Text

Initial Exam 2011-301 Final Administrative Documents
	ML112310044
Person / Time
Site:	Hatch
Issue date:	08/18/2011
From:	; Division of Reactor Safety II
To:	; Southern Nuclear Operating Co
References
	50-321/11-301, 50-366/11-301
	Download: ML112310044 (53)
	v • d • e

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: HATCH 201 1-301 Date of Examination: 6/06/2011 Examinations Developed by: it / NRC (circle one)

Target Chief Date* Task Description (Reference) Examiners Initials

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

-120 2. NRC examiners and facility contact assigned (0.1 .d; C.2.e)

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

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

[-90] [5. Reference material due (0.1 .e; C.3.c; Attachment 2)]

-75 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-is, 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 licensee (C.2.h; C.3.e)

-45 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference materials due (0.1 .e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (0.1.1; C.2.g; ES-202)

-14 10. Final license applications due and Form ES-201-4 prepared (0.1.1; C.2.i; ES-202)

-14 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) 1

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

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

-7 14. Final applications reviewed; examination approval and waiver letters sent (C.2.i; Attachment 4; ES-204) I.

-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee (0.3k)

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

Target dates are keyed to the examination date identified in the corporate notification letter.

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

[ } Applies only to examinations prepared by the NRC.

ES-201 Examination Outline Quality Checklist Form ES2O12 Facility: HATCH 2011-301 Date of Examination: 06-06-2011 to 05-23-2011 Initials Item Task Description

1. a. Verity that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

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. ti 4f+/-

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

d. Assess whether the justifications for deselecled or rejected K/A statements are appropriate. j/3 j4

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, S and major transients. L./.

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 from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

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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. ,/4 c,t.

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 ii on the form. Wf) C

b. Verity 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 A (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 At? ,

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 A in the appropriate exam sections. j1) (J

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. j

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

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

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

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

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b. Facility Aeviewer() (../t4/iC.

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c, NRC Chief Examiner (#) 9 6.(

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d. NRC Supervisor ALI4LL,oIJL , ,. W,?AL4AfAJ p

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Note: tf Independent NRC reviewer initial items in Co mn c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines

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Cj Southern Nuclear C ing Company Nuclear NMP-TR-423-F20 Management Sample Examination Security Agreement CPNY Version 1 .0 Form Page 1 of 1 Page / of NOTE: Utilize ES-201-3, Examination Security Agreement.

I Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of%D//

on as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons ho have rfot been authorized by the NRC Chief Examiner. I understand that I am not to participate in any instruction, evaluation, or other training-related activities involving those applicants scheduled to be administered these licensing examinations from this date until completion of examination administratio

n. I further 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.

Post-Examination To the best of my knowIedg, I did not ivu)ge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of //Qcii / From the date I entered into this security agreement until the completion of examination administration, I did not participate in ny training related activities involving those applicants who were administered those licensing examinations.

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Southern Nuclear O ating Company Nuclear NMP-TR-423-F20 Management Sample Examination Security Agreement Version 1.0 CNIPP1V Form Page 1 of 1 Page of .7 TNOTE: Utilize ES-201-3, Examination Security Agreement.

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I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons ho have not b6en authorized by the NRC Chief Examiner. I understand that I am not to participate in any instruction, evaluation, or other training-related activities involving those applicants scheduled to be administered these licensing examinations from this date until completion of examination administratio

n. I further 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.

Post-Examination To the best of my knowledge, I did not div)Jlge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of /(4./// /Y/ It From the date I entered into this security agreement until the completion of examination administration, I did notpárticipate irian9 training related activities involving those applicants who were administered those licensing examinations.

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H i c 2 Southern Nuclear 0 ating Company Nuclear NMP-TR-423-F20 SaLJTHERN4. Management Sample Examination Security Agreement COIPNY Version 1.0 Form Page 1 of 1 Page 2 of NOTE: Utilize ES-201-3, Examination Security Agreement.

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I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of //2U// />? z /

as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who hae not beeh authorized by the NRC Chief Examiner. I understand that I am not to participate in any instruction, evaluation, or other training-related activities involving those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration. I further 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.

Post-Examination To the best of my knowledge, I did not Jivu)ge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of ////i - ///Ai . From the date I entered into this security agreement until the completion of examination administration, I did not participate in ny training related activities involving those applicants who were administered those licensing examinations.

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T Southern Nuclear 0 ating Company Nuclear NMP-TR-423-F20 SOUTUERN4I. Management Sample Examination Security Agreement CAPANV Version 1 .0 Form Page 1 of 1 Page of NOTE: Utilize ES-201-3, Examination Security Agreement.

I Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 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 participate in any instruction, evaluation, or other training-related activities involving those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration. I further 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.

Post-Examination To the best of my knowIecge I did not 1ivq1ge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of : //2c// 4/2V/ii From the date I entered into this security agreement until the completion of examination administration, I did not aricipate in anj training related activities involving those applicants who were administered those licensing examinations.

NRC FINAL Administrative Topics Outline ES-301-1 FACILITY: HATCH Date of Examination: 06/06/11 Exam Level: RO X SRO-I X SRO-U X Operating Test Number: 201 1-30 1

. . Type Admin Topic (see Note) Code* Describe activity to be performed Admin 1 ALL Heat Stress Stay Time Determination G2.1.26 N R Conduct of Operations Admin 2 SRO Only Fatigue Rule Determination G2.L5 N R Conduct of Operations Admin 3 RO Only Determine Bulk Average DW temperature per Conduct of Operations D, S/R 34SV-SUV-0 19-1, and then determine if any additional DW cooling requirements. G2.1.7 Admin 4 SRO Only Evaluate Venting DW Irrespective of Offsite Release M R Radiation Control rates lAW PCG G2.3.11 Admin 5 RO Only Determine the Evacuation Route During an D R Emergency Procedures/Plan Emergency G2.4.39 Admin 6 SRO Only Determine if an ENN Form (with errors) is ready for N R Emergency Procedures/Plan approval by Emergency Director G2.4.40 Admin 7 ALL Determine the effect of the failure of a relay on D R Equipment Control system performance. G 2.2.41 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)

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

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

ES-301 Control Roomlln-Plant Systems Outline -RO FINAL Form ES-301-2 Facility: PLANT E. I. HATCH HLT 6 Date of Examination: 06/06/201 1 Exam Level: RO X SRO-l SRO-U Operating Test No.: 2011-301 Control Room Systems0 (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function SF-I CR/SIM I Inject SBLC (With a Pump Trip &

- A ,D, S Reactivity Failure of 2G3 I -F004) 21 1 000A2.0 1 (3.5/3.8)

SF-2 CR/SIM 2 With ED required, Term/Prevent

- M, S Reactor Water Level Control Cond/FW 3PM LR-JP-20l02 (10 mins) 25900 1K4.05 (4.0/3,9)

SF-3 CR/SIM 3 Maintain Rx. Press within 600-800

- A, N, L, S Reactor Pressure Control psig using BPVs, then transition to SRVs with 269002A4.Ol same band, after BPVs fail close.

SF-4 CR/SIM 4 - RCIC/Place RCJC In Pressure Control N, L, S Heat Removal From The Core Mode 217000A4.07 SF-5 CR1SIM 5 RHRJLPCI: Containment Spray Mode

- A, L, N, S Containment Integrity

/ Initiate Torus Spray with failure 226001 A2. I I SF-6 CRJSIM 6- Transfer 4l60V Station Service 2A to D, Electrical Normal (SAT) 3PM 27,40 262001A4 04 SF-7 CR!SIM 7 Respond to a Recirc Pump trip, close

- N, S Instrumentation discharge valve, plot on P/F Map with Recirc speed 216000A3.01

<35%

SF-9 CR/SIM 8 Manually place MCREC in

- A, C, M, EN Radiation Release pressurization Mode after failure to auto with 290003A4.0l COI2A not starting 3PM 25041 0 (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

In-Plant Systems SF-8 PLANT I Crosstie Reactor Bldg Plant Service

- A, D, E, L, R Plant Service Systems Water JPM LR-LP-25029 295018AA1.0l SF-I PLANT 2 - Insert a Scram using the RPS Breakers D, B Reactivity 295006AA1_.05 SF-6 PLANT 3 - Transfer Vital AC from Alternate to D, R Electrical Normal 262002A4.01

@ 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 RD I SRO-l / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power I Shutdown 1 / 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/a2/a 1 (P)revious 2 exams 3 I 3 / 2 (randomly selected)

(R)CA (S)imulator

ES-301 Control Roomlln-Plant Systems Outline SRO I FINAL Form ES-301-2 Facility: PLANT E. I. HATCH HLT 6 Date of Examination: 06/06/2011 Exam Level: RO SRO-l X SRO-U Operating Test No.: 2011-301 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / 1PM Title Type Code* Safety Function SF-I CRJSIM I Inject SBLC (With a Pump Trip &

- A ,D, S Reactivity Failure of2G3l-F004) 21 1000A2.0l (3.5/3.8)

SF-2 CR/SIM 2 With ED required, Term/Prevent

- M, S Reactor Water Level Control Cond/FW 1PM LR-JP-20102 (10 mins) 25900 lK4.05 (4.0/3,9)

SF-3 CR/SIM 3 Maintain Rx. Press within 600-800

- A, N, L, S Reactor Pressure Control psig using BPVs, then transition to SRVs with 269002A4,Ol same band, after BPVs fail close.

SF-S CRJSTM 5 RHRJLPCI: Containment Spray Mode

- A, L, N, S Containment Integrity

/ Initiate Torus Spray with failure 22600lA2.l I SF-6 CR!SIM 6 Transfer 41 60V Station Service 2A to

- D, Electrical Normal (SAT) 3PM 2740 26200 lA4.04 SF-7 CRJSIM 7 Respond to a Recirc Pump trip, close

- N, Instrumentation discharge valve, plot on P/F Map with Recirc speed 216000A3.0I

<35%

SF-9 CR/SIM 8 Manually place MCREC in

- A, C, M, EN Radiation Release pressurization Mode after failure to auto with 290003A4.Ol COl 2A not starting 3PM 25041 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

SF-8 PLANT I Crosstie Reactor Bldg Plant Service

- A, D, E, L, R Plant Service Systems Water 1PM LR-LP-25029 29501 8AA 1.01 SF-I PLANT 2 - Insert a Scram using the RPS Breakers D, E Reactivity 295006AA 1.05 SF-6 PLANT 3 - Transfer Vital AC from Alternate to D, R Electrical Normal 262002A4.01

@ All RD 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 RD / SRO-l / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)

(R)CA (S)imu lator

ES-301 Control Roomlln-Plant Systems Outline SRO-U FINAL Form ES-301-2 Facility: PLANT E. I. HATCH HLT 6 Date of Examination: 06/06/201 1 Exam Level: RO SRO-l SRO-U X Operating Test No.: 2011-301 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System / JPM Title Type Code* Safety Function SF-5 CRISIM 5 RHR!LPCI: Containment Spray Mode

- A, L, N, S Containment Integrity I Initiate Torus Spray with failure 226001A2.l I SF-6 CR/SIM 6- Transfer 4160V Station Service 2A to D, S Electrical Normal (SAT) JPM 27.40 262001A4.04 CR!SIM 8 Manually place MCREC in SF-9

- A, C, M, EN Radiation Release pressurization Mode after failure to auto with 290003A4,Ol C0I 2A not starting JPM 25041 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

SF-8 PLANT I Crosstie Reactor Bldg Plant Service

- A, D, E, L, R Plant Service Systems Water JPM LR-LP-25029 295018AA1.Ol SF-I PLANT 2 - Insert a Scram using the RPS Breakers D, E Reactivity 295006AA1 .05

@ All RD 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 RD I SRO-l / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrombank 9/814 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - I - I 1 (control room system)

(L)ow-Power I Shutdown 1 / 1 I 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 I 1 (P)revious 2 exams S 3 I 5 3 I 5 2 (randomly selected)

(R)CA 1I1I1 (S)imulator

ES-301 Operating Test Quality Checklist Form ES3J3 Facility: HATCH Date of Examination: 06-06-2011 Operating Test Number: 2011-301 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., 10CFR55.45, operational importance, safety function distribution). ,i1_t.

b. There is no day-to-day repetition between this and other operating tests to be administered iv during this examination. A1

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

d. Overlap with the written examination and between different parts of the operating test is within acceptable limits. / t4

e. It appears that the operating test will differentiate between competent and less-than-competent 1

,4L applicants at the designated license level. 7 4 U

2. Walk-Through Criteria -- --

a. Each JPM includes the following, as applicable:

initial conditions

initiating cues

references and tools, including associated procedures

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

operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards 43 (/

restrictions on the sequence of steps, f applicable

h. 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 A on those forms and Form ES-201-2.

3. Simulator Criteria -- --

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

Form 3

/

Date

)

a. Author

b. Facility Reviewer()

c. NRC Chief Examiner (II) 10 1

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

ft Independent NRC reviewer initial items in Column C: chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES-3Oi4 Facility: HATCH Date of Exam: 06-06-2011 Scenario Numbers: 1 /2/ 3 I 4 Operating Test No.2011 -301 QUALITATIVE ATTRIBUTES Inmals a b c#

1, The initial conditions are realistic, in that some equipment and/or instrumentation may be out ot service, but it does not cue the operators into expected events, ,4-S

2. The scenanos consist mostly of related events. ,/QfS L..

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)

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the event termination point (it applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario 4/? . .

without a credible preceding incident such as a seismic event. /Y L

5. The events are valid with regard to physics and thermodynamics. ,.4- c.

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain A/7 . /1 complete evaluation results commensurate with the scenario objectives. /4 C

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.

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 ,4j functional fidelity is maintained while running the planned scenarios. /T15 C.

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. 5 VL i_.,. Vy 1 1. All individual operator competencies can be evaluated, as verified using Form ES-301 -6 (submit the ,? . ,

form along with the simulator scenarios). C

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). t L

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

1 /2/3/4

1. Total malfunctions (58) 7 / /

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2. Malfunctions after EOP entry (12) a. / / /

3. Abnormal events (24) 3 / tI I / 4 ii_..

4. Major transients (12) j / 1 / / / / 42 c

5. EOPs entered/requiring substantive actions (12) / -

6. EOP contingencies roquiring substantive actions (02) 1 / C / / / / E,, kIt

7. Criticaltasks(23) 3 / 3 ii / , / .

ES-301 Transient and Event Checklist Form ES-301-5 Facility: E. I. Hatch Date of Exam: 06-06-2011 Operating Test No.:201 1-301 A E Scenarios P V 1 2 3 4 T M P E 0 I L N CREW CREW CREW CREW T N T POSfl1ON POSn1ON POSmON poso A C S A B S A B S A B S A B L A T R T 0 R T 0 R T 0 R T 0 M(*)

N Y 0 c P 0 c P 0 c P o C P R lU T P E

RO RX 2 6 1 3 4110 X NOR 1 1 21 4111 SRO-l El SRO-U 65253A64216442 MAJ 7 7 7 7 7 7 7 7 4 2 2 1 El TS NA NA NA NA NA NA NA NA NA 0 2 2 RX 2 6 1 4 4 110 RO El SRO-l NOR 1 1 2 1 4 111 I/C 3,4, 2,3, 3,4, 2,3, 16 4 4 2 X 5,6 4,5 5,6 5,6 SRO-U MAJ 7 7 7 7 4221 TS 3,4,6 3,4 4,5,6 5,6 10 0 2 2 RO RX 2 6 1 4 4110 NOR 1 1 2 1 4 1 1 1 o-i El SRO-U I/C 3,4, 5,6 2,3, 4,5 3,4, 5,6 2,3, 5,6 16 4 4 2 X MAJ 7 7 7 7 4221 TS 3,4,6 3,4 4,5,6 5,6 10 0 2 2 NOR O-I El SRO-U I/C 442 MAJ 2 2 1 El TS 022 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.

ES-301 Competencies Checklist FpfnE$ -3D16 Facility: Plant E. I. Hatch Date of Examination: 06106/2011 Operating Test No.: 2011-301 APPLICANTS RO X RO El RO El RD El SRO-l El SRO-l X SRO-l El SRO-I El SRO-U El SRO-U El SRO-U X SRO-U El Competencies NAJO_ NjO_ CN.JO_ CAJO_

1 234123412341234 Interpret/Diagnose All All All All All All All All All All All All Events and Conditions Comply With and All All All All All All All All All All All All Use Procedures (1)

Operate Control All All All All All All All All N/A N/A N/A N/A Boards (2)

Communicate All All All All All All All All All All All All and Interact Demonstrate N/A N/A N/A N/A All All All All All All All All Supervisory Ability (3)

Comply With and N/A N/A N/A N/A 3,4 3,4 4,5 5,6 3,4 3,4 4,5 5,6 Use Tech. Specs. (3) 6 6 6 6 Notes:

(1) Includes Technical Specification compliance for an RD.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

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

ES-401, Rev. 9 - BWR Examination Outline Form ES-401 -1

{PRIVATE ) Facility: Hatch Date of Exam: June 2011 RO K/A Category Points SRO-Only Points Tier Group A2 (3* Total KKKKKKAAAAIG 41*

1 2 3 4 5 6 1 2 3 Total

1. i 433 34 20 3 4 7 Emergency &

2 T 7 T 1 T 7 1 2 3 Abnormal Plant N/A I NIA Evolutions Tier Totals 6 1 27 6 10 1 32323222232 26 2 3 5

2. 11 2 1 1 1 11 1 1 21 12 0.1 2 3 Plant Systems Tier Totals

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

1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (I.e., except for one category In Tier 3 of the SRO-only outline, the Tier Totals 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, Systemslevolutlons within each group are Identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

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

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

6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.

7. The genetic ((3) K/As in Tiers I and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.

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

1 does not apply). Use duplicate pages for RO and SRO-oniy exams.

9. For Tier 3, select topics from SectIon 2 of the KIA 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 BWR EXAMINATION OUTLINE FORM ES4O1-1 KA NAME / SAFETY FUNCTION: IA Ki K2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295001 AK1.0l Partial or Complete Loss of Forced 3.5 3.6 Natural circulation Core Flow Circulation / 1 & 4 LI [J U 295003AK1.04 Partial or Compete Loss of AC / 6 3.1 3.2 Electrical bus divisional separation U LI [] LI [1 U [1 Fl [7 [7 295004AK3.02 Partial or Total Loss of DC Pwr/ 6 2.9 3.3 F] U [ LI UI LI LI LI LI [] LI Ground isolation/fault determination 295005G2.4.34 Main Turbine Generator Trip /3 4.2 4.1 Knowledge of RO tasks performed outside the main

[7 [7 LI LI LI U] [] fl [7 LI

. control room during an emergency and the resultant operational effects 295006G2.4.l SCRAM /1 4.6 4.8 Knowledge of EOP entry conditions and immediate action

[1 LI LI LI LI LI LI LI LI f]

steps.

295016AA1.04 Control Room Abandonment!? 3.1 3.2 A.C. electrical distribution UI UI LI LI LI LI ti LI LI LI LI 295018AK1.01 Partial or Total Loss of CCW / 8 3.5 3.6 Effects on component/system operations LI LI LI LI LI LI LI LI LI LI 29501 9M201 Partial or Total Loss of Inst. Air / 8 3.5 3.6 Instrument air system pressure LI LI LI LI LI LI LI ] [1 [7 LI 295021G2.4.8 Loss of Shutdown Cooling / 4 3.8 4.5 Knowledge of how abnormal operating procedures are LI LI U] LI LI ((7 LI LI LI LI ]

used in conjunction with EOPs.

295023AP,2.02 Refueling Aco Cooling Mode / 8 3.4 3.7 Fuel pool level LI LI LI LI LI LI LI LI LI LI 295024EK2.01 High Dywell Pressure / 5 3.9 4.0 [IPCI (FWCI): Plant-Specific LI [ [] LI LI LI LI LI LI LI LI Page 1 of 2 11/29/2010 6:06 AM

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295025EK3.02 High Reactor Pressure! 3 3.9 4.1 Recirculation pump trip: Plant-Specific Li [j El []

295028EA1.01 Suppression Pool High Water Temp. I 4.1 4.1 Suppression pool cooling 5

El LI LI LI LI [I i LI LI C] LI 295028EK3.06 High Drywell Temperature? 5 3.4 3.7 ADS LI LI ] LI LI LI LI LI LI LI LI 295030EK2.O1 Low Suppression Pool Wtr Lvi / 5 3.8 3.9 HPCI: Plant-Specific C] C] [] [] fl C] [J [] []

295031 EA2.01 Reactor Low Water Level? 2 4.6 4.6 Reactor water level Ci El LI LI LI C] LI ] El LI []

295037EK1.01 SCRAM Condition Present and Power 4.1 4.3 Reactor pressure effects on reactor power Above APRM Downscale or Unknown

(] LI El El C] El Cl LI El H []

/1 295038EA1.03 High Off-site Release Rate / 9 3.7 3.9 Process liquid radiation monitoring system LI Li El LI LI Li ll LI Li LI LI 600000AK2.04 Plant Fire On Site? 8 2.5 2.6 Breakers / relays? anti disconnects El li LI LI LI LI C] El LI LI C]

700000AP2.01 Generator Voltage and Electric Grid 3.5 3.6 Operating point on the generator capability curve Distrurbancecs LI LI C] Li Li LI LI i LI LI LI Page 2 of 2 11/29/2010 6:06 AM

ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-4O11 KA NAME / SAFETY FUNCTION: IR Kl 1<2 K3 1<4 1<5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295002AK1.04 Loss of Main Condenser Vac /3 3.0 3.3 Increased oftgas flow

[j [1 [] Li [1 H [1 H LI 295007AK2.03 High Reactor Pressure /3 3.1 3.2 RHR/LPCI: Plant-Specific LI [I Li LIE LI [1 295022AK3.02 Loss of CRD Pumps / 1 2.9 3.1 CRDM high temperature

[J Li F1 LI LI LIE C LI LIE]

295029EA2.03 High Suppression Pool Wtr Lvi 15 3.4 3.5 DrywelLfcontainment water level LI Li El LI [IL] LI 1 [IL] LI 295033EK1 .02 High Secondary Containment Area 3.9 4.2 Personnel protection Radiation Levels! 9 LI [I [I LID [I [I [I LI [I 295034G2.2.39 Secondary Containment Ventilation 3.9 4.5 Knowledge of less than one hour technicai specification High Radiation /9 C LI LI LI LI [I LIE LI LI [1 action statements for systems.

295036EA1.04 Secondary Containment High 3.1 3.4 Radiation monitoring: Plant-Specific Sump/Area Water Level / 5 EEEEEDDLLL Page 1 of 11/29/2010 6:06AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 203000A2.13 RHRILPCI: Injection Mode 3.2 3.3 Valve openings LI LI [1 LI Li Li [] [J [ [] []

203000K5O1 RHR/LPCI: Injection Mode 2.7 2.9 Testable check valve operation

[] F] F] [] j [] F] F] [] F]

205000A4.12 Shutdown Cooling 3.4 3.4 Recirculation loop temperatures LI F] F] Li Li Li Li Li Li F]

206000A4.10 HPCI 3.7 3.5 System pumps: BWR-2,3,4 F] F] F] F]j [] [] F] F] [] F]

209001 K5.Ol LPCS 2.6 2.7 Indications at pump cavitation F] F] F] Li F] [] {J LI F] F]

2110001(6.04 SLC 2.7 2.8 Core spray system: Plant-Specific

[F] Li LI F] Li J Li Li LI Li LI 212000A3.02 RPS 3.2 3.5 [j Individual system relay status; Plant-Specific Li F] LI F] Li F] F] F] F]

215003A1.06 JRM 3.3 3.2 Lights and alarms F] E] L] F] Li F] 1 Li Li Li F]

215003K5.01 IRM 2.6 2.7 Detector operation fl LI Li Li I LI Li Li [1 F] F]

215004A3.O1 Source Range Monitor 3.2 3.2 Meters and recorders F] F] F] F] F] F] F] F] F] F]

2150051(3.01 APRM / LPRM 4.0 4.0 RPS Li Li Ii Li F] F] Li Li LI F] F]

Page 1 of 3 11/29/2010 6:06 AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO 217000Kt01 RCIC 3.5 3.5 Condensate storage and transfer system

] [] [] [] fl [U [] [U] LI []

218000K2.O1 ADS 3.1 ADS logic LI LI Li Li [I LI LI [1 LI LI 223002G2.4.3 PCIS/Nuclear Steam Supply Shutoff 3.7 3.9 Ability to identify post-accident instrumentation.

LI [1 LI El Li LI LI LI Li LI 239002A4.04 SRVs 4.3 4.3 Suppression pool temperature Cl LI LI LI LI [II Ci CI [1 I1 LI 239002K1.05 SRVs 3.1 3.3 [Uj Plantairsystems: Plant-Specific

[ [1 LI [] [ fl Li [U] LI 259002K3.03 Reactor Water Level Control 2.7 2.9 Rod worth minimizer: Plant-Specific

[U] [ [J [ [] [U] [Ui [U] [] [U] [U]

259002K-a07 Reactor Water Level Control 3A 3.4 Reacturwaterlevet-tntiicatioii

[ [ j [ [U] [U[ [U] [U] [U] [U] LI 259002K3.02 3.7 3.7 Reactor Feedwater system 2610001<4.04 SGTS 2.7 2.9 Radioactive particulate filtration LI LI LI LI LI LI [U] LI LI LI 262001 A2.O1 AC Electrical Distribution 3.4 3.6 Turbin&generator trip LI LI LI LI LI [U] LI LI LI LI 262002A1.02 LiPS (ACIDC) 2.5 2.9 Motor generator outputs __________________

LI LI LI LI LI LI E?l LI LI LI LI 2630001<4.02 DC Electrical Distribution 3.1 3.5 Breaker intertockspemiissives, bypasses and cross ties:

LLILILEILILIL1LILILI Plant Specific Page 2 of 3 11/29/2010 6:06AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES4O1-1 KA NAME / SAFETY FUNCTION: IFR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO 264000K 1.04 EOGs 3.2 3.3 Emergency generator cooling water system fl Li [I C] Li E] Li [1 Li Li 264000K6.08 EDGs 3.6 3.7 A.C.power flflLiEEflfl[JL]

300000K2.O1 InstrurnentAir 2.8 2.8 lnstrumentaircompressor C] C] [] C] [1 Li Li C] C) []

400000G2.1.30 Component Cooling Water 4.4 4.0 Ability to locate and operate components, including local C] [] C] Li C] Li. Li Li C). Li controls.

Page 3 of 3 11/29/2010 6:06 AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO 201002A2.04 RMCS 3.2 3.1 Control rod block fl [1 [] fl Li [] [ [1 201003A4.02 Control Rod and Drive Mechanism 3.5 3.5 fl Li, El CRD mechanism position: Plant-Specific

[] [1 Li L] LI [1 201 006A4.02 RWM 2.9 2.9 Ej Pushbutton indicating switches: P-Spec(Not-BWR6) fl Li [J fl [] [] [] []

219000A1 09 RHRJLPCI: Torus/Pool Cooling Mode 3.2 33 Suppression chamber air temperature: Plant-Specific Li Li LI [1 LI LI [ LI EL Li Li 2300001<2.02 RHR/LPCI: Torus/Pool Spray Mode 2.8 2.9 fl El fl Pumps

[ LI fl [ j 245000K1 .04 Main Turbine Gen. / Aux. 3.6 3.7 Reactor protection system Li LI LI LI LI LI LI Li LI LI 2560001<5.10 Reactor Condensate 2.8 2.8 Air ejection operation Li LI LI LI LI Li [I LI LI Li 2590011<6.01 Reactor Feedwater 3.0 3.0 Plant air systems Li Li LI Li LI E1 LI LI ELI LI LI 2710001<4.09 Offgas 2.8 3.1 [1 Filtration of radioactive particulate Li LI [I Li EL LI LI Li LI LI 272000A3.01 Radiation Monitoring 3.8 3.9 Main steam isolation indications

[] LI LI Li Li Li Li Li Li []

28800052.1.32 Plant Ventilation 3.8 4.0 Ability to explain and apply all system limits and Li Li Li Li Li Li Li Li C] Li precautions.

Page 1 of 2 11/29/2010 6:06 AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: tR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

FiO SRO 290001K3.O1 Secondary CTMT 4.0 4.4 F Oft-site radioactive release rates

[] [] [] [] [] [] [] ]

Page 2 of 2 11/29/2010 6:06 AM

ES-401, REV 9 T3 BWR EXAMINATION OUTliNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: JR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 62.1.20 Conduct ot operations 4.6 4.6 Ability to execute procedure steps.

[] ] LI [] [] [] [] LI [] LI ]

62.1.8 Conduct of operations 3.4 4.1 Ability to coordinate personnel activities outside the

[] H LI C] C] LI C] [I LI LI control room.

G249 Equipment Control 23 3A Ej Knowtedge of maintenance work order requirements.

C] C] C] C] [j []

2.2. 13 4 .1 3 Knowledge of tagging & clearance procedures.

62221 Equipment Control 2.9 4.1 Knowledge of pre- and post-maintenance operability 1 H LI LI LI LI LI [} [] []

requirements.

62.3.11 Radiation Control 3.8 43 F] Ability to control radiation releases.

fl J J C] C] [] C]

623.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to

[] LI C] C] C] C]

licensed operator duties 62.3.13 Radiation Control 34 3.8 Knowledge of radiological safety procedures pertaining to fl LI LI LI LI LI LI LI LI licensed operator duties G2.4.16 Emergency Procedures/Plans 3.5 4.4 Knowledge of EOP implementation hierarchy and fl LI [] [] [J (]

coordination with other support procedures or guidelines.

62.4.4 Emergency Procedures/Plans 4.5 4.7 Ability to recognize abnormal Indications for system LI LI LI Cl C] LI LI C] LI LI operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

62.4.6 Emergency Procedures/Plans 3.7 4.3 Knowledge of the organization of the operating

[] C] C] C] [] C] { LI [] [] []

procedures network for normal, abnormal and emergency evolutions.

Page 1 of 1 11/29/2010 6:07AM

ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 k4 K5 K6 Al A2 A3 A4 G TOPIC:

Rb SRO U.

29500132.4.41 Partial or Complete Loss of Forced 2.9 4.6 Knowledge of the emergency action level thresholds and Core Flow Circulation! 1 & 4 classifications.

29500532.1.23 Main Turbine Generator Trip / 3 4.3 4.4 Ability to perform specific system arid integrated plant LI LI LI LI LI LI [] [] []

procedures during all modes of plant operation.

295018M2.03 Partial or Total Loss of CCW /8 3.2 3.5 Cause for partial or complete loss F] [] fl [] [J []

295021 32.1.23 Loss of Shutdown Cooling / 4 4.3 4.4 Ability to perform specific system and integrated plant LI LI LI LI LI LI LI LI LI procedures during all modes of plant operation.

295026EA2.01 Suppression Pool High Water Temp. / 4.1 4.2 Suppression pool water temperature 5

F] F] LI LI LI LI LI F] []

295031 G2.2.25 Reactor Low Water Level / 2 3.2 4.2 Knowledge of the bases in Technical Specifications for LI LI LI LI LI LI LI LI LI LI limiting conditions for operations and safety limits.

295038EP,2.03 High Off-site Release Rate / 9 3.5 4.3 F] Radiation levels F] [] [] [] LI LI J F] [] []

Page 1 of 1 11/29/2010 6:07AM

ES-401, REV 9 Sf0 T1G2 BWR EXAMINATION OUTUNE FORM ES4O1-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 1(4 1(5 K6 Al A2 A3 A4 G TOPIC:

RO SIRO 295009G2.4.6 Low Reactor Water Level / 2 3.7 4.7 Knowledge symptom based EOP mitigation strategies.

LI LI LI LI LI [I LI LI LI LI []

295o20Ga4.2 Inadvertent Cont. Isolation IS & 7 4.5 4.6 Knowledge of system set points, interlocks and automatic LI LI LI LI LI LI LI LI LI LI actions associated with EOP entry conditions.

295034EA2.02 Secondary Containment Ventilation 3.7 4.2 Cause of high radiation levels High Radiation / 9 LI LI LI LI LI LI LI I] LI LI LI Page 1 of 1 11/29/2010 6:07AM

ES-401, REV 9 Sf0 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR Ki 1<2 K3 K4 1<5 K6 Al A2 A3 A4 G TOPIC:

Rb SRO 20500002.4.20 Shutdown Cooling 3.8 4.3 Knowledge of operational implications of EOP warnings,

[1 [] [] [] [] [] [] [] []

cautions and notes.

217000024.45 RCIC 4.1 4.3 Ability to prioritize and interpret the significance of each El annunciator or alarm.

259002A2.04 Reactor Water Level Control 3.0 3.1 RFP runout condition: Plant-Specific El LI LI El LI LI El I: LI L. [.J 262001A2.06 AC Electrical Distribution 2.7 2.9 Deenergizing a plant bus

[] [] fl [] [] [] []

26400002,2.12 EDGe 3.7 4.1 Knowledge of surveillance procedures.

LI [] [] [ [] [] [] [J El Page 1 of 1 11/29/2010 6:07 AM

ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 201 002G2.1 .32 RMCS 3.8 4.0 Ability to explain and apply all system limits and precautions.

256000G21.23 Reactor Condensate Ability to perform specific system and integrated plant L1L1DL1DE1 procedures during all modes of plant operation.

288000A2.Ol Plant Ventilation High drywell pressure: Plant-Specific E[1EL]EiEL1 Page 1 of 1 11/29/2010 6:07AM

ES-401, REV 9 SRO T3 BWR EXAMiNATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 1<2 1<3 K4 1<5 KS Al A2 A3 A4 G TOPIC:

RO SRO G2.1.44 Conduct of operations 3.9 3.8 Knowledge of RO duties in the control room during fuel LI LI [1 LI LI [1 LI Li [1 LI handling.

(32.2.23 Equipment Control 3.1 4.6 [1 Ability to track Technical Specification limiting conditions C] LI LI LI LI Li C] Li []

for operations.

(32.2.5 Equipment Control 22 3.2 Knowledge of the process for making design or operating Ci LI LI LI Li Li LI [1 LI LI {]

changes to the facility (32.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to LI LI LI LI LI LI LI LI LI LI {]

licensed operator duties (32.3.15 Radiation Control 2.9 3.1 Knowledge of radiation monitoring systems LI LI LI LI LI LI LI ((1 LI (32.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency Li [El LI LI LI LI Li LI CI [C]

response to sabotage.

(32.4.50 Emergency Procedures/Plans 4.2 4. Ability to verify system alarm setpoints and operate LI [1 LI Li LI. LI C] Li LI LI iI controls identified in the alarm response manual.

Page 1 of 1 11/29/2010 6:07AM

Hatch ES-401 Record of Rejected KJAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KIA 2/1 259002K3.03 The RWM, at Plant Hatch, does not use any input from the RWL Control System, as some plants do. Our RWM uses the APRMs only for power determination; therefore a malfunction of the RWL Control System has no direct effect on the RWM.

3 G2.2.19 RO Importance Rating was < 2.5 Replaced with G2.2.13

ES-401 Written Examination Quality Checklist Form ES4 01-C Facility: Plant E. I. Hatch Date of Exam: 06-23-2011 Exam Level. RO X SRO X Item Description

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

2. a. NRC K/As are referenced for all questions.

h. Facility eaming objectives are referenced as available.

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

4. The sampling process was random and systematic (If more than 4 AC cr2 SRC questions were repeated from the last 2 NRC licensing exams, consult the NRA CL program

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

,:lhe licensee certifies that there is no duplication: or other (explain)

6. Bank use meets limits (no more than 75 percent from Bank the bank, at least 10 percent new, and the rest new or modified); enter the actual AC / SAC-only question (5 / j L-ci .:i 4i /4. y distribution(s) at right. I

7. Between 50 and 60 percent of the questions on the AC Memory C/A exam are written at the comprehension) analysis level; the SAC exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels: enter U/f / , /

g 1 the_actual_AC)_SRC_question_distribution(s)_at_right.

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

9. Questioo content conforms will, specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned: deviations are justified.

10. Cr.iestion psychometric quality and format meet the guidelines in ES Appendix B.

11 The exam contains the required number of one-point, multiple choice items; the total is correct and agrees witlr the value on the cover sheet.

Printed Name Sig fur // Date

& 1/ /

a. Author

b. Facility Reviewer () I L. dIftt z /Z X ./sy7>i)

c. NRC Chief Examiner hi) vjt C -tr.V I U4 --

d. NRC Regional Supeniisor 1 L uJ.c9t.4L Vf1pMf,J

/( p Note: The facility reviewers initials/signature are not applicable for NRC-developed examinations.

It lndeoendent NRC reviewer initial items in Column C: chief examiner concurrence recuired.

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 INITIAL DRAFT EARLY REVIEW 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 (LCD) of each question using a 1 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.

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

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

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

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

At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not_being met).

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

Q# LOK LCD 1

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ I Back- Q SRO U/E/S Explanation Focus Dist. Link unitsj ward K/A Only O1 002A2.04 ppears to be OK. Do we need to say whether the rod has stopped or not 1 F 2 S t position 10?

5/27/11 Licensee stated that this is not necessary based on the locations

)f the alt. reed switch postions.

01 003A4.02 2 F 3 S \ppears to be OK.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 01 006A4.02 3 H 2 ppears to be OK.

03000A2.1 3 should the valves be labeled as Outbd and lnbd injection valves? The procedure does not give direction to trip the RHR pump. This would give 4 H way Q#5. If someone asks during the exam which one is the inbd or 3

utbd valve, you could not respond or else give away answer to Q#5. It ays to close the injection valve and stop RHR pumps in section 7.3.1 Shutdown from LPCI.

/27/11 Reviewed on site. SAT 03000K5.01 5 H 3 5 Ensure question 4 does not affect this question.

/27/11 Verifed that Q4 does not overlap with this on site w/ the licensee.

05000A4.1 2 6 H 3 ppears to be OK.

06000A4.1 0 ppears to be OK.

7 F 2 E /27/1 1 Question had to be revised due to a change in Scenario #5 (spare cenario) during prep week that included a HPCI shutdown by using the S PTL Aux Oil Pump feature. New question written to ask what the mm op peed of HPCI is and why. This changed the cognitive level and LOD rom H3 to F2.

09001 K5.01

&C are looking at the same reasoning (If motor amps go up, motor inding temperature would go up also) and are therefore both cant be 8 F 3 E orrect.

S I27/1 1 New distractor written to replace C distractor. SAT This was an asy change; therefore, this was credited as n editorial change and NOT is UNSAT.

11000K6.04 Q#9 KA: KA asks for the effect of a loss of CS will have on SBLC system. The 9 P H 3 X juestion is a CS component electrical fault that causes a loss of MCC that ilso powers a SBLC component. Look at to see if there is an example of lirectly meeting this KA if not I will accept.

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9

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

Q# LOK LOD I 1 (F/H) (1-5) Stem ICues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/S Explanation Focusi Dist. Link 1ts ward K/A Only V27/l 1 Reviewed on site and agreed w/ licensee to keep as is.

1 2000A3.02 10 H 3 S

.ppears to be OK.

1 50003A1 .06 11 H 3 S

.ppears to be Ok.

15003K5.01 001 u he KA asks for detector operation. The question has to do with the effect 12 H 2 X if a loss of power to the detector on the detector circuitry. The question tself is ok.

S/27/1 1 Reviewed on site. SAT 15004A3.01 001 E red Dist: Explain why A is plausible. Is there a condition that the SRM 13 H 3 X

ould be in when a single SRM failed high would NOT give a half scram?

/27/1 1 Reviewed on site. SAT 15005K3.01 001 red Dist: Explain why D is plausible. Analysis really doesnt sound 14 3 redible. Licensee to explain in more detail. If the question was changed H X E a APRM are you saying that D would be the correct answer?

I27/1 1 Question slightly modified to increase plausibility of D distractor by idding that the B APRM is bypassed.

17000K1.01 001 Not sure why anyone would pick anything other than D. Why would you remove a suction source before your assured that another source is lined U up? If I opened 31 first, would 10 close or would it not close until 29 was 15 F 1 X ullopen?

I assume that the analysis means the C distracter instead of the D listracter.

/27/1 1 Reviewed on site. Corrections made SAT.

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

Q# LOK LCD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus Dist. Link units ward K/A Only 18000K2.01 001 Vould cabinet B be incorrect? It seems like it would and it would be a E better distracter. Does anything come off of cabinet 2C, 2E or 2L that would be easily confused with ADS logic? How about:

Vith respect to the Unit 2 ADS A logic, which ONE of the following tates: (1) the normal power supply and (2) the backup power supply?

A. (1) 2R25-S001, 125 VDC Cabinet2A (2) 2R25-SXXX, 125 VDC Cabinet 2B 16 F 2 X B. (1) 2R25-SOO1, 125 VDC Cabinet 2A (2) there is no backup power supply C. (1) 2R25-SXXX, 125 VDC Cabinet 28 (2) 2R25-S001, 125 VDC Cabinet 2A D. (1) 2R25-SXXX, 125 VDC Cabinet 2B (2) there is no backup power supply S

This is based on the reference material provided.

/27/1 1 Licensee modified based on our suggestion.

19000A1.09 001 17 H 2 S ppears to be ok.

23002G2.4.3 001 Do SRVs fall under PCIS/Nuclear Steam Supply Shut-off? I really couldnt E md anything in the lesson.

re the SRV control switches classified as PAM instrumentation? I guess ts a wording thing. Does it mean indication for the SRVs?

18 F 2 he plausibility statements really havent convinced me.

/27/1 1 The 2n1 part of the distractor for the blue dots has been changed S o make the distractors more plausible. They now correlate the blue dot with the Group 2 isolation signal. This correlation is true; however, there ire no blue dots above the SRV control switches and is therefore an ncorrect choice.

30000K2.02 001 19 F 2 S

)k with this one

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9

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

Q# LOK LOD 1 (F/H) (1-5) Stem Cues I T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 39002A4.04 001 The KA Ability to manually operate and/or monitor in the control room:

Relief/Safety Valves. The only thing in the question about SRVs is that it 20 H 2 x ells you that one is leaking. There is no monitoring or operation.

an we say elevated instead of high torus temperature? I think it is onfusing to say the lowest of the high.

5/27/1 1 On site review SAT.

39002K1 .05 21 F 3 S ppears to be OK.

45000K1 .04 22 F 3 5 ppears to be OK.

56000K5.1 0 23 F 3 LOD1?GFES 5 5/27/11 Reviewed on site and agreed w/ licensee that there is site specific knowledge required to answer this question.

59001K6.01 E Eo make D plausible, why not add to the stem that air press is decreased 24 F 2 X 0 40 psig?

s 5/27/11 Changed as noted above.

59002K3.02 25 H 3 LOD 2? Appears it should be higher.

5/27/11 Changed as noted above.

59002K3.07 E Do you need to add the word BOTH after INITIALLY. Otherwise could

,ou not argue that RFPT speed will eventually increase.

26 H 3 5/27/11 Changes made as noted above.

S

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 61 000K4.04 E Simplify to ask, Which ONE of the following SGTS components removes 27 F 2 s )articulate radioactivity as small as 0.3 microns or larger in size?

5/27/1 1 Change made as noted above.

62001A2.01 E Nhy not ask in the 2r part of B, which busses can be manually re 28 H 3 s nergized? i.e. A&B or C&D.

5/27/1 1 Above change noted.

62002A1 .02 E I think the question would read better if you had (Assume no operator actions have been taken) after the opening question so that the l 2 H 3 X rtatement is, When power is restored to 600V 1 D, the 1 B RPS MG Set...) Why would anyone choose B to have the MG set auto restart with the brks closed in at the same time. Not sure if I buy in to the S 9nalysis reasoning on this.

5/27/1 1 Reviewed on site and agreed with licensees logic for plausibility.s 63000K4.02 30 H 3 S ppears to be OK.

E 64000K1.04 Should the stem give the Select Switch Position as Unit 1. Doesnt 31 H 3 thange the answer but prevents the question during the exam and makes

& B more viable.

S 5/27/11 Reviewed on site. Changes made as noted above E 64000K6.08 Reword question to match distractor order: (. ...status of EDG 2A and KV bus 2E). Isnt C an incomplete statement with regard to the 32 H 3 X luestion. It asks what happens to EDG 2A? If you only say that the Test ckt deenergizes, isnt that an incomplete thought and therefore not redibIe?

5/27/11 Changed made as noted. LCD rasied from a 2 to a 3.

33 F 2 S 71000K4.09 ppears to be OK

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401 -9

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 72000A3.01 E

How would an NPO observe these valves? Is this realistic? If not just say 34 H 3 hat the valves are open. Could someone argue there is no correct

-mnswer since enough info is not given to determine a FEF is suspected?

5/27/11 Change made to include FEF and the valves are in the CR.

88000G2.1 .32 E Do you need to add the word automatically after the 2 question (i.e.

TRIP Automatically. Also, can we delete the word subsequently. It appears that this is leading the though from the 1 question (i.e. if the 35 H 3 wpply fan will not START w/o an Exhaust fan than the exhaust fan will IRIP w/o a supply fan. The 2 question could also be changed to ask vhat happens if the A SF was taken to STBY. The A SF will NOT run.

5/27/11 Reviewed on site with suggested changes made. Accepted logic nd or keeping the 2 part of the question.

90001 K3.01 E Do you need to designate where the RWCU break is at. If the the break is upstream of the demins with high radioactivity, could someone argue that he airborne levels would be high enough that even with SGT in operation 36 H 4 hat the release rates could be higher than before. Change question so hat the order matches the answer response. Currently your asking for 5t Rx. Bldg dp response 1 but the i answer response is for the change in s release rate.

/27/1 1 Reviewed the question on site and is acceptable as is.

95001AK1 .01 D plausibility analysis does not support choosing D. If A jet pump flow is E not subtracted than Core Flow should be either just the B jet pump flow r A + B jet pump flows (its neither).

37 H 3 X 5/27/11 Reviewed question w/licensee on site. Noted to the licensee that S his question is identical to a JPM in the simulator. The licensee agreed nd revised the question such that pump speed is >35% speed in the tem. This modification changes the correct answer (must subtract nstead of add) and it is now different than the JPM given in the simulator.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO UIEIS Explanation Focus Dist. Link units ward K/A Only 95002AK1 .04 E Vhy not just say that current vacuum is at 20 and decreasing slowly.

lso put steam seal hdr press before vacuum in the stem. Incorrect ARP noted in anyalysis, Main Cond Vac L0wARP is N61-002-2 not N61-001-2.

38 H 4 Lower the power level to make A&B more plausible. Maybe 14% so if hey though it was 15% for the MVPs. Opening F004 appears ONLY in he ARP, not the AB procedure? Need to revise question to say lAW s RP.

/27/11 Changed made as noted above.

95003AK1 .04 Q#39 E

is checked as correct. C in the analysis is correct. LOSP?

39 P H 3 R: Licensee will correct the distractor for the correct answer to be A.

Modified quostion, where is the original?)

/27I1 I Reviewed on site SAT.

95004AK3.02 40 F 3 5 ppears to be OK.

95005G2.4.34 41 H 3 S

.ppears to be OK.

95006G2.4. 1 E ,,

an you see 149.5 on the indications available? Should DW press be 42 H 2 x ncluded? Not sure how plausible TC is as a distractor.

S /27/1 1 Licensee replaced DW temp in the stem with DW press. Agreed i/licensee on inclusion of TC as a plausible distractor.

95007AK2.03 E

43 H 3 dd listed to specify this is not the shutoff head value (220#) but the HIGHEST listed Reactor Pressure

/27/1 1 Changes made as noted.

95016AA1.04 Jhat AC electrical distribution are you operating or monitoring? KA 44 H 3 E match? This question is just asking for the 2A CRD Pump pwr supply.

S /27/1 1 Agreed upon review w/ licensee on site that the original question met the KA. The licensee reworded the question and changed from a 2

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9

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

Q# LOK LOD 1 (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus Dist. Link units ward K)A Only part question to a one part question.

95018AK1.01 D distractor plausibility doesnt make sense. We tell them in the 1 part of he answer that the standby RBCCW pump auto started. The distractor 45 F 2 E inalysis states the standby pump did not start on low pressure? D is only plausible if the applicant thinks that both A&B pumps are powered from C 600 VAC and the standby pump (2C) is powered from another bus.

5/27/1 1 Reviewed on site. No changes necessary.

9501 9AA2.01 46 H 3 S

\ppears to be OK.

95021G2.4.8 Need a 2 check on this question to see if it meets the KA. Is this KA 47 H 3 -asking for when AOPs can be used with EOPs? Need licensee to explain he Mode 4 and the requirement for being in the EOPs analysis reasoning or plausibility on A&B statement.

5/27/11 Reviewed on site and agreed w/ licensee that this meets the KA.

95022AK3.02 uestion can be simplified. Which ONE of the following describes CRD 48 H 3 S response of U2 to a High DW Press scram? CRDM temps are expected to Only one is decreasing, non symmetrical.

5/27/1 1 Changes made as noted above.

95023AA2.02 U

Does not meet the KA statement. How are you determining or interpreting nd 49 H 3 uel pool level in this question? Also, the 2 part of the answer is not echnically correct as is. The bundle has to placed in a fuel rack not just lowered into the fule pool anywhere.

S 5/27/11 Question modified to meet the KA.

S/E 95024 EK2.01 50P F 2 X d 2

Dred Dist: part of B & D not plausible unless there is some room

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only entilation system starts on a temperature signal. Would rather see a Jiven pressure in the stem and the jst part asking if HPCI is operating or not.

S (This is a modified question, where is the original?) This was provided but vas not in the electronic info.

5/27/11 SAT 95025EK3.02 E How about having another press increase event to match up with the

\TWS? Is NON-ATNS a plausible match up? If I had to choose between 51 F 2 X n ATWS (much worse event) vs non-ATWS I would not consider the non

\TWS distractors.

5/27/11 2fl part of question changed to a Load Reject as recommended ibove.

95026EA1 .01 52 H 3 S

\ppears to be OK.

E 95028EK3.06 heck C plausibility statement. Does not seem to agree with distractor. B 53 H 3 is the only choice that is not about the ADS initiation signal. No symmetry ftith other choices.

5/27/11 Question modified as noted.

95029EA2.03 E

Simplify question by getting rid of 1st sentence in the stem and just adding Stopped he procedure title into the question. Why not spell out Drywell? Is there a Here reason to use the acronym DRWL? What instruments are these and what 54 H 3 ire they used for? Is the assumption made that the applicant might think 5/27111 hat DP is converted to lvi using the procedure? Cant tell from the Jistractor analysis.

S 5/27/1 1 Changes made as noted above.

E 95030EK2.01 s this question stated correctly? Should it ask, which ONE is available?

u lso, not the best KA match. A better KA match is, if HPCI is running and 55 low water level condition occurs in the Torus. Or If a low Tours lvi exist nd an auto HPC1 signal is received...

/27/11 Question does not meet the KA. Do to conflicts with the sim and ther test questions the licensee asked for another KA to be selected.

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401 -9 1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus Dist. Link units ward KIA Only S /1/1 1 Reveiwed new question. SAT 95031 EA2.O1 56 F 2 S

.ppears to be OK.

95033EK1 295033 EK1.02 001 S question should ask for the position of F15 in the desired lineup? Can he Isolation Mode be argued as a correct answer if the applicant ssumes that the operator actions have been completed for this lineup?

Maybe the question should be reworded to imply that he should perform 57 he actions that should have auto occurred.May have to modify the H 2 uestion such that there is no doubt that the Roll Filter Bypass valve is in u he desired position. Is OPEN the normal position?

5/27/1 1 This question overlaps WI the JPM in the Control Room.

/1/11 Reviewed modification to question. SAT 95034G2.2.39 001 U

LOD: The question is 100% accurate and a novice RO from a PWR 58 F 3 :ouldnt miss this one. Recommend asking 4 different actions if isolation apability is not restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

s

/27/1 1 Reviewed and agreed w/ licensee that his is not a LOD 1 and is alid as is.

95036 EA1.04 E

59 P H Remove ONLY from A & C (Should the word MAX be in capital letters? It S

hould match the EOP flow chart) R: Changed to by themselves.

E 95037EK1.01 Distractor D not plausible.

60 H 2 X S /1/11 New distractor is more plausible. Move answer C to the D position o make the distractors flow from longest to shortest.

61 F 3 X U 95038 EA1 .03 Cred Dist: 2 part of C&D. For a system with this

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/EIS Explanation Focus Dist. Link units ward K/A Only ignificant of a flow to isolate on high rad seems to be not plausible.

lased on the description provided, if RHRSW ties into the PSW line efore being monitored, then one could argue that the discharge from the HRSW system is being monitored.

/27/1 1 System do not tie together; therefore, this is plausible as is.

62 F 2 S ooooo K2.01 001 00000 G2.1.30 001 63 F 2 00000 AK2.04 001 E

64 H 3 )red Dist: At 100%, its not very plausible to say that the reactor will not rip. Recommend making power 30% or 25%.

5/27)1 1 Recommended change made. SAT 100000 AA2.01 001 Stem Focus: Can I be within the bounds of the capability curve if Im in 65 H 3 X StE 34AB-S11-011-2? Licensee to validate plot on the graph during review.

May be ok 5/27/1 1 Reviewed on site w/ licensee. SAT 2.1.8. 001 E

66 F 2 red Dist:A not very plausible for a non-licensed operator to manipulate reactivity without direct oversight.

5/27/1 1 Distractor A revised based on the above comment.

2.1.20 001 E

67 H 2 Modify A & C to open as necessary to depressurize while maintaining ooldown rate < 100°F S

5/27/11 Changes noted per the above.

u 2.2.13 001 red Dist: Operating Permit and Danger tags co-existing on the same 68 F 2 X omponent doesnt seem plausible at all. Not placing a Danger Tag on

. op doesnt seem plausible.

5/27/1 1 Reviewed on site. SAT as is.

69 H 3 5 32.2.21 001 70 F 3 5 32.3.11 001

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only E Not sure why A could not be considered a correct answer. It the reason mu are maintain personnel accessibility is to operate plant equipment isnt his the same as maintaining equipment availability?

5/27/1 1 Changed the wording from equipment availability to operability.

32.13.12 001 Dred Dist: Can you ever make an entry at power without a tagout to prevent control rod withdrawal? If there are instances where you can, Im U )k with this Q. If not, the second part of C&D are not plausible.

The 2 sentence in the stem is not needed to answer the question.

71 F 2 X X

)uestion does not meet KA. Q71 and 72 meet KA 2.3.13. This question s for 2.3.12 (principles) not 2.3.13 (procedures) 127/1 1 The licensee revised the question to match the KA (radiological principles).

2.3.13 001 E

72 F 3 red Dist: Issuing keys to an NPO doesnt seem plausible. How about ssued from (or via) Work Control (to the NPO) or HP?

S 5/27/1 1 Slightly revised question to include Work Control in distractors.

2.4.16 001 Stem Focus: If I have one 4160 VAC bus energized, it is a station lackout? If the blackout procedure is used as guidance only as the upporting information suggests, would I actually exit it? The second part f the stem seems to lead the applicants towards station blackout since it Od 73 H 3 X S has you exiting that procedure. 2 question needs to be clarified to make 5t t separate and distinct from the 1 question. This question seems to have ots of traps. If licensee can walk through these concerns, I may be Ok.

lso, you can add the word procedure(s) to the stem of the question.

/2/1 1 Reviewed w/licensee and is SAT as is based on site specific riteria for entering blackout procedure with a loss of only one 4KV bus.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO UIEIS Explanation Focus Dist. Link units ward K/A Only 32.4.4 001 Dred Dist: D seems not too likely. Isnt 95 °F the requirement for supp 74 H 2 X E/S )ool cooling? It would seem much more plausible to have a time based n this.

5/27/11 Reviewed on site SAT.

32.4.5.001 EIJ Dred Dist: A & C dont appear to be plausible unless the licensee can give xamples of when the OP or EOP DO give guidance for notifying agencies. It just doesnt seem that these procedures would ever have this uidance.

75 F 2 X X KA: Do Nuclear Management Procedures fall under the operating

)rocedures network?

Is there a condition that would require performing an OP or AP while in the EOP? Like loss of IA AP or the OP for CRD.

5/27/1 1 Changed Distractor A from 34FH-OPS to 34AB-J1 1 to increase plausibility.

Generic Comments

1. If the stem of the question has the word correctly in it, please remove it from the question.

2. When writing questions, should it be Unit One or Unit 1?

3. need to establish a convention concerning how to emphasize adjectives. For example, underline, bold, bold and underline, etc.

SRO ONLY Questions 0 1002G2. 1.32 Is this a reasonable position for this rod to be in @ 80% pwr?

E uestion seems convoluted. We are asking if we move the rod 76 H 3 :hen if we cannot move the rod. Maybe, move the 1 question up so that it corresponds with moving the rod to its new position.

5/25/1 1 Licensee changed the power level to 60% & incorporated

he above comments.

U 05000G2.4.2O 77 H 3 S EOP Title incomplete RC RPV Control (Non-ATWS). 31EOLEOP1082,

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 Alternate RPV Depressurization does not exist within the EOP-010 ramework? Therefore, are B&D Plausible?

/25/11 Licensee changed the question to eliminate the EOP procedure election and replaced with whether or not we can use the the nstrumentation.

,,d 2

/26/1 1 Licensee made one additional change to emphasize on the art of the question that SDC is NOT available.

17000 G2.445 SRO Q#78 Licensee to show in the procedure when you have to leave RCIC isolated.

his affects the plausibility of distracters. (If more than one system was 78 P H 3 S vailable for injection is bypassing the timer still allowed? If so, include nother system to increase the plausibility of NOT bypassing the timer) icensee stated that if another system or if level was at ÷33 inches then ou would not unisolate RCIC.

5600002. 1.23 Vhen would the combination in choice C be plausible?

E 79 H 4 Reviewed again on 5/24/11. Cond & Feed is always the Preferred method S nstead of CoreSpray. Why would someone choose Core Spray?

Thanged the choice slection from CS to HPCI (HPCI Isolated on low pressure).

59002A2.04 seed C & D distractor analysis explained. Why would this be a correct

[nswer if in single element control?

th 4

80 H 4 s 5/25/1 1 Modified the bullet to remove Auto. Changed LOD rom 3 to 4.

E 62001A2.06 s the question supposed to be asking for loss of recirc loops instead of 81 H 3 recirc pumps? 3.4.2 is Jet Pumps s /25/1 1 Licensee incorporated changes.

64000 G2.2.12 SRO Q#82 82 P F 2 S Modified, where is the original question?)

/25/11 Original question was reviewed.

88000 A2.01 SRO Q#83 st Stem focus: change 1 part of answers to has/has not or should/should not or should have/should not have. The action has already happened md stating will happen/will not is future tense.

The distracter analysis for the second part of B states that [it will only be lone if necessary and as directed by the SRO. In this case it is E necessary] Im not understanding why its incorrect.

83 P H 3 X Is this why you have the 4 th th and 5 bullets? Also suggest putting U2 in he statement prior to the bulleted items: A U2 event occurs In the tern of the question, if Rx power is at 100%, do you need to state that U2 Refueling Hatch is installed? R: Yes to prevent a possible alignment uestion during the exam) This is also a modified question, where is the riginal?

i/25/1 1 Reviewed on site, SAT.

95001 G2.4.41 84 H 3 S Make sure this question does not overlap with the EPlan JPM.

5/25/1 1 Reviewed on site.

95005G2.1 .23 Have licensee show the words in NMP-EP-1 10 that represent this 85 H 3 ondition.

5/25/1 1 Reviewed on site. Modified question to clarify 2 question. SAT 95009G2.4.6 86 H 3 Is D plausible? Why would anyone consider the SAG at this point?

5/25/11 SAT 9501 8M2.03 Note: The LP only requires the applicant to know from memory the 1 & 4 87 H 3 S hr notifications. By default, w/o a reference, the answer has to be 4 hrs.

Does a loss of the two RBCCW valves cause a loss of all RBCCW?

5/25/1 1 Changed 8 hr to 1 hr and added report is required to each 2 part.

95O2OG2.4.2 adding ... concerning Rx press entry conditions for this 88 H 3 Suggest procedure to clarify that the question is referring to RCA (ATWS) EOP.

fJhat other current condition besides hi RX press is met for this EOP? If none, then the answer has to be yes for hi press being the current entry

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 ondition.

5/25/11 Reviewed on site with minor changes.

95O2lG2.l.23 u This is a mod question; therefore, I need to see the original.

89 H 3 S ot sure this is SRO Only.

5/25/1 1 Reviewed on site and agreed with licensee logic. SAT 95026EA2.01 Isnt the 1 part direct lookup? Is there any way to misinterpret this? You E re under the graph (safe area) if you interpolate or not. Not sure if the 2 90 H s )art is SRO Only?

5/251111 st part of question has now been modified. 2 part of question to sk for the procedure referenced to direct the applicable instruction.

95031 G2.2.25 SRO Q#91 (Why not use the Level 3 nomenclature throughout vs. a mix of Level 3 91 P F 2 S md +3 inches? This is a SRO question, if you give the +3inches, cannot he SRO use RO level knowledge to weed out the ECCS distractors?)

Licensee agrees with the change.

95034 EA2.02 SRO Q#92 E Licensee explains why a dropped irradiated fuel bundle will NOT give the rtated alarms. I was ok until I read the analysis, now Im not sure.

92 P H 3 X Remove ONLY from B & D. (Change the wording to make one sentence, the SRO exits 34AB-T22.... And enters 31E0...)

S (What makes this SRO Only? Not given in the plausibility analysis)

R: Performing concurrently is the SRO Only.

Z9503 8EA2.03 93 H 4 S Should the question be reworded to state that sufficient plant onditions exist to provide enough information to declare..

5/27/11 SAT 32.1.44 94 F 3 S No comment, looks OK.

32.2.23 E Why isnt the answer 10:00 on 12/26? Isnt this the more estrictive time as stated below?

The total Completion Time allowed for completing a Required Action to iddress the subsequent inoperability shall be limited to the more 95 H 4 restrictive of either:

. The stated Completion Time, as measured from the initial entry into the

)ondition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the ubsequent inoperability.

S 5/27/11 Reviewed, the licensee modified the question to ensure the uestion is stated clearly. SAT 32.2.5 u ould rule out distractors B&C since they both correlate to the 96 F 3 same reasoning.

S 5/27/1 1 Question was revised to change TRM to TRM Bases to nake plausible.

32.3. 12 skilled exam taker will know that 24 hrs is not the answer since E io reference is given.

97 H 3 d S 5/27/1 1 Licensee changed the 2 question to eliminate knowing i time. Now the question asks if, due to a mode change, if the RAS (LCO Required action statement) is still applicable.

32.3.15 SRO Q#98 E Stem focus: Change l part of question to provide a rad level and then isk if the valves are open are closed.

(Remove the from before 2T48-F and 2T48-F.., the sentence does not 98 P F 3 X make since with it in, also need to remove the comma before the and onnector. Should these valves have their nomenclature titles put in?

\lso, remove e.g., MSIV5 from the distractor, this is leading) R: will S remove and check again during validation.

5/27/11 Changes made SAT S 32.4.28 99 H 3 No comment looks OK.

U 32.4.50 100 H 3

)oes not appear to meet the KA. What actions are taken from the

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401 -9 s IARP?

15/27/11 Licensee wrote a new Is part to the question that requires tARP Knowledge.

ES-401, Rev. 9 2 Form ES-401-9

ES-403 Wriften Examination Grading Form ES-403-1 Quality Checklist

_Facility: HATCH Date of Exam: 6/23/2011 Exam Level: RO/SRO Initials Item Description a b c

1. Clean answer sheets copied before grading i

2. Answer key changes and question deletions justified and documented

3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations) 1i

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

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

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

a. Grader

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

/. 7 (3

d. NRC Supervisor (*) QJA[WU7,fA4JAJ jj ,,

1

//

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

ML112310044

Text

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