Text

Initial Exam 2011-301 Final Administrative Documents
	ML111990551
Person / Time
Site:	Farley
Issue date:	07/02/2011
From:	; NRC/RGN-II
To:	; Southern Nuclear Operating Co
References
	50-348/11-301, 50-364/11-301, ES-201, ES-201-1
	Download: ML111990551 (61)
	v • d • e

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Farley Date of Examination: 05109/11 Developed by: Written - Facility LI NRC LI II Operating - Facility LI NRC LI Target Chief Date* Task Description (Reference) Examiners Initials

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

-120 2. NRC examiners and facility contact assigned (C.1 .d; C.2.e) rfa

-120 3. Facility contact briefed on security and other requirements (C.2.c) rfa

-120 4. Corporate notification letter sent (C.2.d) rfa

[-90] [5. Reference material due (C.1 .e; C.3.c; Attachment 3)] rfa

{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, rfa ES-301-1, ES-301-2, ES-301-5, ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1 .e and f; C.3.d)

{-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility rfa licensee (C.2.h; C.3.e)}

{-45} 8. Proposed examinations (including written, walk-through JPMs, and rfa scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1 .e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; rfa ES-202)

-14 10. Final license applications due and Form ES-201-4 prepared (CII; C.2.i; rfa ES-202)

-14 11. Examination approved by NRC supervisor for facility licensee review rfa (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g) rfa

-7 13. Written examinations and operating tests approved by NRC supervisor rfa (C.2.i; C.3.h)

-7 14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm rfa qualifications I eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed rfa with facility licensee (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions rfa distributed to NRC examiners (C.3.i)

ES-201-2 Examination Outline Quality Checklist FINAL SUBMITTAL Facility: Farley Nuclear Plant Date of Examination: May 9, 2011 Operating Test Number: FA2O1 1-301 Initials Item Task Description

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. 2 R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.

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

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

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

S and major transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and 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 A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

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

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within the limits specified on the form..

T (3) no tasks are duplicated from the applicants audit test(s) -

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

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

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

c. Determine if there are enough different outlines to test the projected number and mix ..i..

of applicants and ensure that no items are duplicated on subsequent days.

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

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

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 2 R d. Check for duplication and overlap among exam sections. -

L e. Check the entire exam for balance of coverage. 2

f. Assess_whether the_exam_fits_the_appropriate job_level_(RO_or SRO).

b. FacWty Reviewer (*)

c. NRC Chief Examiner (#) /ciJ d2 6 9 L/ I)

d. NRC Supervisor ID,UAA.frJ Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines

Form ES-201-3 ement Examination Security Agre ES-201

1. Pre-Examination scheduled for the week(s) of as of the date that I have acquire d special ized knowledge about the NRC licensing examinations by the I acknow ledge ations to any persons who have not been authorized my signatu re. I agree that I will not knowin gly divulge any information about these examin to be admini stered of ck to those applicants scheduled to instruct, evaluate, or provide performance feedba NRC chief examiner. I understand that I am not specifically noted below and author ized by the NRC completion of examination administration, except as these licensing examinations from this date until the training conten t or provid e direct or indirec t nicator is acceptable if the individual does not select (e.g., acting as a simulator booth operator or commu ented in the facility license es proced ures) and al security measures and requirements (as docum feedback). Furthermore, I am aware of the physic examin ations and/or an enforcement action against me or agreement may result in cancel lation of the understand that violation of the conditions of this ions or suggestions that examination security license e. I will immed iately report to facility management or the NRC chief examiner any indicat the facility may have been compromised.

2. Post-Examination ning the NRC licensing examinations administered e any unauthorized persons any information concer To the best of my knowledge I did not divulg to etion of examination administration, did not t!LFrom the date that I entered into this security agreement until the compl during the week(s) of these licensi ng examinations, except as specifically noted ck to those applicants who were administered instruct, evaluate, or provide performance feedba below and authorized by the NRC.

DATE SIGNATURE (2) DATE NOTE JOB TITLE! RESPONSIBILITY JIGNATURE (1)

PRINTED NAME 4t1 a

1. rr octc/ etitiz. -

L_L..je..(_ s-,4jM ji \ 7

.iI Z!e.tL. oi,-,( z;f

2. -q--Il A

3. pCAJELL I3JYIS -

7n EMP.C4- F S41.LI 7//7/)/

6.

S-cs

7. ;41 L -

z7-l/

8. 7 IL 1 SSS 5/24fjj

9. itrvoi Fefk 0P5 LVSZ 7

10. 1cQ °S 1jL4k- 4I%

11. t!%. j:5-/(,

12. J U4

13. Peq CZS Lé40 :2

___________ 5-i7I / 4 0

14. i

/AJ5r NOTES: J. 14c5 iL S vo 2 19 V

-t 1 Ae Adf-4 OA n +/-f c UA1L ES-20 1, Page 27 of 28 p

4 (p(eJ L-,z% () Pr-

ES-201 -3 Examination Security Agreement

1. Pre-Examination ?DcS 2 3 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weeks of 5- 9 -201 1 as of the date f my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of --t -iLw.L (-Zl- (I 1 . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

1. Billy Thornton Nuclear OPS TRNG INST 74-

-cF-- c- a 5 -.

2. Howard Fitzwater Nuclear OPS TRNG INST /o/s//O S 5-, /

3. Gary Ohmstede Lead Instructor-Exam Development /o(y/ 5-25-((

4. Darryl Stevenson Control Technician j-c-)

5. Michael Galle Simulator Coordinator . /ø

6. Kevin Riley Nuclear Specialist I /1/h/Jo (

7. Candice Wright Engineer II

8. Zst-,i. t $I4 4 .-J.So--

9. l>.)1V?9 (llIOi& Pkyvt y.iz-V -K 3 If I

10. rk r,oMfrN c,-t S.-vtc i L(3[1I

11. ILka

12. -124M 13.JoflA i,j. 4...,d.rs 5. 5/.t II 14

.4,i-i ticie.,, S 2- ;;

,/.zr/ii

,,-,i ,i,

15. ,piA4# A Pieø 10. l. Z__... f- 2.7-it NOTES:

5yf C

I CQ 5 ° krn U (4 I S fQ. f 1CO j pSC

ES-201-3 Examination Security Agreement

1. P re-Examination acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weeks of 5-9 -201 1 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 5-9-2011 through 5-24-201 1 . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

1. John H. Lewis Plant Operator see signed sheet 4/7/11 5/31/11 2.

3.

4.

5.

6.

7 8.

9.

10.

11.

12.

13.

14.

15.

NOTES:

ES-301 -1 Administrative Topics Outline HNAL SUBMITTAL Facility: Farley Nuclear Plant Date of Examination: May 9, 2011 Examination Level: RO X SRO X Operating Test Number: FA2011301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Title:

Critical Safety Function Status Tree

a. A.1.a Evaluation Conduct of Operations M, R

Description:

Students will be provided a listing of plant parameters.

This will require manually evaluating each status tree to determine the SRO + RO challenges to each tree and identify the highest priority challenge.

K/A: G2. 1.7 (RD 4.4 SRO 4.7)

b. A.1 .b

Title:

Determine Active License Status

Description:

The SRO will have to evaluate the status of 3 RDs to Conduct of Operations D, determine their license status for sitting the control board position.

SRO only KIA:G2.1.4(SRO3.8)

Title:

Determine Required Volume, Controller Settings And Integrator Settings For A Makeup

b. A.1 .b To The RWST.

Conduct of Operations P, D, R

Description:

The RD will be required to use nomographs and tank RO only curves to calculate the makeup to the RWST from the Makeup water system.

006A1.02 (RO-3.O SRO-3.6)

c. A.2.c

Title:

A) Determine Isolation Boundaries for a CCW Equipment Control Pump (RO & SRO)

SRO +RO part A B) Identify the Required Tech Specs for the Condition. (SRO only)

SRO part B only

Description:

Part A: Determine Isolation Boundaries for a CCW Pump N, R (mechanically) with a check valve that is spraying water and has to be isolated immediately; Determine the appropriate boundary points and required positions of components to safely isolate the CCW pump and; Eit: determine the required Tech Specs for the condition.

G2.2.41 (RO-3.5 SRO-3.9)

G2.2.40 (SRO-4.7)

d. A.3.d M, R

Title:

Determine Dose Rates, Projected Dose, and Radiation Control Dress out requirements

Description:

in preparation to adding oil to a RCP, the applicant will SRO +RO have to review the RWP and determine dose rates encountered, total projected dose, if the job can be done based on the dose and RWP provided and dressout requirements G2.3.4 (RO-3.2 SRO-3.7)

G2.3.7 (RO-3.5 SRO-3.6)

e. A.4.e N, R

Title:

Provide an updated PAR Emergency

Description:

PAR upgrade where a General Emergency already exists. The wind direction changes which requires a follow up Procedures/Plan notification and PAR upgrade.

SRO only 02.4.44 (SRO-4.4) Time critical JPM.

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

Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) [1/1]

(N)ew or (M)odified from bank ( 1) [3/4]

(P)revious 2 exams ( 1; randomly selected) [110]

ES-301-2 Control Room/In-Plant Systems Outline FINAL SUBMITTAL Facility: Farley Nuclear Plant Date of Examination: May 9, 201 1 Exam Level: RO IZI SRO-I IZI SRO-U-1 Operating Test No.: FA2011301 Control Room Systems© (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. CRO-033A: Perform Corrective Actions For Recovery Of A A,D,E,S 1 Misaligned Rod OO3AA1.02 RO-3.6 SRO-3.4 Est: 15 mm 001A2.11 RO-4.4 SRO-4.7 001A4.06 RO-2.9 SRO-3.2

b. CRO-343C: Establish Letdown as required following a Spurious A, M, 5 2 Letdown Isolation Signal and Stabilize Pressurizer Level Est: 15 mm 004A2.07 RO-3.4 SRO-3.7 004A4.05 RO-3.6 SRO-3.1

c. CRO-333D modified: Perform The Required Actions For Cold A, M, E, S 3 Leg Recirculation during a Large Break LOCA Est: 15 mm 011 EA1.11 RO-4.2 SRO-4.2

d. CR0-NEW: Stop the RCP with a degraded seal per the A, E, L, N, S 4P guidance of step 8 of AOP-4.1 and complete the necessary lOAs of AOP-4.0 upon stopping the RCP.

003A2.02 RO-3.7 SRO-3.9 Est: 10 mm 015/O17AA1.05 RO-3.8 SRO-3.8 015/O17AA1.08 RO-3.0 SRO-2.9

e. Isolate SW to the affected CNMT Cooler using SOP-i 2.1 E, N, 5 5 section 4.6 (ARP BB1 Step 6.1): Est: 12 mm 022A2.05 RO-3.1 SRO-3.5 W/EO15EA1.1__RO-3.i_SRO-3.5

f. CRO-41 5A, Start the station Blackout DIG D, E, 5 6 064A4.06 RO-3.9 SRO-3.9 Est: 10 mm 055EA1 .02 RO-4.3 SRO-4.4

g. CRO-328B: Restore IA to containment following SBLOCA. A, D, E, 5 8 065AA1.03 RO-2.9 SRO-3.1 Est: 10 mm

g. ALTERNATE Place Computer Room HVAC in operation

- E, N, 5 8 following Smoke detector operation (plant fireNF4 actions complete)

Description:

SOP-56.0 alignment to restore Computer Est: 10 mm Room HVAC back into service starting at step 4.1.2.

067AA1 .05 RO-3.0_SRO-3.1

h. CRO-395D, Display Individual CETC values D, E, S RO ONLY 7

017A4.01 R0-3.8 SRO-4.1 EST 7 mm In-Plant Systems@ (3 for Rb); (3 for SRO-I); (3 or 2 for SRO-U)

i. SO-590, Place The SJAE Filtration Unit In Service during a D, E 3 Steam Generator Tube Leak EST: 5 mm 037AA1.02 RO-3.1 SRO-2.9

j. S0-449, Supply EMERGENCY AIR to SG ARVs from D, E 8 Emergency Air Compressors during a Loss of instrument air Est: 10 mm APEO65AA1 .04_R0-3.5 SR03.4

j. ALTERNATE - SO-448, Align Backup Air To PORVs From D, E, R 8 Nitrogen Bottles Est:10 mm APE065AA2.07 RO-2.8 SRO-3.2

k. SO-95B, Align the Recycle Holdup Tank To Drain To Waste D, R 9 Holdup Tank Est: 10 mm 068K1 .07 RO-2.7 SRO-2.9

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

Type Codes Criteria for RO / SRO-I Alternate G impact (A)Iternate path 4-6 [5/5] (-11-1)

(C)ontrol room [0]

(D)irect from bank 8 [7/6] (-1/-i)

(E)mergency or abnormal in-plant 1 [9(1)/8(1)] (0/0)

(EN)gineered safety feature - (control room system) [N/A]

(L)ow- Power / Shutdown 1 [1]

(N)ew or (M)odified from bank including 1 (A) 2 [4(1 )/4(1 )]W/ 3(A) (+11+1)

(P)revious 2 exams 3 (randomly selected) [0]

(R)CA 1 [1/1]

(S)imulator [8(1)17(1)] (0/0)

NOTE: the (+/- x/ +/- y) demonstrates the impact_of_implementing_alternate_g.

ES-301-3 Operating Test Quality Checklist HNALSUbMH AL Facility: Farley Nuclear Plant Date of Examination: May 9, 2011 Operating Test Number: FA2O1 1-301 Initials

1. General Criteria a b* c#

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

sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution). L /

b. There is no day-to-day repetition between this and other operating tests to be administered 4 during this examination.

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

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

acceptable limits.

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

2. Walk-Through Criteria -- --

a. Each JPM includes the following, as applicable:

initial conditions -

initiating cues -

references and tools, including associated procedures

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

operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues i.-,

statements describing important observations to be made by the applicant.

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

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

3. Simulator Criteria -- --

The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-30l-4 and a copy is attached. I Printed N e / Si nature Date

a. Author: Howard_Fitzwater__/

b. Facility Reviewer(*) Gary Ohmstede__/ 4 I)

c. NRCChiefExaminer(#) / )

d. NRC Supervisor 9 hi oq/.

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

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

ES-301-4 Simulator Scenario Quality Checklist RNAL SUBMrrTAL Facilty: Farley Date of Exam: May 9, 2011 Scenario Numbers: 1/2/3/4 Operating Test No.: FA2011-301 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. fri.>

2. The scenarios consist mostly of related events.

3. Each event description consists of

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. pt#

5. The events are valid with regard to physics and thermodynamics. 2_.

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain (1,3 complete evaluation results commensurate with the scenario objectives. 2.

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

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

Cues are given.

8. The simulator modeling is not altered. 1... &

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated -

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

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

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

11. All individual operator competencies can be evaluated, as verified using Form ES-301 -6 (submit the form along with the simulator scenarios). 2.. (tZ

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

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

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

Scenario Numbers:

1 1213/4

1. Total malfunctions (58) 9/11 / 11/8 2.... .._

2. Malfunctions after EOP entry (12) 4/6/5/2 -z. *j_ -

3. Abnormal events (24) 3/4/5/4 z. 4.)

4. Majortransients(l2) 2/2/3/2 2.. txt)

5. EOPs entered/requiring substantive actions (12) 1 / 1 /2/1 2..

6. EOP contingencies requiring substantive actions (02)

0/1 /1 /1 Z.

7. Critical tasks (23) 3/3/3/2 possible contingency procedure entry Page 1 of 1

ES-301-4 Simulator Scenario Quality Checklist FINAL SUBMITTAL Facilty: Farley Date of Exam: May 9, 2011 Scenario Numbers: 6/7 Oøerating Test No.: FA2O1 1-301 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 description consists of

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

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

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

. the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

5. The events are valid with regard to physics and thermodynamics. e.

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

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

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

Cues are given.

8. The simulator modeling is not altered. 4

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated .J J.

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

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

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

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

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios). /)-A

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

Scenario Numbers:

617

1. Total malfunctions (58) 10/10 2.

2. Malfunctions after EOP entry (12) 4/5 2_-

3. Abnormal events (24) L

4. Major transients (12) 1 /2 -

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

6. EOP contingencies requiring substantive actions (02) 0/1

7. Critical tasks (23) 3/3 Page 1 of 1

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Farley Nuclear Plant Date of Exam: May 9, 2011 Operating Test No.: FA2O11-301

. FjNALSLEBMITTAL A E Scenarios V 1 2 3 4 M p E T I L CREW POSITION CREW POSITION CREW POSITION CREW POSITION 0 N I T I C T A M A y S A B S A B S A B S A B L U N P R T 0 R T 0 R T 0 R T 0 M()

T E o c p 0 C P 0 C P 0 C P RIU RX 1 1* 1 1 2 2 3 3 T T M 4*

NOR 2 111 A

I/C 2,3,4 2,5,6 3,4,6 2,3,4 4,5,6 2,3,4, 1,3,4, 1,3,7 4,5,7, 1,2,4 1,2,6 4,5,6 T 1 T T 5,6,7 5,7 7 5,7,8, 8,9 5,6,7 E 9 R MAJ 6, 7 6, 7 6,7 6,7 6,7 6,7 6,8,9 6,8,9 6,8,9 6,7 6,7 6,7 2 2 T TS 2,3, 3,4 2,4 2,4 0 2 2 5

RX 0110 SRO-i NOR 0 1 1 1 I/C 2,3,4 2,3,4 1,3,4, 1,2,4 24 T 5,6,7 5,7 5,7,8, 5,6,7 9

MAJ 6, 7 6,7 6,8,9 6,7 9 T TS 2, 3, 3,4 2,4 2,4 9 0 2 2 5

RX 1 1 2 3 4110 RO NOR 4 2 2* 1 1 1 I/C 2,5,6 4,5,6 1,3,7 1,2,6 12 4 4 2 MAJ 6, 7 6,7 69 6,7 9 2 2 7 TS 0022 RX 1 1 2 3* 1 1 0 4

BOP NOR 0 1 1 1 IC 3,4,6 2,3,4, 4,5,7, 4,5,6 15 4 4 2 7 8,9 MAJ 6,7 6,7 6,8,9 6,7 9 2 2 7 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 must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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

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

NUREG-i 021, Revision 9 Supplement 1 Page i of 2 Farley Facsimile Rev. 0

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Farley Nuclear Plant Date of Exam: May 9. 2011 Operating Test No.: FA2011-301 A B Scenarios V 6 7 M p E T I L CREW POSITION CREW POSITION 0 N I T I C T A M A S A B S A B L U N P R T 0 R T 0 M()

T E 0 C P 0 C P RIU RX 1 1 4 4 110 M

NOR 2* 1 1 1 A

I/C 2,3,4 2,4,6, 3,5,6, 1,2,3, 1,3,7 2,5,7 4 4 2 T

5,6,7 7 7 5,7 E MAJ 7 7 7 6,8 6,8 6,8 2 2 1 R

TS 2,4 1,2,5 0 2 2 RX TTT SRO-i NOR 0 1 1 1 I/C 2,3,4 1,2,3, 11 4 4 2 5,6,7 5,7 MAJ 7 6,8 3 2 2 7 TS 2,4 1,2,5 5 0 2 2 RX 1 4 7 RO NOR 2* 1* 1 1 1 I/C 2,4,6, 1,3,7 7 T 1 7

MAJ 7 6,8 7 T T T TS 0022 RX 1 4 2T10 BOP NOR 1 1 1 I/C 3,5,6, 2,5,7 7 4 4 2 7

MAJ 7 6,8 T T T TS 0022 Instructions:

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

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

6. 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.

NUREG-1 021, Revision 9 Supplement 1 Page 2 of 2 Farley Facsimile Rev. 0

ES-301-6 Competencies Checklist FINAL SUBMITTAL Facility: Farley Nuclear Plant Date of Examination: May 9, 2011 Operating Test No.: FA2O1 1-30 1 APPLICANTS Competencies SRO-I X RO X BOP X SCENARIO SCENARIO 1234 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 2 3 2 3 1 2 1 2 2 5 45 1 2 1 2 3 46 23 24 3 4 andConditions 45 45 34 34 67 67 36 36 7 67 56 56 67 67 56 56 78 7 78 7 78 7 9 9 9

ComplyWithand 12 12 12 12 12 14 12 12 134 12 24 34 UseProcedures(1) 3434343456 56 36 36 67 36 56 56 56 56 56 56 7 7 78 7 7 78 7 7 7 78 7 9 9 9

Operate Control 1 2 1 4 1 2 1 2 1 3 4 1 2 24 3 4 Boards(2) 56 56 37 36 67 36 57 56 7 7 89 7 7 89 7 Communicate 12 12 12 12 12 14 12 12 134 12 24 34 andlnteract 34 34 34 34 56 56 36 36 67 36 56 56 56 56 56 56 7 7 78 7 7 78 7 7 7 78 7 9 9 9

Demonstrate Supervisory 2 3 2 3 1 2 1 2 Ability (3) 4 5 4 5 3 4 3 4 67 67 56 56 78 7 9

Comply With and 23 34 24 24 Use Tech. Specs. (3) 5 Notes: (1) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

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

ES-301-6 Competencies Checklist RNAL SUBMTTAL Facility: Farley Nuclear Plant Date of Examination: May 9, 2011 Operating Test No.: FA2O1 1-301 APPLICANTS Competencies SRO-I X RO X BOP X SCENARIO SCENARIO 67 6 7 6 7 Interpret/Diagnose Events 23 1 2 24 1 3 35 25 and Conditions 45 34 67 46 67 78 67 56 78 78 Comply With and 1 2 1 2 1 2 1 3 1 3 24 Use Procedures (1) 34 34 46 67 56 56 5656 7 8 7 78 7 78 Operate Control 12 1 3 1 3 24 Boards (2) 46 45 56 56 7 67 7 78 8

Communicate 1 2 1 2 1 2 1 3 1 3 24 and Interact 34 34 46 45 56 56 5656 7 67 7 78 7 78 8 Demonstrate Supervisory 1 2 1 2 Ability (3) 34 34 56 56 7 78 Comply With and 2 4 12 Use Tech. Specs. (3) 5 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 competencyfor every applicant.

ES-401 PWR Examination Outline Form ES-401-2 Facility: FARLEY Date of Exam: MAY 2011 SRO-Only_Points Tier Group KK KKKKAAAAG 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 .L .2__ N/A 1 2 N/A 1 9 2 2 4 Evohjons Tier Totals 4 5 5 4 5 4 27 5 5 10 1 22332232333 28 3 2 5 2.

Plant 2 1111111 111 0 10 0 2 1 3 Systems Tier Totals 3 3 4 4 3 3 4 3 4 4 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 .2 2 2 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).

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

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/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 (lR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select 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 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.

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

nO SRO 009EA2.01 Small Break LOCA /3 4.2 4.8 Actions to be taken, based on RCS temperature and pressure, saturated and superheated 011 EK2.02 Large Break LOCA / 3 2.6 2.7 []r Pumps 01 5AK1 .04 RCP Malfunctions /4 2.9 3.1 [] [] [] (] [ Basic steady state thermodynamic relationship between RCS loops and SIGs resulting from unbalanced RCS flow 025AK1 .01 Loss of RHR System /4 3.9 El El El El El El El El El El Loss of RHRS during all modes of operation 026AA1 .06 Loss of Component Cooling Water! 8 2.9 2.9 El El El [] El El Control of flow rates to components cooled by the CCWS 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 El El El El El El El El El El Controllers and positioners Malfunction / 3 029EK3. 12 ATWS! 1 4.4 4.7 [ [ [] [] Actions contained in EOP for ATWS 038EG2.4.1 Steam Gen. Tube Rupture / 3 4.6 4.8 El El El El El El El El El El Knowledge of EOP entry conditions and immediate action steps.

055 EA2.06 Station Blackout! 6 3.7 4.1 El El El El El El El El El El Faults and lockouts that must be cleared prior to re energizing buses

/;L 056AG2.2.2 Loss of Off-site Power! 6 4.0 4.7 El El El El El El El El El El Knowledge of limiting conditions for operations and safety limits.

057AA1 .04 Loss of Vital AC Inst. Bus / 6 3.5 3.6 El El El El El El El El El El RWST and VCT valves Page 1 of 2 9/15/2010 1:09PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 058AK3.01 Loss of DC Power! 6 3.4 3.7 Use of dc control power by DIGs 062AA2.01 Loss of Nuclear Svc Water / 4 2.9 3.5 Location of a leak in the SWS 065AK3.08 Loss of Instrument Air! 8 3.7 3.9 Actions contained in EOP for loss of instrument air 077AG2.4.45 Generator Voltage and Electric Grid 4.1 4.3 Ability to prioritize and interpret the significance of each Disturbances! 6 annunciator or alarm.

WEO4EK2.l LOCA Outside Containment! 3 3.5 3.9 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE05EK1 .3 Inadequate Heat Transfer Loss of 3.9 4.1 Annunciators and conditions indicating signals, and Secondary Heat Sink! 4 remedial actions associated with the (Loss of Secondary Heat Sink).

WE1 1 EA1 .3 Loss of Emergency Coolant Recirc. / 4 3.7 4.2 Desired operating results during abnormal and emergency situations.

Page 2 of 2 9!15!2010 1:09PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO OO1AA1 .03 Continuous Rod Withdrawal /1 3.4 3.2 Boric acid pump control switch 036AK3.02 Fuel Handling Accident / 8 2.9 3.6 Interlocks associated with fuel handling equipment 037AK1 .01 Steam Generator Tube Leak! 3 2.9 3.3 Use of steam tables 051 AA2.02 Loss of Condenser Vacuum / 4 3.9 4.1 Conditions requiring reactor and/or turbine trip 068AA2.04 Control Room Evac. /8 DELI S/Gpressure 076AK2.0l High Reactor Coolant Activity! 9 2.6 3 LI Process radiation monitors WEO3EK2. 1 LOCA Cooldown Depress. /4

- 3.6 4.0 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEO8EK3.2 RCS Overcooling - PTS /4 3.6 4.0 LI LI LI LI LI LI LI LI LI LI Normal, abnormal and emergency operating procedures associated with (Pressurized Thermal Shock).

wel 5EG2.4.2 Containment Flooding /5 4.5 4.6 LI LI LI LI LI LI LI LI LI LI Knowledge of system set pojnts, interlocks and automatic actions associated with entry conditions.

Page 1 of 1 9/15/2010 1:09PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K6.14 Reactor Coolant Pump 2.6 2.9 Starting requirements 004A3.l 1 Chemical and Volume Control 3.6 3.4 Charging/letdown 004K3.04 Chemical and Volume Control 3.7 3.9 RCPS 005K5.05 Residual Heat Removal 2.7 3.1 Plant response during solid plant: pressure change due to the relative incompressibility of water 006K2.01 Emergency Core Cooling 3.6 3.9 ECCS pumps 007A4.1O Pressurizer Relief/Quench Tank 3.6 3.8 Recognition of leaking POR V/code safety 008A2.O Component Cooling Water 2.5 2.8 Consequences of high or low CCW flow rate and tempera- ture; the flow rate at which the CCW standby pump will start 01 OK1 .06 Pressurizer Pressure Control 2.9 3.1 LI CVCS 012A3.05 Reactor Protection 3.6 3.7 LI LI LI LI LI LI LI LI LI LI Single and multiple channel trip indicators 013K5.02 Engineered Safety Features Actuation 2.9 3.3 LI LI LI LI LI LI LI LI LI LI Safety system logic and reliability 022A1 .02 Containment Cooling 3.6 3.8 LI LI LI LI LI LI LI LI LI LI Containment pressure Page 1 of3 9/15/2010 1:09PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

AC SAC 022A3.01 Containment Cooling 4.1 4.3 Initiation of safeguards mode of operation 026G2.4.50 Containment Spray 4.2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

026K4.0l Containment Spray 4.2 4.3 Source of water for CSS, including recirculation phase after LCCA 03902.1.20 Main and Reheat Steam 4.6 4.6 j Ability to execute procedure steps.

059A2.12 Main Feedwater 3.1 3.4 Failure of feedwater regulating valves 059K1 .02 Main Feedwater 3.4 3.4 AFW system 6

061 K4.3 Auxiliary/Emergency Feedwater 2.6 2.9 El El Reset of MFW reactor trip logic 061 K6.01 Auxiliary/Emergency Feedwater 2.5 2.8 El El El El El El El El El El Controllers and positioners 062K3.03 AC Electrical Distribution 3.7 3.9 El El El El El El El El El El DC system 063A1 .01 DC Electrical Distribution 2.5 3.3 El El El El El El El El El El Battery capacity as it is affected by discharge rate 063K3.02 DC Electrical Distribution 3.5 3.7 El El El El El El El El El El Components using DC control power Page 2 of 3 9/15/2010 1:09 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064A1 .04 Emergency Diesel Generator 2.8 2.9 Crankcase temperature and pressure 073A4.02 Process Radiation Monitoring 3.7 L1LL1 Radiation monitoring system control panel 076A4.02 Service Water 2.6 2.6 SWS valves 08 076K24 Service Water 2.5 2.6 Reactor building closed cooling water 078G2.l .32 Instrument Air 3.8 4.0 Ability to explain and apply all system limits and precautions.

1 03K4.04 Containment 2.5 3.2 Personnel access hatch and emergency access hatch Page 3 of 3 9/15/2010 1:09PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

d- RO SRO 001 K6.Q Control Rod Drive 2.9 3.2 Purpose and position switch of alarm for high flux at shutdown 01 1A4.0l Pressurizer Level Control 3.5 3.2 El Charging pump and flow controls 015K5.l0 Nuclear Instrumentation 2.8 3.0 LI j Ex-core detector operation 028K2.01 Hydrogen Recombiner and Purge 2.5 2.8 Hydrogen recombiners Control 041 A3.03 Steam Dump/Turbine Bypass Control 2.7 2.8 Steam flow 045A1 .06 Main Turbine Generator 3.3 3.7 [ Expected response of secondary plant parameters following T/G trip 055K1 .06 Condenser Air Removal 2.6 2.6 LI LI LI L] LI LI [] LI [] LI PRM system 056A2.04 Condensate 2.6 2.8 LI LI LI LI LI [] E] [] LI LI Loss of condensate pumps 072K4.01 Area Radiation Monitoring 3.3 3.6 LI LI LI LI LI LI LI LI LI LI Containment ventilation isolation 075K3.07 Circulating Water 3.4 3.5 LI LI j LI LI LI LI LI LI LI LI ESFAS Page 1 of 1 9/15/2010 1:09 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401 -2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .25 Conduct of operations 3.9 El El El El El El El El El El 42 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

G2.l .34 Conduct of operations 2.7 El El El El El El El El El El 35 Knowledge of primary and secondary chemistry limits G2.2.13 Equipment Control 4.1 El El El El El El El El El El 43 Knowledge of tagging and clearance procedures.

G2.2.39 Equipment Control 3.9 El El El El El El El El El El 5

4 Knowledge of less than one hour technical specification action statements for systems.

G2.3.13 Radiation Control 3.4 El El El El El El El El El El 38 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 El El El El El El El El El El 38 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 El El El El El El El El El Knowledge of radiation exposure limits under normal and emergency conditions G2.4.23 Emergency Procedures/Plans 3.4 4AEl El El El El El El El El El Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

G2.4.25 Emergency Procedures/Plans 3.3 El El El El El El El El El El 37 Knowledge of fire protection procedures.

G2.4.46 Emergency Procedures/Plans 4.2 El El El El El El El El El El 42 Ability to verify that the alarms are consistent with the plant conditions.

Page 1 of 1 9/15/2010 1:09PM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 008AG2.4.41 Pressurizer Vapor Space Accident! 3 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.

054AG2.1 .23 Loss of Main Feedwater / 4 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

055EA2.Q2 Station Blackout /6 3.9 4.7 Actions necessary to restore power 058AG2.2.25 Loss of DC Power! 6 3.2 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

077AA2.1O Generator Voltage and Electric Grid 3.6 3.8 Generator overheating and required actions Disturbances / 6 WEO5EA2.1 Inadequate Heat Transfer Loss of

- 3.4 4.4 1EiL1 Facility conditions and selection of appropriate Secondary Heat Sink! 4 procedures during abnormal and emergency operations.

Page 1 of 1 9!15!2010 1:09PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO 4, 001 AA2.Q Continuous Rod Withdrawal! 1 4.4 4.6 Uncontrolled rod withdrawal from available indications j ARM System Alarms! 7 061 AA2.G 3.2 4.1 Required actions if alarm channel is out of service 9

069AG2.2t Loss of CTMT Integrity! 5 3.8 3.9 Lj (multi-unit license) Knowledge of the design, procedural and operational differences between units.

074EG2.4.20 mad. Core Cooling! 4 3.8 4.3 Ej Knowledge of operational implications of EOP warnings, cautions and notes.

Page 1 of 10!6!2010 10:11 AM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 006G2.4.9 Emergency Core Cooling 3.8 4.2 Knowledge of low power! shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

01 2A2.05 Reactor Protection 3.1 3.2 Faulty or erratic operation of detectors and function generators 039A2.0 Main and Reheat Steam 4 2.7 Decrease in turbine load as it relates to steam escaping from relief valves 62?

078A2.01 Instrument Air 2.4 2.9 Air dryer and filter malfunctions 36 103G2.1 20 Containment 4.0 L1L1L Ability to locate and operate components, including local controls.

Page 1 of 1 9/15/2010 1:09PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028A2.@1 Hydrogen Recombiner and Purge 3.4 3.6 Hydrogen recombiner power setting, determined by using Control plant data book 035A2.Ol Steam Generator 4.5 4.6 Faulted or ruptured S/Gs 071 G2.2.38 Waste Gas Disposal 3.6 4.5 Knowledge of conditions and limitations in the facility license.

Page 1 of 1 9/15/2010 1:09PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .35 Conduct of operations 2.2 Knowledge of the fuel handling responsibilities of SROs G2.2.12 Equipment Control 3.7 4.1 Knowledge of surveillance procedures.

G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance activities during shutdown operations.

G2.3.12 Radiation Control 3.2 DDL1L1 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.

G2.4.44 Emergency Procedures/Plans 2.4 Knowledge of emergency plan protective action recommendations.

Page 1 of 1 9/15/2010 1:09PM

ES-401 -4 Record of Rejected K/As Page 1 of 3 FINAL SUBMITTAL K/A listed in column 2 is the rejected K/A Tier! Randomly Selected Reason for Rejection Group K/A TxGx ORIGINAL KA Reason for replacement SRO/RO Examiner (NRC) randomly selected new KA# as the replacement K/A.

Ti/Gi 056AG2.2.22 . .

The onginal K/A required knowledge of LCOs and safety limits RO related to a Loss of Offsite Power, written at an RO level. In depth knowledge of Tech Specs, and in particular Tech Specs related to a Loss of Offsite Power, is an SRO function.

Examiner randomly selected K/A 056G2.2. 12 as the replacement K/A.

Approved by Ron Aiello 10/18/2010.

T2/G1 008A2.07 . .

The onginal K/A was related to the flow rate at which the CCW RO standby pump will start. FNP is not equipped with an autostart of CCW pumps from a flow rate.

Examiner provided K/A 008A2.05 as the replacement K/A.

Approved by Ron Aiello 10/18/2010.

T2/Gl 061K4.l0 . .

The onginal K/A was related to Reset of MFW reactor trip RO logic. FNP is not equipped with a Reactor trip signal generated directly by a trip of MFW, thus there are no resets associated.

Examiner provided K/A 061K4.06 as the replacement K/A.

Approved by Ron Aiello 10/18/2010.

T2/G1 076K2.04 The onginal K/A was related to Reactor Building closed cooling RO water. FNP is not equipped with a Reactor Building closed cooling water system.

Examiner provided K/A 076K2.08 as the replacement K/A.

Approved by Ron Aiello 10/18/2010.

ES-401-4 Record of Rejected K/As Page 2 of 3 ANAL SUMtTTAL.

Tier / Randomly Selected Reason for Rejection Group KJA T2/G2 001K6.08 The original K/A was related to positioning the high flux at shutdown alarm switch as a sub component of the Control Rod RO Drive system. FNP has no direct interrelationship between the high flux at shutdown alarm and the Control Rod Drive system.

Examiner provided K/A 001K6.02 as the replacement K/A.

Approved by Ron Aiello 10/18/20 10.

T1G1 055EA2.03 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A 055EA2.02 as the replacement K/A.

Approved by Ron Aiello 10/18/20 10.

T1G2 OO1AA2.05 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A OO1AA2.03 as the replacement K/A. Approved by Ron Aiello 10/18/20 10.

T1G2 061AA2.06 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A 061AA2.05 as the replacement K/A. Approved by Ron Aiello 10/18/2010.

T1G2 069AG2.2.3 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A 069AG2.2.7 as the replacement K/A. Approved by Ron Aiello 10/18/20 10.

T2G1 039A2.02 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A 039A2.05 as the replacement K/A. Approved by Ron Aiello 10/18/2010.

T2G1 078A2.01 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A 079A2.01 as the replacement K/A. Approved by Ron Aiello 10/18/2010.

ES-401-4 Record of Rejected K/As Page 3 of 3 FINAL SUBMITTAL Tier / Randomly Selected Reason for Rejection Group K/A T2G1 103G2. 130 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A I 03G2. 1.30 as the replacement K/A. Approved by Ron Aiello 10/18/20 10.

T2G2 028A2.01 Unable to write an SRO level question to this KA.

SRO Examiner randomly selected K/A 028A2.02 as the replacement K/A. Approved by Ron Aiello 10/18/2010.

T1G2 061AA2.05 Unable to write to an SRO level without oversampling SRO Emergency Classification procedures.

NOTE: Second REPLACEMENT of this KA ( see 10/18/2010 above)

Examiner randomly selected K/A 061 AA2.04 as the replacement K/A. Approved by Ron Aiello 1/27/2011.

ES-401-6 Written Examination Quality Checklist r,,L_

Facility: FA2O1 1 -301 Date of Exam: May 9, 2011 Exam Level: RO x SRO x Initial Item Description a b* c#

1. Questions and answers are technically accurate and applicable to the facility. 2 ,tk

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

b. Facility learning objectives are referenced as available.

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

4. The sampling process was random and systematic (If more than 4 RD or 2 SRO questions ,

were repeated from the last 2 NRC licensing exams, consult the NRR OL program office).

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

the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed independently; or the licensee certifies that there is no duplication; or other (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest ._

new or modified); enter the actual RD / S RD-only 22 / 1 16/ 5 37 / 19 question_distribution(s)_at_right.

7. Between 50 and 60 percent of the questions on the RD Memory C/A exam are written at the comprehension! analysis level; the SRO exam may exceed 60 percent if the randomly (2 31 /7 44 / 18 selected K/As support the higher cognitive levels; enter the actual RD / SRO question distribution(s) at right.

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

9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; 1-deviations are justified.

10. Question psychometric quality and format meet the guidelines in ES Appendix B. 2 .8 \

11. The exam contains the required number of one-point, multiple choice items; ,k.O \

the total is correct and agrees with the value on the cover sheet.

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor Note: The facility reviewers initials/signature are not applicable for NRC-developed examinations.

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

ES-401 Written Examination Form ES-401-9 Review Worksheet Farley 2011-301

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD I (CIA) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus . Link units ward K/A Only Dist.

Instructions

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

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

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

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

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

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

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

One or more distractors is not credible.

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

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

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

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

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

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

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

5. Based on the reviewers judgment, is the question as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

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

RO/SRO Combined Question Generic:

NP Not Plausible DV Discriminatory Value DLU = Direct Lookup VOOTF = Which one of the following FITB = Fill in the blank

0

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/LOKLOD (C/A) (1-5) Stem Cues TIF Cred Partial Job- Minutia #1 Back- Q= SRO U/E/S Explanation Focus . Link units ward K/A Only Dist.

M U01J\1.03 2 Y N S Nocomment RFA 03/03/11 Deleted the word correctly from the question stem.

RFA 4/512011 2

003K6.14 M 2 Y N S Nocomment RFA 03/03/11 M

003K6.14 2 Y N s Nocomment RFA 03/03/11 Re-arranged the WOOTF statement.

RFA 4/5/2011 UU4/\i.1 1 C 4. Y N Because the stem states the actual values for seal leak off and seal injection, the Q has no DV 3 - in the stem that Seal nj and leak off are normal.

Q is U because too much information is provided in m thus yielding no DV.

A 03/03/11 moved extraneous information from stem and dded SI and Seal leakoff are normal.

T0 318/11 ccepted resolution 4/5/2011 ralidators identified that Seal injection could be iithin NORMAL range of 6-13 gpm. IF assumed C could be correct, and

. seal injection parameter.

is between 6-9 gpm which bounds the answer to J.Y choice A.

Added the following bullets:

- Seal injection is in the green band.

- RCP #1 Seal leak off flow is normal.

Accepted resolution RFA 4/1 3I201 I U4K3.04 I think a typo in the stem OUnit 1 should be Unit 1 Distractor B is NP. Normal leakage under normal circumstances ever go to the sumps other than some relief valves but only if something went wrong. Either change out B or put something in the stem to give it

C__ 0

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOKLOD (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- 0 SRO UIE/S Explanation Focus . Link units ward K/A Only Dist.

= credibility.

RFA 03/03/11 Fixed typo unit I B is a plausible distracter blc the #3 RCP seal drains to the ctmt sump normally 1000 cclhr and there are at least 2 relief valves that discharge straight to the ctmt sump from the PRT and RCDT, as well as some CCW and SW reliefs. Also when the SI occurs, normal seal return is isolated which causes a relief valves to lift. One relief valve discharge flow path is to the ctmt sum ps.

Fixed feedback for the B distracter GTO 318111 Accepted resolution RFA 4I5!201 I 005K5.05 6 nd 2

M 2 X Y N bullet: RHR is in service not on service.

No matter where PH-145 is, if there is a clog nothing with respect to the location of PK-145 will solve the problem. Distractor B is NP RFA 03/03/11 Changed on to in service.

Changed distracter B to rise until the RHR inlet isolation valves go closed (MOVs 8701A1B and 8702AIB) These MOVs have a closing signal of 700 psig. A common misconception would be that these MOVs close prior to the relief valve lifting.

GTO 3I8I1 I Changed distracter B to rise until the RHR loop suction isolation valves go closed RFA 4i51201 I 006K2.01 M

2 Y N s Nocomment RFA 03/03/11 007A4.I0 8

C 2 X Y N i Change C2 and D2 to 120 psig. 150 psig is too extreme.

in the stem, state that Pzr vapor space temperature is S 650 degrees F. This will make B1 and Cl a little more plausible.

This Q is U because of more than I NP distractor.

. q:i RFA 03/03/11

fl

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#I LOK LOD (CIA) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- Q= U/EIS Explanation Focus Link units ward K/A Only Dist.

I did not add pzr vapor space is 650 °F to the stem bic that is teaching in the stem. At 100% power,

- IF is the normal temp in the pzr and we are not Isupposed to add this type of info to the stem.

II do not agree with the Unsat for this question since value we used (150 psici) has been used on other exams and is a reasonable value for a relief.

efs in ctmt lift at 25. 75. 150. 180, 220, 300, 600 L

- J3I8111 Thanged distracter C and D setpoints to 75 psig.

FA 41512011 9

C 3 Y N Is. No comment RFA 03/03/11 009EA2.01 10 C 3 X Y N No comment RFA 03/03/11 Added per the applicable FRP to the stem.

RFA 41512011 S

010K106 C 3 Y N S No comment RFA 03/03/11 011A4.01 12 C 3 X Y N 1 Given the initial conditions, a small RCS break will NOT cause VCT level to rise, and if FCV-122 failed open Pzr level would NOT fall. Therefore distractors A and B are S NP.

s Q is U because of 2 NP distractors.

03/03/11 I distracters A and B and changed ack. GTO 3I9I1 I cepted resolution

415I201 I 11EK2.02 13 C 2 X Y N Securing RCPs will NOT lower peak clad Temps. This distractor is NP.

RFA 03/03/11 s Replaced distracter and REORDERED based on length. NEW correct answer is B and replaced

0 0

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Cther 6. 7.

Q#I LOK LCD (CIA) (1-5) Stem Cues TIE Cred Partial Job- Minutia #1 Back- Q= SRC UIEIS Explanation Focus Link units ward K/A Cnly Dist.

=

= distracter is now D. GTO 319111 Accepted resolution RFA 4I5I201 I 14 1U12A3.05 M 2 X Y N U I 22. outHowever, of 2 is NP. Nothing in reactor trip logic is 2 out of there is 2 out of 3.

This Q is U because distractors BI and Dl are NP RFA 03/03/11 I did not change anything for the following reasons:

1. The KA asks for single and multiple trip indicators which is what the question asks

1. There 9*Q_

require

- - clearona

. Also P-6 clears on 2I2.

Using a 2!3 for the IR channels is not plausible e there are only 2 channels and moving to a 213 ogic moves away from the KA for single trip ndicators.

) 318111 le-reviewed distracter analysis and determined that 2 out of 2 coincidence is plausible. Accepted

- ,n as submitted. Question is ry as submitted.

4I5I201 I 013K5.02 15 C 2 X Y N U Psychometrics: If D was correct, A and C would be correct also. If C was correct, A would be correct also.

Therefore B is the only plausible choice.

S This Q is U due to psychometric flaws.

RFA 03/03/11 Added ONLY to the distracters A, B and D GTO 3i8I11 Accepted resolution RFA 4!5i201 I 015/O17AK1.04 16 C 3 Y N S No comment RFA 03/03/11 015K5.10 17 C 3 Y N S No comment RFA 03/03/11

1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#l LOKLOD (C/A) (1-5) Stem Cues TIF Cred Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus . Link units ward K/A Only Dist.

022A1.02 18 C 2 X Y N g The word may is an act of permission. Change may to will.

RFA 03/03/1 1 s Added WILL to A and B distracters per above GTO 318111 Accepted resolution RFA 41512011 022A3.01 19 M 2 X Y N 1 Al and Bi: There is no significance to containment pressure reaching 4 psig in this situation or at least it was not explained in the reference material. Therefore, E distractors Al and Bl are NP.

This Q is U because Al and Bl are NP.

S RFA 03/03/11 Added more information to feedback to explain why a candidate would pick ctmt pressure vs.

temperature.

The significance to ctmt pressure is this is when the SI signal actuates and this causes fans to either start or shift to SS, the SW MOVs to roll open and the ctmt cooler dampers will open when the fans start. The drop out plate is a different issue and does not open on the SI signal at 4psig but rather opens when temp increases to 135F when the fusible link melts.

Changed stem to take away the SI signal and added ctmt pressure is 15 psig and rising.

Changed this to Bank question in source category area.

GTO 3I8I1 I Plausibility of 4 psig is accepted due to the actuation of SI at 4 psig. Modified stem bullet and all four choices to say exceeds instead of reaches. New version of the question has better testability.

Downgraded question to E versus U.

RFA 4I5I201 I U25AKI.Ol 20 C 3 Y N S No comment RFA 03/03/11 U26AAI.06 21 C 3 Y N S No comment RFA 03/03/Il 026G2.4.50

fl

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#I LOK LCD (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #I Back- U/E/S Explanation Focus Link units ward K/A lOnly Dist.

j Y N o comment. However; note, I would have declared stractors Cl and Dl NP had the validation matrix

- ri provided. It is not clear to me why half the tators would choose 126 for RWST b-b after o of the distractors had 4S.

FA 03/03/11 23 )26K401 M 2 x Y N ontainment screens are pretty much common in ALL WRs. Because of this, distractors A, C, and D are NP.

This Q is U because of 3 NP distractors.

FA 03/03/11 ilaced question with question from FNPs 2010

.C exam. Within allowance of NUREG 1021, 401-6 irm (<4 RO, <6 totalcurrent count is I RO)

TO 319I11

- resolution A 41512011 Iis.us 24 C 3 Y N S No comment RFA 03/03/11 028K2.01 25 M 2 Y N S No comment RFA 03/03/11 utitr,3. 12 26 M Y N U Inadequate information is provided in the stem to validate the plausibility of distractors A, C, and D. None of the distractors except C have anything to do with 2 S reactivity control and that is what the question is all o is U due to low DV.

PA 03/04/11 ceplaced question to a new one that is a 2+2 type nd includes the action as well as the reason.

- )3!8I11 Accepted new question. Added 2 nd bullet stating SG pressures are 1035 psig to increase plausibility to rsB2andD2.

- 41512011 27 C 2 I suggest emphasizing raised/lowered, up/down, wtc.

RFA 03/04/11 S Bolded raisedllowered, up!down per comments above

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/LOKLOD (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus . Link units ward K/A Only Dist.

GTO 3I8I11 Accepted resolution RFA 41512011 28 J37AK1.91 C 2 X Y N E Where ever references are provided, use a generic phrase Reference Provided then just say WOOTF S RFA 03/04/11 Added reference provided per above suggestion GTO 3I8I11 Accepted resolution RFA 4/512011 29 uisizc.4. I C 2 x Y N I disagree with your distractor analysis. Under the circumstances, I dont believe that the applicant will choose distractor B. Consider replacing B.

RFA 03/04/11

- have seen students pick EEP-0 on exams as the iroper place to transition when another SI or ituation requiring an SI is encountered. However, B racter has been changed and a su gested fix is 9

n. ECP-3.1 is the suggested fix since there is a 4

with a SB LOCA and this is transition criteria from EEP-3.0.

GTO 3/8/11 Accept original question 4/5I2011

.1.2O 30 2 mmon sense that opening the steam dumps y exacerbate the probFem of high DP.

ors Al and B1 are NP.

Q is U because of two NP distractors.

03/04/11 I the first distracter to a more plausible r.

GTO3/1 6/11 Accepted new question.

RFA4I5/2011 iu4lA3.03 No comment RFA 03/04/11 U45A1 .06

\ ) flI

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

LOK Luu (C/A) (1-5) Stem Cues TIE Cred Partial Job- Minutia #1 Back- Q= SRO U/E/S Explanation Focus . Link units ward K/A Only Dist.

32 C 3 Y N I

IL FA 03/04/11 33 iiv.u C 3 X Y N S No comment RFA 03/04/11 Deleted from distracter D as non applicable information Continue to investigate the cause of S the loss of vacuum.

RFA 41512011 055EA2.06 M 2 X Y N Why dont you just say at 10:15, the 1-2A DG has been made available and delete al that 10:15 fru fru stuff?

s RFA 03/04/11 Removed the fru fru stuff and added the procedure title to the #2 fitb GTO 319I1 I Accepted resolution RFA 4I5I201 I 055K1.06 M 2 Y N S No comment RFA 03/04/11

, J Added the word system to the stem.

I RFA4I512011 4

UOR2.0 36 C 2 X Y N Trjpping the reactor for a single condensate pump trip is NP. A2 and C2 are NP. Replace A2 and C2.

S This Q is U because of 2 NP distractors.

RFA 03/04/11 T uestions available to change this one j j, but we believe that the current on is plausible as is and we changed the eedback to provide a better justification as to why it is plausible.

GTO 311611 I Editorial changes to modify stem and choices to increase plausibility for tripping the reactor.

A4!5I11 comment J RFA 03/04/11 057AA1 .04

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

n Q#/ LOK Luu (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus . Link units ward K/A Only Dist.

C T Y S No comment RFA 03/04/11 E Changed from mod to bank GTO 3116111 Removed extra information from distracters B and C which also increased plausibility.

RFA415iII 058AK3.01 C 3 Y N 5 No comment RFA 03/04/1 1 E Modified distracters A.2 and C.2 to say ATS (Automatic Transfer Switch) instead of ABT (Automatic Bus Transfer) switch. This terminology S has changed and the previous terminology is incorrect.

GTO 311 6I1 I Accepted comment, question changed from S to E.

RFA 415I201 I 40 059A2.12 C 2 X Y N I I believe that Al and Bi will be more plausible if changed from open to as is.

This Q is E because validators did pick D in some

. instances.

. 03/04/1 1 Changed Al and BI to as is as requested GTO 3i9111 lAccept original question air operated valves either U open or closed, they dont fail as is.

- 41512011 41 j <1.02 C 2 X Y N Inadequate recirc flow is not plausible because it is based on lack of basic system knowledge.

i: C 2 to water hammer or and D2 to water is Q is U because of two NP distractors.

A 03/04/1 1 all distracters as requested and changed FITB to fit the new distracters.

0 319111 epted resolution FA 41512011

fl II)

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOL (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #I Back- Q= SRO U/E/S Explanation Focus . Link units ward K/A Only Dist.

42 061 K4.06 C 3 X Y N 6 Change Al to stop and remain stopped. Since A2 is wrong, this will be more plausible.

s RFA 03/04/11 Changed Al distracter as requested GTO 3!9I11 Accepted resolution RFA 4I5I201 I 061K6.0l C 3 X Y N 6 Distractor D doesnt make any sense. If the valve fails closed there will be no steam available not even for an auto start. I suggest changing to will NOT start until S (some logic ckt) is made up.

D is NP because it is confusing.

RFA 03/04/1 1 Changed D distracter and removed confusing part.

Updated the feedback for the D Distracter to further clarify why this is a plausible distracter since the TDAFWP is INOPERABLE when one stm supply line is closed.

GTO 3I9111 Accepted resolution RFA 4i5I201 I Ub2AA2.U1 C 3 X Y N E What is in the stem to indicate a degraded head?

Facility re-verify the plausibility of distractor C.

s RFA 03/04/11 A severely degraded SW pump could cause pressure in a train to drop below 60 psig which would give AD4 annunciator. Since AF4 has a low range and high rane flow (DP) it is plausible that a candidate would mistakenly select this as a correct answer.

I have an alternate proposal to this distracter if necessary.

GTO 3!9I11 Removed 20% from degraded head distracter C. Re ordered distracter A and C.

RFA 41512011 Add to the stem ... states the minimum time...

RFA 03/04/11 as requested

Th

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#I LOK LOD I

(CIA) (1-5) Stem Cues TIE Cred Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus . Link units ward K/A Only Dist.

S GTO 319111 Accepted resolution RFA 41512011 46 063A1.01 M 2 X Y N U B2 and D2 are NP because it is common knowledge that loads are minimized to prolong battery life. Change A2 and C2 to prolong battery life ONLY S Change B2 and D2 to prevent damae to DC

.,jnents AND prolong battery life 1

This Q is U due to two NP distractors RFA 03/04111 Added as requested Do not believe this is unsat as is since the ments are plausible.

3I10I11 d resolution 512011

M 2 Y N No comment RFA 03/04/11 064A1 .04 48 C 3 Y N S No comment RFA 03/04/11 Distractors A2 and C2: This is too vague. Replace with C 3 X Y N something more specific. Since there was a good split between B and 0, this 0 was rated as E.

RFA 03/04/11 S Made A2 and C2 more specific and put in CCW valves that would restore RCP support conditions and then changed Q#2 to ensure 2 answers were not correct GTO 3110111 Accepted resolution RFA415I2011 068AA2.04 50 M 2 X Y N g No comment RFA 03/04/11 Removed last two bulleted items in stem of question due to non applicability.

s RFA4I5I2011 072K4.01

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

D Q#/ LOK LOD (C/A) (1-5) Stem Cues TIE Cred Partial Job- Minutia #1 Back- Q SRO UIE/S Explanation Focus . Link units ward K/A Only Dist.

M Y IN I FA 03/04/11 (J1k4.UZ 52 C 3 X Y N Since the sample valve does not have a manual hand wheel, distractor A is NP. Replace A.

S RFA 03/05/11 Replaced the A distracter and re-arranged the distracters due to length. Added one bullet to the stem to make the new distracter plausible.

GTO 3I1 0111 Accepted resolution RFA 41512011 C

3 Y

N ri S

075K3.07 No comment RFA 03/05/11 076A4.02 M 2 X N J This Q is supposed to be Service water NOT circ water.

y The question would appear to be SW but the distractor analysis talks about circ water.

E Furthermore, I am not convinced that all the distractors are plausible. The defense states what the applicant s may think. My question is, does the system have any other automatic valves? If not then the distractors are NP.

This Q is U until the KA satisfaction and plausibility issue is resolved.

RFA 03/06/1 1 There are other SW valves that change position on various parameters, however the valves in this question were plausible.

Replaced this question with a new one for SW to TB MOVs, and what position they will be in for a certain event, one train LOSP followed by a SI. This is now a CIA question GTO3II 6111 Redefined KIA to be met after further discussion.

Question deemed E instead of U after clarification.

Changed to new question, and is now acceptable.

RFA 41512011 076AK2.01 M 2 X Y N No comment RFA 03/06/11 Moved the Gross Failed Fuel Detector out of the

r Q#/ LOK LCD

2. 3. Psychometric Flaws

4. Job Content Flaws C

5. Other

6. 7.

(C/A) (1-5) Stem Cues TIF Cred Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus . Link units ward KIA Only Dist.

WOOTF statement.

S RFA4I5I2011 56 076K2.08 M 2 Y N S No comment RFA 03/06/11 077AG2.4.45 C 3 X Y N E Stem: Restate to read as follows: WOOTF actions will be performed first? The way it is written is confusing.

s RFA 03/06/1 1 Rewritten to incorporate the above comments.

GTO 319I11 Accepted resolution RFA 41512011 Following final validation: Added the words that are Lit to the WOOTF statement.

Accepted resolution RFA 411312011 078G2.1.32 58 M 2 X Y N The question stem is confusing. State the initial conditions then come in with the WOOTF statement.

s RFA 03/06/11 Rewritten to incorporate the above comments.

GTO 3I10I11 Accepted resolution, and also made IA the NC that is on the MCB position due to recent changes in the plant to maintain IC selected to the sequencer.

Added IA NC in distracter C because as written, C could potentially be a correct answer per OPS.

RFA 4i5I201 I 103K4.04 M 2 Y N This question involves more than just memory because one has to go through the logic sequence in their mind first. This C should be C/A.

M S RFA 03/06/11

Would like to keep this a memory level since it is

.. lessentially remembering how the door works. There many ways to reach this same conclusion and then you are correct and it would be CA. Since this could be either or and we have 44 CA already we Nould like to leave as is.

iAccept original question

1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/LOKLOD (C/A) (1-5) Stem Cues TIE Cred Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus . Link units ward K/A Only Dist.

F ! hFA4I5I2011 60 G2.1.25 C 4 Y N S This is a good analytical question.

RFA 03/06/11 61 G2.1 .34 M 2 Y N This is a good Q. Due the complexity of the analysis, it should be C/A NOT M C s RFA 03/06/11 Changed to CA GTO 319111 Accepted resolution RFA 41512011 G2.2.13 62 M 2 X Y N By the nature of a danger tag, its importance would never supersede a danger tag. Distractor B is NP.

s RFA 03/06/11 Replaced one distracter GTO 3116111 Accepted resolution RFA 41512011 G2.3.39 G2.2.39 63 C 3 X Y N E Placing N-32 in the tripped condition with N-31 OOS is NP as an only action while SD because you would be left with no means to monitor power.

S DisNP.

RFA 03/06/11 This should be KA G2.2.39 per sample plan We do not believe the distracter is NP since 9ammametrics is available and we could use this instrument during refueling, so why not here as well?

Changed D distracter to be more plausible and corrected justification in feedback section.

GTO 3!16I11 Went back to original question and added 6 th bullet to perform a channel check on Gamma Metrics source range instrumentation.

RFA 4I5I201 I G2.3.13 M

2 X

Y N U To have a guard continuously posted in the area a stem bullet needs to be added to make B2 and C2 plausible or state that the guard would be posted in a

In

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

LOK LCD (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- U/E/S Explanation Focus Link units ward KIA lOnly Dist.

iiow or no close area to guard me door.

nt now, as is, B2 and C2 are NP and the Q is U f\03106/ll nged this question to remove the guard since us could be a correct answer in appeals and then changed distracters to be more plausible.

GTO 03115111 Accepted resolution after changes to distracters.

RFA 415I201 I 65 (2.3. 14 C 3 x Y N No comment RFA 03/06/11 Changed distracter A due to plausibility.

RFA 41512011 MOVED CRITICAL DATA to bottom of bulleted list so less likely to be overlooked.

Validators felt that CTMT pressure was hidden.

Accepted resolution RFA 4113111 66 02.3.4 M 2 X Y N E Stem: Delete the second following RFA 03/06/11 S Deleted the second following GTO 3I9i11 Accepted resolution RFA 41512011 67 G2.4.23 M 2 Y N S No comment RFA 03/06/11 68 G2.3.1 G2.4.25 M 2 X N I think the wrong KA package was submitted. This Q should be a fire control KA but a rad control KA was provided. Resubmit with the correct KA package, This Q is an E until corrected.

In A and B, move the and up and just make a full sentence out of it and CAP the and RFA 03/07/1 1 This should be KA G2.4.25 per the sample plan and our submitted package.

Fixed the fire control question addressed above as indicated.

j1

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus . Link units ward K/A Only Dist.

GTO 3110111 Accepted resolution RFA 41512011 Validators questioned what LOCALLY meant and some challenged that l&C might be capable of lifting leads in the cable spreading room or some local panel to perform this action.

Added on the Hot Shutdown Panels to the WOOTF statement Accepted resolution RFA 4I13I11 69 G2.4.46 C 3 Y N S No comment RFA 03/07/11 Changed expected to will in the stem.

RFA415I2011 70 vvioe range pressure ana i now increasing are INU I C 3 x Y N plausible for voiding in the RCS. Replace these distractors. I suggest making this a two part Q:

S I 2. AA

3. AB BA BB sQ is U because of two NP distractors 03/07/11 hanged this question to a 2+2 and asked which components, when operated, will cause a void and which instruments are used to determine when a ci exists.

) 03115111

- i resolution after changes to distracters.

A 41512011 bU4EK2. 1 tors A and B leak isolated are NOT credible in the initial conditions and are therefore NP.

Replace A and B.

RFA 03/07/11 hanged this question to a 2+2 and asked about

,hich components are isolated and which instruments are used to determine when the intersystem LOCA has been secured.

03I15I11

(Th ,

)

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#I LOK LCD Focus I

(C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

. Link units ward KIA Only Dist.

- lution after deleting terminologyto iocate the leak in the stem.

I RFA 41512011 72 .,,E05EKI.3 C 3 X Y N No comment RFA 03/07/11 Deleted two non applicable bullets.

RFA 41512011 S

E08EK3.2 C 3 X Y N U Distractors A and D are NP because the stem talks about pressurized thermal shock. Neither A nor D have anything to do with PTS.

S This Q is U because of two NP distractors.

RFA 03/07/11 Changed this question to a 2+2 and asked about which component is affected (SG vs. Rx vessel) and then if CDR restrictions arelare not required.

GTO 03115111 Accepted resolution after changes to part 2 of the distracters to 500 I 100°.

RFA 41512011 VVe1IEA1.3 M 2 Y N S No comment RFA 03/07/11 SWAPPED order of bullets such that the components are train orientated.

Accepted resolution RFA 411 3l1 I

0

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#I LOK LOD (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus . Link units ward KIA Only Dist.

WEI5EG2.4.2 C X Y N Make Containment sump level 7.5 feet and make B the correct choice. This will increase the level of difficulty.

3 The Q is E due to a minor change to correct.

S RFA 03/07/11 Changed sump level to 7.2 feet since from a memory level standpoint and appeal standpoint 7.6 and 7 and 1/2 can be argued to be the same.

Changed answer to B and changed wording on fill in the blank moved doesldoes not exist into each distracter.

GTO 3!10i11 Accepted resolution RFA 41512011 SRO ONLY 76 001AA2.03 rd 3

C 3 X bullet: restate as follows: A unsuccessful manual reactor trip was attempted with reactor power at 14%

Delete the 4 th bullet because this is teaching.

RFA 03/02/11 Changed as suggested above.

GTO 3118111 Accepted resolution RFA 41512011 Validators stated: This is an awkward way to discuss rod motion.

TECHNICALLY RODS STOP every time between steps (even while stepping in the outward direction. (step--

stop-- step--stop). ONE validator reported that since the stem told him that rods STOPPED he assumed he missed something and was searching for something that would cause motion beyond the temp mismatch.

IMMEDIATELY step in or STOP when placed in AUTO was unanimously suggested by 5 validators.

Deleted immediately stopped from the WOOTF statement.

Added immediately to choices A and C.

Added stopped to choices B and D.

Accepted resolution RFA4i13111

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#I LOK LOD I

(C/A) (1-5) Stem Cues TIE Cred Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus . Link units ward KJA Only Dist.

L3bG2.4.9 C 3 X Y Y E Can you delete the TS part in the stem? With the information in the bullets, the TS reference should not be needed. If it is needed, put it with the bullets and take it out S of the WOOTF statement because it is confusing.

RFA 03/02111 Removed TS reference from stem.

GTO 3118111 Accepted resolution RFA 41512011 78 008AG2.4.41 C 3 X Y Y i Since Pressure Boundary is 2 of the 4 options, why would identified be a plausible option especially since the drawing is provided? Can the drawing be eliminated thus E making the applicant visualize the system? Pressure Boundary may not be so obvious.

The Q is U because Al and Cl are NP.

s REA 03/02/11 Do not agree with NP distracters. Suggest this is an editorial for the reasons below:

Answer to QI: STEM provides information that satisfies MOST of RCS TS LEAKAGE definition in that it is:

leaking into Containment Atmosphere

. SPECIFICA LLY located.

Answer Q2: The drawing can be eliminated. The validators reported the stem was overly lengthy and preferred the dwg. This has been worked on and we will discuss this.

Recent OE:

Over the past year, FNP has had an issue regarding UNIDENTIFIED leakage on Both UNITS. The leak was on a check valve, not isolable, and on the flange between the bonnet and the cap. The leak was originally classified as Unidentified, then when it was discovered was classified as identified. The resultant discovery of its location has lead to many discussions and revealed a common misunderstanding of the definitions of RCS leakage: UNIDENTIFIED being qualified as IDENTIFIED when discovered, AND particularly the seal on a valve being IDENTIFIED vs. PRESSURE BOUNDARY leakage.

Changed the question to remove the picture and shortened the stem.

Q#I LOK LOD

2. 3. Psychometric Flaws 4. Job Content Flaws n5. Other 6. 7.

.0 (C/A) (1-5) Stem Cues TIF Cred Partial Job- Minutia #1 Back- Q= SRO UIEIS Explanation Focus Link units ward K/A Only Dist.

i.Ti 0 3118111 Picture was removed, downgraded to E. Added bullet with a description of the leak location in lieu of a picture RFA 41512011 012A2.05 C 3 Y Y S No comment RFA 03/02/11 80 028A2.02 C 3 X Y Y U When you plug Does NOT into blank #1, it makes no sense. If H2 does not exceed the limit why would it be a concern?

S Furthermore, the way the second part is written, how could H2 NOT be a concern?

. :sQisubecauseAl andBl are NP

A03,02/11 de the following correction.

TO previously submitted (DEC 13) idea.

iced with doesldoes NOT exceed lower limit. FSAR 6.2.5.3.1 and basis for Caution V. EEP-1.0.

TO 3118111 epted resolution 41512011 81 C 3 X X Y Y E Is EP-GLOI ,figurel provided? If not, is it expected that the applicant have it memorized. If it is provided, state in the Q that a reference is provided. Now, if the ref is S provided, does it become a DLU? The Q is an E until resolved.

RFA 03/02/11 Answer to QI: NO. The reference is NOT intended to be provided.

Answer to Q2: The applicant is not expected to memorize EP-GLOI, but is required to know the conditions that would be entry criteria to the emergency classifications. Based on the information provided, the applicant should be able to discern that ctmt is intact.

Changed NMP title to NMP-EP-11O-GLOI, FNP EALS -

ICs, Threshold Values And Basis, GTO 3l18I11 Accepted resolution RFA 41512011 82 C 3 Y Y No comment

fl fl

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#I LOK LCD (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #1 Back- Q= SRO U/E/S Explanation Focus . Link units ward KIA Only Dist.

RT-A 03/02/11 83 054G2.1.23 C 3 Y Y S No comment RFA 03/02/11 84 055EA2.02 C 3 X Y Y I recommend changing the up and down arrows to raising and Lowering. These are hard to see.

s RFA 03/02/11 Corrected as suggested above.

GTO 3I18I11 Accepted resolution RFA 41512011 85 058AG2.2.25 C 2 Y Y S No comment RFA 03/02/11 86 061AA2.04 M 2 Y Y I When would an alarm function not be required for TS operability? If there are no cases, distractors Al and Bl are NP.

S This Q is U unless an alarm function can be identified

\ 03/02/1 1 ility request reassessment of plausibility with the wing additional information:

13.3.4-1 lists 4 other sets of 2 Setpoint as NIA. R-29B, JOA,B,C, and D, and F - i and C. Functional with no alarm function.

TR 13.3.4 condition B requires HP to conduct irveillances every 24 hrs, AFTER the first 24 hrs of NON nctionality. This action statement is UNIQUE and ers the idea that the capability of MONITORING is of Ireater importance than WARNING.

e believe it is reasonablelplausible for a candidate to that the alarm feature is NOT required, as long as

, , DRING is capable.

0 3118111 ation acceptable, question stands as is.

ion is acceptable as is, SAT.

41512011 87 G2.2.

M 2 X Y Y Remove the is from the second fill in the blank. How did this get by all of the validators?

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LCD (CIA) (1-5) Stem Cues TIE Cred Partial Job- Minutia #1 Back- Q SRO UIE/S Explanation Focus . Link units ward K/A Only Dist.

Th-A 03/02/11 Corrected GTO 3I18I11 Accepted resolution RFA 41512011 88 071 G2.2.38 C 3 Y Y S No comment RFA 03/02/11 89 074EG2.4.20 C 3 Y Y S No comment RFA 03102/11 077AA2.10 90 C 3 Y Y S No comment RFA 03/02/11 91 Inst Air isolation at 55 lbs is a common number. This C 3 x x u renders Distractors Al and Bi NP.

This Q is U because of 2 NP distractors.

I recommend another parameter. Service air isolates at 80 psi. maybe the question could be massaged around that number.

S RFAO3/02111 Do not agree with NP distracter. Suggest editorial vs.

UNSAT or accepting as is for the reasons below:

1) There are four pressures at which automatic actions occur in the IA system, 80, 70, 55 and 45 psig. Any is just as plausible as any other.

2) The suggested (80 psig) pressure will NOT result in any of the conditions of the stem to occur.

3) Requires specific knowledge V903 setpoint.

4) The setpoint is listed in the same referenced procedures (ARPs and AOPs and SOPs) together.

Changed Al, BI, Cl, and Dl Changed the stem focus from the air pressure to the valves that close. Due to the valve name I believe this makes for a more plausible distracter and takes the focus from a pressure value to a valve number.

GTO3II 8111 Add the word setpoint to the first fill in the blank, to satisfy the nonplausibility issue. Question downgraded to E versus U.

n 2. 3. Psychometric Flaws 4. Job Content Flaws 0

5. Other 6. 7.

Q#/ LOK LOD (C/A) (1-5) Stem Cues T1F Cred Partial Job- Minutia #1 Back- Q= SRO U/E/S Explanation Focus Link units ward K/A Only Dist.

= = = = = =

= A -41512011 ARROWs were replaced with words for consistency in the stem.

Accepted resolution RFA 4113/11 92 103G2.1.36 M 2 Y Y S No comment RFA 03/02/1 1 G2.1.35

4. Y Y j This question has no DV. Make this a two part Question.

Additionally it is a memory level Question.

M 2 Suggest you format as follows:

WOOTF are the Fuel Handling Supervisor required to do?

a.AA b AB

c. BA

d. BB This Q is U because the DV it to low.

RFA 03/02/11 Generated a replacement question in the 2+2 format.

GTO 3118111 Accepted resolution FA 4/512011 32.2.12 M 2 X Y Y E Distractor A is NP. Immediate is too radical without having stated which surveillance was missed.

Suggest changing it to 24 hrs.

s This Q is E since one NP distractor.

RFA 03/02/1 1 Changed per request and added some verbiage to ensure the distracter is incorrect. WIO verbiage a strong case could be made as to 2 correct answers.

GTO3II 8111 Accepted resolution RFA 4I5I201 I G2.2.18 C 2 X Y Y Stem: Delete (in the form of a GREEN SHEET) from both parts. The Q can be answered with or without it.

s RFA 03/02/11 We need GREEN SHEET to remain as is since this defines the approval required. Without the narrow scope, one could say that some type of re-approval

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#l LOK LCD I (C/A) (1-5) Stem Cues T/F Cred Partial Job- Minutia #/ Back- Q SRO U/E/S Explanation Focus . Link units ward K/A Only Dist.

._____._._-1_____

always need to be obtained and is always the nservative way to do business. If this were true then distracter would be plausible.

TO 3118111 ecepted comments. This question becomes S versus

--- .4l5I20ll UL.i.1Z 96 C 3 X Y Y Suggest Al and Bl say may be left it its Suggest Cl and Dl say must be up righted from S Dist C and D: The term May not has no destination of final position. It just hangs and is NP.

k 0 is U until resolved.

i\

03/02/11

orrected as suggested above.

T0311 8l1 I ecepted resolution 4i5l201 I 97 M 2 X Y Y E DisNP Change C to read But as a minimum two...

s Change D to read But as a minimum two licensed operators are required.

This Q is E because of 1 NP distractor.

RFA 03/02/li Changed C as requested and changed D as requested.

GTO3II 8111 Accepted resolution after modification to C2 to add ONLY.

RFA 41512011

+.28 The 3ft bullet needs grooming. It is difficult to read. You dont head to mode 4. You are in it or you arent. You need to decide where you are, RFA 03/02/11 Corrected: Removed Mode reference altogether, not necessary part of question.

GTO3iI Bill Accepted resolution RFA4i512011

(

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LCD (C/A) (1-5) Stem Cues TIF Cred Partial Job- Minutia #i[Back Q= SRO U/E/S Explanation Focus Link units I ward KJA Only 01st.

M Y Y IL RFA 03/02/11 100 VV/EO5EA2.

C 3 X Y Y No comment RFA 03/02/11 E Removed SI from stem for clarification issues.

GTO3II 8!l1 s Accepted resolution RFA 41512011 17 14/3) Us 42 31/11) Es 41 30/11) Ss

ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Farley Date of Exam: May 24, 2011 Exam Level: ROISRO Initials a b c Item Description

1. Clean answer sheets copied before grading na mjr

2. Answer key changes and question deletions justified and rfa N/Ai mjr documented

3. Applicants scores checked for addition errors rfa N/A mjr (reviewers spot check> 25% of examinations)

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, na N/A mjr as_applicable,_+/-4%_on_the_SRO-only)_reviewed_in_detail

5. All other failing examinations checked to ensure that grades rfa N/At mjr are_justified

6. Performance on missed questions checked for training nfa N/A mjr deficiencies and wording problems; evaluate validity of questions_missed_by_half_or_more_of the_applicants Printed Name/Si nature Date

a. Grader/Reviewer

b. Facility Reviewer(*)

Mark J. Riches/

N/A 217 I 0

c. NRC Chief Examiner (*) Ronald F. Aiello/ (/2 X/jj

d. NRC Supervisor (*) Mark E. Franke 7///I

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

2

/ -7 LAST NAME FIRST NAME MI PLATEAU ID TEST FORM TEST VERSION I I I I I I I I I I II I I I I I I I I I I I Li Li aDaDaD aD aD aD aD aD aD aD aD aD aD aD aD aD aDaDc aD F aDaDaDc aD aD aD aD aD

@ aD aD aD aD CD CD CD CD CD CD aD aD aDaDaDaD aD QJCD GD CD CD GD aD ccc CD CD SOUTHERN COMPANY aDaDaDaDaDaDaDaDaDaDaDaDaD aDaDaDaDaDaDaDaDaDaDTaDaDaDaDaDaDaDaDaD CD CD aDaDaDaDaDaDaDaDJaDaDaD CD CD CD CD C- O. 2 PENCIL ONLY aDaDaDaDaDDaDaDaD aDaDaDaDaDaDaDaDaDaDaDaDaDaD *EXAMPLE:

aDaDaDaDaDaDczaDaDaDaDaDaDaD2DaD

ERASE COMPLETELY TO CHANGE (T) (F) (T) (F) (T) (F) (T) (F) 26.CD IacJ 5t CD f 2ØCD CD CD 27. .) (j) 52.CD CD CD*

3.CD SaD ( 28.5 CD CD CD 53.CD CD CD CD 78.CD 0 CD 45 CD CD (J 29CD CD CD 54(X) CD CD 79CD SaD CD 5CD CD 30CD CD CD 55CD CD CD£ 8OcAJ CD CD 6.5 CD CD CD 31JX) 5 56. CD CD 81.(CD CD CD S 7CD ( J 5 32CD ( 5 575 CD CD 82CD 5 CD CD 8.0 CD CD CD 33CD

CD 58.5 () () CD CD 83.5 CD 9.CD CD 5 CD 34. CD CD CD 59.5 CD CD CD CD CD 0 10.CD JCD 35.2X) CD aDS 60.CD CJ©. 85.CD *C )

11.5 CD 36.CD a CD CD 61.CD CD CD 86.aD (.)

CD 12.CD CD CD* 37.:CD CD 62.CD () *aD 87JCD aDSaD 13.CD 0 CD 38.X) )X) CD S 63.5 CD CD CD. 88.CD CD CD S 14.aD CD5 39.5 64. S2CD 89.5 ZaD CD 15.5 CD CD CD 4O.C.) CD

CD 65.2X) S CD CD 902 aD a CD 16.CD CD CD 41.*CD CD CD 66.CD

aDaD 91JCD aDaDS 17.CD 5 42.iX) 5 67.5 CD () CD 92.aD CD S CD 18CD CD 43CD 5 68 WaD CD 93CD CD SaD 19(X) CD CD

44(X) *CD 69CD CD CD 94CD CD CD 20() 5 CD CD 45(X) CD CD 70X) SaD CD 95* CD CD CD 21.J(X) CD 5 ( 46.5 CD CDi CD 71.() CD S CD 96.aD S CD CD 22()* CD CD 475 (. CD CD 721X) CD CD 97() CDCD 23.CD CD S 48.CD CD* CD 73.CD CDCD 98.0 CD CD CD 24.5 CD CD CD 49.CD CD 74.1) aDS CD 99C) CDCD S

ML111990551

Contents

Text

Title:

Description:

Title:

Description:

Title:

Description:

Title:

Description:

Title:

Description:

Title:

Description:

Description:

= = = = = =

Navigation menu

ML111990551

Text

Title:

Description:

Title:

Description:

Title:

Description:

Title:

Description:

Title:

Description:

Title:

Description:

Description:

= = = = = =

Navigation menu

Search