ML113340420

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Initial Exam 2011-301 Final Administrative Documents
ML113340420
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/28/2011
From:
NRC/RGN-II/DRS/OLB
To:
Progress Energy Florida
References
50-302/11-301
Download: ML113340420 (61)


Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: ((I.jm Rye,- Date of Examination:

Developed by: Written - Facility NRC D // Operating - Facility NRC D Target Chief Date* Task Description (Reference) Examiners Initials

-180 1. Examination administration date confirmed (Cia; C2.a and b)

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

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

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

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

{-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-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.i.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-3D 1-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.i.e, f, g and h; C.3.d)

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

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

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

-14 12. Examinations reviewed with facility licensee (C.1.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; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent Jj (C.2.i; Attachment 5; ES-202, C.2.e; ES-204) _I V

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

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

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

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

ES-201, Page 25 of 28

ES-201 Examination Outline Quality Checklist Form ES-201-2 2011 Crystal River NRC Exam Facility: Crystal River Unit #3 Date of Exam: 09/12/11 thru 09/23/11 Item .

Task Description V Initials b*

a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. AK MVS W b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.l R NRC NRC of ES-40l and whether all KIA categories are appropriately_sampled.

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

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

AK MVS

2. a. Using Form ES-30l-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major AK MVS transients.

S Assess whether there are enough scenario sets (and spares) to test the projected number and mix of b.

applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or AK MVS significantly modified scenario, that no scenarios are duplicated from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

A T

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. AK MVS
a. Verify that the systems walk-through outline meets the criteria of Form ES-30l-2:

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

...2) task repetition from the last two NRC examinations is within the limits specified on the fonn AK MVS

3. (3) no tasks are duplicated from the applicants audit lest(s)

A4) the number of new or modified tasks meets or exceeds the minimums specified on the form w ,.5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

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

T (1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified AK MVS (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 of applicants and ensure that no items are duplicated on subsequent days. AK MVS
a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the

. appropriate exam sections. AK MVS G b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate AK MVS

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

A e. Check the entire exam for balance of coverage. AK MVS

f. Assess whether the exam fits the appropriate job level (RO or SRO) AK MVS Printed Name / Signature Date Alan Kennedy 06-27-li
a. Author Mark VanSicklen 06-27-i I
b. Facility Reviewer (*)
c. NRC Chief Examiner (#)
d. NRC Supeivisor LhcAJI.AAwJ .,

Note: # Independent NRC reviewer initial items in Column C; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines Page 1 of I F:\NRC -201 1\Forms\Form ES-201-2 (Outline Quality Checklist) NRC 2011 Rev 0.docx ES-201

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

1. Pre-Examination for the week(s) of 09/12/11 thru 10/05/11 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled examinations to any persons who have not been as of the date of my signature. I agree that I will not knowingly divulge any information about these or provide performance feedback to those applicants scheduled to authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, examination administratio n, except as specifically noted below and be administered these licensing examinations from this date until completion of training content or r is acceptable if the individual does not select the authorized by the NRC (e.g., acting as a simulator booth operator or communicato (as documented in the facility provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements of the examinations and/or an licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation NRC chief examiner any indications or enforcement action against me or the facility licensee. I will immediately report to facility management or the suggestions that examination security may have been compromised.
2. Post-Examination NRC licensing examinations administered To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the entered into this security agreement until the completion of examination during the week(s) of 09/12/11 thru 10/05/Il. From the date thatl performance feedback to those applicants who were administered these licensing examinations, administration, I did not instruct, evaluate, or provide except as specifically noted below and authorized by the NRC.

DATE NATU E ( ) DATE NOTE PRINTED NAME JOB TITLE I RESPONSIBILITY

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 09112111 thru 10I05I11 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 09/12/11 thru 10105/11. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 09112111 thru 10/05111 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 perlormance 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 09/12/11 thru 10105/11. 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 SIGNATJJRE (1) DATE IGNATUR- ( ) DATE NOTE 1.-.,iz i- 9 -2h-/J L47f5

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 09/12/11 thru 10/05111 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 provide performance feedback to those applicants scheduled to authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or of examination administratio n, except as specifically noted below and be administered these licensing examinations from this date until completion or communicato r is acceptable if the individual does not select the training content or authorized by the NRC (e.g., acting as a simulator booth operator provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility an licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or indications or enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any 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 09112111 thru 10/05/11. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations except as specifically noted below and authorized by the NRC.

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

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M NOTES:

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 09/12/11 thru 10105111 as of the date of my signature. 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 09I1 2111 thru I 0I05I1 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

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ES-301, Rev. 9, Supp. 1 Administrative Topics Outline Form ES-301-1 Facility: Crystal River Unit #3 Date of Exam: 09/12/11 thru 09/29/11 Examination Level: RO SRO Operating Test Number: 1 (NRC)

Administrative Topic Type Describe activity to be performed (See Note) Code*

RO & SRO - (CO1) - Perform an RCS boron change calculation.

Conduct of Operations M, R K/A - G2.1.37 RO 4.3 SRO 4.6 OP-304 RO & SRO - (CO2) - Calculate SDM with a misaligned rod.

K/A - G2.1.7 RO 4.4 SRO 4.7 Conduct of Operations D, R SRO Only - After completing the SDM calculation determine required ITS actions, if any.

K/A - G2.2.40 SRO 4.7 SP-421 RO & SRO - (EC1) - Perform a QPTR calculation.

K/A - G2.2.12 RO 3.7 SRO 4.1 SRO Only - After completing the QPTR calculation Equipment Control M, R determine required ITS actions, if any.

K/A - G2.2.40 SRO 4.7 SP-303 RO & SRO - (RC1) - Determine stay times using survey maps.

Radiation Control D, R K/A - G2.3.4 RO 3.2 SRO 3.7 DOS-NGGC-0004 SRO Only - (EP1) - Determine Emergency Action Level and Protective Action Recommendations.

Emergency Procedures D, P, R K/A - 2.4.41 SRO 4.6

/ Plan K/A - 2.4.44 SRO 4.4 EM-202 All items (5 total) are required for SROs. RO applicants require only 4 items unless Note:

they are retaking only the administrative topics, when all 5 are required.

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

  • Type Codes & Criteria:

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

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

Page 1 of 1C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-301-1 (JPM Admin Outline) NRC 2011 Rev 0.docxES-301

ES-301, Rev. 9, Supp. 1 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: Crystal River Unit #3 Date of Exam: 09/12/11 thru 09/23/11 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 (NRC)

Control Room systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Type Safety System / JPM Title Code* Function

a. CRDS - Perform actions of AP-504 D, S 1 K/A - 001A4.15 RO 3.1 SRO 3.1 (AP-504) [RO]
b. ESFAS - Respond to an ES Actuation [SRO-U]

A, EN, N, S 4

K/A - BW/E03EA1.1 RO 4.1 SRO 3.8 (EOP-3) [RO, SRO-I] Primary

c. PPCS - Respond to a stuck open PZR spray valve A, D, L, P, 3

K/A - 010A4.01 RO 3.7 SRO 3.5 (AP-520) [RO, SRO-I] S

d. EFW - Establish Auxiliary Feedwater flow N, S 4

K/A - 061G2.1.20 RO 4.6 SRO 4.6 (EOP-04) [RO, SRO-I] Secondary

e. CSS - Initiate Reactor Building Spray [SRO-U]

A, L, M, S 5 K/A - 026A3.01 RO 4.3 SRO 4.5 (EM-225C) [RO, SRO-I]

f. EDG - Synchronize Off-Site Power with EDG-1A D, S 6 K/A - 064A4.09 RO 3.2 SRO 3.3 (AP-770) [RO, SRO-I]
g. CWS - Start CWP-1C While at Power [SRO-U A, D, P, S 8 K/A - 075G2.1.31 RO 4.2 SRO 3.9 (OP-604) [RO, SRO-I]
h. WGS - Respond to a Waste Gas Header leak A, D, S 9 K/A - 060AA2.05 RO 3.7 SRO 4.2 (AP-250) [RO, SRO-I]

SPARE MU - Restart a MUP following an RCS leak isolation D, S 2 K/A - 002A2.01 RO 4.3 SRO 4.4 (AP-520)

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

i. ECCS - Respond to a CFT Low Pressure condition [SRO-U]

D, E, L, R 3 K/A - 006A1.13 RO 3.5 SRO 3.7 (AP-404) [RO, SRO-I]

j. HRPS - Place a Hydrogen Analyzer in Service A, D, E, L 5 K/A - 028A4.03 RO 3.1 SRO 3.3 (EOP-14) [RO, SRO-I]
k. WGDS - Perform a Waste Gas Release to the RB [SRO-U]

D, R 9 K/A - 071G2.3.11 RO 3.8 SRO 4.3 (OP-412A) [RO, SRO-I]

SPARE FS/OTSG - Transfer excess secondary inventory to FST D, E 8 K/A - 038EK3.06 RO 4.2 SRO 4.5 (EOP-14, Enc. 9)

All RO and SRO-I 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 / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (EN)gineered safety feature (control room system) - / - />1 (L)ow Power / Shutdown >1/>1/>1 (N)ew or (M)odified from bank including 1 (A) >2/>2/>1 (P)revious 2 exams (randomly selected) <3/<3/<2 (R)CA >1/>1/>1 (S)imulator Page 1 of 1C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301

ES-301 Operating Test Quality Checklist Form ES-301-3 2011 Crystal River NRC Exam Facility: Crystal River Unit 3 Date of Exam: 09/12/11 thru 09/23/11 Operating Test No:

Initials

1. General Criteria A B*
a. The operating test conforms with the previously approved outline; changes are consistent with AK MVS sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).
b. There is no day-to-day repetition between this and other operating tests to be administered AK MVS during this examination.
c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1 a.) AK MVS
d. Overlap with the written examination and between different parts of the operating test is within AK MVS acceptable limits.
e. It appears that the operating test will differentiate between competent and less-than-competent AK MVS 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: AK MVS -

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

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

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

Printed Namyignature Date

a. Author Alan Kennedy 07/25/1 1
b. Facility Reviewer(*) Mark VanSicklen 07/26/11
c. NRC Chief Examiner(#) I Lih
d. NRC Supervisor L() T NOTE:
  • The facility signature is not applicable for NRC-developed tests.
  1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

ES-301, Rev. 9 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Crystal River Unit #3 Date of Exam: 09/12/11 thru 09/23/11 Scenario Numbers: 1 / 2 / 3 / 4 Operating Test Number: I (NRC) nitias QUALITATIVE ATTRIBUTES a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out AK MVS 4.c.

of service, but it does not cue the operators into expected events.

2. The scenarios consist mostly of related events. AK MVS
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 AK MVS

  • 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 AK MVS without a credible preceding incident such as a seismic event.
5. The events are valid with regard to physics and thermodynamics. 1,1
6. Sequencing and timing of events is reasonable, and allows the examination team to obtain AK MVS 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 N/A N/A constraints. Cues are given.

8. The simulator modeling is not altered. AK MVS
9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator perfonTlance deficiencies or deviations from the referenced plant have been evaluated to AK MVS Jk 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. AK MVS All_other_scenarios_have_been_altered_in_accordance_with_Section_D.5_ofES-301.

1 1. All individual operator competencies can be evaluated, as verified using Form ES-30 1-6 AK MVS (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and AK MVS events_specified_on_Form_ES-30l-5_(submit_the_form_with_the_simulator_scenarios).
13. The level of difficulty is appropriate to support licensing decisions for each crew position. AK MVS Target Quantitative Attributes . Actual Attributes (Per Scenario; See Section D.5.d) 1 2 3 4
1. Total malfunctions (58) 6 7 7 8
2. Malfunctions after EOP entry (12) 2 1 2 2
3. Abnormal events (24) 2 2 2 2
4. Major transients (12) 1 1 1
5. EOPs entered/requiring substantive actions (12) 2 1 2 2
6. EOP contingencies requiring substantive actions (02) 1 0 1 1
7. Critical tasks (23) 2 3 2 3 June 27,2011 E:\NRC - 2011 \EXAM Submittal\FonTl ES-30 1-4 (Scenario Quality Checklist) NRC 2011 Rev 1 .docx ES-3 01

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Crystal River #3 Date of Exam: 09/12/11 thru 09/23/11 Operating Test No.: 1 A E Scenarios - SRO-I3, SRO-I4, RO-5 P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

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

N Y O C P O C P O C P O C P R I U T P E

RO RX 4 6 2 1 1 0 NOR 1 1 1 SRO-I I-3 I/C 2/5 1/5/8 5/8 3/4/7 11 4 4 2

/8 SRO-U MAJ 7 7 5 6 4 2 2 1 TS 2/3 1/2 1/4 6 0 2 2 RX 4 6 5 3 1 1 0 RO NOR 1 1 1 1 1 SRO-I I-4 I/C 4/5/ 1/3/4 1/5/6 2/3/8 13 4 4 2 10 /7 SRO-U MAJ 7 7 5 6 4 2 2 1 TS 2/3 2 0 2 2 RO RO-5 RX 1 1 0 NOR 1 5 2 1 1 1 SRO-I I/C 4/9/

2/3/8 1/4/6 1/4/7 12 4 4 2 10 SRO-U MAJ 7 7 5 6 4 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

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

6/27/11 Page 1 of 3 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-301-5 (Transient and Event Checklist) NRC 2011 Rev 3.docx

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Crystal River #3 Date of Exam: 09/12/11 thru 09/23/11 Operating Test No.: 1 A E Scenarios - SRO-I1 & I2, RO-1, RO-2, RO-3 & RO-4 P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

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

N Y O C P O C P O C P O C P R I U T P E

RO RX 4 6 2 1 1 0 NOR 1 1 1 1 1 SRO-I I1 & 2 I/C 4/5/

1/5/8 1/4/6 2/5/8 12 4 4 2 SRO-U 10 MAJ 7 7 5 6 4 2 2 1 TS 2/3 2/3 1/4 6 0 2 2 RX 4 5 5 3 1 1 0 RO RO-1 & 3 NOR 1 1 1 1 1 SRO-I I/C 4/9/

1/5/6 2/3/8 9 4 4 2 10 SRO-U MAJ 7 7 6 3 2 2 1 TS 0 2 2 RO RO-2 & 4 RX 6 2 1 1 0 NOR 5 1 1 1 1 SRO-I I/C 2/3/ 1/3/4 5/8 1/4/7 12 4 4 2 8 /7 SRO-U MAJ 7 7 5 6 4 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

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

6/27/11 Page 2 of 3 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-301-5 (Transient and Event Checklist) NRC 2011 Rev 3.docx

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Crystal River #3 Date of Exam: 09/12/11 thru 09/23/11 Operating Test No.: 1 A E Scenarios - SRO-U1 & SRO-U2 P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

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

N Y O C P O C P O C P O C P R I U T P E

RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 3/4/7 2/5/8 6 4 4 2 SRO-U MAJ 5 6 2 2 2 1 TS 1/2 1/4 4 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 MAJ 2 2 1 SRO-U TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

3. 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.
4. 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-1 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.

6/27/11 Page 3 of 3 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-301-5 (Transient and Event Checklist) NRC 2011 Rev 3.docx

2011 Crystal River NRC Exam ES-301 Competencies Checklist Form ES-301-6 Facility: Crystal River #3 Date of Exam:09/12/11 thru 09/23/11 Operating Test No.: 1 APPLICANTS RO RO RO SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 1/2/3/ 2/3/4/5 1/2/3/ 1/2/3/ 1/2/3/5 2/3/4/5/ 1/2/3/4/ 1/2/4/5 1/2/3/5 2/3/4/5 1/2/3/4 1/2/4/5 5/6/7 /7/8/9/ 4/5/6/ 4/5/6/ /6/7 7/8/9/10 5/6/7/8/ /6/7/8 /6/7 /7/8/9/ /5/6/7/ /6/7/8 Events and Conditions 10 7 7/8 9 10 8/9 Comply With and 1/2/3/ 1/2/4/5 1/3/4/ 1/2/3/ 1/2/3/4 1/2/4/5/ 1/3/4/5/ 1/2/3/4 1/2/3/4 1/2/4/5 1/3/4/5 1/2/3/4 4/5/6/ /6/7/8/ 5/6/7 4/5/6/ /5/6/7/ 6/7/8/9/ 6/7 /5/6/7/ /5/6/7/ /6/7/8/ /6/7 /5/6/7/

Use Procedures (1) 7/8 9/10 7/8 8 10 8 8 9/10 8 Operate Control 1/2/3/ 1/4/5/6 1/3/4/ 1/2/3/ 1/2/3/4 1/4/5/6/ 1/3/4/5/ 1/2/3/4 4/5/6/ /7/8/9/ 5/6/7 4/5/6/ /5/6/8 7/8/9/10 6/7 /5/6/7/

Boards (2) 8 10 7/8 8 Communicate 1/2/3/ 1/2/3/4 1/2/3/ 1/2/3/ 1/2/3/4 1/2/3/4/ 1/2/3/4/ 1/2/3/4 1/2/3/4 1/2/3/4 1/2/3/4 1/2/3/4 4/5/6/ /5/6/7/ 4/5/6/ 4/5/6/ /5/6/7/ 5/6/7/8/ 5/6/7 /5/6/7/ /5/6/7/ /5/6/7/ /5/6/7 /5/6/7/

and Interact 7/8 8/9/10 7 7/8 8 9/10 8 8 8/9/10 8 Demonstrate 1/2/3/4 2/3/4/5/ 1/3/4/5/ 1/2/3/5 1/2/3/4 2/3/4/5 1/3/4/5 1/2/3/5

/7/8 6/7/8/9/ 7 /6/8 /7/8 /6/7/8/ /7 /6/8 Supervisory Ability (3) 10 9/10 Comply With and 2/3 2/3 1/2 1/4 2/3 2/3 1/2 1/4 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

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

6/9/2009 5:36 AM Form ES-301-6 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-301-6 (Competencies Checklist) NRC 2011 Rev 0.docx

ES-401 SRO - PWR Examination Outline - (Sept, 2011) Form ES-401-2 Facility: Crystal River Unit #3 Date of Exam: September, 2011 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G TOTAL A2 G* TOTAL 1 2 3 4 5 6 1 2 3 4

  • 1 18 3 3 6 1.

Emergency

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

Plant 2 10 2 1 3 Systems Tier 38 5 3 8 Totals

3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 7 2 2 1 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 that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section d.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in 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.

June 21, 2011 Page 1 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 007EA2.04 - Ability to determine or interpret the following as they apply to a reactor trip: If 007 (BW/E02 & E10) reactor should have tripped but has not done so, Reactor Trip - Stabilization X manually trip the reactor and carry out actions 4.6

- Recovery - 1 in ATWS EOP (not linked to 10CFR55.43) 008 Pressurizer Vapor Space Accident / 3 009 Small Break LOCA / 3 011 Large Break LOCA / 3 015/17 RCP Malfunctions /4 022 Loss of Rx Coolant Makeup / 2 025 Loss of RHR System / 4 026 Loss of Component Cooling Water / 8 027 PZR Pressure Control System Malfunction / 3 029 ATWS / 1 038EG2.4.20 - Knowledge of operational 038 Steam Generator Tube Rupture / 3 X implications of EOP warnings, cautions, and 4.3 notes: Steam Generator Tube Rupture BW/E05EA2.1 - Ability to determine and 040 (BW/E05) Steam Line interpret the following as they apply to Rupture - Excessive Heat X Excessive Heat Transfer: Facility conditions 4.2 Transfer / 4 and selection of appropriate procedures during abnormal and emergency operations.

054 Loss of Main Feedwater

/4 June 21, 2011 Page 2 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 055 Station Blackout / 6 056 Loss of Offsite Power /

6 057AA2.06 - Ability to determine and interpret 057 Loss of Vital AC the following as they apply to the Loss of Vital Instrument Bus / 6 X AC Instrument Bus: AC instrument bus alarms 3.7 for the inverter and alternate power source.

058 Loss of DC Power / 6 062AG2.2.36 - Ability to analyze the effect of 062 Loss of Nuclear maintenance activities, such as degraded power Services Water / 4 X sources, on the status of limiting conditions for 4.2 (Raw Water/RW) operations: Loss of Nuclear Services Water (RW) 065 Loss of Instrument Air /

8 BW/E04 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 077 Generator Voltage and 077AG2.2.37 - Ability to determine operability Electric Grid Disturbances / X and/or availability of safety related equipment: 4.6 6 Generator voltage and electric grid disturbances K/A Category Totals 3 3 Group Point Total 18/6 June 21, 2011 Page 3 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 001 Continuous Rod Withdrawal / 1 003AA2.02 - Ability to determine and interpret the following as they apply to the Dropped 003 Dropped Control Rod / 1 X Control Rod: Signal inputs to rod control 2.8 system 005 Inoperable/Stuck Rod /

1 024 Emergency Boration / 1 028 PZR Level Malfunction

/2 032 Loss of Source Range NI / 7 033 Loss of Intermediate Range NI / 7 036 (BW/A08) Fuel Handling Accident / 8 037 Steam Generator Tube Leak / 3 051 Loss of Condenser 051AA2.02 - Ability to determine and interpret Vacuum / 4 the following as they apply to the Loss of X Condenser Vacuum: Conditions requiring 4.1 reactor and/or turbine trip 059 Accidental Liquid RadWaste Rel. / 9 060 Accidental Gaseous Radwaste Rel. / 9 061 ARM System Alarms / 7 June 21, 2011 Page 4 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 067 Plant Fire On-site / 8 068 (BW/A06) Control Room Evac. / 8 069 Loss of CTMT Integrity

/5 074 Inad. Core Cooling / 4 076 High Reactor Coolant Activity / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel BW/A05AG2.2.12 - Knowledge of surveillance X procedures: Emergency Diesel actuation 4.1 Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08 LOCA Cooldown - BW/EO8EG2.4.18 - Knowledge of the specific Depress. / 4 X bases for EOPs: LOCA Cooldown / 4.0 Depressurization BW/E09 Natural Circ. / 4 K/A Category Totals 2 2 Group Point Total 9/4 June 21, 2011 Page 5 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump / 4 004 Chemical and Volume Control / 1 & 2 005 Residual Heat Removal / 4 006 Emergency Core Cooling / 2 & 3 007 PZR Relief/Quench Tank / 5 008G2.4.41 - Knowledge of the emergency 008 Component Cooling X action level thresholds and classifications: 4.6 Water / 8 SW / DC cooling 010A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based 010 Pressurizer Pressure X on those predictions, use procedures to 3.6 Control / 3 correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures 012 Reactor Protection /

7 013 Engineered Safety Features Actuation / 2 022A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on 022 Containment X those predictions, use procedures to correct, 2.6 Cooling / 5 control, or mitigate the consequences of those malfunctions or operations: Fan motor vibration June 21, 2011 Page 6 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 026A2.08 - Ability to (a) predict the impacts of the following malfunctions or operations on the BSS; and (b) based on 026 Containment Spray /

those predictions, use procedures to correct, 5 X control, or mitigate the consequences of 3.7 those malfunctions or operations: Safe securing of containment spray, when it can be done 039 Main and Reheat Steam / 4 059G2.1.25 - Ability to interpret reference 059 Main Feedwater / 4 X materials, such as graphs, curves, tables, 4.2 etc.: Main Feedwater 061 Auxiliary /

Emergency Feedwater /

4 062 AC Electrical Distribution / 6 063 DC Electrical Distribution / 6 064 Emergency Diesel Generator / 6 073 Process Radiation Monitoring / 7 076 Service Water / 4 078 Instrument Air / 8 103 Containment / 5 K/A Category Totals 3 2 Group Point Total 28/5 June 21, 2011 Page 7 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 034 Fuel Handling Equipment / 8 035 Steam Generator / 4 041 Steam Dump/Turbine Bypass Control / 4 045 Main Turbine Generator / 4 055 Condenser Air Removal / 4 056 Condensate / 4 068 Liquid Radwaste / 9 071G2.2.38 - Knowledge of conditions and 071 Waste Gas Disposal X limitations in the facility license: Waste 4.5

/9 Gas disposal 072 Area Radiation Monitoring / 7 075 Circulating Water /

8 079 Station Air / 8 086 Fire Protection / 8 K/A Category Totals 2 1 Group Point Total 10/3 June 21, 2011 Page 9 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive /

1 002 Reactor Coolant / 2

&4 011 Pressurizer Level Control / 2 014 Rod Position Indication / 1 015A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on 015 Nuclear X those predictions, use procedures to correct, 3.8 Instrumentation / 7 control, or mitigate the consequences of those malfunctions or operations: Core void formation 016 Non-nuclear Instrumentation / 7 017 In-core Temperature Monitor / 7 027 Containment Iodine Removal / 5 028 Hydrogen Recombiner and Purge Control / 5 029A2.01 - Ability to (a) predict the impacts of the following malfunctions or 029 Containment Purge / operations on the Containment Purge 8 System; and (b) based on those predictions, X use procedures to correct, control, or 3.6 mitigate the consequences of those malfunctions or operations: Maintenance or other activity taking place inside containment 033 Spent Fuel Pool Cooling / 8 June 21, 2011 Page 8 of 9 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (SRO Written Exam Outline) NRC 2011 (401-2) Rev 0.docx

ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 SRO - 2011- Crystal River 3 Facility: Crystal River Unit #3 Date of Exam: September, 20 II I RO SRO-Only Category KIA # Topic I I I I IR I # I IR I # I Knowledge of administrative requirements for temporary management directives, such as standing 2.1.15 orders, night orders, Operations memos, etc. 3.4 I (not linked to IOCFR55.43)

1. Ability to locate control room switches, controls Conduct of and indications and to determine that they are Operations 2.1.31 correctly reflecting the desired plant lineup. 4.3 I (not linked to IOCFR55.43)

Subtotal 2 Knowledge of the process for conducting special or 2.2. 7 infrequent tests. 3.6 I

2. Knowledge of maintenance work order 2.2.19 requirements. 3.4 I Equipment Control Subtotal 2 Knowledge of radiation exposure limits under 2.3.4 normal or emergency conditions. 3.7 I 3.

Radiation Control Subtotal 1 Knowledge of how abnormal operating procedures 2.4.8 are used in conjunction with EOPs. 4.5 I

4. Knowledge of RO tasks performed outside the Emergency 2.4.34 main control room during an emergency and the 4.1 I Procedures I resultant operational effects.

Plan Subtotal 2 I Tier 3 Point Total I I 10 I I 7 I June 27, 201IF:\NRC - 201 1\Outlines\Written\SRO NRC 2011 Written Exam Outline - Generic (401-3) Rev O.docx

ES-401 RO Form ES-401-2 Facility: Crystal River Unit #3 Date of Exam: September, 2011 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G TOTAL A2 G* TOTAL 1 2 3 4 5 6 1 2 3 4

  • 1 3 3 3 3 3 3 18 6 1.

Emergency

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

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

3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 7 3 3 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 that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section d.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in 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.

June 21, 2011 Page 1 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 007 (BW/E02 & E10) 007EK3.01 - Knowledge of the reasons for the Reactor Trip - Stabilization X following as they apply to a reactor trip: 4.0

- Recovery - 1 Actions contained in EOP for reactor trip 008AK3.02 - Knowledge of the reasons for the following responses as they apply to the 008 Pressurizer Vapor Space Accident / 3 X Pressurizer Vapor Space Accident: Why PORV 3.6 or code safety exit temperature is below RCS or PZR temperature 009EK1.01 - Knowledge of the operational implications of the following concepts as they 009 Small Break LOCA / 3 X apply to the Small Break LOCA: Natural 4.2 circulation and cooling, including reflux boiling 011EK2.02 - Knowledge of the interrelations 011 Large Break LOCA / 3 X between the Large Break LOCA and the 2.6 following: Pumps 015/017AG2.4.46 - Ability to verify that the 015/17 RCP Malfunctions /4 X alarms are consistent with the plant conditions: 4.2 RCP malfunctions 022 Loss of Rx Coolant Makeup / 2 025AK1.01 - Knowledge of the operational implications of the following concepts as they 025 Loss of RHR System / 4 X apply to Loss of Decay Heat Removal System: 3.9 Loss of DH System during all modes of operation 026 Loss of Component Cooling Water / 8 027AA2.15 - Ability to determine and interpret 027 PZR Pressure Control the following as they apply to the Pressurizer System Malfunction / 3 X Pressure Control Malfunctions: Actions to be 3.7 taken if PZR pressure instrument fails high June 21, 2011 Page 2 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 029EK2.06 - Knowledge of the interrelations 029 ATWS / 1 X between the ATWS and the following: 2.9 Breakers, relays and disconnects 038 Steam Generator Tube 038EA1.32 - Ability to operate and monitor the Rupture / 3 X following as they apply to a SGTR: Isolation of 4.6 a ruptured S/G 040 (BW/E05) Steam Line 040AG2.4.3 - Ability to identify post-accident Rupture - Excessive Heat X instrumentation: Steam Line Rupture. 3.7 Transfer / 4 054AA1.04 - Ability to operate and /or monitor 054 Loss of Main Feedwater the following as they apply to the Loss of Main

/4 X Feedwater (MFW): HPI, under total feedwater 4.4 loss conditions 055EK3.01 - Knowledge of the reasons for the following responses as the apply to the Station 055 Station Blackout / 6 X Blackout: Length of time for which battery 2.7 capacity is designed 056AK1.04 - Knowledge of the operational implications of the following concepts as they 056 Loss of Offsite Power /

6 X apply to Loss of Offsite Power: Definition of 3.1 saturation conditions, implication for the systems 057 Loss of Vital AC Instrument Bus / 6 058AG2.4.9 - Knowledge of low power /

058 Loss of DC Power / 6 shutdown implications in accident (e.g. LOCA X or loss of DH) mitigation strategies: Loss of 3.8 DC Power 062AA2.02 - Ability to determine and interpret 062 Loss of Nuclear Services Water / 4 X the following as they apply to the Loss of Raw 2.9 Water: The cause of possible RWS loss 065AA2.01 - Ability to determine and interpret 065 Loss of Instrument Air / the following as they apply to the Loss of 8

X Instrument Air: Cause and effect of low 2.9 pressure instrument air alarm June 21, 2011 Page 3 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 BW/E04EK2.2 - Knowledge of the interrelations between the (Inadequate Heat Transfer) and the following: Facilitys heat BW/E04 Inadequate Heat removal systems, including primary coolant, Transfer - Loss of X emergency coolant, the decay heat removal 4.2 Secondary Heat Sink / 4 systems, and relations between the proper operation of these systems to the operation of the facility.

077AA1.03 - Ability to operate and/or monitor 077 Generator Voltage and the following as they apply to Generator Electric Grid Disturbances / X Voltage and Electric Grid Disturbances:

3.8 6

Voltage regulator controls K/A Category Totals 3 3 3 3 3 3 Group Point Total 18 June 21, 2011 Page 4 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 001 Continuous Rod Withdrawal / 1 003AK3.06 - Knowledge of the reasons for the following responses as they apply to the 003 Dropped Control Rod / 1 X Dropped Control Rod: Reset of relative 2.7 position indication to zero 005AK1.06 - Knowledge of the operational 005 Inoperable/Stuck Rod / implications of the following concepts as they 1

X apply to Inoperable / Stuck Control Rod: Bases 2.9 for power limit for rod misalignment 024 Emergency Boration / 1 028AA1.02 - Ability to operate and / or 028 PZR Level Malfunction monitor the following as they apply to the

/2 X Pressurizer Level Control Malfunctions: MU 3.4

& P System 032AK2.01 - Knowledge of the interrelations between the Loss of Source Range Nuclear 032 Loss of Source Range Instrumentation and the following: Power NI / 7 X supplies, including proper switch positions 2.7 (Electrical interlocks - PR or IR failures de-energizing SR OK per MAB, 2-23-11) 033 Loss of Intermediate Range NI / 7 036 (BW/A08) Fuel Handling Accident / 8 037 Steam Generator Tube Leak / 3 051 Loss of Condenser Vacuum / 4 059 Accidental Liquid RadWaste Rel. / 9 June 21, 2011 Page 5 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 060 Accidental Gaseous Radwaste Rel. / 9 061 ARM System Alarms / 7 067 Plant Fire On-site / 8 068 (BW/A06) Control Room Evac. / 8 069AK2.03 - Knowledge of the interrelations 069 Loss of CTMT Integrity between the Loss of Reactor Building Integrity

/5 X and the following: Personnel access hatch and 2.8 equipment access hatch 074 Inad. Core Cooling / 4 076 High Reactor Coolant Activity / 9 BW/A01 Plant Runback / 1 BW/A02AA1.2 - Ability to operate and / or BW/A02&A03 Loss of NNI- monitor the following as they apply to the Loss X of NNI-X: Operating behavior characteristics 3.4 X/Y / 7 of the facility.

BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07AK1.2 - Knowledge of the operational implications of the following concepts as they BW/A07 Flooding / 8 X apply to Flooding: Normal, abnormal and 3.3 emergency operating procedures associated with Flooding.

June 21, 2011 Page 6 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / K K K A A G K/A Topic(s) IR Safety Function 1 2 3 1 2 BW/E03EA2.2 - Ability to determine and interpret the following as they apply to BW/E03 Inadequate Inadequate Subcooling Margin: Adherence to X appropriate procedures and operation within the 3.5 Subcooling Margin / 4 limitations in the facilitys license and amendments.

BW/E08 LOCA Cooldown -

Depress. / 4 BW/E09 Natural Circ. / 4 BW/E09EG2.4.6 - Knowledge of EOP X mitigation strategies: Natural Circulation 3.7 BW/E13&E14 EOP Rules and Enclosures K/A Category Totals 2 1 2 2 1 1 Group Point Total 9 June 21, 2011 Page 7 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 003A3.01 - Ability to monitor automatic 003 Reactor Coolant X operation of the RCPS including: Seal 3.3 Pump / 4 injection flow.

004K1.35 - Knowledge of the physical connections and/or the cause-effect relationships between the MU & P system X and the following system: Understanding of 2.5 004 Chemical and interface with the LRS (Liquid Radwaste Volume Control / 1 & 2 System)

(MU & P System) 004A1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding X design limits) associated with operating the 3.8 MU & P controls including: RCS pressure 005A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding X design limits) associated with operating the 3.5 DHR system controls including: Heatup /

cooldown rates 005 Residual Heat Removal / 4 005A4.05 - Ability to manually operate and/or monitor in the control room:

X Position of BWST recirculation valve 2.8 (locked when not in use, continuously monitored when in use).

006K4.18 - Knowledge of ECCS design 006 Emergency Core feature(s) and/or interlock(s) which provide X for the following: Valves normally isolated 3.6 Cooling / 2 & 3 from their control power 007K5.02 - Knowledge of the operational 007 PZR Relief/Quench implications of the following concepts as Tank / 5 X they apply to the RCDT: Method of 3.1 (RCDT) forming a steam bubble in the PZR 008K2.02 - Knowledge of bus power 008 Component Cooling X supplies to the following: SW / DC pump, 3.0 Water / 8 including emergency backup June 21, 2011 Page 8 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 008K3.01 - Knowledge of the effect that a (SW & DC) loss or malfunction of the SWS / DCS will X have on the following: Loads cooled by 3.4 SWS / DCS 010A1.07 - Ability to predict and/or monitor changes in parameters (to prevent 010 Pressurizer Pressure X exceeding design limits) associated with 3.7 Control / 3 operating the PZR PCS controls including:

RCS pressure.

012K6.04 - Knowledge of the effect of a 012 Reactor Protection / X loss or malfunction of the following will 3.3 7 have on the RPS: Bypass-block circuits 013K5.02 - Knowledge of the operational 013 Engineered Safety implications of the following concepts as X they apply to the ESFAS: Safety system 2.9 Features Actuation / 2 logic and reliability.

022K2.01 - Knowledge of power supplies 022 Containment X to the following: Reactor Building cooling 3.0 Cooling / 5 fans 026K1.01 - Knowledge of the physical connections and/or cause-effect X relationships between the BSS and the 4.2 following systems: ECCS 026 Containment Spray / 026K4.02 - Knowledge of BSS design 5 feature(s) and/or interlock(s) which provide for the following: Neutralized boric acid to X reduce corrosion and remove inorganic 3.1 fission product iodine from steam (TSP) in reactor building spray 039A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on 039 Main and Reheat predictions, use procedures to correct, X control, or mitigate the consequences of 3.4 Steam / 4 those malfunctions or operations:

Indications and alarms for main steam and area radiation monitors (during SGTR)

June 21, 2011 Page 9 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 059A3.06 - Ability to monitor automatic 059 Main Feedwater / 4 X operation of the MFW, including: 3.2 Feedwater isolation 061K2.01 - Knowledge of bus power 061 Auxiliary /

X supplies to the following: EFW system 3.2 Emergency Feedwater /

MOVs 4

062K3.03 - Knowledge of the effect that a 062 AC Electrical loss or malfunction of the AC distribution X system will have on the following: DC 3.7 Distribution / 6 system 063K3.02 - Knowledge of the effect that a loss or malfunction of the DC electrical X system will have on the following:

3.5 Components using DC control power 063 DC Electrical Distribution / 6 063K4.01 - Knowledge of DC electrical system design feature(s) and/or interlock(s)

X which provide for the following:

2.7 Manual/automatic transfers of control 064A3.02 - Ability to monitor automatic operation of the ED/G system, including:

Minimum time for load pickup X (MCB indications / MVAR loading limits 3.4

/ how to adjust if outside of limits. OK 064 Emergency Diesel per MAB, 02-23-11)

Generator / 6 064K6.08 - Knowledge of the effect that a loss or malfunction of the following will X have on the ED/G system: Fuel oil storage 3.2 tanks 073A4.03 - Ability to manually operate and/or monitor in the control room: Check X source for operability demonstration 3.1 073 Process Radiation (same KA as 2009 NRC)

Monitoring / 7 073G2.4.3 - Ability to identify post-X accident instrumentation: Process radiation 3.7 monitoring system June 21, 2011 Page 10 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 076G2.1.28 - Knowledge of the purpose 076 Service Water / 4 X and function of major system components 4.1 (RW / CW) and controls: RW / CW system 078A4.01 - Ability to manually operate 078 Instrument Air / 8 X and/or monitor in the control room: 3.1 Pressure gauges 103A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the reactor building system 103 Containment / 5 and (b) based on those predictions, use X procedures to correct, control, or mitigate 2.9 the consequences of those malfunctions or operations: Emergency reactor building entry K/A Category Totals 2 3 3 3 2 2 3 2 3 3 2 Group Point Total 28 June 21, 2011 Page 11 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 001K5.88 - Knowledge of the following operational implications as they apply to the CRDS: Effects of boron on the temperature 001 Control Rod Drive / coefficient.

X (Effects of temperature change on boron 2.9 1

concentration (makeup demins) /

relationship to rod movement. OK per MAB, 02-23-11) 002 Reactor Coolant / 2

&4 011K3.03 - Knowledge of the effect that a 011 Pressurizer Level X loss or malfunction of the PZR LCS will 3.2 Control / 2 have on the following: PZR PCS 014K4.06 - Knowledge of RPIS design 014 Rod Position feature(s) and/or interlock(s) which provide X for the following: Individual and group 3.4 Indication / 1 misalignment.

015 Nuclear Instrumentation / 7 016 Non-nuclear Instrumentation / 7 017A4.01 - Ability to manually operate 017 In-core Temperature X and/or monitor in the control room: Actual 3.8 Monitor / 7 in-core temperatures 027 Containment Iodine Removal / 5 028 Hydrogen Recombiner and Purge Control / 5 029K1.04 - Knowledge of the physical connections and/or cause-effect relationships between the Containment 029 Containment Purge / Purge System and the following systems:

X Purge System 3.0 8

(Interlocks between purge valves/purge fans / containment rad monitors OK per MAB, 02-23-11)

June 21, 2011 Page 12 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 K K K K K K A A A A System # / Name G K/A Topic(s) IR 1 2 3 4 5 6 1 2 3 4 033 Spent Fuel Pool Cooling / 8 034A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System; 034 Fuel Handling X and (b) based on those predictions, use 3.3 Equipment / 8 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Mispositioned fuel element 035 Steam Generator / 4 041A3.05 - Ability to monitor automatic 041 Steam X operation of the Turbine Bypass Valves, 2.9 Dump/Turbine Bypass including: Main steam pressure Control / 4 045G2.4.6 - Knowledge of EOP mitigation 045 Main Turbine X strategies: Main turbine generator 3.7 Generator / 4 055 Condenser Air Removal / 4 056 Condensate / 4 068K6.10 - Knowledge of the effect of a loss or malfunction on the following will 068 Liquid Radwaste / 9 X have on the Liquid Radwaste System:

2.5 Radiation monitors 071 Waste Gas Disposal

/9 072 Area Radiation Monitoring / 7 075K2.03 - Knowledge of bus power 075 Circulating Water / X supplies to the following: Emergency / 2.6 8 essential RW System pumps 079 Station Air / 8 086 Fire Protection / 8 K/A Category Totals 1 1 1 1 1 1 0 1 1 1 1 Group Point Total10 10 June 21, 2011 Page 13 of 13 C:\Users\pcapeh60\Desktop\WORK\2011 CR\Form ES-401-2 (RO Written Exam Outline) NRC 2011 Rev 3.docx

ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 RO - 2011- Crystal River 3 Facility: Crystal River Unit #3 Date of Exam: September, 2011 KJA# Topic RO SRO-Only Category IR # IR #

Ability to manage the control room crew during 2.1.6 plant transients. 3.8 I Ability to use plant computers to evaluate system or 2.1.19 component status. 3.9 I I.

Conduct of Ability to perform specific system and integrated Operations 2.1.23 plant procedures during all modes of plant 4.3 I operation.

Subtotal 3 Ability to manipulate the console controls as 2.2.2 required to operate the facility between shutdown 4.6 I and designated power levels.

Knowledge of the process for managing

2. 2.2.17 maintenance activities during power operations. 2.6 I Equipment Control 2.2.21 Knowledge of pre- and post-maintenance operability requirements. 2.9 I Subtotal 3 Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 I conditions.

3.

Radiation 2.3.II Ability to control radiation releases. 3.8 I Control Subtotal 2 Ability to recognize abnormal indications for system operating parameters which are entry-level 2.4.4 conditions for emergency and abnormal operating 4.5 I procedures.

4.

Emergency Ability to diagnose and recognize trends in an Procedures / 2.4.47 accurate and timely manner utilizing the 4.2 I Plan appropriate control room reference material.

Subtotal 2 ITier 3 Point Total I I 10 I I 7 I June 21, 20 II F:\NRC - 2011 \Outlines\Written\RO NRC 2011 Written Exam Outline - Generic (401-3) Rev O.docx

ES-401 Record of Rejected K/As Form ES-401-4 RO - 2011- Crystal River 3 Tier/ Randomly Reason for Rejection Group Selected K/A Not applicable to CR3. PZR PCS has no effect on RCP seal 1/1 027AA2.14 injection flow. NRC randomly selected 027AA2.15 to use as a replacement. - MAB 3/7/2011 Too close to SRO 038EG2.4.20. Only NOTES in EOP applicable to SRO level knowledge deal with OTSG level limits.

1/1 038EA1.44 NRC randomly selected 038EA1.32 to use as a replacement. -

MAB 3/7/2011 Not possible to prepare a psychometrically sound question related to this KA. Only SPO/PPO tasks dealing with a steam line 1/1 040AG2.4.35 rupture are to de-energize EFW and CFT valves. NRC randomly selected 040AG2.4.3 to use as a replacement. - MAB 3/7/2011 Not applicable to CR3. No EOP entry conditions or immediate 1/1 058AG2.4.1 actions steps for loss of DC power. NRC randomly selected 058AG2.4.9 to use as a replacement. - MAB 3/7/2011 Not applicable to CR3. No RO EOP guidance for loss of RB 1/2 069AK3.01 integrity. NRC randomly selected 069AK2.03 to use as a replacement. - MAB 3/7/2011 Not possible to prepare a psychometrically sound question related to this KA. Not an RO knowledge requirement at CR3 to make 1/2 BW/E09EG2.4.30 reports to external agencies due to plant being on Natural Circulation. NRC randomly selected BW/E09EG2.4.6 to use as a replacement. - MAB 3/7/2011 Not applicable to CR3. No surveillance test for isolating DH 2/1 005A1.06 suction valves. NRC randomly selected 005A1.01 to use as a replacement. - MAB 3/7/2011 Not applicable to CR3. No automatic actions based on MFWP 2/1 059A3.03 suction pressure. NRC randomly selected 059A3.06 to use as a replacement. - MAB 3/7/2011 Not applicable to CR3. No EOP guidance for containment iodine 2/2 027G2.4.6 removal. NRC randomly selected 045G2.4.6 to use as a replacement. - MAB 3/7/2011 Not possible to prepare a psychometrically sound question related 2/1 007A1.03 to this KA. NRC randomly selected 004A1.03 to use as a replacement. - MAB 6/22/11 Not applicable to CR3. No post-accident process radiation 2/1 073G2.4.3 monitors. NRC randomly selected 073G2.4.11 to use as a replacement. - PC 08/25/11 August 31, 2011 E:\NRC - 2011\POST PREP Week 31-11\Written Outlines\Form ES-401-4 (RO Rejected KAs - Written) NRC 2011_FINAL.docx

ES-401 Record of Rejected K/As Form ES-401-4 SRO - 2011 - Crystal River 3 Tier/ Randomly Reason for Rejection Group Selected K/A Not an SRO duty at CR3. Reactor engineering performs this function.

1/2 003AA2.05 Replaced with 003AA2.02 per MAB, 03-31-11.

Not possible to prepare a psychometrically sound question related to this KA. Only one EOP step that deals with inoperable/stuck control rods with the action to borate the RCS. All operators know that 1/2 005AG2.4.18 ensuring adequate SDM is the reason for this step.

Replaced with BW/E08EG2.4.18 per MAB, 04-01-11.

Not applicable to CR3. RB Spray pumps take a suction from the BWST / RB sump and spray into containment. There is no recirc path back to the 2/1 026A2.09 BWST to create a radiation hazard.

Replaced with 026A2.08 per MAB, 03-31-11.

Not applicable to CR3. NRC randomly selected 2/2 029A2.01 029A2.03 to use as a replacement. - PC 08/25/11 August 31, 2011 E:\NRC - 2011\POST PREP Week 31-11\Written Outlines\Form ES-401-4 (SRO Rejected KAs - Written) NRC 2011_FINAL.docx

2011 Crystal River NRC Exam ES-401 Written Examination Quality Checklist Form ES-401-6 Date of Exam: 09112111 thru 09123111 Exam Level: RD SRO Facility: Crystal River Unit 3 Initial a b* c#

Item Description AK MVS

1. Questions and answers are technically accurate and applicable to the facility.
2. a. NRC K/As are referenced for all questions. AK MVS
b. Facility learning objectives are referenced as available.

AK MVS

3. SRO 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 RD or 2 SRO questions were_repeated_from_the_last_2_NRC_licensing_exams,_consult_the_NRR_CL_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 AK MVS the examinations were developed independently; or the licensee certifies that there is no duplication; or other (explain)

Bank use meets limits (no more than 75 percent Bank Modified New 6.

from the bank, at least 10 percent new, and the rest AK MVS new or modified); enter the actual RD I SRO-only 42 / 10 0/0 33 /15 question_distribution(s)_at_right.

Between 50 and 60 percent of the questions on the RD Memory C/A 7.

exam are written at the comprehension/ analysis level; AK MVS the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter 36 / 8 39 I 17 the_actual_RD_/_SRO_question_distribution(s)_at_right.

8. References/handouts provided do not give away answers AK MVS or aid in the elimination of distractors.
9. Question content conforms with specific K/A statements in the previously approved AK MVS examination outline and is appropriate for the tier to which they are assigned; deviations are justified.

AK MVS

10. Question psychometric quality and format meet the guidelines in ES Appendix B.
11. The exam contains the required number of one-point, multiple choice items; AK MVS the total is correct and agrees with the value on the cover sheet.

Printed Name / Date Alan Kennedy tt 07/25/11

a. Author

(*) Mark VanSicklen 07/26/11

b. Facility Reviewer
c. NRC Chief Examiner (#) .ji1,l1
d. NRC Regional Supervisor r.\JlrL&lM/ i ,i Note:
  • The facility reviewers initials/signature are not applicable for NRC-developed examinations.
  1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

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

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 sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6. 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?
7. 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 LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 1 H 2 S 001K5.88 New 003A3.01 New Licensee to verify that on a loss of NNI-X, other valves/equipment failures 2 H 2 X S will NOT result in a change in seal injection flow.

CR3 - No change in seal injection flow. Verified on simulator 8-21-11.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 003AK3.06 New Cred Dist: A & B Not plausible because nothing was changed to parameters that give the lamp/alarm.

CR3 - Dist A: RPI provides the input for the Sequence Inhibit indication/lamp. It seems plausible that resetting RPI to match API could 3 F 2 X S clear this alarm/lamp.

CR3 - Dist B: Plausible misconception since a 7 inch delta is required for this alarm. Resetting RPI to match API removes this delta.

C should include some part of the TS. ensure that API and RPI agree with the limit specified in the COLR CR3 - Dist C: Modified C as recommended 004A1.03 New Cred Dist: A & C, 273 degrees would be much more plausible as it is the temperature stated in OP 209. A & B licensee explain why it would be plausible to assume that all of the MUPs would be secured at this point.

4 F 2 X S CR3 -All MUP knife switches are opened in Mode 5.

Do MUVs 23/24/25/26 constitute ALL HPI valves? Step 4.2.3.5 states that these are the valves that are tagged.

CR3 - These are the only 4 HPI valves.

CR3 - Modified stem and first part of all distracters.

004K1.35 New Stem Focus: Does a LOOP always result in a loss of power to the MUDM isolation valves. Is the reactor still at power? C could be the correct answer if on-site power is still there.

CR3 - A LOOP always results in a loss of power to the MUDM isolation valves, until the EDGs load on the bus, and a reactor trip.

5 H 2 X X S Cred Dist: C. If LD is not isolated, why would I think that there would be a release path created?

B. If LD is isolated, why would I think that a relief would not be lifting?

Is there an interface between the MU&P system and the LRS without going through the AB sump.that you could write a question to?

CR3 - No other interface between the MU & P system and the LRS.

CR3 - Following discussion no changes made to question.

005A1.01 Bank 6 F 2 S

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 7 F 2 S 005A4.05 New 005AK1.06 Bank Cred Dist: Explain why 60% and minimize local fuel temperature gradients are plausible. 3.1.4 states 60% as a power limit. Is this where the 60%

comes from?

8 F 2 X S CR3 - 60% is the power limit with 4 RCPs running, 45% is the limit with 3 RCPs running.

Recommend: to ensure DNB limits are not exceeded.

nd CR3 - Changed 2 part of distracters A & B to peaking due to Xenon oscillations.

006K4.18 New Cred Dist: Having to choose between a LBLOCA or a SBLOCA for CFT requirement makes the SBLOCA not plausible.

Stem Focus: energized in the open position doesnt make a lot of sense 9 F 1/2 X S the way it is written.

Recommend having when the valves are to be de-energized and then maybe the tagging requirements for the valves.

CR3 - Completely re-worded stem and all choices.

007EK3.01 Bank Cred Dist: D second part not plausible since the control rods are out now and Xenon will take hours to build in.

CR3 - Second part of distractor reworded to remove Xenon.

C second part is not plausible with the stated conditions (no steam leak).

CR3 - The RCS lowers approximately 25 degrees post trip.

10 H 3 X S If the NIs dont indicate shutdown (they should) the IAs would have you borate. With the information provided in the stem (or lack of), A may be correct. Need more information in the stem to eliminate A.

CR3 - A is incorrect because the reason for an RCS Boration during the performance of the Immediate Actions is to shutdown the reactor, not to ensure adequate SDM.

CR3 - Added NI indication to stem to ensure A distractor can be eliminated.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 007K5.02 New Cred Dist: D, if level is 290, then I already have a bubble.

CR3 - Dont always have a steam bubble with this level.

11 F 2 X S Change C to From a solid condition, the PZR is heated CR3 - This will change the symmetry of the distracters.

CR3 - Following discussion no changes made to question.

008AK3.02 Bank LOD: GFES question. Make 1/2 of this question plant specific. Give 12 F 1 S conditions that indicate a leak in the top of the PZR and ask for proceduresomething like that.

CR3 - Modified stem and first part of A & B distractors.

008K2.02 New Cred Dist: B there are no actions taken. With the conditions stated, it doesnt seem that taking no action is plausible. Would like to see each answer with just actions (dump the ensure.).

13 H 3 X S Licensee to walk through this question.

CR3 - B distractor would be correct if the BEST was lost.

CR3 - Modified all distractors.

14 H 3 S 008K3.01 Mod 009EK1.01 Bank Cred Dist: D, at 455 psig, LPI is not plausible (if pressure were 225 psig maybe. Something closer to LPIP shutoff head)

CR3 - Lowered RCS pressure in stem.

With respect to RCPs, what is considered adequate subcooling margin.

15 H 2 X S At what subcooling margin are RCPs required to be secured?

Reflux boiling should be not correct because your 3 degrees subcooled.

The analysis states that it could be correct later in the accident. If conditions degraded I would agree. If you assume that at 3 degrees, I am effectively saturated, and without additional information in the stem, how can you say that you dont currently have reflux boiling?

CR3 - Modified all stem conditions and added reference.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 010A1.07 New Cred dist: C & D RCS pressure lowering not plausible on SASS output failing low.

A may not be correct. Manual control of PZR heaters are not required if spray is used. There is not enough information in the stem to eliminate spray being used.

16 H 2 X X X S Part: B could be correct. The stem doesnt limit the actions to a procedure. Operation of the PORV and spray will prevent a high pressure trip.

The stem of this question needs more information to help make the selected correct answer black and white.

CR3 - Modified stem and all distractors.

011EK2.02 Bank 17 H 3 S Licensee to walk through in procedure CR3 - Following discussion no changes made to question.

011K3.03 Bank Stem Focus: The stem should state that Pzr is at the program level for 18 H 2 X S 100% or something that will make sure that they could not challenge the initial level.

CR3 - Following discussion no changes made to question.

012K6.04 New Stem Focus: Do I need ONLY? Is bypassing A & C turbine trip bypass 19 F 2 X S bistables a condition that I would procedurally be allowed to do?

CR3 - Following discussion no changes made to question.

20 H 2 S 013K5.02 Bank 21 F 3 S 014K4.06 Mod 22 H 2 S 015/017AG2.4.46 Bank 23 F 1/2 S 017A4.01 Bank

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 022K2.01 New Are Ventilation MCC 3A and 3B normally powered from the 480V Turbine 24 F 2 S Aux Buses?

CR3 - Yes CR3 - Following discussion no changes made to question.

025AK1.01 Bank Cred Dist: D Even with not much information in the stem, BWST gravity feed is not plausible.

Part: A Do the DH system pumps serve as LPI pumps? Assuming the suction is from the RCS during DH mode you can assume that RCS pressure is somewhat higher but just going into the DH mode is not specific enough? Would like to see a pressure or the status of RCPs. I assume they have to come off at a set pressure/curve.

25 H 2 X X S B For HPI cooling, does there have to be an open vent path or just a path available. AP 404 reads as if you just vent with the PORV as necessary to prevent exceeding the LTOP limit.

While it should be obvious that cooling with the OTSGs is preferred, its not obvious from reading the stem that A or B is incorrect.

Get with licensee to shore up the stem of the question to ensure that there is only ONE correct answer and replace D.

CR3 - Added IAW AP-404 to stem and replaced D distractor.

026K1.01 Bank Cred Dist: A/ With one train bypassed/reset and nothing done to the other train, both trains not starting is not plausible.

C/ If nothing is done to the B train equipment, ONLY A train starting is not 26 H 3 X S plausible. Nothing was done to the B train equipment so an answer that doesnt include the B train equipment starting doesnt seem plausible.

CR3- Modified stem to state that both ES trains were bypassed per Rule 2.

026K4.02 Bank Cred Dist: C & D/ Since these are design features and not really a parameter that is controlled, they dont seem plausible. Picking chemicals 27 F 2 X S and addition methods could be a way to go for a 2/2 taken twice. i.e.

Boron or TSP added by staging in the sump or added via chem.

Addsomething like that.

CR3 - Modified question as recommended.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 027AA2.15 Bank Cred Dist: A & C/ Tripping the reactor may be a required action but stating 28 H 2 X S that it will stop the pressure decrease is not plausible. Just swapping in different action would make this question SAT.

CR3 - Modified second part of distractors A & C as recommended.

028AA1.02 Bank Stem Focus: The stem states that the Pzr level xmitter fails mid-scale.

The analysis for the correct answer states what happens when the xmitter fails low. Licensee to clarify. Can licensee verify this actually happens on 29 H 3 X S the simulator? Would you expect the applicants to know that while Pzr level will increase, it wont increase enough to cause a high pressure trip?

CR3 - Question verified correct on simulator. Following discussion no changes made to question.

029EK2.06 Bank Cred Dist: A & C/ Contacts opening when in parallel with contacts that are 30 F 2 X S closed will not cause a reactor trip.

CR3 - Modified all distractors following discussion.

029K1.04 Bank Cred Dist: B/ Having a fan operating with its discharge valve/damper closed is not plausible. This is effectively the discharge valve for AHF-31 F 2 X S 6A/6B is it not? Are there any vent fans at CR that will stay operating if their discharge damper closes?

CR3 - These fans have recirc dampers and are normally started with this valve closed. Following discussion no changes made to question.

32 F 3 S 032AK2.01 Bank 034A2.03 New Cred Dist: C & D/ To have a TS action required when the TS LCO is not being violated is not plausible.

33 H 2 X S CR3 - Second part of C & D are NOT TS required actions. Second part of C is required per FP-203. Second part of D is a reasonable action to take if a fuel assembly is placed incorrectly.

CR3 - Modified stem and slightly modified distractors for clarity.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 038EA1.32 Bank Stem Focus: The step asks what criteria satisfied prior to implementing TRACC. Assuming that implementing means initiating Enclosure 12, 34 H 3 X S ensuring that RCS pressure is performed after TRACC is implemented (step 12.2). Is this stated in the EOP before implementing Enclosure 12?

If not, the stem needs to be modified to reflect this.

CR3 - Modified stem for clarity.

039A2.03 New 35 H 2 S Need to verify on conversion table.

CR3 - Verified on conversion table. No changes made to question 040AG2.4.3 New Is it enough to state that a steam line rupture inside containment has occurred. Is A correct if ACC conditions do not exist yet. The stem needs 36 H 2 X S to be more detailed in that A has to be correct and D is not.

CR3 - A always correct for most reliable post accident information. No changes made to question.

041A3.05 Bank Stem Focus: Is being at 870 psig operationally valid? Would I ever be 37 F 2 X S here? What was my original setpt.

CR3 - Following discussion no changes made to question.

38 F 2 S 045G2.4.6 New 054AA1.04 New Stem Focus: Try to work in MUV-26 (4) into the answers or there is no reason to have it in the stem.

A (1&2) or (3&4) and either 5 or 6 39 F 2 X S B (1&3) or (2&4) and either 5 or 6 C (1&2) or (3&4) and (5&6)

D (1&3) or (2&4) and (5&6)

Something to this effect.

CR3 - Modified D distractor as recommended.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 055EK3.01 New Licensee to discuss designed vs required. It is designed for 2 hr per TS 40 F 2 S bases. It is required for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per EOP 12.

CR3 - Modified stem as recommended.

056AK1.04 New nd st Stem Focus: The 2 part seems disconnected from the 1 part. If Tc is rising toward where it should be going to, why would you open the ADV?

I understand what it will do, it just seems like its something you wouldnt 41 H 3 X X S do under the current conditions.

KA: Dont think this defines saturated conditions and implications on systems.

CR3 - Following discussion no changes made to question.

42 H 3 S 058AG2.4.9 New 059A3.06 New Cred Dist: C / Dont think that the B MFWP running is plausible. Discuss 43 H 3 S just the A MFWP and valve.

CR3 - Modified stem slightly and all distractors.

44 F 2 S 061K2.01 Bank 062AA2.02 Bank Stem Focus: Is there a ES 4160V lockout at this time? The analysis hints at it. If its a lockout, you would have to reset it manually correct. Need to 45 H 3 X S discuss.

CR3 - There is an ES 4160V lockout for this condition but this lockout does not affect the status of the RWPs.

CR3 - Following discussion no changes made to question.

46 H 3 S 062K3.03 New 47 F 2 S 063K3.02 Bank

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 063K4.01 New Part: D & C/ A kirk-key is a mechanical interlock which makes C a subset 48 F 2 X S of D. i.e. if it were a kirk-key interlock, I could pick C and still be correct.

Need to distinguish C as different than a Kirk Key interlock.

CR3 - Modified C and D distractors.

064A3.02 New Are the applicants required to know the KW and MVAR acceptance criteria?

49 F 1/2 S A & D are GFES. Having 2600 kW and 1.4 MVAR would seem to be more discriminating. Will discuss.

CR3 - Changed VAR loading to +2.0 064K6.08 Bank K/A: Declaring the DGs INOP is not really an effect on the system. How 50 F 2 X S about the TS as half and how long the DGs could run as the other half?

CR3 - Following discussion no changes made to question.

065AA2.01 New Cred Dist: C & D/ Its not plausible to think that the alarm would be in with one compressor running and not in with no compressors running. This is 51 H 2 X S sort of a subset issue. The analysis explains why only one compressor is plausible for the electrical configuration but not why its plausible to have a low pressure alarm with one compressor running.

CR3 - Modified stem and all distractors.

52 F 2 S 068K6.10 New 069AK2.03 Bank Cred Dist: A/ No action in Mode 4 is not plausible. Rec: Must immediately verify the outer door is closed. This would mean a change to B to 53 F 2 X S eliminate a subset issue. Must verify the outer door is closed any time within the next hour. Something like that.

CR3 - Following discussion no changes made to question.

073A4.03 Bank 2009 NRC If there are some RMs at CR that have an electronic check source, Im ok 54 F 2 S with it.

CR3 - Hi range detectors use an electronic check source.

CR3 - Following discussion no changes made to question.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only 073G2.4.3 New KA: The KA asks for a process radiation monitor and the question is written for an area radiation monitor. I did not see any process rad 55 55 F 2 X S monitors listed in the TS Bases table 3.3.17-1. Rec New KA.

CR3 - New KA provided by examiner. 073G2.4.11 CR3 - Replaced question.

075K2.03 Bank Cred Dist: Why is A plausible? If power were < 80%, would A be correct?

56 56 F 3 X S CR3 - Yes, if the stem didnt state which transformer was feeding the Unit buses.

CR3 - Following discussion no changes made to question.

57 F 2 S 076G2.1.28 New 58 F 2 S 077AA1.03 New 59 59 F 1/2 S 078A4.01 New 103A2.05 New Cred Dist: A&B/ radio notification may plausible unless (in this case) your 60 60 F 2 X S comparing it to containment evacuation alarm. B&D/ opening a containment door against dp as an interlock doesnt sound plausible.

CR3 - Modified stem and second part of all distractors.

61 61 F 2 S BW/A02AA1.02 New BW/A07AK1.2 Mod Stem Focus: C&D/ they dont read correctly with the stem.

62 62 F 3 X X S Cred Dist: D/ Tripping the turbine before the reactor - Not plausible CR3 - Modified C & D distractors and re-ordered.

BW/E03EA2.2 Bank NRC 2009 Exam 63 63 H 3 X S Stem Focus: Should have trend on RCS pressure.

CR3 - Added trend to stem as recommended.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only BW/E04EK2.2 Bank 64 64 F 1 S LOD: GFES knowledge CR3 - Following discussion no changes made to question.

BW/E09EG2.4.6 Bank Cred Dist: A/ Not plausible that inventory would be an issue when cooling 65 65 F 2 X S down at the Natural Circ rate. Not plausible that maintaining DT is a basis for cooldown rate.

CR3 - Following discussion no changes made to question.

G2.1.19 Mod Cred Dist: Using avg NI would give you 717 MW th which would seem 66 F 2 X S more plausible than using MWe in A. Using the lowest NI power is not conservative and not plausible.

CR3 - Modified as recommended.

67 H 3 S G2.1.23 Bank 2009 NRC G2.1.6 Bank 68 L 1 S LOD: I have a hard time calling this a 2.

CR3 - Replaced question.

G2.2.17 Bank 69 L 2 X S Cred Dist: B&D/ Explain why + 36 hr and + 48 hr are plausible.

CR3 - Modified stem and 2 distractors.

70 H 2 S G2.2.2 Bank 71 F 2 S G2.2.21 New G2.3.11 Bank 2009 NRC Stem Focus: Add to the question a part about which procedure is used.

.from the RB and which procedure will be used to direct these actions.

72 H 2 X S As the question is now, D also looks correct because it would describe actions necessary to terminate the release.

CR3 - Slightly modified stem and each distractor for clarity.

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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only G2.3.7 Bank LOD: Plant Access training 73 L 1/2 X S Cred Dist: Change C to 80 minutes based on staying at the spot long enough to get 100 mr.

CR3 - Modified C distractor as recommended.

G2.4.4 Mod Cred Dist: At 70%, there is little doubt that you will tripnot plausible.

74 H 2 X S Would the answer be the same if power were 35%, what about 25%.

CR3 - Following discussion no changes made to question.

G2.4.47 Bank Cred Dist: A&C / leak not plausible based on the stated conditions.

75 H 2 X X S Stem Focus: Is there a relief in any of the systems that may lift if temperature were to get too high There needs to be more in the stem to make A & C more plausible or find a different 1/2 distractor.

CR3 - Replaced question.

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.
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 #/ Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward K/A Only SRO ONLY Questions 003AA2.02 This question is labeled as MOD at the top and listed as NEW at the bottom. Which is it? If Modified, where is the original question its modified from? Licensee clarified that all mod questions should be labeled as bank. No questions on the exam were modified. Either bank or new.

This question is stated as reactor power must be reduced. TS 76B 3.1.4 provides the operator with an option to verify SDM or (1) S lower power level. Stem should be reworded to say that the lowering power option is the choice selected. This question is similar to question 10 on the RO exam. Verify there is no double jeopardy.

CR3 - TS 3.1.4 requires verifying SDM within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND reducing power to 60% of allowable.

CR3 - Verified NO double jeopardy.

007EA2.04 Need to reword 1st two distractors to make symmetrical with the final two choices to improve plausibility.

77B In the stem of the question, you state that the PORV opened and (2) X S operated as designed. With this statement there, why is B plausible.

CR3 - Discussed with Chief Examiner. NO changes made.

008G2.4.41 Verify DCP terminology. Are these DC panels? It so, it does not match the terminology used in the DC LP (i.e.

78N DPDP-1A, DPDP-1B)

(3) S CR3 - DCP is the acronym for Decay Heat Closed Cycle Cooling Pump.

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 010A2.01 Should C say Normal PZR. Heater and D say 79N Emergency PZR heater?

(4) S CR3 - Discussed with Chief Examiner. NO changes made.

015A2.05 Could lower be argued as also being correct. Is the time of voiding limited enough to rule out that indicated NI level 80N has not started to decrease? Change to say starts to rise.

(5) S CR3 - Change made to question and reviewed with Chief Examiner.

022A2.02 Are A & B plausible? You can use logic to deduce that using the OP will always provide guidance to isolate the system and is therefore the correct answer.

81N (6) X S 8/10/11 Reviewed w/ licensee on phone conference. Licensee agreed to look at rewording question to make A & B plausible.

CR3 - Change made to A & B distracters to address use of another OP instead of the AR.

026A2.08 Check this KA. It does not match the sample plan.

82B The sample plan shows this as 026A2.09. Did not see a rejected (7) S KA list.

CR3 - Verified to be correct K/A IAW sample plan.

029A2.01 Does not match the KA. The reference provided suggests the entire EM-0225 will be given. This will make the question a direct lookup. Licensee asked for another KA to be selected. Could replace with 029A2.03 or 029A2.04. Found a previous bank question for KA 029A2.01 (QID 20179, 10/29/2001 Byron):

The following conditions exist on Unit 1:

- Unit 1 is in MODE 1.

- All RCFCs are in HIGH speed.

83B - Containment air sample results require a purge of containment to allow maintenance.

(8) X S

- Containment release package has appropriate approvals.

- Mini-Flow Purge Exhaust Isolation Valves (1VQ005A, B and C) are OPEN.

- Mini-Flow Purge Supply Isolation Valves (1VQ004A, and B) are OPEN.

The operator takes the control switch for the Mini-Flow Purge Supply Fan to "START" and then IMMEDIATELY releases the switch to the "NAC" position. The Mini-Flow Purge Supply fan . . .

A: Does NOT Start. The operator must hold the start switch in the start position until the suction damper, 1VQ01Y, is OPEN.

D1: Does NOT Start. The operator must start the Mini-Flow Purge Exhaust fan first. D2: Starts CR3 - New question developed tied to K/A 029A2.03 and reviewed with Chief Examiner.

038EG2.4.20 It does not appear that the current cooldown rate is needed to answer the question? Is there a time when you ONLY steam the nonaffected SG? Why not raise the B SG lvl and 84B change two of the distractors to say this, otherwise why are A &

(9) X S C plausible? Why would you choose to steam a LLL SG over a SG that has a high level?

CR3 - Discussed with Chief Examiner. NO changes made.

051AA2.02 Reword C &D to match A &B. i.e. Ensure the 85N SG/RX Demand station in HAND or AUTO and (10) S Concurrently CR3 - C & D distracters re-worded to match A & B.

057AA2.06 Need comma With the alarm still in, . Question is poorly constructed. You are asking for what alarm should 86N be in based on the given plant conditions.

(11) S CR3 - Question modified to address construction issues and reviewed with Chief Examiner.

059G2.1.25 Why 10 min. later? Following the MFT trip, FW 87N temp is expected to stabilize at ____.

(12) S CR3 - Replaced 10 min later with stabilize in question stem.

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 062AG2.2.36 Need to be walked through the 3.0.3 conditions. I do not see them. Also, you are only given out the 3.8.1 TS as a reference. If the other 3.0.3 condition is due to 3.7.9 it would 88N need to be given also.

(13) S CR3 - Question modified and reviewed with Chief Examiner.

Question no longer addresses LCO 3.0.3 and no longer requires a reference.

071G2.2.38 Distractor A does not make sense. You say it can not be repaired in the stem of the question. Then in choice A you say it must be repaired. Change A to say once an indicated flow 89B measurement can be established.

(14) X S CR3 - Removed statement from question stem concerning inability to repair the release flow monitor. Also, re-ordered answers shortest to longest in length. A is now the correct answer.

077AG2.2.37 This is another 3.0.3 question. Q# 3 & 13 are also 90N 3.0.3 questions.

(15) S CR3 - Discussed with Chief Examiner. Question #13 no longer addresses LCO 3.0.3.

BW/A05AG2.2.12 B & D not plausible. Subset issue. . 20 seconds is a subset of 35 seconds therefore if 20 sec. is correct, 35 sec. is always correct. Why is the 2nd part of the question not 91N asking the 67 second criteria for HPI w/ a LOOP? The time (16) X S setpoints could then be 35 or 67 seconds CR3 - Added maximum to question stem to address subset issue. Discussed plausibility of 20 seconds with Chief Examiner.

BW/E05EA2.1 Does not meet the KA. The correct response has to be associated with the Excessive Heat Removal EOP. Cant 92B meet the KA by not being in the EOP.

(17) X S CR3 - Question replaced with one that has EOP-05 as the correct answer and reviewed with Chief Examiner.

93N (18) S BW/E08EG2.4.18 Looks OK.

G2.1.15 The wording of D seems to overly imply that it is not 94B implausible. Why in ONLY needed. If it is not, remove it to (19) S make the sentence structure the same as C.

CR3 - Modified D and reviewed with Chief Examiner.

95N G2.1.31 Is the 1st sentence necessary? Seems to be teaching.

(20) S CR3 - Discussed with Chief Examiner. NO changes made.

96N (21) S G2.2.19 Looks OK 97N (22) S G2.2.7 Looks OK 98B (23) S G2.3.4 G2.4.34 Shouldnt it state that levels are above their minimum 99N levels.

(24) S CR3 - Modified B and C to state NAT CIRC setpoint.

Re-ordered answers shortest to longest in length.

G2.4.8 Change this question to give an actual event that mandates the use of an AP in conjunction with an EOP.

100B (25) S CR3 - Question replaced with one addressing an actual event using EOPs/APs and reviewed with Chief Examiner.

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

ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Crystal River Date of Exam: 9/22/201 1 Exam Level: ROISRO Initials a b c Item Description

1. Clean answer sheets copied before grading -
2. Answer key changes and question deletions justified and documented
3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail
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/Signature Date
a. Grader Daniel Bacon /
b. Facility Reviewer(*) NA
c. NRC Chief Examiner (*) Phillip Capeha /

A

d. NRC Supervisor (*) Bruno Caballero /

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