ML17193A926

(U1) 2016-301 Exam Administrative Items - Delay Release

ML17193A926
Person / Time
Site:	Summer
Issue date:	07/12/2017
From:	NRC/RGN-II
To:	South Carolina Electric & Gas Co
References
Download: ML17193A926 (71)

Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: V,C- S.\e (L)/* 1) Dateof Examination:

Developed by: Written: Facility RI NRC II Operating Facility NRC Target Task Description (Reference) Examiners ate Initials

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

-150 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

-150 3. Facility contact briefed on security and other requirements (C.2.c) gL.

-150 4. Corporate notification letter sent (C.2.d)

[-120] 5. Reference material due (C.1.e; C.3.c; Attachment 3) rJt

(-90] 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1, ES-401-1/2, ES-401N-1/2, ES-401-3, ES-401N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; C.3.d)

(-85) 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)

{-60] 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES 301-5, ES-301-6, and ES-401-6, ES-401N-6, and any Form ES-201-2, ES-201-3, ES-301-1, or ES-301-2 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

-45 9. Written exam and operating test reviews completed. (C.3.f)

-30 10. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)

-21 1 1. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-21 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

-14 13. Final license applications due and Form ES-201-4 prepared (Cli; C.2.i; ES-202)

-14 14. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 15. Facility licensee management queried regarding the licensees views on the examination. (C.2 j)

-7 16. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

-7 17. Proctoring/wriffen exam administration guidelines reviewed with facility licensee (C.3.k)

-7 18. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

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

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

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Date of Examination:

Initials Item Task Description

1. a. Verity that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401N. T R b. Assess whether the outline was systematically and randomly prepared in accordance with

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

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

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. 7JL

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

M b. Assess whether there are enough scenario sets (and spares) to test the projected number and u mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T applicants audit test(s), and that scenarios will not be repeated on subsequent days. 1

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.

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed W among the safety functions as specified on the form A (2) task repetition from the last two NRC examinations is within the limits specified on the form L (3) no tasks are duplicated from the applicants audit test(s)

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

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

(1) the tasks are distributed among the topics as specified on the form G

U (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

. (J.

H Determine if there are enough different outlines to test the projected number and mix of

c.

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

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

b. Assesswhetherthe 10 CFR 55.41/43 and 55.45 sampling is appropriate. 4 F

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

R d. Check for duplication and overlap among exam sections. tIl L e. Check the entire exam for balance of coverage. E!L f.__Assess_whether the_exam_fits_the_appropriate_job_level_(RO_or_SRO).

a. Author

(*)

b. Facility Reviewer

c. NRC Chief Examiner (#)

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

Not applicable for NRC-prepared examination outlines.

O U 0 ES-201 Examination Security Agreement Form ES-207-3

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of W/- 4(II. 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 auth rized 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 m To the best of my knowlecjge1 I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during SI) the week(s) of - Wl71 IC. From the date that I entered into this security agreement until the completion of examination administration, I did not N) 0 instruct, evaluate, or provid performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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a I 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 oft e 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 knowege, I cud not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of %ICftC-gçt4 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.

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a 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) ofCJ(ft /t/ I/o 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 m To the best of my nowleçlge1 I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during 0) r) the week(s) ofqf . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or prvide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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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) /Irl t3/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 m To the best of my fr>iowled,ge, did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during cc) the week(s) of// 41fl/tt . From the date that I entered into this security agreement until the completion of examination administration, I did not C instruct, evaluthe( or prdvidé performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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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 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 knowle,dge, J d1d not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of//l y1ftFrom the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or Flrdvide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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GOLDSTEIN, RICHARD From: Linda Stewart <Iindastewart74@gmail.com>

Sent: Tuesday, June 21, 2016 8:33 AM To: GOLDSTEIN, RICHARD

Subject:

Re: Security Statement

• • • This is an EXTERNAL email. Please do not click on a link or open any attachments unless you are confident it is from a trusted source.

I agree.

Linda Stewart (803) 361-3525 On Jun 21, 2016, at 7:49 AM, GOLDSTEIN, RICHARD <Richard.Goldstein@scana.com> wrote:

Dear Linda,

We have completed the administration of the Initial License Examination for class 14-01. As required by NUREG-1021, Operator Licensing Examination Standards for Power Reactors, we are required to close out the security agreement for that exam.

Please review the statement below and respond with a statement of your compliance with security requirements. A response of I agree will suffice if you fully complied.

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 June 6, 2016 and June 13, 2016. 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.

1

ES-30f Administrative Topics Outline Form ES-3d-f Facility: V.C. Summer Date of Examination: 6/6/201 6 Examination Level: RD SRO E Operating Test Number: NRC-ILO-14-01 Administrative Topic Type Describe activity to be performed (see Note) Code*

ROISRO Common Conduct of Operations Determine the volume required to be available in the holdup tanks to accommodate dilution of the RCS to the Al -a1 D R estimated critical boron concentration.

(JPA-021A(C)N16) K/A: 2.1.25 (RO: 3.9, SRO: 4.2)

K/A: 2.1.37 (RO: 4.3, SRO: 4.6)

Conduct of Operations Determine if offsite power source voltages are within specifications in accordance with plant procedures.

(Al-b) N,S K/A: 2.1.32 (RO: 3.8, SRO: 4.0)

(JPA-050-(R)N1 6)

Perform a manual Reactor Coolant leak rate Equipment Control (\)

M,R surveillance calculation.

(JPA81D(R)N16) K/A: 2.2.12 (RO: 3.7, SRO: 4.1)

Radiation Control (A3) ROISRO Common M,R Determine worker stay times.

(JPA-042-(C)Nl6) K/A: 2.3.7 (RO: 3.5, SRO: 3.6)

Emergency Plan (A4) Not selected for RD.

NOTE: All items (five total) are required for SROs. RD applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Administrative Topics Outline Form ES-301-l JPM

SUMMARY

STATEMENTS CONDUCT OF OPERATIONS (Al-a): This is a bank JPM. The plant will be in Mode 3 pending Reactor start up. A current RCS boron concentration and the estimated critical boron concentration will be provided along with a copy of the Curve Book. The candidate will determine the volume required to be available in the holdup tanks to accommodate dilution of the RCS to the estimated critical boron concentration. This JPM will be modified from JPMs in the bank by changing the current and critical boron concentrations. (JPA-021A-(C)N16)

K/A 2.1.25: Ability to interpret reference materials such as graphs, curves, tables, etc.

(R0: 3.9, SRO: 4.2)

K/A 2.1.37: Knowledge of procedures, guidelines, or limitations associated with reactivity management. (RO: 4.3, SRO: 4.6)

VCS Task: 0-004-006-01-01, Perform Boric Acid Concentration Change Calculations.

CONDUCT OF OPERATIONS (Al-b): This is a new JPM. The candidate will be required to analyze power distribution to safety-related buses and determine whether voltages from 115KV and 230KV sources are within limits in accordance with operating procedures. (JPA-050-(R)N16)

K/A 2.1.32: Ability to explain and apply system limits and precautions, (RO: 3.8, SRO: 4.0)

VCS Task: 0-62-004-01-01, Monitor the AC Electrical Distribution System.

EQUIPMENT CONTROL (A2): This is a modified version of a JPM from the bank. Given values for plant parameters, the candidate will calculate a Reactor Coolant System leak rate. (JPA 81 D-(R)N16)

K/A 2.2.12: Knowledge of surveillance procedures. (RO: 3.7, SRO: 4.1)

VCS Task: 0-002-002-02-01, Perform an RCS Leakrate Calculation with The IPCS Unavailable, lAW STP-1 14.002.

ES-301 Administrative Topics Outline Form ES-301-1 RADIATION CONTROL fA3): This is a modified JPM. Given a radiation work permit, a survey map and worker exposure histories, the candidate will determine if workers can perform the required tasks without an extension of administrative limits. (JPA-042-(C)N16)

K/A 2.3.7: Ability to comply withradiation work permit requirements during normal or abnormal conditions. (RO: 3.5, SRO: 3.6)

VCS Task: 0-508-001-02-04, Perform Radiological Controlled Area Entry.

EMERGENCY PLAN (A4): Not selected for RO.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: V.0. Summer Date of Examination: 6/6/2016 Examination Level: RO E SRO Operating Test Number: NRC-ILO-14-01 Administrative Topic (see Type Describe activity to be performed Note) Code*

ROISRO Common Conduct of Operations Determine the volume required to be available in the holdup tanks to accommodate dilution of the RCS to (Al-a) DP,R the estimated critical boron concentration.

(JPAO2IA(C)N16) K/A: 2.1.25 (RO: 3.9, SRO: 4.2)

K/A: 2.1.37 (RO: 4.3, SRO: 4.6)

Determine if offsite power sources meet Conduct of Operations specifications and determine the applicable action (Al-b) N,R statement.

(JPA-051-(S)N16) K/A: 2.1.32 (RO: 3.8, SRO: 4.0)

K/A: 2.2.40 (RO: 3.4, SRO: 4.7)

Perform a manual Reactor Coolant leak rate Equipment Control (A2) surveillance calculation and apply technical M R specifications.

(JPA-81D-(S)Nl6) K/A: 2.2.12 (RO: 3.7, SRO: 4.1)

K/A: 2.2.40 (RO: 3.4, SRO: 4.7)

Radiation Control (A3) ROISRO Common M,R Determine worker stay times.

(JPA-042-fC)N16)

K/A: 2.3.7 (RO: 3.5, SRO: 3.6)

Declare a General Emergency in accordance with Emergency Plan (A4) EPP-00l and complete the EPP-002 notification form.

N R (JPA-1007-(S)N16) K/A: 2.4.40 (RO: 2.7 ,SRO: 4.5)

K/A: 2.4.41 (RO: 2.9 SRO: 4.6)

NOTE: All items (five total) ate requited for SROs. RO applicants requite only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

(P)tevious 2 exams f I; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-l 1PM

SUMMARY

STATEMENTS CONDUCT OF OPERATIONS (Al-a): This is a bank JPM. The plant will be in Mode 3 pending Reactor start up. A current RCS boron concentration and the estimated critical boron concentration will be provided along with a copy of the Curve Book. The candidate will determine the volume required to be available in the holdup tanks to accommodate dilution of the RCS to the estimated critical boron concentration. (JPA-021A-(C)N16)

K/A 2.1.25: Ability to interpret reference materials such as graphs, curves, tables, etc.

(RO: 3.9, SRO: 4.2)

K/A 2.1 .37: Knowledge of procedures, guidelines, or limitations associated with reactivity management. (RO: 4.3, SRO: 4.6)

VCS Task: 0-004-006-01-01, Perform Boric Acid Concentration Change Calculations.

CONDUCT OF OPERATIONS (Al-b): This is a new JPM. Given a partially completed copy of an electrical distribution system surveillance, the candidate will determine if offsite power sources meet requirements and then determine the applicable action statement(s). (JPA-051-(S)N16)

K/A 2.1.32: Ability to explain and apply system limits and precautions. (RO: 3.8, SRO: 4.0)

K/A 2.2.40: Ability to apply Technical Specifications for a system. (RO: 3.4, SRO: 4.7)

VCS Tasks: 0-062-004-01-01, Monitor the AC Electrical Distribution System.

0-119-015-03-01, Apply Tech Spec Requirements.

EQUIPMENT CONTROL (A2): This is a modified version of a JPM from the bank. Given values for plant parameters, the candidate will calculate a Reactor Coolant System leak rate and apply Technical Specifications. (JPA-81 D-(S)N 16)

K/A 2.2.12: Knowledge of surveillance procedures. (RO: 3.7, SRO: 4.1)

K/A 2.2.40: Ability to apply Technical Specifications for a system. (RO: 3.4, SRO: 4.7)

VCS Tasks: 0-002-002-02-01, Perform an RCS Leakrate Calculation with the IPCS Unavailable lAW STP-1 14.002.

0-11 9-01 5-03-01, Apply Tech Spec Requirements.

ES-301 Administrative Topics Outline Form ES-301-1 RADIATION CONTROL (A3): This is a modified JPM. Given a radiation work permit, a survey map and worker exposure histories, the candidate will determine if workers can perform the required tasks without an extension of administrative limits. (JPA-042-(C)N 16)

K/A 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions. fRO: 3.5, SRO: 3.6)

VCS Task: 0-508-001-02-04, Perform Radiological Controlled Area Entry.

EMERGENCY PLAN (A4): This is a new JPM. The candidate will declare a General Emergency in accordance with EPP-001, Activation and Implementation of Emergency Plan.

The candidate will make the declaration due to an inadequate core cooling event that results in the Fuel Clad Barrier and the Reactor Coolant System Barrier and a potential loss of the Containment Barrier. The candidate will also be required to complete the EPP-002, Communication and Notification, Attachment I, Nuclear Power Plant Notification Form. This is a time critical JPM. (JPA-1 007-fS)N 16)

K/A 2.4.41: Knowledge of the emergency action level thresholds and classifications.

(RO: 2.9, SRO: 4.6)

K/A 2.4.40: Knowledge of the SROs responsibilities in emergency plan implementation.

(RO: 2.7, SRO: 4.5)

VCS Task: 0-343-063-03-02, Classify Given Several Events, Determine The Emergency Action Level For Each Event, lAW EPP-001.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: V.C. Summer Date of Examination: 6/6/2016 Exam Level: RO SRO-l SRO-U Operating Test No.: NRC-ILO-14-01 Control Room Systems:8 for RO; 7 H 3hc1-l; or 3 fr O-U System / JPM Title Type Code* Safety Function APE 24: Emergency Boration (JPSF-086-N16)

a. A,D,L,S 1 Initiate Emergency Boration due to two stuck rods following a Reactor Trip. (Alternate Path)

System 004: Chemical and Volume Control System (JPSF-046-N16) b, A,D,S 2 Transfer In-Service Charging Pump (Alternate Path)

W/E03: LOCA Cooldown and Depressurization (JPSF-142A-N16)

c. Isolate the SI Accumulators and depressurize the B SI Accumulator A,D,L,S 3 by venting due to a failed open discharge isolation valve. (Alternate Path)

EPE 011: Large Break LOCA (JPS-002A-N16)

d. D,EN,L,S 4P Initiate Hot Leg Recirculation following a LOCA.

W/E 13: Steam Generator Overpressuce (JPSF-149B-N16)

e. A,L,M,S 4S Respond To Steam Generator Overpressure. (Alternate Path)

W/E 16: High Containment Radiation (JPSF-1003-N16)

f. A,S,L,N 5 Respond to High RB Radiation Level. (Alternate Path)

APE 033: Loss of Intermediate Range Nuclear Instrumentation (JPSF-029A-N16) A,D,L,S 7 g.

Loss of Intermediate Range Instrumentation. (Alternate Path)

System 029: Containment Purge System (CPS) (JPS-1001-N16)

h. D,L,P,S 8 Establish Reactor Building Purge Supply and Exhaust.

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

. Genetic System 013 (JPP-006B-N16)

E,L,N 2 Locally_Reset_SI_lAW SOP-112._(B_Train_Only)

. Generic Abnormal Plant Evolution 040 (JPP-107A-N16)

D,EL,P 4S Locally De-energize and Close MS Loop B and C to the Turbine Driven_Emergency_Feedwater_Pump_(EOP-3.0,_E-2)

, Generic APE 063 (]PP-052A-N16)

D,R 6 Startup The Swing Battery Charger and Place on DPN 1 HA.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

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

Type Codes Criteria for RD i ;io-l / sI-.o-u ] RD (A)ernatepath - 4-6/4-6I2- -

} 6 -

(C)ontrolroom .,--- --.-.-.- - -

(D)irect from bank 91h4 j 8 (E)mergency orabnormal in-plant 1 Jl/1 -.

2 (EN)gineered safety feature / L.°1i°° system) - ] 1 (L)ow-Power/Shutdown -

1 LI.._ I.

(N)ewor(M)odifiedfrornbankincludtngl(A) 2/?C/ .

(P)revious2exams 3I :i2 (randomly selected) 2 fR)CA -

1 / 1 / 1 - - -

J 1 (S)imulator J VC SUMMER NRC 1PM

SUMMARY

a. This is a bank JPM. The plant has tripped with two control stuck fully withdrawn. The candidate will be directed to implement EQ P-i .1, Reactor Trip Recovery, step 5 Verify all Control Rods are fully inserted. MVT-8104, Emerg Borate, will not open requiring implementation of AOP-1 06.1, Emergency Boration as an alternate path.

K/A 000024AK3.06: Ability to operate and I or monitor the following as they apply to Emergency Boration: Manual boration valve and indicators (R03.2*, SRO-3.3)

NUREG 1122 APE: 024, Emergency Boration VCS Task: 0-000-024-05-01, Perform Emergency Boration

b. This is a bank JPM. The Unit is in Mode 1. The CRS directs the candidate to complete start the A Charging Pump on the A Header and stop the B Charging Pump. The CCW valve to the A Charging Pump fails to open on the pump start. The Alternative Action associated with the Annunciator Response Procedure Corrective Actions requires stopping the A Charging pump within 20 minutes when local temperature monitoring is unavailable.

K/A 004000A8.08: Ability to manually operate and/or monitor in the control room: Charging (R0-3.8, SRO-3.4)

NUREG 1122 System: 004 Chemical and Volume Control System VCS Task: 0-004-015-01-01 Monitor the Chemical and Volume Control System Operation

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

c. This is a bank JPM. The candidate will be directed to isolate the SI Accumulators in EOP 2.0, Loss of Reactor or Secondary Coolant. The alternate path is required because MVG 8808B, Accumulator Discharge Isolation Valve, does not close. The Alternative Actions require the candidate to vent the B SI Accumulator.

K/A 000W/EO3EAI .1: Ability to operate and / or monitor the following as they apply to the (L0CA Cooldown and Depressutization): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (RO 4.0 SRO 4.0)

NUREG 1122 W/E: E03, LOCA Cooldown and Depressurization VCS Task: 0-000-084-05-01 Respond to Post-Loss of Coolant Accident Cooldown and Depressurization EOP-2.OJEOP-2.1

d. This is a bank JPM. EOP-2.3, Transfer to Hot Leg Recirculation, has been implemented eight hours after a LOCA. The candidate will be directed to align charging for Hot Leg Recirculation.

K/A 00001 1 EA1 .11: Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term cooling of core (RO 4.2 SRO 4.2)

NUREG 1122 EPE: 011, Large Break LOCA VCS Task: 0-000-137-05-01, Transfer RHR from Cold Leg to Hot Leg Recirculation per EOP-2 .3/EQ P-2 .0

e. This is a modified JPM. The candidate will be directed to implement EOP-15.1, Response To Steam Generator Overpressure, in response to High Pressure in the B SG. The Feedwater flow isolation valves to the B SG failed to close automatically requiring the operator to close at least one valve to prevent SG overfill. The B MS Isolation Bypass valve cannot be open requiring the implementation of Alternative Action to depressurize the B SG using a SG PORV.

K/A 000W/EI3EAJ .1 Ability to operate and / or monitor the following as they apply to the (Steam Generator Overpressure): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (RO: 3.1, SRO: 3.3)

K/A 000W/El 3EA2.l: Ability to determine and interpret the following as they apply to the (Steam Generator Overpressure): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (RO 2.9 SRO 3.4)

NUREG 1122 W/E: El 3, Steam Generator Overpressure VCS Task: 000-092-05-01, Respond to Steam Generator Overpressure Per EOP I 5.l/EOP-12.0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

f. This is a new JPM. The candidate will be directed to implement EOP-17.2, Response to High Reactor Building Radiation Level, in response to High Containment Radiation. XCP IIOB, RBCU 64B HERA FLTR BYP DMPR, fails to position to FILTER requiring the Alternative Action of repositioning the RBCU Train B Switch to XCP-l 11 B. As a result of the failure, RBCU 65B will be started.

K/A 000W/El 6EAI .3: Ability to operate and / or monitor the following as they apply to the (High Containment Radiation): Desired operating results during abnormal and emergency situations. (RO: 2.9, SRO: 3.0)

NUREG 1122W/E: E16, High Containment Radiation VCS Task: 0-311-018-06-01, Response to High RB Radiation Level

g. This is a bank JPM. The candidate will respond to the loss to the failure of an Intermediate Range channel during a plant startup in accordance with AOP-401 .8, Intermediate Range Channel Failure.

K/A 000033AA2.08: Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Intermediate range channel operability (RO: 3.3, SRO,3.4)

NUREG 1122 APE: 033, Loss of Intermediate Range Nuclear Instrumentation VCS Task: 0-000-033-05-01, Respond to Intermediate Range Instrumentation Channel Failure

h. This JPM was randomly selected from the 2015 exam. With the plant in mode 5 the candidate will be directed to place Reactor Building purge in service using SOP-I 14, Reactor Building Ventilation System, Section 111G.

K/A 029000A201: Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Maintenance or other activity taking place inside containment (RO: 2.9, SRO: 3.6)

NUREG 1122 System: 029, Containment Purge System (CPS)

VCS Task: 0-088-505-01-04, Perform Line ups of the Reactor Building Ventilation Systems.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 This is a new JPM. The Candidate will be directed to locally reset Safety Injection in accordance with SOP-112, Safety Injection System V.A., Manual Reset of Solid State Protection from the Relay Room Train A. Pictures will be provided for the contents of the following cabinets:

Logic Cabinet for XPN7O1O, Solid State Protection Cabinet Safeguards Test Cabinet Train A Test Cabinet Solid State Protection Cabinet Train A Output Cabinet 01 3000K4.01: Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following: SIS reset (RO: 3.9, SRO: 4.3)

NUREG 1122 System: 013, Engineered Safety Features Actuation System (ESFAS)

VCS Task: 0-000-007-05-04, Respond to Reactor Trip/Safety Injection Actuation

j. This JPM was randomly selected from the 2013 exam. The candidate will be directed to de energize and locally close and the MS Loop B and C to turbine driven Emergency Feedwater pump in accordance with EOP-3.0 (E-2), Faulted Steam Generator Isolation.

K/A: 00004OAA1 .10: Ability to operate and/or monitor the following as they apply to the Steam Line Rupture: AFW system (RO: 4.1, SRO: 4.1)

NUREG 1122 APE: 040, Steam Line Rupture VCS Task: 0-000-169-05-04, Locally Isolate a Faulted Steam Generator per EOP-3.0.

k. This is a bank JPM. The candidate will be directed to place the swing charger, XBCIA-1 B in service on DPN1 HA in accordance with SOP-31 1, 125 VDC System,Section IV.C and IV.P.

K/A: 06300K4.01: Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Manual/automatic transfers of control (RO: 2.7, SRO: 3.0*)

NUREG 1122 System: 063, D.C. Electrical Distribution VCS Task: 0-063-007-01-04, Place a Battery Charger in Service Per SOP-31 I

ES-301 Control Roomlln-Plant Systems Outline Form ES-3O1.2 Facility: V.C. Summer Date of Examination: 6/6/2016 Exam Level: RO SRO-l SRO-U Operating Test No.: NRC-ILO-14-01 Control Room Systems: ioiRC; / 1o SRO-l; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function APE 24: Emergency Boration (JPSF-086-N16)

a. ADL,S I Initiate Emergency Boration due to two stuck rods following a Reactor Trip. (Alternate Path)

b. Not selected for SRO-U

c. Not selected for SRO-U EPE 011: Large Break LOCA (JPS-002A-N16)

d. D,EN,L,S 4P Initiate Hot Leg Recirculation following a LOCA

e. Not selected for SRO-U W/E 16: High Containment Radiation (JPSF-1003-N16)

f. A,S,L,N 5 Response to High RB Radiation Level (Alternate Path)

g. Not selected for SRO-U

h. Not selected for SRO-U In-Plant Systems* (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

i. Not selected for SRO-U Generic Abnormal Plant Evolution 040 (JPP-107A-N16) 45 D,E,L,P Locally De-energize and Close MS Loop B and C to the Turbine Driven_Emergency_Feedwater_Pump_(EOP-3,0,_E-2)

, Generic APE 063 (JPP-052A- N16) 6 D,R Startup The Swing Battery Charger and Place on DPN 1 HA.

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

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Type Codes Criteria for RID! SRC!i / SRO-U SRO-U (A)lternate path 4J/4-3/2-3 - - 2 (C)ontrol room (D)irect from bank 9 ! 3/ 4 4 (E)mergency or abnormal in-plant 1 / / I (EN)gineered safety feature I 1 / 1 (control room system) 1 (L)ow-Power / Shutdown I ! I / 1 4 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 1 (P)revious 2 exams - 3/ 3 / 2 (randomly selected)

(R)CA iIlI1 I (S)imulator VC SUMMER NRC JPM

SUMMARY

a. This is a bank JPM. The plant has tripped with two control stock fully withdrawn. The candidate will be directed to implement EQ P-I .1, Reactor Trip Recovery, step 5 Verify all Control Rods ate fully inserted. MVT-8104, Emerg Borate, will not open requiring implementation of AOP-1 061, Emergency Boration as an alternate path.

K/A 000024AK3.06: Ability to operate and / or monitor the following as they apply to Emergency Boration: Manual boration valve and indicators (R03.2*, SRO-3.3)

NUREG 1122 APE: 024, Emergency Boration VCS Task: 0-000-024-05-01, Perform Emergency Boration

b. Not selected for SRO-U

c. Not selected for SRO-U U. This is a bank JPM. EOP-2.3, Transfer to Hot Leg Recirculation, has been implemented eight hours after a LOCA. The candidate will be directed to align charging for Hot Leg Recircu lation.

K/A 000011 EAI .11: Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term cooling of core (RO 4.2 SRO 4.2)

NUREG 1122 EPE: 011, Large Break LOCA VCS Task: 0-000-137-05-01, Transfer RHR from Cold Leg to Hot Leg Recirculation per EOP-2.3/EOP-2.0

e. Not selected for SRO-U

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

f. This is a new JPM. The candidate will be directed to implement EOP-1 7.2, Response to High Reactor Building Radiation Level, in response to High Containment Radiation. XCP 11OB, RBCU 646 HEPA FLIR BYP DMPR, fails to position to FILTER requiring the Alternative Action of repositioning the RBCU Train B Switch to XCP-1 1 1 B. As a result of the failure, RBCU 65B will be started.

K/A 000W/El 6EAI .3: Ability to operate and I or monitor the following as they apply to the (High Containment Radiation): Desired operating results during abnormal and emergency situations. (RO: 2.9, SRO: 3.0)

NUREG 1122 W/E: El6, High Containment Radiation VCS Task: 0-311-018-06-01, Response to High RB Radiation Level

g. Not selected for SRO-U

h. Not selected for SRO-U Not selected for SRO-U

j. This JPM was randomly selected from the 2013 exam. The candidate will be directed to de energize and locally close and the MS Loop B and C to turbine driven Emergency Feedwater pump in accordance with EOP-3.0 (E-2), Faulted Steam Generator Isolation.

K/A: 000040M1 .10: Ability to operate and/or monitor the following as they apply to the Steam Line Rupture: AFW system (R0:4.1, SRO: 4.1)

NUREG 1122 APE: 040, Steam Line Rupture VCS Task: 0-000-169-05-04, Locally Isolate a Faulted Steam Generator per EOP-3.0,

k. This is a bank JPM. The candidate will be directed to place the swing charger, XBCIA-1 B in service on DPN1HA in accordance with SOP-311, 125 VDC System,Section IV.C and IV.P.

K/A: 06300K4.01: Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Manual/automatic transfers of control (RO: 2.7, SRO: 3.0*)

NUREG 1122 System: 063, D.C. Electrical Distribution VCS Task: 0-063-007-01-04, Place a Battery Charger in Service Per SOP-311

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Date of Examination: Operating Test Number:

. Initials

1. General Criteria a b* c#

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

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

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

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

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

2. walk-Through Criteria --

a. Each JPM includes the following, as applicable:

• initial conditions initiating cues

• references and tools, including associated procedures

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

• operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards 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-3d-I and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.

3. SImulator Criteria --

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

Printed Na Sig ature Date

a. Author -

S7l1/1(e

b. Facility Reviewer(*) 57 kt.7 ,,4Y) S -/

c, NRC Chief Examiner (#) Lk- rI ri . P- s i i

d. NRC Supervisor C*w& / (( 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 Simulator Scenario Quality Checklist Form ES-301 -4 Date of Exam: 06/06/2016 Scenario Numbers: 1 / 2 / 3 Operating Test No.: NRC ILO 14-01 tcility: VC Summer QUALITATIVE ATTRIBUTES Initials a b* 4

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

2. The scenarios consist mostly of related events. i_

3. Each event description consists of

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

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

. the symptoms/cues that will be visible to the crew c3i( 4

. the expected operator actions (by shift position)

. the event termination point (if applicable)

4. The events are valid with regard to physics and thermodynamics. 57 ( .L

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

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

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

Cues are given.

7. The simulator modeling Is not altered. .t i

8. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

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

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

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

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

13. The level of difficulty is appropriate to support licensing decisions for each crew position. 4 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1/2/3

1. Malfunctions after EOP entry (1-2) 3 /

.1 -_

2. Abnormal events (2.4) 4 / 5 I 4 j.

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

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

5. EOP contingencies requiting substantive actions (0-2) 0 / 1 / 1 (1

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

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

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: VC SUMMER Date of Exam: 06/06/2016 Operating Test No.: NRC-ILO-14-01 A E Scenarios 2 3 L N CREW CREW

• I T MINIMUM ()

POSITION POSITION A c

A T S A B S A B L R T 0 R T 0 N

0 C P C P T P R I U E

RO RX 3 1 1 g.ESRO-l

-i;j-, I/C 24 12 4 4 4LJ

. SRO-U MAJ762 2 LI a a RO RX I I I T i SRO-l I/C 35 45 4 4 LI SRO-U MAJ762 2 LI TS 0 0 RO RX 3 1 1 LU SRO-I I/C 24 12 4 4 LI SROUMAJ762 2 LI is o o RO RX I I I T i SRO-I

-F-i I/C 35 45 4 4 1 U

SROUMAJ 7 6 2 2 LI TS 0 0 Instructions:

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

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

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

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-l applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

ES-3d Transient and Event Checklist Form ES-301-5

[fciIity: VC SUMMER Date of Exam: 06/06/2016 Operating Test No.: NRC-ILO-14-01 A E Scenarios 2 3 L N CREW CREW

• T MINIMUM ()

I POSITION POSITION A c S A B S A B L A T R T 0 R T 0 N C P P 0 C I P R I U E

RO RX 3 1 1 ai NOR1 I I SRO-l I L_Z L!El 2 1 SRO-U MAJ 7 6 2 El TS 0 0  ; 2 RO R)( 1 1 1 1 i i SRO-l 4

El SRO-U MAJ 7 6 2 2 El TS RX 0 0 RO NOR 1 3 2 El SRO-l 34 6

El 5 SRO-UMAJ 7 6 2 )

TS35 4 RO RX El 2 SRO-l 34 14 6 2 2 El Instructions:

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

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but

(*) Reactivity and normal evolutions may be replaced with must be significant per Section C.2.a of Appendix D.

additional instrument or component malfunctions on a one-for-one basis.

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

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-l applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: VC SUMMER Date of Exam: 06/06/2016 Operating Test No.: NRC-ILO-14-01 A Scenarios P V L N CREW CREW CREW T MINIMUM

• I T POSITION POSITION POSITION c A A T S A B S A B S A B L R T 0 R T 0 R T 0 N 0 C P o C P 0 C P T P R I U E

0 1 RD NOR 13 2 1 SRO-l 34 14 I/C 6 4 4 2 SRO-U 2 2 IS 35 25 4 0 2 2 RX RD NOR 12 SRO-l I/C 4

< ri 56 O LJ

° SRO-U MAJ 7 2 2 IS 6

RO RX 2 uJI 1 SRO-l

< I/C 46 2 o_

° 7 SRO-U MAJ RD RX SRO-l

<El I/C 35 .2 1 Q

°SROUMAJ 7 E TS 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 RD applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRD-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRD-l additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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

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

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRD-l applicants in either the ATC or BOP position to best evaluate the SRD-l in manipulating plant controls.

ES-301 Competencies Checklist Form ES-301-6 Facility: VC Summer Date of Examination: 06/06/2016 Operating Test No.: NRC ILO 14-01 APPLICANTS Anderson, Dustin Black, Kris Derrick, Evan Fern, Mike RO I RO RO I RO Ii Competencies SRO-l LI SRO-l LI SRO-l LI SRO-l LI SRO-U LI SRO-U LI SRO-U LI SRO-U LI SCENARIO SCENARIO SCENARIO SCENARIO BOP RO RO BOP BOP RO RO BOP 1 2341 234 1 234 1 234 I nterpreUDiagnose Eventsand 24 12 35 45 24 12 35 45 Conditions Comply With and 12 12 13 34 12 12 13 34 UseProcedures(1) 47 36 57 56 47 36 57 56 Operate Control 12 12 13 34 12 12 1 3 3 4 Boards(2) 47 36 57 56 47 36 57 56 Communicate 1 2 12 1 3 3 4 1 2 12 1 3 3 4 andlnteract 47 36 57 56 47 36 57 56 Demonstrate Supervisory Ability (3)

Comply With and Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

ES-301 Competencies Checklist Form ES-301-6 Facility: VC Summer Date of Examination: 06/06/2016 Operating Test No.: NRC ILO 14-01 APPLICANTS Holcombe, Terry Riordan, Josh Micklash, Tavis Pawlak, Jason RO [] RO RO LI RD LI Competencies SROI LI SRO1 LI SROI LI SROI LI SRO-U LI SRO-U LI SRO-U [] SRO-U []

SCENAPJO SCENARIO SCENARJO SCENARIO SOP RO RO BOP SRO SRO SRO SRO 1 234 1 234 1 2341 234 Interpret/Diagnose Eventsand 24 12 35 45 35 45 35 45 Conditions Comply With and 12 12 13 34 13 13 UseProcedures(1) 36 57 56 56 56 Operate Control 12 12 1 3 34 Boards (2) 47 36 57 56 12 12 12 Communicate 1 2 12 1 3 3 4 34 34 34 3 4 andlnteract 47 36 57 56 56 56 56 56 7

12 12 Demonstrate 12 12 34 34 Supervisory Ability (3) 34 56 56 56 56 7 7 Comply With and Use Tech. Specs. (3) 3 5 2 3 5 25 Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the appIicants license type and enter one or more event numbers that will allow the examiners to evaluate evenj applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

ES-301 Competencies Checklist Form ES-301-6 Facility: VC Summer Date of Examination: 06/06/2016 Operating Test No.: NRC ILO 14-01 APPLICANTS Winn, Rodger ROATC BOP SRO-U RO LI RO I] RO RD LI Competencies SRO1 LI SROI LI SRO1 LI SR01 LI SRO-U SRO-U LI SRO-U LI SRO-U SCENARIO SCENARIO SCENARIO SNARIO_

SRO SRO RO BOP SRO 1 234 1 2341 234 1 234 Interpret/Diagnose Events and 35 45 46 35 46 Conditions Comply With and 12 12 23 1 3 24 UseProcedures(1) 67 3 5 45 7 67 Operate Control 24 12 Boards (2) 67 35 7

. 12 12 Communicate 12 12 34 24 34 and Interact 56 67 35 6 56 7

5 7 7

12 12 Demonstrate 12 34 34 Supervisory Ability (3) 56 56 56 7 7 Comply With and Use Tech. Specs. (3) 3 2 s 6 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 even, applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-3Q3-1 and ES-303-3.)

ES4OI. Rev. 10 PWR Examination Outline Form ES4OI-2 Facility: V.C. Summer Unit 1 Date of Exam: June 2016 RO K/A Category Points SRO-Only Points Tier Group 1 =

KKKKKKAIAAAG A2 G* Total 1 2 3 4 5 6 1f2 3 4 Total

i. i 333 33 318 3 3 6 Emergency &

Abnormal Plant 2

T NIA 1 2 N/A 9 2 2 4 Evolutions Tier Totals 4 5 5 4 5 4 27 5 5 10 I 322233323 26 3 2 5 2 10 1 1 ii i ii 10 2 1 3 it Systems Tier Totals 4 2 ,.3 3 A 4 4 4 3 3 4 38 3 8

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

1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO.onIy outline, the Tier Totals In each KIA 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 I from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the S RD-only exam must total 25 poInts.

3. Systemslevolutlons within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section 0.1 .b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

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

5, Absent a plant-specific priority, only those KIAs having an importance rating fIR) of 2.5 or higher shall be selected.

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

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

7. 9he generic (G) KIAs 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 0.1 .b of ES4OI for the applicable KAs.

8. On the following pages, enter the KA numbers, a brief description of each topic, the topicsRmportance ratlngs(lRs) 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals f#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43..

ES-401, REV 10 TIGI PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO7EK1 .02 Reactor Trip Stabilization Recovery

- - 3.4 3.8 ] [1 El LI LI LI LI LI H [1 ri Shutdown margin

/1 OO8AA1.O6Pressunzer Vapor Space Accident I 3 3.6 3.6 fi fi fi [] H F] , LI LI flJ H Control of PZR level 009EK3.23 Small Break LOCA /3 4.2 4.3 [] [] [] [] [J [] RCP tripping requirements O11EA2.08 Large Break LOCA / 3 3.4 3.9 H Li LI LI LI H LI r LI H H Conditions necessary for recovery wten accident reaches stable phase 015AA2.09 RCPMalfunctions/4 3.4 3.5 LI Li LI Li Li Li Li F} Li Li Li When to secure RCPs on high statortemperatures 022AK1 .03 Loss of Rx Coolant Makeup / 2 3 3.4 ] LI LI LI LI H H LI LI LI LI Relationship between charging flow and PZR level 025M1 .11 Loss of RHR System / 4 2,9 3 H LI LI Li Li LI [1 H H LI LI Reactor building sump level indicators 026AG2.4.49 Loss of Component Cooling Water / 8 4.6 4.4 LI H LI LI H Li LI LI LI H Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

029EK2.06 ATWS /1 2.9 3.1 LI LI LI LI H H LI Li Li H Breakers, relays, and disconnects.

038EK1.03 Steam Gen. Tube Rupturel3 3.9 4.2 . LI H LI LI LI LI LI Li LI LI Natural circulation 040AG2.l.31 Steam Line Rupture Excessive Heat

- 4.6 4.3 H LI Li H LI LI LI LI LI LI Ability to locate control room switches, controls and Transfer 14 indications and to determine that they are correctly reflecting the desired plant lineup.

Page 1 of 2 08/10/2015 8:15AM

E5401, REV 10 TI GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 054AK3.01 Loss of Main Feedwater /4 41 44 H LI LI LI LI LI LI Reactor and/or turbine trip, manual and automatic 056AA2.32 Loss of Off-site Power /6 4.3 4.3 Fl LI LI LI LI LI F] LI LI LI Transient trend of coolant temperature toward no-load I-ave 3%MG-1-i Loss of Vital AC Inst Bus /6 ,_39a-i7I,c/ t/,o LID LLJZ J - b esaa4e-sy&tem-or eemponcnt-3tatus.t4 j- /.1-e e4+C 6 2 i. 0

)CAI (oDJ.

Loss of Nuclear Svc Water /4 33 flL HF]HEiEE LI O(L rj. o 9.0 L oees-of-CCW{ & u Ii tioP LoSi o 1et çec 065l .05 Loss of Instrument Air? 8 3.3 3.3 LI LI LI LI LI LI i LI LI LI LI RPS 077AK2.06 Generator Voltage and Electric Grid 3.9 4.0 LI [i LI LI LI LI LI LI LI LI LI Reactor Power Disturbances I 6 WEO5EK2.2 Inadequate Heat Transfer Loss of

- 3.9 4.2 LI F F] LI LI LI H LI LI LI LI Facilitys heat removal systems, including primary Secondary Heat Sink /4 coolant, emergency coolant, the decay heat removal systems and relations between the proper operation ot these systems to the operation of the facility.

Page2of2 08/10/2015 8:15AM

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ES-401, REV fO T2GI PWR EXAMINATION OUTLINE FORM ES4OJ-2 KA NAME I SAFETY FUNCTION: IR Ki 1(2 K3 K4 K5 1(6 Al A2 A3 A4 C TOPIC:

RO SRO 0031(602 Reactor Coolant Pump 2.7 3.1 [j [] fl fl [] U U [] RCP seals and seal water supply 0031(6.04 Reactor Coolant Pump 2.8 3.1 U U U U U 1 U U U U U Conlainmit isolation valves affecting RCP operation 004r(3,08 Chemical and Volume Control 3.6 3.8 U U U U fl U U U U U RCP seal injection 005K5.01 Residual Heat Removal 2.6 2.9 U U U U U U U U U U Nil ductility transition temperature (brittle fracture) 006A4.07 Emergency Core Cooling 4.4 4.4 [] U U U U U U U U ] ] ECCS pumps and valves O?X- Pressurizer RieUQuench Tank 13V U U U U U U [1 U o7,-3OJ -1,_i (20 -rt.\ dd-cZe

.1z P_.

008A10l ComponentCooling Water 2.6 2.9 U U U U U U U U U U CCWflowrate 0081(3.03 Component Cooling Water 4,1 4.2 U U E1 U U U U U U U U RCP 0101(1.08 PressurizerPressureControl 3.2 3.5 11 U U U U U U U U U U PZRLCS 012A2.05 Reactor Protection 3.1 3.2 U U U U U U U U U U Faulty or erratic operation of detectors and function generators 012A4.02 Reactor Protection 3.3 3.4 U U U U U U U U U U Components for indMdual channels Pe1o13 0811012015 8:15AM

ES4OI, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME I SAFETY FUNCTION: IR Ki 1<2 1<3 K4 K5 1<6 Al A2 A3 A4 G TOPIC:

RO SRO 0131<2.01 Engineered Safety Features Actuation 3.6 3.8 D1E DODD DEED ESFASlsafeguards equipment control 013K5.02 Engineered Safety Features Actuation 2.9 3.3 LIED D]DE DEED Safety system logic and reliability 022A3.01 Containment Coding 4.1 4.3 DEE ELIDE EEE Initia tion of safeguards mode of operation O662-(k Containment Spray DDE DEED DDD f.multi-43niHieen6.c 0 rrr

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039A2.01 Main and Reheat Steam 3.1 3.2 DEE DEED I1DDE Flow paths of steam during a LOdA 0391<4.07 Main and Reheat Steam 3.4 3.7 LIED DDD DEED Reactor building isolation 059A2.1 1 Main Feedwater 3.0 3.3 DDE DEED 1DDE Failure of feedwater control system 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 DDE DLI 1D DEED Pumps 062A1.01 AC Electrical Distribution 3.4 3.8 LI LIE LI LIE DEED Significance of DIG load limits 0621<1.04 AC Electrical Distribution 3.7 4.2 [ LI LI DEED DEED Off-site power sources 063A1.01 DC Electrical Distribution 2.5 3.3 LI LI LI LIDD DEED Battery capacity as it is affected by discharge rate Pe2 013 08110/2015 8:15AM

ES-401, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064G2.4.l Emergency Dies Generator 4.6 4.8 fl [2] E] El El El E] 12] 12] El [] Knowledge of EOP entry conditions and immediate action steps.

-I#6- Process Radiation Monitoring LlElEl )) El C] t] 12] [1 [1 [1 Lotun ioteuon on nign--+-

o9 q,oi o L13 s5 +r,I,g1CiO_, JTh tA e--d5 5d-p,-

076K2.04 SenAce Water 2.5 2.6 El L] C] C] C] El El El El El El Reactor building dosed coding water 078K1.04 Instrument Jr 2.6 2.9 C] C] C] C] C] El El El El C] Coding water to compressor 103A3.01 Containment 3.9 4.2 C] El El El El El El El ] El C] Containment isolation 103G2.4.6 Containment 3.7 4.7 C] El El El El El El El El El [] Knowledge symptom based EOP mitigation strategies.

Pe3of3 08110/2015 8:15AM

ES4OI, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002K6.06 Reactor Coolant 2.5 2.8 Li LI Li L1 LI Fi El F] El F] F] Sensors and Detectors 015K5.18 Nuclear Instrumentation 2.9 3.2 F] F] F] F] F] F] F] F] F] F] Definition of reactor poison 016A4.O1 Non-nuclear Instrumentation 2.9 2.8 F] F] F] F] F] F] F] F] F] fl NNI channel select controls

-933A&61-& Spent Fuel Pool Cooling .242-?t4 3,o 3.3 F] F] JF] F] F]F]F].F] F] Tempeature-controfvatves9 O33I, 3 Se-- JLe! fw_

0341<1 .01 Fuel Handling Equipment 2.5 3.2 F] F] F] F] (F] F] F] F] F] F] RCS 035K3 02 Steam Generator 4.0 4.3 F] F] j F] F] F] F] F] F] F] F] ECCS 071A1 .06 Waste Gas Disposal 2.5 2.8 F] F] F] Li Li Li F] F] F] F] Ventilation system 072A2.02 Area Radiation Monitoring 2.8 2.9 F] F] F] F] F] F] F] F] F] F] Detector failure 0791<4.01 Station Air 2.9 3.2 F] F] F] (J F] F] F] F] F] F] F] Cross-connect with AS 086G2.4.49 Fire Protection 4.6 4.4 F] F] F] F] F] F] F] F] F] F] Ability to perform without reference to procedutes those actions that require immeiiate operation of system components and controls.

Page 1 of 1 08/10/2015 8:15AM

ES-401, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2445- Conduct of operations *2:73:4fl meeer 3,9* )_

r] i H -

(I.,

G2.l .34 Conduct of operations 2.7 3.5 LI LI LI LI LI LI LI LI LI LI Knowledge of primary and secondary chemistry limits G2.l.37 Conduct of operations 4.3 4.6 LI [] LI J [J L] LI LI Knowledge of procedures, guidelines orlimitahons associated with reactivity management G2.2.14 Equipment Control 3.9 4.3 LI J LI Knowledge of the process for controlling equipment configuration or status Equipment Control -LI LI LI LI LI LI LI LI LI LI I]

Cz. z. -f. 94 andoperahonaesbetween-tmit i4

- Ic c.-t1J G2.3.13 Radiation Control 34 3.8 LI LI LI LI LI LI LI LI LI LI Ii Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 LILIELILILD1 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.12 Emergency Procedures/Plans 4.0 4.3 LI LILILILILILILILILI Knowledge of general operating crew responsibilities during emergency operations.

G2.4.47 Emergency Procedures/Plans 4.2 4.2 LILILILLILILILJLJL] Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

G2.4.6 Emergency ProceduresiPlans 3.7

• LILILI[1LILILILIL]L1 Knowledge symptom based EQP mitigation strategies.

Page 1 of 1 0811012015 8:15AM

ES4OI, REV 10 SRO TIGI PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME / SAFETY FUNC11ON: IR KI 1<2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RD SRO 007EA2.02 Reactor Trip Stabilization Recovery I

- - 4.3 4.6 [] [] [] 0 [1 C] C] [] [] [] [] Proper actions to be taken if the automatic safety func- tions I have nottaken place 009EG2.4.47 Small Break LOCA / 3 4.2 4.2 C] C] C] C] C] C] C] C] C] C] Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

01 1EP2.05 Large Break LOCA /3 3.3 3.7 0 C] C] C] C] C] C] [] [1 C] C] Significance of charging pump operation 026AG2.2.22 Loss of Component Coding Water / 8 4.0 4.7 [] C] [] C] [] [] C] [] C] C] Knoviedge of limiting conditions for operations and safety limits.

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

Generator Voltage and Electric Grid C] Gee aeeeeabiilh1-Gve- t Disturbances /6 L/3 3 77c(

f) o( eC/je..-C) dQ3p O17A -, g 3

Page 1 of 1 08110/2015 8:16AM

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ES-401, REV 10 SRO T2GI PWR EXAMINATION OUTLINE FORM ES401-2 KA NAME I SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 012A2.05 Reactor Protection 3.1 3.2 LDDDLIDE1[] Faulty or erratic operation of detectors and function generators 039A2.O1 Main and Reheat Steam 3.1 3.2 Flow paths of steam during a LOCA 076G2.4.6 Service Water 3.7 4.7 DÜDJLL1 Knowledge symptom based EOP mitigation strategies.

078A2.O1 Instrument Air 2.4 2.9 Air dryer and filter malfunctions 103G2.1 .7 Containment 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Page 1 of 1 08110/2015 8:16AM

ES4OI, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES4OI -2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028A2.03 Hydrogen Recombiner and Purge 3.4 4.0 El J Z J El fl [] El El El The hydrogen air concentration in excess of limit flame Control propagation or detonation with resulting equipment damage in containment 8e34 Liquid Radwaste El El El El El El El1enee-the ii 2o1 33 3,3 cL.(- (f /:?,ocJ,c L+iw

.03442 Waste Gas DPOSaI El Ci El El t troI 1 I L S 7Ic.2Z.3 - ae4ioebetweeA-s-at-rfatthty2 Cc,)1 h1 ,... 12z -

Page 1 of 1 08/10/2015 8:16AM

ES4OI, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KB Al A2 A3 A4 G TOPIC:

RO SRO G2.l.13 Conduct of operations 2.5 3.2 El El fl fl fl H H H fl Knowledge of facility requirements for controlling vital!

controlled access.

G2.2.12 Equipment Control 3.7 4.1 El [1 El El [7 [7 [7 [7 [7 [j j Knowledge of surveillance procedures.

G2.2.44 Equipment Control 4.2 4.4 [7 [7 [7 [7 [7 ((7 [7 [7 [7 [7 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system a conditions G2.3.14 Radiation Control 3.4 3.8 El El [7 [7 [7] El El [7 El ] KnoMedge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.6 Radiation Control 2.0 3.8 El El El El El El El LI H H [ Ability to aprove release permits G2 4 18 Emergency Procedures/Plans 33 40 [7 [7 [7 ] Knowledge of the specific bases for EOPs G2.4.31 Emergency Procedures/Plans 4.2 4.1 El El El El El El El El El El [l Knowledge of annunciators alarms, indications or response procedures Page 1 of 1 06/10/2015 6:16AM

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RD KAs Changes approved in this section on 10/1/15 1/I 062AK3.04 062AK3.04 Loss of Nuclear Svc Water-Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water:

Effect on the nuclear service water discharte flow header of a loss of CC W.

ttllhtv comment: The meaning of this A.1 iS 110! clear. .1 tetLItl it! tiiitt tliscrimiiiating qticstitm 15 110! like/v with the interpretation cf Describe the effrcl oft, loss of ((IVon the Service titer discharge l,eutler Replaced with 062AK3.03. Loss of Nuclear Service water Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: Guidance actions contained in EOP for Loss of nuclear service water, per disctission with Chief Examiner on 10/1/15.

(RO:4.0 SR.O:4.2) 2/I 026G2.2.3 026G2.2.3 Containment Spray (multi-unit license) Knowledge of the design. procedural and operational differences between units.

1tilit coniment: C Sumnier c/ocx not have a similar p/tint on the site.

L2 and 113 tire of the ilexi generation of PWRs with, ESF designs aitd Sttfriv related systenis that are hot relatable to legacy plants.

Replaced with 026, C2.2.44, Containment Spray Ability to interpret control room indications to veri1 the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. er discussion with Chief Examiner on 10/1/15.

(RO:4.2 SRO:4.4) 2/I 073K4.02 073K4.02 Process Radiation Monitoring Knowledge of PRM system design feature(s) and!or interlock(s) which provide for the following:

Letdown isolation on high-RCS activity 1tilitj cwnment: V C. Simninser does lit)! have an ttiitomutic function or interlock that provides Ietdo wn isolation for high RCS activity.

Replaced with 073K4.01. Process Radiation Monitoring Knowledge of PRM system design laturc(s) and!or interlock(s) which provide for the IC)llOwing Release termination when radiation exceeds setpoint. PCI.

discussion with Chief Examiner on 10/1/15. C RO:4.0 SRO:1.3)

ES-401 Record of Rejected K/As Form ES-401-4 2/2 033A3.Ol 033A3.Ol Spent Fuel Pool Cooling Ability to monitor automatic operation of the Spent Fuel Pool Cooling System including: Tctnperature control valves.

Utility coni,ne,zt: 14 C Summer ttoes not htive a temperature control valve that at1tomnatkall) regulates spent fuel pooi temperature.

Replaced with 033K3.0l. Spent Fuel Pool Cooling Kncm ledge of the effect that a loss or mal function of the Spent Fuel Pool Cooling System will have on the following: Area ventilation sxstems. pci discussion with Chief Examiner on 10/I/I 5. (RO:2.6 SRO:3. I 3 G2. 1.15 Knowledge ot administrative requirements for temporary nanavement directives such as standing orders, night orders. Operations memos. etc.

Utility comment: The RO candidate is not required to review .sttmnding orders or similar docmunents as ptrt of shift turnover or other duties.

Replaced with G2.I.25. Ability to interpret reference materials, such as graphs. curves, tables. etc., per discussion with Chief Examiner on 10/I/IS. (RO:3.9 SRO:4.2) 3 G2.2.3 (multi-unit license) Knowledge of the design. procedural and operational differences between un its.

Uti!it comment: C. Summer does not have a similar phmt on the site.

U2 and (B tire under construction nut! oft/ic next generation of PWRs.

Replaced with G2.2.2. Ability to manipulate the console controls as required to operate the fcility between shutdown and designated power levels, per discussion with Chief Examiner on 10/1/15. (RO:4.6 SRO:4. 1)

ES-401 Record of Rejected K/As Form ES-401-4 SRO KAs Changes approved in this section on 10/1/15 2/2 068A2.t)3 068A2.03 liquid Radwaste Ability to (a) predict the inipacts of the lollowing malfunctions or operations on the Liquid Radwaste System ; and

( h) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Insufficient sampling frequency of the boric acid in the evaporator bottoms.

C tititv comment: jvot operationally relevant or important. ilte Boric A chI Evaporators are no loitger tisetl.

Replaced with 068A2.04, Liquid Radwaste Ability to (a) piedict the impacts of the follo ing malfunctions or operations on the Waste Gas Disposal System: and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation. per discussion with Chief Examiner on 10/1/15. (RO:3.3 SRO:3.3 2/2 07lG2.2.4 07lG2.2.4 Waste Gas Disposal (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

C/ti//fl contntent: ! C Stinuner c/ocx not have a similar plant on the site.

1/2 and U3 are tinder construction aitcl of the next genertition of PIJRs.

Replaced with 071G2.2.38, Waste Gas Disposal Knowledge of conditions and limitations in the thcilitv license, per discussion with Chief Examiner on 10/1/15. (RO:3.6 SRO:4.5)

ES-401 Record of Rejected K/As Form ES-401-4 ADDITIONAL RO KAs Changes approved in this section on 2/17/16 1/2 074EK3.04 074EK304 Inadequate Core Cooling Knowledge of the REASONS for the tollowing responses as they apply to the event: Tripping RCPS I 7tilit comment: RCPs are tripped late in lb e inadequate core cooling procedure when R(S temperatures are low ttnd when they tire no longer needett for core cooling. Tli e operational relevance is that tutu they tire maintained running. Tripping the RCPs at a particular tcmperature is a detttllecl basL item above tint! heytmcl the RO level of knowledge.

Replaced with 074 EK3.1 I Guidance contained in EOP for Inadequate Core Cooling per conversation with Chief Examiner on 2/1 7/16 ( RO:4.0 SRO:4.4) 1/2 WEO I EKI .1 WEt) I EK 1.1 Rediagnosis Knowledge oftfie operational implications of the following concepts as they apply to the event: Components. capacity.

and function of emergency systems.

Utility coinnient: .4 ttiscriiniitating question ctmnot he written at tite RO level. 4ttempts nettled procedure selection questions that approach the SRO level of knowledge.

Replaced with WEOIEKI,2 Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection / rediagnosis).

per conversation with Chief Examiner on 2/17/16. (RO:3.4 SRO: 40) 2/1 007K5.02 007K5.02 Pressurizer Relief/Quench Tank Knowledge of the operational implications of the following concepts: Method of forming a steam bubble in the PZR 1/tility continent: There tire lit) operational implications will, impact on the Pressurizer Relief Tank will, regtird to the method of forming a steam bubble, i.e., energizing pressurizer heaters.

Replaced with 007A3.01 Components which discharge to the PRT per conversation with Chief Examiner on 2/17/16 (RO:2.7 SRO:2.9) 2/2 033K3.0i 033K3.0 1 Spent Fuel Pool Cooling Knowledge of the effect that a loss or malfunction of the system will have on the following: Area ventilation systems Utility comment: Ventilation aligminments tire ierifled and changed in

,40P-123.4, LOSS OF SPENT FUEL COOLING, tlependbmg oim the system,,, hut the tletaitsftr lii ese items tire beyond the RO level of knowledge. There tire no interlocks or tu,tomtitic actions tit I C Summer tictuatedfrom Fuel Httndlimig Building rtiditition monitors.

Replaced with 033K3.03 Spent Ftiel Temperature per conversation with Chief Examiner on 2/17/16 (RO:3.0 SRO:3.3 )

ES-401 Record of Rejected K/As Form ES-401-4 ADDITIONAL SRO KAs Changes approved in this section on 2/17/16 (SRO) I/I 077AA2.Ol 077AA2.O1 Generator Voltage and Electric Grid Disturbances Determine-and interpret the following as they apply to the event: Operating point on the generator capability curve 1/lilly coifliflelit There is not tt discrmunatmg question on this tc)pic tittit ctm be written tit the SRO Ievcl.

Replaced with 077AA2.09 Operational stattis of emergency diesel generators per conversation with Chief Examiner on 2/1716 (RO:3.9 SRO:4.3)

(SRO) 1/2 069AG2.4.49 069AG2.4.49 Loss of C1M[ Integrity Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

1titity comment: There are no ,iwuedittte actions that ilitist he taken front menwrj for tt loss of containment integrity. There is not a ttiscriminating question on this topic that can he ,sritten ttt tite SRO level.

Replaced with 069 2.4.2 I Knowledge of the parameters and logic used to assess the status of safi.ty ftinctions, such as reactivit control, core cooling and heat removal, reactor coolant system integrity, containment conditions.

radioactivity release control, etc per conversation with Chief Examiner on 2/17/16 (RO:4.O SRO:4.6)

ES-401 Record of Rejected K/As Form ES-401-4 ADDITIONAL RO KA Chan es approved in this section on 5/5/16 (RO) 1/1 057G2.l.19 057G2.l30 Loss of Vital AC instrument Bus Ability to use plant computer to evaluate system or component status.

There are numerous indicutwns available for a loss of iifitl inStttiiUciit bus that do not relj on computer indication. Computer imidications for tlt is evemit tire not opertitionally relevtmt.

Replaced with 057C2.1.30 Ability to locate and operate components, including local controls, per conversation with Chief Examiner on 5/5/16 (RO:4.4 SRO:4.0)

ADDITIONAL SRO KA Chant es approved in this section on 5/5116

( SRO) 1/2 Ot) I AA204 001 AA2.04 Continuous Rod Withdratval Determine and interpret the following as they apply to the event: Reactor power and its trend ttilltv comment: There is not a discriminating question on this topic that can be urittcn at the SRO leveL Replaced with OOIAA2.03 Continuous Rod Withdrawal Determine and interpret the fullowine as they apply to the event: Proper actions to he taken if atflomatic safety functions have not taken place per conversation with Chief Examiner on 5/5/16 (RO:1.5 SRO:4.8)

Wriften Examination Quality Checklist Form ES-401-6 ES-401 Date of Exam: 6/6116 Exam Level: RD SRO Facility: V.C. Summer Unit 1 Initial Item Description

1. Questions and answers ate technically accurate and applicable to he facility.

a. NRC K/As ate referenced for all questions.

2.

b. Facility learning objectives are referenced as available.

r\  %

3. SRO questions are appropriate in accordance with Section D.2,d of ES-401 ] v ii SRO questions 4 The sampling process was random and systematic (If more than 4 RD or 2 program were repeated from the last two NRC licensing exams, consult the NRR/NRD OL (

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

6. Bank use meets limits (no more than 75 percent from the Bank Modified New bank, at least 10 percent new, and the rest newer modified); enter the actual RD / SRD-only question RD SRO RD ,SRD RD RD 19 3 13 7 43 15 distribution(s) at right

7. Between 50 and 60 percent of the questions on the RD Memory C/A exam are written at the comprehension! analysis level; the SRD exam may exceed 60 percent if the randomly RD 1SRO RD 1SRO selected K/As support the higher cognitive levels; enter 44 18 distribution(s ) at right. 31 7 the actual RD / SRD question of

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

examination

9. Question content conforms to specific K/A statements in the previously approved ied.

outline and_is_appropriate_for_the tier to_which_they_are_assigned;_deviations_are_justif B.

10. Question psychometric quality and format meet the guidelines In ES Appendix total is correct

11. The exam contains the required number of one-point, multiple choice items; the and agrees with the value on the cover sheet, Prinled Name / Signature Date Ath RQ+ Jce

b. Facility Reviewerf) 4il%r,çc4LJ j

c. NRC Chief Examiner f#) f .syi/Ib U. NRC Regional Supervisor -Y 17A14J(LA/

ed examinations, Note:

• The facility reviewers initials or signature are not applicable for NRC.develop items in Column c; chief examiner concurrence required

1. Independent NRC reviewer initials

V.C. Summer 2016-301 ES-401 Written Examination Review Worksheet Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A 007EK1.02 1 H 3 X  ? N E Question statement needs to be a WOOTF statement like the other questions.

Regarding the SRO only justification for question #76, please explain why this is not SRO only.

4/29/16 - Revised question is satisfactory.

3 K/A 008AA1.06 2 H X N E Question choices combined with the answer choices are long and difficult to read. Could easily split this up into two questions. Need to ask both questions in accordance with the applicable procedure.

Need to discuss this question.

4/29/16 - Revised question is satisfactory.

3 K/A 009EK3.23 3 H X B E Is it possible for a SBLOCA to cause a 13 psig pressure rise in containment in one minute?

4/29/16 - Revised question is satisfactory.

3 K/A 011EA2.08 4 F X M E Based on the procedure step, the stem question should read the CCW train in the active loop, vice the CCW train with the active loop.

4/29/16 - Revised question is satisfactory.

3 K/A 015AA2.09 5 F M S Question is Satisfactory.

3 K/A 022AK1.03 6 H N S Question is Satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 025AA1.11 7 F N E Are the conditions given operationally valid? If you are below the RWST level where automatic switchover should have automatically occurred, but also below the sump level where ECCS pump suction requirements are not met then it seems to me that this is a very poor plant design or water from the RWST went someplace other than the sump which would lead to choice A also being potentially correct.

Verified that conditions would lead to EOP-2.5 entry. Question is satisfactory.

3 K/A 026AG2.4.49 8 H B S Question is Satisfactory.

9 H 2 X X N U K/A 029EK2.06 Since all of the bullets in step 1 of EOP-1.0 are not met for verifying the reactor tripped, could an applicant argue that the reactor is not tripped?

Need to specify in the initial conditions that all or both reactor trip breakers are closed.

Choice B is not a plausible distractor when contrasted with choice A.

Choices D is not plausible. Question is unsatisfactory due to two non-plausible distractors.

5/3/16 - Revised question is satisfactory.

3 K/A 038EK1.03 10 H X X N E Discussion on page 22 of 34 in the EOP-4.0 training handout seems to describe choice D as another correct answer.

4/29/16 - Revised question is satisfactory.

3 K/A 040AG2.1.31 11 F X X B E Could have XCP 615, 1-2, RCS TAVG LO in alarm but not yet have a feedwater isolation (1/3 for alarm vice 2/3 for feedwater isolation). I do not believe that both B and C are both plausible distractors since they are at the same setpoint for the same parameter.

4/29/16 - Reviewed revised question. What makes choice A plausible? What caused the reactor trip? Need to further discuss.

5/2/16 - Based on discussion with the licensee, the revised question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 054AK3.01 12 H X X B E Question was submitted for preliminary ten sample question review and will not be used for evaluating the quality of the final submittal.

Most issues identified during the sample review were addressed however distractors A and B are still basically the same thing stated with different words.

5/4/2016 - Revised question is satisfactory.

3 K/A 056AA2.32 13 H X N E The difference between 557 and 559 degrees F is minutia.

4/29/16 - Revised question is satisfactory.

3 K/A 057AG2.1.19 14 H X X  ? N U/E Need to discuss this question. The first part of the question does not seem to relate to the loss of vital 120VAC power which would mean that the K/A was not matched and would make the question unsatisfactory. Do you have any breakers that are controlled by AC power for plausibility of the distractor? Are the applicants expected to know by memory what APN-5901 is along with its loads?

K/A 057G.2.1.30 5/5/16 - Revised question is satisfactory.

3 K/A 062AK3.03 (This is a replacement K/A.)

15 H X X N U What is the significance of reading step 1 of AOP-117.1?

The title of AOP-117.1 is not TOTAL LOSS OF SERVICE WATER.

Based on step 15 of AOP-117.1, it appears that cooling to each diesel generator must be manually aligned, therefore the selected answer choice is not fully correct. I understand that the pump starts automatically, but there appears to be valves that must be manually aligned. The question also does not seem to be worded to ask for a reason, therefore is not a good K/A match. I have a very easy fix that we can discuss.

Question is unsatisfactory due to incorrect answer and K/A mismatch.

4/29/16 - Reviewed the revised question. The question stem asks whether fire service water will be initiated manually or automatically in accordance with the AOP. The AOP directs that it be done manually, but the conditions listed would have caused it to be done automatically. Need to tighten up the question.

5/4/2016 - Revised question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 065AA1.05 16 H X X B E Distractor A and C are not plausible, especially with power at 5%.

5/4/2016 - Revised question is satisfactory.

3 K/A 077AK2.06 17 H X M E Need a dash in AP-301.1 in the question statement.

The a in the first question statement needs to removed and placed in choices C.1) and D.1).

4/29/16 - Revised question is satisfactory.

3 K/A WE05EK2.2 18 F X X B E For the plausibility of distractor A with the conditions given, if feed and bleed was not required and sufficient SGWL was available, why would steaming be done through the SG PORVs?

4/29/16 - Revised question is satisfactory.

3 K/A 024AK3.01 19 F X X N E The note in the Lo-Lo ARP states that shutdown margin is in question. Choice B.2) plausibility is weak with no AFD indications given.

4/29/16 - Revised question is satisfactory.

2 K/A 036AA2.03 20 H N S Question is satisfactory.

3 K/A 059AA1.02 21 H N S Question is satisfactory.

3 K/A 069AK2.03 22 F X M U This should be K/A 069G2.2.42.

Choice B is not plausible when both questions are considered together. Choice C is not plausible since you have stated that both doors are inoperable due to bad seals.

Question is unsatisfactory due to two non-plausible distractors.

5/5/16 - Revised question is satisfactory.

3 K/A 074EK3.11 (This is a replacement K/A.)

23 F X B E Should probably complete the sentence and state that a small break LOCA has occurred.

4/29/16 - Revised question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A WE01EK1.1 24 F X N U Question was submitted for preliminary ten sample question review and will not be used for evaluating the quality of the final submittal.

The ES-401-4 states that this should be K/A WE01EK1.2.

Question does not appear to meet the K/A of the replacement K/A.

Question is unsatisfactory due to K/A mismatch.

5/4/2016 - Revised question is satisfactory.

3 K/A WE03EK2.1 25 H M S Question is satisfactory.

3 K/A WE13EA2.1 26 F X N E Choice D is not plausible.

5/4/2016 - Revised question is satisfactory.

3 K/A WE16EK2.2 27 F N S Question is satisfactory.

3 K/A 003K6.02 28 H X N U If you lose seal injection, then how could differential pressure remain stable? If you normally have seal injection and thermal barrier cooling and then lose one, how could temperature remain stable.

Question is unsatisfactory due to two non-plausible distractors.

5/5/16 - Revised question is satisfactory.

3 K/A 003K6.04 29 H B S Is MVG-9568 TO RB LOAD or LOADS? Question is otherwise satisfactory.

3 K/A 004K3.08 30 H N S Question is satisfactory.

2 K/A 005K5.01 31 H N S Question is satisfactory.

3 K/A 006A4.07 32 H X X N U Is there more to the valve nomenclature than CHG PP? If not, do you expect the applicants to recognize that it is a mini-flow isolation.

When you state that transfer to cold leg recirculation is complete, how can suction from the RWST be plausible. Question is unsatisfactory due to two non-plausible distractors.

4/29/16 - Revised question is satisfactory.

3 K/A 007A3.01 (This is a replacement K/A.)

33 H N S Question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 008A1.01 34 H X N E Question was submitted for preliminary ten sample question review and will not be used for evaluating the quality of the final submittal.

Need to discuss whether VCT level being lower would be a better distractor and not possibly have two correct answers for a period of time.

4/29/16 - Revised question is satisfactory.

3 K/A 008K3.03 35 F N S Question is satisfactory.

3 K/A 010K1.08 36 H N S Question is satisfactory.

3 K/A 012A2.05 37 H N S Question is satisfactory.

3 K/A 012A4.02 38 H M S Question is satisfactory.

3 K/A 013K2.01 39 F N S Question is satisfactory.

3 K/A 013K5.02 40 H X B U Choices A and C are not plausible. Question is unsatisfactory due to two non-plausible distractors.

4/29/16 - Reviewed revised question. Do not believe that choices C and D are plausible because they would lead to a 3 of X coincidence. Do you have any logic that requires 3 of X?

5/3/16 - Revised question is satisfactory.

3 K/A 022A3.01 41 H B S Question is satisfactory.

3 K/A 026G2.2.44 (This is a replacement K/A.)

42 H N S Question is satisfactory.

3 K/A 039A2.01 43 F N E It may be confusing that the rate of steam generator pressure decrease is given in two different units in the conditions.

4/29/16 - Revised question is satisfactory.

3 K/A 039K4.07 44 F X M S Question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 059A2.11 45 F X M E Choices B.2) and D.2) are not plausible because the initial conditions state that the valve will not move manually. Need to specify from the control board.

4/29/16 - Revised question is satisfactory.

3 K/A 061K6.02 46 H X B S/E What is the difference between IFV-3531(3541)(3551) and FCV-3531(3541)(3551)?

Licensee is changing answer choices to FCV.

4/29/16 - Revised question is satisfactory.

3 K/A 062A1.01 47 F X M E A partial loss of all off-site power? Some of the choices do not work grammatically with the question stem. Is choice D an or, an and, or and/or?

5/3/16 - Revised question is satisfactory.

2 K/A 062K1.04 48 H B S Question is satisfactory.

2 K/A 063A1.01 49 F  ? B E/U Need to discuss and ensure that this is not an SRO level bases knowledge question. If this were a license level mismatch, the question would be unsatisfactory.

4/29/16 - Reviewed revised question. The question stem should state contain vice contains.

5/3/16 - Revised question is satisfactory.

3 K/A 064G2.4.1 50 H X X N E The immediate actions should match the step name in the applicable procedure. The first part of distractors A and B are from the same step in EOP-13.0. This would make distractor B not plausible.

4/29/16 - Revised question is satisfactory.

3 K/A 073K4.01 (This is a replacement K/A.)

51 F X B S Question is satisfactory.

3 K/A 076K2.04 52 F B S Question is satisfactory.

3 K/A 078K1.04 53 H B S Question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 103A3.01 54 F B S Are there any sample valves closed by phase A or B that are normally open? Do you expect operators to know the normal position for sample valves listed in chemistry procedures? Is it their job function?

Operations Management representative states that this is expected knowledge.

3 K/A 103G2.4.6 55 F B S Question is satisfactory.

3 K/A 002K6.06 56 H X B E Question stem needs to be slightly reworded. Power should be restored not the loss of power.

4/29/16 - Revised question is satisfactory.

3 K/A 015K5.18 57 H X N E Need to be specific about the time frame for the second part question. Would it be better to ask the direction vice closer to or farther from the upper limit?

4/29/16 - Revised question is satisfactory.

3 K/A 016A4.01 58 H X M E Do not believe that it is plausible for Tref to be median selected or averaged when the initial conditions state that it is selected to 446.

Choice C.2) is not plausible.

5/4/2016 - Revised question is satisfactory.

3 K/A 033K3.03 (This is a replacement K/A.)

59 F X N S Should the answer choices be 1DA2/1DB2 vice 1DA/1DB? What loads are on buses 1A and 1B (Just need to verify that they are plausible)?

Question is satisfactory.

3 K/A 034K1.01 60 F X M U This question does not appear to match the K/A. Question is unsatisfactory due to K/A mismatch.

5/3/16 - Revised question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 1.5 K/A 035K3.02 61 H X N E Although ensuring the reactor makeup system is in auto is listed in EOP-1.2, I dont believe that it is a plausible distractor for this situation and makes level of difficulty very low.

5/3/16 - Revised question is satisfactory.

3 K/A 071A1.06 62 F M S Question is satisfactory.

5/18/16 - Original question replaced due to overlap with the audit exam. New question is satisfactory.

3 K/A 072A2.02 63 H X B U Question is unsatisfactory due to K/A mismatch. I do not believe that this is an area radiation monitor. Isnt it a process radiation monitor?

5/4/2016 - Revised question is satisfactory.

3 K/A 079K4.01 64 F B S Question is satisfactory.

3 K/A 086G2.4.49 65 F  ? N SE Question is satisfactory.

1 K/A G2.1.25 (This is a replacement K/A.)

66 H M U Question is unsatisfactory due to LOD=1.

5/5/16 - Revised question is satisfactory.

3 K/A G2.1.34 67 F X N E It would probably be safer to ask if the TS does or does not apply in mode 5.

4/29/16 - Revised question is satisfactory.

3 K/A G2.1.37 68 F M S Question is satisfactory.

3 K/A G2.2.14 69 H  ? B E Do you expect operators to know the normal position of this particular valve from memory?

4/29/16 - Revised question is satisfactory.

3 K/A G2.2.2 (This is a replacement K/A.)

70 F N S Question is satisfactory.

3 K/A 033K3.02 71 F M S This should be K/A 2.3.13 Question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A G2.3.4 72 H X M U This question is unsatisfactory because it overlaps with an administrative JPM.

5/4/2016 - Revised question is satisfactory.

3 K/A G2.1.20 73 H X N E This should be K/A 2.4.12.

Do you expect operators to remember actions by step number?

4/29/16 - Revised question is satisfactory.

3 K/A G2.4.47 74 H N U Question is unsatisfactory due to LOD =1.

5/4/2016 - Revised question is satisfactory.

1.5 K/A G2.4.6 75 F X N U Choices A and D are not plausible. Just because an action is listed in another procedure does not necessarily mean that it is plausible for the given plant conditions.

4/29/16 - Revised question is satisfactory.

3 K/A 007EA2.02 76 H X M E Need to reword question stem to be in accordance with E-0, the crew is required to transition to. The second part of distractor C could be considered a subset of the other second part choices. You may actually be in the source range with a negative startup rate prior to adding that much borated water. However, it is not really plausible wording for an EOP step. Need to discuss whether or not this is overlap with question #1.

5/4/2016 - Revised question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 1 K/A 009EG2.4.47 77 H X X N U This question is LOD =1 with the references provided. Question is unsatisfactory due to LOD=1.

Yellow and Red Path entry conditions are RO knowledge. When you are to the left of the line that is furthest away from the region of acceptable operation, how could is not be the correct answer.

Although bases knowledge can be SRO only knowledge, not all information listed in the bases is. Do you have an SRO only learning objective for this information?

4/29/16 - Reviewed revised question. Need to include in the second part question that is in accordance with 5/5/16 - Revised question is satisfactory.

3 K/A 011EA2.05 78 F X X N U The valve nomenclature given in the question does not exactly match what is given in EOP-2.2. Need to further discuss this question. Are two charging pumps running in the initial conditions or not. Is runout ever a concern for your charging pumps?

All answer choices should begin with the same words: C should be closed while in This does not appear to be SRO only. You have an RO objective in your lesson plan for knowing the bases or reasons for cautions and notes in EOP-2.2.

Question is unsatisfactory due to not being SRO only.

5/4/2016 - Revised question is satisfactory.

3 K/A 026AG2.2.22 79 H M S Question is satisfactory.

3 K/A 054AG2.1.23 80 H X X N U WOOTF statement should say procedure SRO should implement next? or ...required to be implemented next? rather than CRS will, if the CRS waited before making a decision, the CRS will implement E-0 next.

Question is unsatisfactory because it is not SRO only. This question can be answered with RO knowledge alone.

5/4/2016 - Revised question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 077AA2.09 (This is a replacement K/A.)

81 H X X N E Choice A should say, Transition to COLD SHUTDOWN is not required with the current conditions.

4/29/16 - Revised question is satisfactory.

3 K/A 001AA2.04 82 H X X N WOOTF statement should say words to the effect of what is required or what the procedure requires to be done rather than what the CRS will do.

Does not meet SRO only criteria:

Knowledge of entry conditions for AOPs is RO level. Knowing all entry conditions for AOP 403.3 and AOP 401.7 doesnt meet requirement for 10CFR55.43(b)5 - procedure selection.

U Question is unsatisfactory because it is not SRO only.

K/A 001AA2.03 5/4/2016 - New question does not meet the K/A at the SRO level.

5/5/16 - Newer question does not meet the Continuous Rod Withdrawal portion of the K/A and the thermodynamics combined with the feed status and steam generator level status does not seem to be operationally valid.

5/18/16 - Revised question is satisfactory.

3 K/A 060AG2.1.20 83 H N E-plan S

Question is satisfactory.

3 K/A 061AA2.06 84 H N TS question S

Question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 069AG2.4.21 (This is a replacement K/A.)

85 F X X M E The The at the beginning of choice A.2) should not be capitalized.

4/29/16 - Revised question is satisfactory.

3 K/A 012A2.05 86 H B TS question S

Question is satisfactory.

3 K/A 039A2.01 87 H M S

Question is satisfactory.

3 K/A 076AG2.4.6 88 H X B S Question is satisfactory.

3 K/A 078A2.01 89 H X N TS question WOOTF statement should say latest time by which the plant must E be placed The second bullet at time 0030 does not read well.

4/29/16 - Revised question is satisfactory.

3 K/A 103G2.1.7 90 H N E-plan S

Question is satisfactory.

3 K/A 028A2.03 91 F X N For answer choice D, spell out procedures the same as in other choices. Why does the WOOTF say, if any at the end?

Choice A is not plausible in that it is the only choice with SOP-114 U where all the others are parts of SOP-122. Choice D is not plausible to have the option to choose either procedure.

Question is unsatisfactory due to two non-plausible distractors.

5/4/2016 - Revised question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A 068A2.04 (This is a replacement K/A.)

92 H N TS question (ODCM)

S Question is satisfactory.

3 K/A 071G2.2.38 (This is a replacement K/A.)

93 H X N Question was submitted for preliminary ten sample question review and will not be used for evaluating the quality of the final submittal.

E Remove the word shutdown from choices A and C to improve plausibility. Shutdown too directly points at answer.

4/29/16 - Revised question is satisfactory.

1 K/A G2.1.13 94 H N Question is unsatisfactory due to LOD = 1. With the reference provided, the applicant only needs to know that the diesel is in a vital area, a diesel part is not special nuclear material, tailgating is not a U failure of a safeguard system, and there is more than one diesel.

With the reference, this seems to be nearly GET level.

5/3/16 - Revised question is satisfactory.

3 K/A G2.2.12 95 H X M TS question Choice D is not plausible since the reference is given and clearly E states that 18 months is for a different surveillance than what is identified in the stem of the question.

4/29/16 - Revised question is satisfactory.

3 K/A G2.2.44 96 F B S Question is satisfactory.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 K/A G2.3.14 97 H X N Question was submitted for preliminary ten sample question review and will not be used for evaluating the quality of the final submittal.

E-plan E The third bullet in the given conditions has an extra is in it.

4/29/16- Reviewed revised question. Third bullet should have units.

5/4/2016 - Revised question is satisfactory.

3 K/A G2.3.6 98 H X B Does not meet SRO only criteria:

The question requires knowledge on the RO level according to HPP-709 lesson plan objectives. It is RO level of knowledge that a sample is required prior to releasing a tank that has been in service, and RO knowledge that a tank should not be release with wind from U a certain direction. This is considered system knowledge.

This question overlaps with question # 62.

Question is unsatisfactory due to not being SRO only.

5/4/2016 - Revised question is satisfactory.

3 K/A G2.4.18 99 F X M Two non-plausible distractors:

Contrary to the distractor analysis, the first part of choices A and B is not plausible because the first step of EOP-4.0 is to check for RCP trip criteria. This is also a continuous action step.

U Question is unsatisfactory due to two non-plausible distractors.

4/29/16- Reviewed revised question. The word vent at the end of choices B.2) and C.2) should be event.

5/4/2016 - Revised question is satisfactory.

3 K/A G2.4.31 100 H N S Question is satisfactory.

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

7. 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?

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

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: V.C. Summer (Unit 1) Date of Exam: 6/16/2016 Exam Level: RD [?1sRo [

Item Description Initials a b c

1. Clean answer sheets copied before grading

2. Answer key changes and question deletions justified and documented l r)J

3. Applicants scores checked for addition errors (reviewers spot check > 25% of examinations) 4/

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

5. All other failing examinations checked to ensure that grades are Justified 4

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants r L.

Printed Name/Signature Date

a. Grader es 6/tv/is

b. Facility Reviewer(*)

c. NRC Chief Examiner(*) 1L t6ø.

d. NRC Supervisor (*) 4vwu.. 7/i(t

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

Neil E. Constance Manager, Nuclear Training 803.345.4028 August 17, 2015 A SCANA COMPANY Mr. Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety U. S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257

Subject:

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATION OUTLINES Based on the guidelines in NUREG-1 021, Operator Licensing Examination Standards for Power Reactors, Revision 10, in particular ES-201, Initial Operator Licensing Examination Process and ES-301, Preparing Initial Operating Tests, South Carolina Electric & Gas Company (SCE&G) has enclosed the following information for your consideration:

• Enclosure 1 ES-201-2, Examination Outline Quality Checklist

• Enclosure 2 ES-201-3, Examination Security Agreement

• Enclosure 3 ES-301-1, Administrative Topics Outline

• Enclosure 4 ES-301-2, Control Room/In-Plant Systems Outline

• Enclosure 5 ES-301-5, Transient and Event Checklist

• Enclosure 6 ES-D-is, Scenario Outlines The enclosed examination materials have been independently reviewed by Mt. Steven M.

Billingsley, Shift Manager, Operations.

In accordance with NUREG-1 021, this material must be withheld from public disclosure until the examinations are complete.

Should there be any questions, please contact Mr. Robert N. Johnston, Nuclear Trainer-Principle, at (803) 931-5173.

Very truly yours, c4,qe Neil E. Constance TS/N EC/kb Enclosures c: (Without Enclosure unless noted)

D. M. Bacon (NRC e-mail notification) RTS (CR-i 5-03755)

NRC Resident Inspector File (814.04, RR 1050)

PRSF (RC-15-0136)

V. C. Summer Nuclear Station P.O. Box 88. Jenkinsville, SC. 29065. F (803) 941-9776

FOR-OFIGlAL-USE-ONLY Neil E. Constance Manager, Nuclear Training 803.345.4028 April 5, 2016 SCE&1 A SCANA COMPANY Mr. Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety U. S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257

Subject:

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 REACTOR AND SENIOR REACTOR OPERATOR WRITTEN EXAMINATION, OPERATING TEST, AND SUPPORTING REFERENCE MATERIAL Based on the guidelines in NUREG-1 021, Operator Licensing Examination Standards for Power Reactors, Revision 10, in particular ES-301, Preparing Initial Operating Tests, South Carolina Electric & Gas Company is providing the following information for your consideration.

• ES-201-2, Examination Outline Quality Checklist

• ES-201-3, Examination Security Agreement

• ES-301-1, Administrative Topics Outline

• ES-301-2, Control Room/In-Plant Systems Outline

• ES-301-3, Operating Test Quality Checklist

• ES-301-4, Simulator Scenario Quality Checklist

• ES-301-5, Transient and Event Checklist

• ES-301-6, Competencies Checklist

• ES-401-4, Record of Rejected K/As

• ES-401-6, Written Exam Quality Checklist

• Written Exam Hard Copy with Supporting Documentation

• Written Exam Electronic Files on DVD-ROM

• Operational Exam Hard Copy

• Operational Exam Electronic Files on DVD-ROM

• Supporting Reference Documentation Files on DVD-ROM The enclosed examination materials have been independently reviewed by Mr. Steven M. Billingsley, Shift Manager. In accordance with NUREG-1 021, this material must be withheld from public disclosure until the examinations are complete.

Should there be any questions, please contact Mr. Robert N. Johnston at (803) 931-5173.

Very truly yours, Neil E. ontance TS/NEC/rp Enclosures c: (Without Enclosures unless noted) NRC Resident Inspector G. J. McCoy RTS (CR-i 5-03755)

D. M. Bacon File (814.04, RR 1050)

R. N. Johnston DMS (RC-16-0051)

V. C. Summer Nuclear Station . P.O. Box 88. Jenkinsville, SC.29065. F (803) 941-9776

- FOR OFFICIAL USE ONLY Neil E. Constance Manager, Nuclear Training Ju 22, 2016 A SCANA COMPANY Mr. Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety U. S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 INITIAL OPERATOR LICENSE EXAMINATION POST EXAMINATION SUBMITTAL The VCSNS Initial Operator License Examination was administered during the weeks of June 6, 2016 and June 13, 2016. The VCSNS Initial License Written Examination was administered on June 16, 2016. VCSNS is enclosing the following as required by Revision 10 of NUREG 1021, Operator Licensing Examination Standards for Power Reactors:

1. Each applicants original answer and examination cover sheets plus two clean copies of each applicants answer sheet;

2. The master examinations and answer keys;

3. Questions asked by and answers given to the applicants during the written examination;

4. Written examination seating chart; and

5. Written examination performance analysis.

There are no formal post-examination comments for this examination. VCSNS does not request a change to any examination item. As agreed, the examination security agreement will be sent via email at a later date.

If you require any additional information or have any questions, please contact Robert Johnston at (803)931-5173.

Very truly yours, Neil E. Constance TS/N EC/sr Enclosures c: (Without Enclosure unless noted)

C. Haney RTS (CR-i 5-03755)

D. M. Bacon (NRC e-mail notification) File (814.04, RR 1050)

NRC Resident Inspector PRSF (RC-16-0105)

V. C. Summer Nuclear Station . P.O. Box 88 ienkinsville, Sc. 29065. F (803) 941-9776