 62 F 2 X N E/U meet the K/A related to the DG but we made the following change to better meet the K/A.

1st FIB - TBSO is required to close MSR STM SUPP ISO (following an Reactor Trip or Only when directed) 2nd FIB - TBSO is required to close MS DRN POT (following any Reactor Trip or Only when directed)

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 G2.2.6.

K/A is met.

Put Pen and Ink in quotes to denote that you are using the term as defined in the procedure. It appears that a procedure can be changed by hand 63 F 3 N E but the full process needs to be followed. By using the defined term in quotes it wont allow a looser definition to be used. drl 7/16/15 Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 G2.2.22.

64 F 2 B S K/A is met. drl 7/20/15 G2.2.35.

65 F 2 N S K/A is met. drl 7/20/15 G2.3.15.

K/A is met.

Why is Beta ONLY more plausible than Gamma ONLY? Recommend using Gamma ONLY as distractor unless there is a good reason not to. drl 7/20/15 66 H 2 X B E This question was a bank question used on a previous NRC exam and we believed that the plausibility of the distractor was not in question but we have made the recommended change. BT 7/27/15 Revised question attached.

The revised question is SAT.drl8/14/15 G2.3.4.

67 H 2 B S K/A is met. drl 7/20/15 G2.4.18.

68 H 2 B S K/A is met. drl 7/20/15 G2.4.27.

69 F 3 B S K/A is met. drl 7/20/15 G2.4.43.

K/A is met.

This General Employee Training information. This is 70 F 1 B U not at the RO level.

You could go with who is responsible for communication with the state (ED or SM) after TSC is setup. drl 7/20/15

Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 WE08EA1.1.

71 H 3 B S K/A is met. drl 7/20/15 WE11EK1.3.

K/A is met.

Could we modify the question slightly? Give that the RWST Lo Level alarm came in and level is at something > 4.5 feet (perhaps the setpoint). This would change the answer to D. drl 7/20/15 Recommended change made. BT 7/27/15 Revised question attached.

72 H 3 X M E The revised question is SAT. drl 8/14/15 After further evaluation, we found that the modified question had become more complex and would require a procedure table as a reference. After discussion with CE changed RWST level back to 3 feet and the question was reverted to the draft submittal version BT 9/18/15 The revised question is SAT. drl 9/23/15 WE12EK1.3.

73 H 3 M S K/A is met. drl 7/20/15 WE13EK1.1.

K/A is met.

Add and rising to the first bullet.

Change the second question to read When FRP-H.2 74 H 3 X N E drl 7/20/15 Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 WE15EK1.2.

75 H 3 N S K/A is met. drl 7/20/15 003AG2.1.23.

76/1 H 3 N S K/A is met. drl 7/20/15 003G2.4.45.

77/2 H 3 N S K/A is met. drl 7/20/15 007A2.03.

K/A is met.

Not really at SRO level. The applicants only need to know the purpose and overall sequence of the procedures.

Suggestion: Give a temperature of the tank above 120 F and pressure above alarm setpoint. Then ask if High pressure alarm is in and whether draining the 78/3 H 2 X M U PRT per section 4.3 will or will not correct al out of specs with the tank. drl 7/21/15 The RO exam has a question that asks if the PRT high pressure alarm is or is not in alarm.

Modified question incorporating your comments.

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 007EA2.03.

79/4 H 3 M S K/A is met. drl 7/21/15

10G2.2.44.

80/5 H 3 M S K/A is met. drl 7/21/15 026A2.03.

81/6 H 3 M S K/A is met. drl 7/21/15 026AA2.03.

K/A is met.

Is there procedural guidance to isolate CCW from the MCR? If so, lets add that information to the question IAW procedure XYZ, the method drl 7/21/15 82/7 H 2 B E There is no specific procedure to isolate CCW to RCPs from the MCB. However, there is NO way possible to isolate CCW to only one RCP from the MCB. The correct answer is correct in all cases.

BT 7/27/15 The original question is SAT. drl 8/17/15 028A2.02.

83/8 H 3 B S K/A is met. drl 7/22/15 028AG2.1.25.

84/9 H 3 N S K/A is met. drl 7/22/15 034G2.4.30.

K/A is met.

Second question distractor is not very plausible and of very low difficulty. Why would the transfer tube level ever be above the reactor flange level (just considering dose issues).

A better question might be to ask what the next action required in AOP 12 is. In this case it would be to begin containment isolation. The distractor would be to commence charging from RWST. drl 7/22/15 85/10 H 2 X N E Based on review of AOP-12, it appears that your suggestion could have 2 correct answers. We used your suggestion for the 2nd FIB.

BT 7/27/15 Revised question attached.

If we changed the revised second question to state Per AOP-12, RHR System Malfunction, the maximum time to complete containment closure is __

hours drl 8/17/15 Revised 2nd question per above. BT 9/18/15 Revised question is SAT. drl 9/23/15 036AA2.02.

K/A is met.

The distractors for question 2 make the answer for question 1 seem obvious. If either one is possible, then AOP entry would be a minimum expectation.

Instead could we reword to be something like the following:

Remove the words causing damage to the spent 86/11 H 3 X M E fuel from the second bullet.

AOP-30 _1_ required to be entered because the basis of TR 13.9.4, Crane Travel Spent Fuel Storage Building, the expected worse case consequences of dropping a load weighing less than 3000 lbs is that the _2_.

A (1) IS

(2) activity release will be limited B (1) IS (2) offsite dose at the site boundary will NOT exceed 10% of 10 CFR100 limits.

C (1) IS NOT (2) no fuel damage would occur.

D. (1) IS NOT (2) any possible distortion of fuel in the storage racks will not result in a critical array.

It still needs work, but I think that this path leads to a better question. drl 7/22/15 Fuel damage has to be a component for AOP-30 entry to be required (initial condition for entry). We may need to discuss more, but we have a proposed question.

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 056AG2.2.44.

K/A is met.

Would it be simpler to just ask if SW is operable and if the EDG is operable at 1017?

IAW TS 3.8.1, the sequencer is inoperable, the 1B DG is/is not operable, and SW is/is not operable.

No reference would be required. drl 7/22/15 Technically, the failure of the sequencer would make Service Water inoperable along with the DG but the Required Action Statements would NOT be entered for SW or the DG. By asking if they were 87/12 H 3 X N E OPERABLE (but the RAS is not required) is a play on words and becomes confusing as to the actual question asked. We feel that this is the best wording for this question. It is essentially testing the SRO knowledge of whether cascading is required, so providing the TS does not give them the answer.

BT 7/27/15 The original question is SAT. drl 8/17/15 During final validation of this question during prep week, one validator found that there was insufficient information to choose the correct answer. After discussion with CE, question was modified and CE approved.

BT 9/18/15 The revised question is SAT. drl 9/23/15 065AG2.4.22 K/A is kind of met.

This would be a better K/A match if we can delete the words due to the loss of instrument air from the first question. This implies that there is a malfunction of 88/13 H 3 X M E some type. I believe that this will then allow some insight into their bases knowledge. drl 7/22/15 We modified question to start in Mode 3 and removed due to the loss of instrument air. Starting in Mode 3

eliminated the concern of Pressurizer level going down due to the Reactor trip, thus confusing the students. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 072A2.03.

K/A is met.

First question is obvious. Of course it affects the ability to evaluate the loss :. Instead you can just 89/14 H 2 X N E ask them how it fails. drl 7/22/15 Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 073A2.01 90/15 H 2 N S K/A is met. drl 7/22/15 G2.1.41.

K/A is met.

Maintenance Supervisor is not plausible. Lets make this a 2x2.

Per FHP-1.0, what requirements must be met prior to latching?

FHS in containment OR in Control Room in direct communications.

91/16 F 2 X M U AND AT least 2 SR flux rad monitors (NI-31,32, or 48) OR Containment is set.

drl 7/22/15 Incorporated changes based on your recommendation. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 G2.2.13.

92/17 F 2 N S K/A is met. drl 7/22/15 G2.2.40.

93/18 H 2 M S K/A is met. drl 7/22/15 G2.3.12.

94/19 H 2 M S K/A is met. drl 7/22/15 G2.3.14.

K/A is met.

Be careful with potential overlap with # 11. drl 7/22/15 95/20 H 2 M E We dont feel there is overlap. These are different Tech Specs, different locations (SFP vs Reactor Cavity), and different questions.

BT 7/27/15 The original question is SAT. drl 8/17/15 G2.4.30.

96/21 H 3 M S K/A is met. drl 7/22/15 G2.4.35.

K/A is met.

Bullet 2 of distractor B is written differently than the other 3. Could the second part of the question be 97/22 H 3 X B E reworded to ask what issues must be addressed due to this action? drl 7/22/15 Revised question to address your concerns.

BT 7/27/15

Revised question attached.

The revised question is SAT. drl 8/17/15 WE04EG2.1.2.

98/23 H 2 M S K/A is met. drl 7/22/15 WE05EA2.1.

99/24 H 3 M S K/A is met. drl 7/22/15 WE10EA2.2.

K/A is met. drl 7/22/15 100/25 H 3 N S This question is not marked SAT, but we are assuming this question is SAT as is.

BT 7/27/15 The original question is SAT. drl 8/17/15

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Farley Date of Exam: October, 2015 Exam Level: RO SRO Item Description Initials a b c

1. Clean answer sheets copied before grading Z

2. Answer key changes and question deletions justified and documented

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

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

5. All other failing examinations checked to ensure that grades are justified /9

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader /1

b. Facility Reviewer(*)

..)/4

c. NRC Chief Examiner (*) 1r/ /

d. NRC Supervisor (*) )1/I)ZoI

/

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

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Farley Date of Examination: Oct., 2015 Developed by: Written: Facility NRC II Operating Facility NRC Target . . Chief Task Description (Reference)

Date Examiners Initials

-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 (C2.d)

[-120] 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-i, ES-401-112, ES-401N-112, ES-401-3, ES-401N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; Cad)

(-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)

-21 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-21 12. Examinations reviewed with facility licensee (Ci.]; C.2.f and h; C.3.g)

-14 13. Final license applications due and Form ES-201-4 prepared (C.1 .1; 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 I 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.

ES-201 Examination Outline Quality Checklist Eprm ES-201-2 Facility: FAR LEY Date of ExaminatIon 10/5/15 Item Task Descnpticn Initiats 1 a. Venfy that the outline(s) fit(s) the appropriate model, In accordance with ES-401 or ES-401N ,* jZ.

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

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

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

$ [ c.

Z..

2. a. Using Form ES-301-5, verily 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 lest(s), and lhat 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 cntena specified on Form ES-301-4 and described in Appendix D.

3. a. Verily that the systems walk-through outline meets the criteria specified ocr 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 repelilion 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 cI new or modified tasks meets or exceeds the nininiums 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 (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 priontles (Including PRA and IPE insights) are covered In the appropriate exam sections b Assesswhetherthe ID CFR 55.41143 and 5545 sampling Isappropnate c Ensure that K/A Importance ratings (except for plant-specific priorities) are at least 2.5 R d. Check for duplication and overlap among exam sections L e. Check the entire exam for balance of covera9e -

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

PnnteNa4ture Date a Author Stanley Jackson 9)22)15

b. Facility Reviewer () Billy Thornton / 9)22/15 c, NRC Chief Examiner (#) .3)o.,c) / LL 9 )?.j/,.,(

d NRC Supervisor

/ --

Note # Independent NRC reviewer initial Items in Column c, chief examiner concurrence required.

Not applicable for NRC-prepared examination outines.

Outline provided by NRC.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO X SRO Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a

Title:

Monitor CSFST. Given a set of conditions, R, D the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, D

Title:

Determine maximum RHR flowrate and time to saturation for a loss of RHR event. Given a set Conduct of Operations of conditionsthe applicant will : Determine maximum RHR flowrate and time to saturation for RO a loss of RHR event.

G2.1.25 - 3.9 / 4.2 A.2

Title:

Perform a QPTR. Given a set of conditions, R, M determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio.

RO G2.2.12 - 3.7 /4.1 A.3

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control R, D conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 NONE SELECTED Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO SRO x Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a R, D

Title:

Monitor CSFST. Given a set of conditions, the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, M

Title:

Determine Active License Status. Given a set of conditions, the applicant will have to Conduct of Operations determine the status of 3 individuals license.

SRO G2.1.4 - 3.3 / 3.8 A.2 R, D

Title:

Perform a QPTR. Given a set of conditions, determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio. Determine what Tech Specs actions, if any, are required.

SRO G2.2.12 - 3.7 / 4.1 G2.2.40 - 3.4 / 4.7 G2.2.42 - 3.9 / 4.6 A.3 R, D

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 A.4 R, M

Title:

Classify an emergency event.

Emergency Plan G2.4.40 - 2.7 / 4.5 G2.4.41 - 2.9 / 4.6 SRO NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: FARLEY Date of Examination: 10/05/15 Exam Level: RO X SRO-I X SRO-U X Operating Test No.: FA2015-301 Control Room Systems: 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. CRO-074: Fill the 1A SIS Accumulator: the 1A Accumulator low and will D, S 2 be filled using SOP-8.0, Safety Injection - Accumulators.

006A1.13 - 3.5 / 3.7 006A4.02 - 4.0 / 3.8

b. CRO-333: Perform the required actions for Cold Leg Recirculation. A, D, EN, L, S 3 During the performance of the procedure, a valve will not close requiring an (SRO-U) alternate path.

011EA1.11 - 4.2 / 4.2 011EA1.13 - 4.1 / 4.2

c. 343G: Restore Service water to normal in response to a spurious Safety D, L, S 4S Injection - Applicant will restore Service Water using ESP-1.1, SI Termination.

062AA1.02 - 3.2 / 3.3 076A4.02 - 2.6 / 2.6

d. CRO-043B: Start the 1A RCP - After starting the 1A RCP, a high bearing A, D, S 4P temp alarm will be received requiring the 1A RCP to be secured.

003A1.02 - 2.9 / 2.9 003A2.03 - 2.7 / 3.1

e. CRO-406B (MOD): Verify Phase B Containment Isolation and A, M, S 5 Containment Spray Initiation. Containment pressure will be above 27psig (SRO-U) and Phase B / Containment Spray will not have actuated. Requires manual actions to start Containment spray and isolate valves.

WE14EA1.1 - 3.7 / 3.7 103A3.01 - 3.9 / 4.2

f. CRO-NEW: Perform Corrective Actions to a trip of the On Service CCW A, N, L, S 8 pump. The plant is in Mode 3 and the loss of the On Service train of CCW occurs while shifting Heat Exchangers.

008A2.01 - 3.3 / 3.6 026AA1.02 - 3.2 / 3.3

g. CRO-033 (MOD): Perform STP-5.0, Full Length Control Rod Operability A, M, S 1 Test. Applicant will insert Control Bank D 10 steps and when the rods are (SRO-U) withdrawn, they will continue to move when the Rod Control Switch is released. When rods are placed in AUTO, they will continue to move requiring a trip.

001A2.11 - 4.4 / 4.7 001A3.02 - 3.7 / 3.6 001AA1.05 - 4.3 / 4.2

h. CRO-039A: Adjust Setpoint of the N-16 Primary to Secondary Leak D, S 7 Detection System (R-70B). Applicant will change the R-70B setpoint to 75 (RO ONLY) gpd.

073A4.02 - 3.7 / 3.7

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

i. CRO- 607A (UNIT 1) : Perform the required actions to minimize DC loads. D, E, L 6 ECP-0.0 is in progress and the applicant is required to minimize DC loads in (SRO-U) the Non-Rad Aux Building.

055EA1.04 - 3.5 / 3.9

j. SO-444 (UNIT 1): Restore Compressed Air Systems After an Auto D 8 Isolation. Unit 1 has an extra valve that is operated by this JPM.

065AA1.03 - 2.9 / 3.1

k. SO-368A: Align RCDT Discharge to the WHT - Applicant is required to D, R 9 reduce RCT level from 50% to 10% per SOP-50.0, Liquid Waste Processing. (SRO-U) 068K1.07 - 2.7 / 2.9

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

• Type Codes Criteria for RO / SRO-I / SRO-U A)lternate path 4-6 / 4-6 / 2-3 5/5/3 (C)ontrol room (D)irect from bank 9/8/4 8/7/3 (E)mergency or abnormal in-plant 1/1/1 1/1/1 (EN)gineered safety feature 1 / 1 / 1 (control room system) 1 / 1 / 1 (L)ow-Power / Shutdown 1/1/1 4/4/2 (N)ew or (M)odified from bank including 1(A) 2/2/1 3/3/2 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0/0/0 (R)CA 1/1/1 1/ 1/ 1 (S)imulator 8/7/3

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: FARLEY Date of ExamInation; 10/5/15 Operating Test Number: FA2015.301 1 General CriterIa Initials 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 distnbution).

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

c. The operating test shall not duplicate Items from the applicanls 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.

a. It appears that the operating test Will differentiate between competent and lass-than-competent lhtl.

applicants at the designated license level.

1:31

2. Walk-Through CrIteria -.

a. Each JPM includes the following, as applicable:

• initial conditions

• Initialing cues

• references and tools, Including associated procedures

- reasonable and validated time limits (average time allowed for completion) and specific designation it deemed 10 be time-critical by the facility licensee

• operationally Important specific performance criteria that Include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria ror successful completion of tile 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 outJines (Forms ES-301-1 and 2) have not caused the test to deviale 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.

Pd t ame I Signature Date

a. Author Stanley Jackson/ - 9/22/15

b. Facility Revlewer() 8ilv Thornton 9/22/15

c. NRC Chle(Examiner(#) ic) L.o.y ,/(

d. NRCSupervisor Ccç\ I y

NOTE:

• The tacitly signature Is not applicable for NRC-developed tests.

1. Independent NRC reviewer initial items In Column c, chief examiner concurrence required. -

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: FARLEY Date of Exam: 10/05115 Scenario Numbers: 2 I 3 I 4 / 51 6 Operating Test No.: FA2O1S-301 QUALITATIVE ATTRIBUTES Initials a b c#

1. The Initial conditions are realistic, In that some equipment and/or Instrumentation may be out of service, but it does not cue the operators Into expected events.

2. The scenarios consist mostly of related events.

3. Each event desaiption 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 syrriptomslcues that will be vIsible to the crew

. the expected operator actions (by shift position)

. the event termination point (II 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.

6. If lime compression techniques are used, the scenario summary dearly so Indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. A çt Cues are given. . f I J

7. The simulator modeling Is not altered.

8. The scenarios have been valIdat. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional A L

fidelity Is maintained while running the planned scenarios.

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

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

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

1 2. Each applicant will be significantly Involved In the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

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

Target Quantitative Attributes (Per Scenario; See SectIon D.5.d) Actual Attributes 213/4/5/6

1. Maifunctlons after EOP entry (1-2)

2. Abnormal events (2-4) 3 / 1 /212 / 2 iL X.

5/5/5/4/4 *1:___ j ,L

3. Major transients (12) 2/2(1 I 2 / 1 Z.

4. EOPs entered/requiring substantive actions (12)

5. EOP contingencies requiring substantive actions (0-2) 1 1 1 I1 10/0 1 I 0/0/ 1 / 1 4-j_ 4_

j fj2 s<)t

6. EOP based Critical tasks (23) 2 I 2 /2 /2 /2 -

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

1. Independent NRC reviewer Initial Items In Column c; chief

• examiner concurrence required.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 10/5/15 Operating Test No.: FA2015-301 A E Scenarios P V 2 5 3 4 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U JOHNSON RX 1 6 1 3 1 1 0 SRO-I NOR 1 1 2 1 1 1 I/C 123 478 245 15 4 4 2 567 67 8

MAJ 78 89 7 5 2 2 1 TS 35 6 346 6 0 2 2 RX 1 6 1 3 1 1 0 KOENIG NOR 1 1 2 1 1 1 I/C 123 478 245 15 4 4 2 SRO-I 567 67 8

MAJ 78 89 7 5 2 2 1 TS 35 6 346 6 0 2 2 RO RX 1 1 0 X

NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2

Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (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-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 10/5/15 Operating Test No.: FA2015-301 A E Scenarios P V 2 5 3 4 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U Darrah RX 1 1 1 1 0 RO NOR 1 1 1 1 1 I/C 35 457 5 4 4 2 MAJ 89 7 3 2 2 1 TS 0 0 2 2 Day RX 3 1 1 1 0 NOR 4 1 2 1 1 1 RO I/C 236 25 267 10 4 4 2 78 MAJ 78 78 7 5 2 2 1 TS 0 0 2 2 Elliot RX 4 1 1 1 0 RO NOR 1 1 2 1 1 1 I/C 157 467 35 8 4 4 2 MAJ 78 78 89 6 2 2 1 TS 0 0 2 2 Patterson RX 3 1 1 1 0 RO NOR 4 1 2 1 1 1 I/C 236 78 25 267 10 4 4 2 MAJ 78 78 7 5 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (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-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: FARLEY Date of Exam: 10/5/15 Operating Test No.: FA2015-301 A E Scenarios P V 2 5 3 4 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U Pollard RX 4 1 1 1 0 RO NOR 1 1 1 1 1 I/C 157 467 6 4 4 2 MAJ 78 78 4 2 2 1 TS 0 0 2 2 Reznikov RX 3 1 1 1 0 RO NOR 4 1 2 1 1 1 I/C 236 78 25 267 10 4 4 2 MAJ 78 78 7 5 2 2 1 TS 0 0 2 2 Sauls RX 4 1 1 1 0 RO NOR 1 1 2 1 1 1 I/C 157 467 35 8 4 4 2 MAJ 78 78 89 6 2 2 1 TS 0 0 2 2 RO RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (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-I in manipulating plant controls.

ES-301 Competencies Checklist Form ES-301-6 Facility: FARLEY Date of Examination: 10/5/15 Operating Test No.:FA2015-301 APPLICANTS RO BOP RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 2 5 3 4 2 5 3 4 2 5 3 4 2 5 3 4 Interpret/Diagnose 14 23 46 13 23 46 13 12 12 23 12 23 57 57 78 45 67 78 58 67 34 45 34 45 Events and Conditions 8 8 9 7 8 9 56 67 56 67 78 8 78 9

Comply With and 14 23 46 14 23 13 13 12 34 24 34 24 57 57 78 57 46 46 58 67 56 56 56 56 Use Procedures (1) 8 8 9 78 78 9 78 78 89 7 Operate Control 14 23 46 14 23 13 13 12 57 57 78 57 46 46 58 67 Boards (2) 8 8 9 78 78 9 Communicate 12 23 45 14 23 13 12 12 12 12 12 12 45 57 67 57 46 46 34 46 34 34 34 34 and Interact 67 8 89 78 78 57 7 56 56 56 56 8 89 78 78 78 7 9

Demonstrate 12 12 12 12 34 34 34 34 Supervisory Ability (3) 56 56 56 56 78 78 78 7 9

Comply With and 35 24 26 34 5 6 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.

ES-301 Competencies Checklist Form ES-301-6 Facility: FARLEY Date of Examination: 10/5/15 Operating Test No.:FA2015-301 APPLICANTS RO BOP RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 6 6 6 Interpret/Diagnose 25 13 12 Events and Conditions 67 47 34 56 7

Comply With and 25 13 34 Use Procedures (1) 67 47 56 7

Operate Control 25 13 Boards (2) 67 47 Communicate 24 13 12 and Interact 56 45 34 7 7 56 7

Demonstrate 12 Supervisory Ability (3) 34 56 7

Comply With and 34 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.

ES-401 PWR Examination Outline Form ES-401-2 Facility: Farley Date of Exam: October, 2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

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

Abnormal 2 2 1 1 N/A 2 1 N/A 2 9 2 2 4 Plant Evolutions Tier Totals 5 4 4 5 4 5 27 5 5 10 1 3 3 2 3 2 3 3 2 3 2 2 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 2 3 2 3 1 2 2 2 7 Note: 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 outline, 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 with justification; operationally important, site-specific systems/evolutions 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 1 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 K/As.

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 a category 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 K/A 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.

G* Generic K/As

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000007 (BW/E02&E10; CE/E02) Reactor X 007EA2.03; Ability to determine or interpret the 4.4 Trip - Stabilization - Recovery / 1 following as they apply to a reactor trip: Reactor trip breaker position.

000008 Pressurizer Vapor Space X 008G.2.1.32; Ability to explain and apply system 3.8 Accident / 3 limits and precautions.

009EA1.17; Ability to operate and monitor the 000009 Small Break LOCA / 3 X following as they apply to a small break LOCA: PRT 3.4 011EK3.05; Knowledge of the reasons for the 000011 Large Break LOCA / 3 X following responses as they apply to the Large Break 4.0 LOCA: Injection into cold leg.

015AA2.08; Ability to determine and interpret the 000015/17 RCP Malfunctions / 4 X following as they apply to the Reactor Coolant Pump 3.4 Malfunctions (Loss of RC Flow): When to secure RCPs on high bearing temperature.

022AA2.02; Ability to determine and interpret the 000022 Loss of Rx Coolant Makeup / 2 X following as they apply to the Loss of Reactor 3.2 Coolant Makeup: Charging pump problems.

025AG2.4.2; Knowledge of system set points, 000025 Loss of RHR System / 4 X interlocks and automatic actions associated with EOP 4.5 entry conditions.

000026 Loss of Component Cooling X 026AG2.4.46; Ability to verify that the alarms are 4.2 Water / 8 consistent with the plant conditions.

027AK2.03; Knowledge of the interrelations between 000027 Pressurizer Pressure Control X the Pressurizer Pressure Control Malfunctions and the 2.6 System Malfunction / 3 following: Controllers and positioners.

029EK2.06; Knowledge of the interrelations between 000029 ATWS / 1 X the following and the following an ATWS: Breakers, 2.9 relays, and disconnects.

038EK1.02; Knowledge of the operational 000038 Steam Gen. Tube Rupture / 3 X implications of the following concepts as they apply 3.2 to the SGTR: Leak rate vs. pressure drop.

WE12EK1.3; Knowledge of the operational 000040 (BW/E05; CE/E05; W/E12) X implications of the following concepts as they apply 3.4 Steam Line Rupture - Excessive Heat to the (Uncontrolled Depressurization of all Steam Transfer / 4 Generators) Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

054AA1.04 ; Ability to operate and / or monitor the 000054 (CE/E06) Loss of Main X following as they apply to the Loss of Main 4.4 Feedwater / 4 Feedwater (MFW): HPI, under total feedwater loss conditions.

055EK3.02; Knowledge of the reasons for the 000055 Station Blackout / 6 X following responses as they apply to the Station 4.3 Blackout: Actions contained in EOP for loss of offsite and onsite power.

056AG2.2.44; Ability to interpret control room 000056 Loss of Off-site Power / 6 X indications to verify the status and operation of a 4.4 system, and understand how operator actions and directives affect plant and system conditions.

057AA2.16; Ability to determine and interpret the 000057 Loss of Vital AC Inst. Bus / 6 X following as they apply to the Loss of Vital AC 3.0 Instrument Bus: Normal and abnormal PZR level for various modes of plant operation.

058AA1.02; Ability to operate and / or monitor the 000058 Loss of DC Power / 6 X following as they apply to the Loss of DC Power: 3.1 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector.

062AK3.01; Knowledge of the reasons for the 000062 Loss of Nuclear Svc Water / 4 X following responses as they apply to the Loss of 3.2 Nuclear Service Water: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers.

065AA2.06; Ability to determine and interpret the 000065 Loss of Instrument Air / 8 X following as they apply to the Loss of Instrument Air: 4.2 When to trip reactor if instrument air pressure is de-creasing.

WE04EG2.2.4; (multi-unit license) Ability to explain W/E04 LOCA Outside Containment / 3 X the variations in control board/control room layouts, 3.6 systems, instrumentation, and procedural actions between units at a facility.

4.4 WE04EG2.1.2; Knowledge of operator X responsibilities during all modes of plant operation.

WE11EK1.3; Knowledge of the operational W/E11 Loss of Emergency Coolant X implications of the following concepts as they apply 3.6 Recirc. / 4 to the (Loss of Emergency Coolant Recirculation):

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation).

WE05EA2.1; Ability to determine and interpret the BW/E04; W/E05 Inadequate Heat X following as they apply to the (Loss of Secondary 4.4 Transfer - Loss of Secondary Heat Sink / 4 Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

077AK2.01; Knowledge of the interrelations between 000077 Generator Voltage and Electric X Generator Voltage and Electric Grid Disturbances and 3.1 Grid Disturbances / 6 the following: Motors.

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000001 Continuous Rod Withdrawal / 1 X 001AG2.1.32; Ability to explain and apply 3.8 system limits and precautions.

003AG2.1.23; Ability to perform specific 000003 Dropped Control Rod / 1 X 4.4 system and integrated plant procedures during all modes of plant operation.

000005 Inoperable/Stuck Control Rod / 1 024AA2.05; Ability to determine and 000024 Emergency Boration / 1 X 3.9 interpret the following as they apply to the Emergency Boration: Amount of boron to add to achieve required SDM.

000028 Pressurizer Level Malfunction / 2 X 028AG2.1.25; Ability to interpret 4.2 reference materials, such as graphs, curves, tables, etc.

000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 037AK1.02; Knowledge of the operational 000037 Steam Generator Tube Leak / 3 X 3.5 implications of the following concepts as they apply to Steam Generator Tube Leak:

Leak rate vs. pressure drop.

000051 Loss of Condenser Vacuum / 4 X 051G2.2.38; Knowledge of conditions 3.6 and limitations in the facility license.

000059 Accidental Liquid RadWaste Rel. / 9 060AK2.01; Knowledge of the 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.6 interrelations between the Accidental Gaseous Radwaste Release and the following: ARM system, including the normal radiation-level indications and the operability status.

000061 ARM System Alarms / 7 067AA1.06; Ability to operate and / or 000067 Plant Fire On-site / 8 X 3.5 monitor the following as they apply to the Plant Fire on Site: Fire alarm.

068AK3.03; Knowledge of the reasons for 000068 (BW/A06) Control Room Evac. / 8 X 3.7 the following responses as they apply to the Control Room Evacuation: Transfer of AFW flow control valves and pumps to local control.

000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 076AA2.03; Ability to determine and 000076 High Reactor Coolant Activity / 9 X 2.5 interpret the following as they apply to the High Reactor Coolant Activity: RCS radioactivity level meter.

W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4

WE15EK1.2; Knowledge of the W/E15 Containment Flooding / 5 X 2.7 operational implications of the following concepts as they apply to the (Containment Flooding): Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

W/E16 High Containment Radiation / 9 WE10EA2.2; Ability to determine and BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X 3.9 interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

WE08EA1.1; Ability to operate and / or CE/A11; W/E08 RCS Overcooling - PTS / 4 X 3.8 monitor the following as they apply to the (Pressurized Thermal Shock):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

K/A Category Point Totals: 2 1 1 2 1/2 2/2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 003A2.03; Ability to (a) predict the 003 Reactor Coolant Pump X impacts of the following malfunctions or 2.7 operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.

003G2.4.45; Ability to prioritize and X interpret the significance of each 4.3 annunciator or alarm.

004A2.24; Ability to (a) predict the 004 Chemical and Volume X impacts of the following malfunctions or 2.8 Control operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Isolation of both letdown filters at one time: down-stream relief lifts.

004A1.05; Ability to predict and/or 2.9 monitor changes in parameters (to X

prevent exceeding design limits) associated with operating the CVCS controls including: S/G pressure and level.

005A1.03; Ability to predict and/or 005 Residual Heat Removal X monitor changes in parameters (to 2.5 prevent exceeding design limits) associated with operating the RHRS controls including: Closed cooling water flow rate and temperature.

005K3.06; Knowledge of the effect that a X loss or malfunction of the RHRS will 3.1 have on the following: CSS.

006K5.07; Knowledge of the operational 006 Emergency Core Cooling X implications of the following concepts as 2.7 they apply to ECCS: Expected temperature levels in various locations of the RCS due to various plant conditions.

X 006K6.05; Knowledge of the effect of a 3.0 loss or malfunction on the following will have on the ECCS: HPI/LPI cooling water.

007G2.2.44; Ability to interpret control 007 Pressurizer Relief/Quench X room indications to verify the status and 4.2 Tank operation of a system, and understand how operator actions and directives affect plant and system conditions.

X 007A2.03; Ability to (a) predict the 3.9 impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Overpressurization of the PZR.

008 Component Cooling Water X 008K2.02; Knowledge of bus power 3.0 supplies to the following: CCW pump, including emergency backup.

010K6.04; Knowledge of the effect of a 010 Pressurizer Pressure Control X loss or malfunction of the following will 2.9 have on the PZR PCS: PRT.

X 010G2.2.44; Ability to interpret control 4.4 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

012K4.09; Knowledge of RPS design 012 Reactor Protection X feature(s) and/or interlock(s) which 2.8 provide for the following: Separation of control and protection circuits.

013 Engineered Safety Features X 013A4.01; Ability to manually operate 4.5 Actuation and/or monitor in the control room:

ESFAS-initiated equipment which fails to actuate.

022K4.01; Knowledge of PRTS design 022 Containment Cooling X feature(s) and/or interlock(s) which 2.6 provide for the following: Quench tank cooling.

025 Ice Condenser 026A1.03; Ability to predict and/or 026 Containment Spray X monitor changes in parameters (to 3.5 prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level.

4.4 026A2.03; Ability to (a) predict the X impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of ESF.

039K5.08; Knowledge of the operational 039 Main and Reheat Steam X implications of the following concepts as 3.6 they apply to the MRSS: Effect of steam removal on reactivity.

059 Main Feedwater X 059A3.03; Ability to monitor automatic 2.5 operation of the MFW, including:

Feedwater pump suction flow pressure.

061 Auxiliary/Emergency X 061K2.03; Knowledge of bus power 4.0 Feedwater supplies to the following: AFW diesel driven pump.

062A3.01; Ability to monitor automatic 062 AC Electrical Distribution X operation of the ac distribution system, 3.0 including: Vital ac bus amperage.

062K2.01; Knowledge of bus power X 3.3 supplies to the following: Major system loads.

063K3.01; Knowledge of the effect that a 063 DC Electrical Distribution X loss or malfunction of the DC electrical 3.7 system will have on the following: ED/G.

064K6.07; Knowledge of the effect of a 064 Emergency Diesel Generator X loss or malfunction of the following will 2.7 have on the ED/G system: Air receivers.

073K1.01; Knowledge of the physical 073 Process Radiation X connections and/or cause effect 3.4 Monitoring relationships between the RPS and the following systems: 120V vital/instrument power system.

X 073A2.01; Ability to (a) predict the 3.6 impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation.

076 Service Water X 076A3.02; Ability to monitor automatic 3.7 operation of the SWS, including:

Emergency heat loads.

X 076A4.04; Ability to manually operate 3.5 and/or monitor in the control room:

Emergency heat loads.

078G2.4.34; Knowledge of RO tasks 078 Instrument Air X performed outside the main control room 4.2 during an emergency and the resultant operational effects.

078K1.05; Knowledge of the physical X connections and/or cause-effect 3.4 relationships between the IAS and the following systems: MSIV air.

103K1.08; Knowledge of the physical 103 Containment X connections and/or cause/effect 3.6 relationships between the containment system and the following systems: SIS, including action of safety injection reset.

X 103K4.01; Knowledge of containment 3.0 system design feature(s) and/or interlock(s) which provide for the following: Vacuum breaker protection.

K/A Category Point Totals: 3 3 2 3 2 3 3 2/3 3 2 2/2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 001K5.47; Knowledge of the following 001 Control Rod Drive X operational implications as they apply to 2.9 the CRDS: Factors affecting SUR: eff ,

l/.

002 Reactor Coolant 011 Pressurizer Level Control X 011K2.02; Knowledge of bus power 3.1 supplies to the following: PZR heaters.

014K1.01; Knowledge of the physical 014 Rod Position Indication X connections and/or cause/effect 3.2 relationships between the RPIS and the following systems: CRDS.

015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017K6.01; Knowledge of the effect of a 017 In-core Temperature Monitor X loss or malfunction of the following ITM 2.7 system components: Sensors and detectors.

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029A3.01; Ability to monitor automatic 029 Containment Purge X operation of the Containment Purge 3.8 System including: CPS isolation.

033 Spent Fuel Pool Cooling X 034G2.4.30; Knowledge of events related 034 Fuel Handling Equipment to system operation/status that must be 4.1 reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

035 Steam Generator X 035A1.02; Ability to predict and/or 3.5 monitor changes in parameters (to prevent exceeding design limits) associated with operating the S/GS controls including: S/G pressure.

041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator X 045A2.17; Ability to (a) predict the 2.7 impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Malfunction of electrohydraulic control.

055 Condenser Air Removal X 055K3.01; Knowledge of the effect that a 2.5 loss or malfunction of the CARS will have on the following: Main condenser.

056 Condensate X 056G2.1.28; Knowledge of the purpose 4.1 and function of major system components and controls.

068 Liquid Radwaste X 068K4.01; Knowledge of design 3.4 feature(s) and/or interlock(s) which provide for the following: Safety and environmental precautions for handling hot, acidic, and radioactive liquids.

071 Waste Gas Disposal 072 Area Radiation Monitoring X 072A2.03; Ability to (a) predict the 2.9 impacts of the following malfunctions or operations on the ARM system- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Blown power-supply fuses.

075 Circulating Water 079 Station Air X 079A2.01; Ability to (a) predict the 3.2 impacts of the following malfunctions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Cross-connection with IAS.

086 Fire Protection K/A Category Point Totals: 1 1 1 1 1 1 1 1/2 1 0 1/1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Farley Date of Exam: October, 2015 Category K/A # Topic RO SRO-Only IR # IR #

2.1.18 Ability to make accurate, clear, and concise logs, records, status 3.6 boards, and reports.

1. 2.1.8 Ability to coordinate personnel activities outside the control 3.4 Conduct room.

of Operations 2.1.41 Knowledge of the refueling process. 3.7 Subtotal 2 1 2.2.21 Knowledge of pre- and post-maintenance operability 2.9 requirements.

2.2.22 Knowledge of limiting conditions for operations and safety 4.0

2. limits.

Equipment 2.2.35 Ability to determine Technical Specification Mode of 3.6 Control Operation.

2.2.13 Knowledge of tagging and clearance procedures. 4.3 2.2.40 Ability to apply Technical Specifications for a system. 4.7 Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 emergency conditions.

2.3.15 Knowledge of radiation monitoring systems, such as fixed 2.9

3. radiation monitors and alarms, portable survey instruments, Radiation personnel monitoring equipment, etc.

Control 2.3.12 Knowledge of radiological safety principles pertaining to 3.7 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.14 Knowledge of radiation or contamination hazards that may 3.8 arise during normal, abnormal, or emergency conditions or activities.

Subtotal 2 2 2.4.18 Knowledge of the specific bases for EOPs. 3.3 2.4.27 Knowledge of fire in the plant procedures. 3.4

4. 2.4.43 Knowledge of emergency communications systems and 3.2 Emergency techniques.

Procedures / Plan 2.4.30 Knowledge of events related to system operation/status that 4.1 must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

2.4.35 Knowledge of local auxiliary operator tasks during an 4.0 emergency and the resultant operational effects.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 011EA2.01 Oversampled. Changed to 007EA2.03.

1/1 025AA2.05 Oversampled. Changed to WE5EA2.1.

1/2 028AK1.01 Oversampled. Changed to 037AK1.02.

1/2 068AA2.11 Oversampled. Changed to 024AA2.05.

1/2 WE09G2.2.38 Oversampled. Changed to 051G2.2.38.

2/1 005A1.05 Oversampled. Changed to 004A1.05.

2/1 022K4.04 Oversampled. Changed to 103K4.01.

2/1 061K2.02 Oversampled. Changed to 062K2.01 2/1 073K3.01 Oversampled. Changed to 005K3.06.

3 G2.3.14 Oversampled. Changed to G2.2.22

E5-401 Wntteri Examination Quality Checklist Form ES-401-.6 Factiuty:FARLEY DateofExarn: 10/5/15 Examlevei: RD SRO tnitjal tern Description 1 Questions and answers are technically accurate and applicable to the facility.

2. a. NRC KJAs are referenced for all questions.

b. Facility teaming objectives are referenced as available.

4

3. SRO questions are appropriate in accordance with SectIon D.2.d of ES-4i)1 The sampling process was random and systematIc (If more than 4 RD or 2 SRO questions f

ware repeated from the last two NRC licensing exams, consult the NRR/NRO DL program

5. Question duplication from the licensee screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate The audit exam was systematically and randomly developed; or the audit exam was completed before the iicense exam was started; or the examinations were developed Independently; or the licensee certifies that there is no duplication; or other (explain)

6. Bank use meets limits (no more than 75 percent from the bank, at least 10 percent new, and the rest new or Bank Modified New modified enter the actual RD / SRO-onty question

7. Between 50 and 60 percent of the questions on the RD 301 3 1 3112 32/10 ZY exam are written at the comprehension.! analysis level; the Memory C/A

• SRO exam may exceed 60 percent if the randomiy selected K/As support the higher cognitive levels. enter the actual RD I SRO_question distribution(s) at rIght.

31/ 5 441 20 14- ](

8. References/handouts provided do not give away answers or aid i the ailmination of dislractors.

9. Question content conforms to specific K/A statements In the previously approved examination j.

outline and Is_appropriate_for the tler to which_they_are_assigned:_deviations are_justified.

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

11. The exam contains the required number of one-paint, multiple choice Items: the total Is correct and agrees with the value an the cover sheeL Printed Name I S gnature Date

a. Author Stanley Jackson /

b. FacIlity Reviewer () SHIy Thornton 9/22115 c.

i NRC Chief ExamIner (if)

NRC Regional Supervisor 2)OdO

/ a?  :::_

6

{ A)

Note: The facility reviewers initials or signature are not appcabte for NRC-developed examinations.

if independent NRC reviewer initials items In Column c; chief examiner concurrence required.

ES-401 Written Examination Review Worksheet - Farley 2015-301 Form ES-401-9

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only 001AG2.1.32.

K/A is met.

Reverse the question order. Then this would NOT pre-dispose the applicants on whether to trip or go to 1 F 2 X N E AUTO. Drl 7/13/15 Reversed the FIB order as requested. BT 7/23/15 Revised question attached.

Revised question is SAT. drl 8/11/15 001K5.47.

2 F 2 N S K/A is met drl 7/13/15 003A2.03.

3 H 3 N S K/A is met. drl 7/13/15 004A2.24.

4 H 3 N S K/A is met. drl 7/13/15 004K4.12.

5 F 2 B S K/A is met drl 7/13/15 05A1.03.

6 F 2 N S K/A is met drl 7/13/15 Instructions (Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts:

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

2. Enter the level of difficulty (LOD) of each question a 1(easy) to 5 ( difficult); (questions with a difficulty between 2 and 4 are acceptable)

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

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

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

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

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

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

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

• Job Link: The question is not linked to the job requirements (i.e., the question has a valid K/A, but as written, is not operational in content).

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

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

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

5. Check questions that are sampled for conformance with the approved K/A and those K/As that are designated SRO-only (K/A and license level mismatches are unacceptable)

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

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

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

ES-401 2 Form ES-401-9

1. 2. 6. Source 7. Status Q 3. Psychometric Flaws 4. Job Content Flaws 5. Other 8. Explanation LO LOD (B/ M / N) (U /E /S)

K (1-5)

Stem Cred. Job- #/ Back Q- SRO (F/ Cues T/F Partial Minutia Focus Dist Link Units ward K/A Only H) 005K6.03.

K/A is kind of met.

Is it possible to supply fire water to the CCW system per AOP-9.0 via a charging pump and thus cool the seals? Looking at the procedures, it appears that this might be the case. If so, then the second question needs altered. Drl 7/13/15 We understand your comment on the K/A match. We could modify the second FIB to ask if that RHR train 7 F 3 X M E/U could / could not be used for recirculation during a LOCA. That would be a direct K/A match.

BT 7/23/15 Revised Question attached Revised question is SAT. drl 8/11/15 After further evaluation, we found that an additional bullet was required in the stem stating that The A Train is the ON SERVICE Train. This was discussed with CE and he concurred.

BT 9/18/15 Revised Question is SAT. drl 9/23/15 006K5.07.

8 H 2 B S K/A is met. drl 7/13/15 006K6.05.

9 F 2 N S K/A is met drl 7/13/15 007G2.2.44.

K/A is not really met. The second part of the question is asking how operator actions and directives affect the plant. Something more on the line of what is the effect of what happened.

First FIB meets ability to interpret control room indications. Second FIB is understanding how operator actions affect plant conditions. Both are related. BT 7/23/15 10 F 2 X X B U Second question distractor does not seem very plausible. Where else in the plant do you control the atmosphere for corrosion concerns? Drl 7/13/15 We use N2 atmosphere for corrosion control of SGs during wet layup conditions, use N2 atmosphere for corrosion control of FW Heaters during shutdown, we use H2 in the RCS to minimize corrosion products.

BT 7/23/15 Revised question is SAT. drl 8/11/15 008G2.1.32.

K/A is not met. The question needs to demonstrate knowledge to explain and apply system limits and precautions associated with a vapor space accident.

Although the indicated level may rise due to this leak, uncovering the core is a real threat. Knowing the LP Reactor Trip set point does not meet the K/A.

11 F 2 X N U The stated basis for meeting the K/A does not match the question, but does hint at a possibly better K/A match. Drl 7/13/15 Question revised based upon comments.

BT 7/23/15 Revised question attached.

Revised question is SAT. drl 8/11/15 008K2.02.

12 H 3 M S K/A is met. drl 7/14/15 009EA1.17.

13 F 2 N S K/A is met. drl 7/14/15 011EK3.05.

14 F 2 N S K/A is met drl 7/14/15 011K2.02.

15 H 3 N S K/A is met. drl 7/14/15 012K4.09.

16 F 2 N S K/A is met. drl 7/14/15 013A4.01.

17 H 3 N S K/A is met. drl 7/15/15 013K2.01.

18 F 2 B S K/A is met. drl 7/15/15 014K1.01.

19 F 3 N S K/A is met. drl 7/15/15 015AA2.08.

K/A is met.

Could we put a procedural reference in the question IAW ARP-1.10 only the drl 7/15/15 There are two ARPs that would need to be referenced, one provides info for Motor Bearing temp limits, the other provides Motor Stator Temp limits.

20 H 3 B E We could be cueing if we provided per ARP-XX.

BT 7/23/15 As long as there are no other references that would conflict with the answer given, this would be SAT. drl 8/11/15 We can find no other reference to cause conflict with the correct answer. BT 9/18/15 Question is SAT. drl 9/23/15 017K6.01.

K/A is met.

A, C, and D are too connected. By disconnecting a CETC you are failing it high. Therefore would an applicant consider C?

A better way to ask this might be to ask it like this:

Which of the following conditions would cause the CETC monitor to generate an alarm?

1. Any CETC input is disconnected.

2. Only 10 valid CETCs

3. Any CETC temperature at 650 °F 21 F 3 X B E A. 1 ONLY.

B. 1 and 3 ONLY.

C. 2 ONLY.

D. 1, 2, and 3.

Drl 7/15/15 Question modified as requested, but also modified stem to clarify that we are only asking about a CETC monitor alarm rather than any alarm (MCB,etc.).

cause a Core Exit Thermocouple (CETC) monitor alarm.

BT 7/23/15

Revised Question Attached Revised question is SAT. drl 8/11/15 022AA2.02.

K/A is met.

Could we change the FCV-122 to failed closed? I believe this would still only be a single correct answer and slightly more plausible. Drl 7/15/15 22 H 2 M E Modified as requested, but used terminology FCV-122 closing since FCV-122 fails open.

BT 7/23/15 Revised Question Attached Revised question is SAT. drl 8/11/15 022K3.01.

K/A is not met.

K/A requires demonstration of knowledge of effects on systems in containment when CCS is lost not just how the CCS responds.

23 H 3 M U Perhaps if you also ask why the fans shift to slow speed, this would cleanly match the K/A. Drl 7/15/15 Modified as requested.BT 7/27/15 Revised Question Attached.

Revised question is SAT. drl 8/11/15 025AG2.4.2.

K/A is met, but backwards.

The applicant should understand the setpoints to determine that nothing happens. This is not wrong, but could be confusing to applicants that are unsure.

Lets discuss this to make sure it is worded the way it should be o test the desired knowledge.

What was the initial pressure? What was the cause of the pressure drop? Do those questions matter?

24 H 3 N E Is there anything else that could be inferred to have happened that would have been an AOP entry condition? drl 7/15/15 To reduce confusion and clarify, modified question.

Removed the HG5 bullet in the stem and changed the second FIB to IF MOV-8701A Closes, then AOP-12 entry (IS or is NOT) required. BT 7/27/15 Revised question attached.

Revised question is SAT. drl 8/11/15 026A1.03.

25 F 2 B S K/A is met. drl 7/15/15 027AK2.03.

26 H 2 N S K/A is met. drl 7/15/15 029A3.01.

K/A is met.

27 H 3 N S Seems like a poor design to leave the fans running deadheaded. Drl 7/15/15 029EK2.06.

K/A is met.

The Part 2 distractor is not plausible. If you know the 28 F <2 X B U RTBs are in parallel, why would you ever consider that a RTBB would do anything else?

LOD is very low for the first part. This is GFES knowledge.

Perhaps you can change it to ask what the status of each breaker is after a valid A or B train actuation. drl 7/15/15 Changed question in response to comment BT 7/27/15 Revised Question Attached Revised question is SAT. drl 8/11/15 035A1.02.

K/A is met.

Wording is a bit awkward. Could we remove due to increased steam demand from the 2B SG from the question and still have a valid question? drl 7/15/15 29 H 3 B E We put that info in the stem due to validator FB. If RCS temperature is lowered using steam dumps in auto, you will get steam flow from C loop, and eventually you could lower 2B SG pressure as RCS cooled down. The extra wording makes answer choice D completely incorrect.

BT 7/23/15 Original question is SAT. drl 8/11/15 038EK1.02.

K/A is met.

GFE Question. drl 7/15/15 This meets the K/A and is operationally valid 30 H 2 B S/E (requires use of plant instrumentation), in that the student has to determine which pressures and temperatures to use to determine the correct answers.BT 7/23/15 After further review, the question is SAT. drl 8/14/15 039K5.08.

31 H 3 B S K/A is met. drl 7/15/15 045A2.17.

32 H 3 B S K/A is met. drl 7/15/15 051G2.2.38.

33 H 3 N S K/A is met. drl 7/15/15 054AA1.04 34 H 3 B S K/A is met. drl 7/15/15 055EK3.02.

K/A is met.

A is not very plausible. How does depressurizing the secondary side minimize the DP. Instead consider something on the lines of minimizing the RCS as a heat source. drl 7/15/15 A is plausible because D/P across the SG U-Tubes is reduced during the procedure but it isnt a reason 35 H 3 B E pressure is reduced.

In ECP-0.0 one additional reason SG Pressure is reduced to 260 psig is to dump accumulators. During SG depressurization the RCS pressure drops due to RCS temperature dropping. Pressure must drop to at least 650psig in order for accumulators to inject.

Initially :

D/P = 2235 psig (RCS) - 1000 psig (SG)=1235 psig

After Secondary Depressurization:

D/P = 650 psig (RCS) - 260 psig (S/G) = 390 psig BT 7/23/15 After further review, the question is SAT. drl 8/14/15 055K3.01.

36 H 2 B S K/A is met. drl 7/15/15 056AG2.4.1.

K/A is kind of met.

The first questions distractors are barely plausible since you tell them that all AC is lost. The second question is not very logical (and kind of minutia) since you are in Mode 4.

Consider changing the stem state that both units are in Mode 5 following a hurricane onsite. Then state that all offsite power is lost and the EDGs fail to start.

There is a report of a fire in the 1B EDG oil system and another report that the 2B EDG air system has 37 H 3 N E ruptured.

Then the first question could remain the same, but the answer would be the AOP. The second question is would ask what that procedure would immediately require them to do. Either restore one of the EDGs or start the SBO EDG. Here the answer should be the SBO EDG. drl 7/15/15 Changed per recommendations.

BT 7/27/15 Revised Question Attached Not quite changed per recommendation, but revised question is still SAT. drl 8/14/15 056G2.1.28.

38 F 2 B S K/A is met. drl 7/15/15 057AA2.16.

K/A is met.

Is LCV-1115A being in AUTO unusual? If his is the normal position for the controller, then this is teaching and needs to be removed from the stem. drl 7/15/15 39 H 3 N E Removed the bullet for LCV-115A being in AUTO.

That is its normal position.

BT 7/23/15 Revised Question attached.

Revised question is SAT. drl 8/14/15 058AA1.02.

40 H 3 B S K/A is met. drl 7/15/15 059A3.03.

41 H 2 B S K/A is met. drl 7/16/15 060AK2.01.

42 H 3 B S K/A is met. drl 7/16/15 061A1.01.

43 H 3 N S K/A is met. drl 7/16/15 062A3.01.

K/A is met.

On a loss of feed event, how quickly would the setpoint for the MDFW pumps to start be reached?

44 H 3 N E Based on the conditions given, I dont think youd reach low level to start the pumps in less than 10 seconds AND since you had a LOSP, there is no auto start on loss of the MFPs. This could cue the applicants towards 0 amps.

An easy fix would be to use the SW pumps (as long as they have amp indication) and make A the answer. This would also remove some overlap from the previous question. drl 7/16/15 The MDAFW pumps are started by the LOSP Sequencer. It is not based on reaching a normal AFW auto start setpoint.

BT 7/23/15 After further review, the question is SAT. drl 8/14/15 062AK3.01.

45 H 3 N S K/A is mostly met. drl 7/16/15 062K2.01.

46 F 2 N S K/A is met. drl 7/16/15 063K3.01.

47 H 3 M S K/A is met. drl 7/16/15 064K6.07.

K/A is kind of met.

Second question distractor is not plausible. For an item that will cause inoperability, youd expect it to have some kind of annunciation in the CR. If you can show me examples where Im wrong, then this will be SAT.

A better K/A match would have the second question ask how many start attempts, by design, would be left if the pressure was at the alarm setpoint before the EDG could not start.

48 F 2 B U This would also raise it to a higher level question. drl 7/16/15 Second FIB changed per recommendation.

BT 7/27/15 Revised question attached In order to get rid of a subset issue, make the second question state that per FSAR section xx, there is enough air pressure drl 8/14/15 Changed the word minimum to maximum in the second question statement per phone communication with CE 8/21/15. BT 9/18/15 Revised question is SAT. drl 9/23/15 067AA1.06.

49 H 2 B S K/A is met. drl 7/16/15 068K3.03.

50 H 3 N S K/A is met. drl 7/16/15 068K4.01.

K/A is met.

How many questions are in the bank that match this K/A? drl 7/16/15 51 H 2 B E There are 4 questions in the bank (questions from other facilities and one from the previous NRC exam). This question was randomly selected per NUREG guidance. BT 7/27/15 This question is SAT.drl 8/14/15 073K1.01.

52 H 3 B S K/A is met. drl 7/16/15 076A3.02.

53 H 3 M S K/A is met. drl 7/16/15 076A4.04.

54 H 2 X X N E K/A is met.

• It seems that the MOC switch could never

be wrong. Although the sequencer appears to be a decent distractor, the MOC switch appears too good.

• Is there a reason you state that the charging pump is running AND the supply breaker is closed. Would that not raise eyebrows if the pump was running with the breaker open or tripped?

• Is changing the first question to Cooler is designed to / is NOT designed to be running? Since other ESF coolers run on a thermostat, I think that might work. We would need to add a room temperature to the question to enhance the distractors.

• We probably dont need the 4th bullet about the lack of damage. Normal should be assumed and we dont want to key the applicants.

drl 7/16/15 changed per recommendation BT 7/27/15 Revised question attached The revised question is SAT. drl 8/14/15 076AA2.03.

K/A is met.

This is OK as long as Operations agrees that the applicants should know that the Hi Alarm is 1x104 55 F 2 N E cpm above background. drl 7/16/15 David Reed (OPS Rep) Reviewed and approved the Current Version of question.

BT 7/28/15 The question is SAT. drl 8/14/15 077AK2.01.

56 H 2 M S K/A is met. GFES type question. drl 7/16/15 078G2.4.34.

57 H 2 B S K/A is met. drl 7/16/15 078K1.05.

58 H 3 N S K/A is met. drl 7/16/15 103K1.08.

K/A is met.

Im not sure why resetting Phase A SI would be plausible for resetting Phase A Containment Isolation especially when you tell them that Phase B Reset switches exist. drl 7/16/15 Removed MLB-1, 2, and 3 lights from the stem 59 H 3 X B E/U This removes reference to Phase A as a separate signal in the stem. This should improve plausibility.

Also, Phase B is a totally separate signal but Phase A occurs upon each SI. So, it is plausible that resetting SI would reset the associated Phase A.

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 103K4.06.

60 H 3 B S K/A is met. drl 7/16/15 G2.1.18.

61 F 2 N S K/A is met. drl 7/16/15

G2.1.8.

K/A is kind of met.

Reducing hydrogen pressure does not seem logical just because you SI. What would this have to do with the SI?

Why not pull something out of the manual EDG start procedure? Ask about something that the RO and non-licensed operator need to coordinate.

There isnt really any procedural direction that would 62 F 2 X N E/U meet the K/A related to the DG but we made the following change to better meet the K/A.

1st FIB - TBSO is required to close MSR STM SUPP ISO (following an Reactor Trip or Only when directed) 2nd FIB - TBSO is required to close MS DRN POT (following any Reactor Trip or Only when directed)

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 G2.2.6.

K/A is met.

Put Pen and Ink in quotes to denote that you are using the term as defined in the procedure. It appears that a procedure can be changed by hand 63 F 3 N E but the full process needs to be followed. By using the defined term in quotes it wont allow a looser definition to be used. drl 7/16/15 Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 G2.2.22.

64 F 2 B S K/A is met. drl 7/20/15 G2.2.35.

65 F 2 N S K/A is met. drl 7/20/15 G2.3.15.

K/A is met.

Why is Beta ONLY more plausible than Gamma ONLY? Recommend using Gamma ONLY as distractor unless there is a good reason not to. drl 7/20/15 66 H 2 X B E This question was a bank question used on a previous NRC exam and we believed that the plausibility of the distractor was not in question but we have made the recommended change. BT 7/27/15 Revised question attached.

The revised question is SAT.drl8/14/15 G2.3.4.

67 H 2 B S K/A is met. drl 7/20/15 G2.4.18.

68 H 2 B S K/A is met. drl 7/20/15 G2.4.27.

69 F 3 B S K/A is met. drl 7/20/15 G2.4.43.

K/A is met.

This General Employee Training information. This is 70 F 1 B U not at the RO level.

You could go with who is responsible for communication with the state (ED or SM) after TSC is setup. drl 7/20/15

Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 WE08EA1.1.

71 H 3 B S K/A is met. drl 7/20/15 WE11EK1.3.

K/A is met.

Could we modify the question slightly? Give that the RWST Lo Level alarm came in and level is at something > 4.5 feet (perhaps the setpoint). This would change the answer to D. drl 7/20/15 Recommended change made. BT 7/27/15 Revised question attached.

72 H 3 X M E The revised question is SAT. drl 8/14/15 After further evaluation, we found that the modified question had become more complex and would require a procedure table as a reference. After discussion with CE changed RWST level back to 3 feet and the question was reverted to the draft submittal version BT 9/18/15 The revised question is SAT. drl 9/23/15 WE12EK1.3.

73 H 3 M S K/A is met. drl 7/20/15 WE13EK1.1.

K/A is met.

Add and rising to the first bullet.

Change the second question to read When FRP-H.2 74 H 3 X N E drl 7/20/15 Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/14/15 WE15EK1.2.

75 H 3 N S K/A is met. drl 7/20/15 003AG2.1.23.

76/1 H 3 N S K/A is met. drl 7/20/15 003G2.4.45.

77/2 H 3 N S K/A is met. drl 7/20/15 007A2.03.

K/A is met.

Not really at SRO level. The applicants only need to know the purpose and overall sequence of the procedures.

Suggestion: Give a temperature of the tank above 120 F and pressure above alarm setpoint. Then ask if High pressure alarm is in and whether draining the 78/3 H 2 X M U PRT per section 4.3 will or will not correct al out of specs with the tank. drl 7/21/15 The RO exam has a question that asks if the PRT high pressure alarm is or is not in alarm.

Modified question incorporating your comments.

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 007EA2.03.

79/4 H 3 M S K/A is met. drl 7/21/15

10G2.2.44.

80/5 H 3 M S K/A is met. drl 7/21/15 026A2.03.

81/6 H 3 M S K/A is met. drl 7/21/15 026AA2.03.

K/A is met.

Is there procedural guidance to isolate CCW from the MCR? If so, lets add that information to the question IAW procedure XYZ, the method drl 7/21/15 82/7 H 2 B E There is no specific procedure to isolate CCW to RCPs from the MCB. However, there is NO way possible to isolate CCW to only one RCP from the MCB. The correct answer is correct in all cases.

BT 7/27/15 The original question is SAT. drl 8/17/15 028A2.02.

83/8 H 3 B S K/A is met. drl 7/22/15 028AG2.1.25.

84/9 H 3 N S K/A is met. drl 7/22/15 034G2.4.30.

K/A is met.

Second question distractor is not very plausible and of very low difficulty. Why would the transfer tube level ever be above the reactor flange level (just considering dose issues).

A better question might be to ask what the next action required in AOP 12 is. In this case it would be to begin containment isolation. The distractor would be to commence charging from RWST. drl 7/22/15 85/10 H 2 X N E Based on review of AOP-12, it appears that your suggestion could have 2 correct answers. We used your suggestion for the 2nd FIB.

BT 7/27/15 Revised question attached.

If we changed the revised second question to state Per AOP-12, RHR System Malfunction, the maximum time to complete containment closure is __

hours drl 8/17/15 Revised 2nd question per above. BT 9/18/15 Revised question is SAT. drl 9/23/15 036AA2.02.

K/A is met.

The distractors for question 2 make the answer for question 1 seem obvious. If either one is possible, then AOP entry would be a minimum expectation.

Instead could we reword to be something like the following:

Remove the words causing damage to the spent 86/11 H 3 X M E fuel from the second bullet.

AOP-30 _1_ required to be entered because the basis of TR 13.9.4, Crane Travel Spent Fuel Storage Building, the expected worse case consequences of dropping a load weighing less than 3000 lbs is that the _2_.

A (1) IS

(2) activity release will be limited B (1) IS (2) offsite dose at the site boundary will NOT exceed 10% of 10 CFR100 limits.

C (1) IS NOT (2) no fuel damage would occur.

D. (1) IS NOT (2) any possible distortion of fuel in the storage racks will not result in a critical array.

It still needs work, but I think that this path leads to a better question. drl 7/22/15 Fuel damage has to be a component for AOP-30 entry to be required (initial condition for entry). We may need to discuss more, but we have a proposed question.

BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 056AG2.2.44.

K/A is met.

Would it be simpler to just ask if SW is operable and if the EDG is operable at 1017?

IAW TS 3.8.1, the sequencer is inoperable, the 1B DG is/is not operable, and SW is/is not operable.

No reference would be required. drl 7/22/15 Technically, the failure of the sequencer would make Service Water inoperable along with the DG but the Required Action Statements would NOT be entered for SW or the DG. By asking if they were 87/12 H 3 X N E OPERABLE (but the RAS is not required) is a play on words and becomes confusing as to the actual question asked. We feel that this is the best wording for this question. It is essentially testing the SRO knowledge of whether cascading is required, so providing the TS does not give them the answer.

BT 7/27/15 The original question is SAT. drl 8/17/15 During final validation of this question during prep week, one validator found that there was insufficient information to choose the correct answer. After discussion with CE, question was modified and CE approved.

BT 9/18/15 The revised question is SAT. drl 9/23/15 065AG2.4.22 K/A is kind of met.

This would be a better K/A match if we can delete the words due to the loss of instrument air from the first question. This implies that there is a malfunction of 88/13 H 3 X M E some type. I believe that this will then allow some insight into their bases knowledge. drl 7/22/15 We modified question to start in Mode 3 and removed due to the loss of instrument air. Starting in Mode 3

eliminated the concern of Pressurizer level going down due to the Reactor trip, thus confusing the students. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 072A2.03.

K/A is met.

First question is obvious. Of course it affects the ability to evaluate the loss :. Instead you can just 89/14 H 2 X N E ask them how it fails. drl 7/22/15 Recommended change made. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 073A2.01 90/15 H 2 N S K/A is met. drl 7/22/15 G2.1.41.

K/A is met.

Maintenance Supervisor is not plausible. Lets make this a 2x2.

Per FHP-1.0, what requirements must be met prior to latching?

FHS in containment OR in Control Room in direct communications.

91/16 F 2 X M U AND AT least 2 SR flux rad monitors (NI-31,32, or 48) OR Containment is set.

drl 7/22/15 Incorporated changes based on your recommendation. BT 7/27/15 Revised question attached.

The revised question is SAT. drl 8/17/15 G2.2.13.

92/17 F 2 N S K/A is met. drl 7/22/15 G2.2.40.

93/18 H 2 M S K/A is met. drl 7/22/15 G2.3.12.

94/19 H 2 M S K/A is met. drl 7/22/15 G2.3.14.

K/A is met.

Be careful with potential overlap with # 11. drl 7/22/15 95/20 H 2 M E We dont feel there is overlap. These are different Tech Specs, different locations (SFP vs Reactor Cavity), and different questions.

BT 7/27/15 The original question is SAT. drl 8/17/15 G2.4.30.

96/21 H 3 M S K/A is met. drl 7/22/15 G2.4.35.

K/A is met.

Bullet 2 of distractor B is written differently than the other 3. Could the second part of the question be 97/22 H 3 X B E reworded to ask what issues must be addressed due to this action? drl 7/22/15 Revised question to address your concerns.

BT 7/27/15

Revised question attached.

The revised question is SAT. drl 8/17/15 WE04EG2.1.2.

98/23 H 2 M S K/A is met. drl 7/22/15 WE05EA2.1.

99/24 H 3 M S K/A is met. drl 7/22/15 WE10EA2.2.

K/A is met. drl 7/22/15 100/25 H 3 N S This question is not marked SAT, but we are assuming this question is SAT as is.

BT 7/27/15 The original question is SAT. drl 8/17/15

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Farley Date of Exam: October, 2015 Exam Level: RO SRO Item Description Initials a b c

1. Clean answer sheets copied before grading Z

2. Answer key changes and question deletions justified and documented

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

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

5. All other failing examinations checked to ensure that grades are justified /9

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader /1

b. Facility Reviewer(*)

..)/4

c. NRC Chief Examiner (*) 1r/ /

d. NRC Supervisor (*) )1/I)ZoI

/

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