ML17192A181

301 Exam Administrative Items 2C - Delay Release 2 Yrs

ML17192A181
Person / Time
Site:	Catawba
Issue date:	07/11/2017
From:	NRC/RGN-II
To:
References
Download: ML17192A181 (94)

Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: C/17i1&v13,4 Date of Examination: iZ4Y 2&/o Developed by: Wntten: Facility NRC II Operating Facility NRC Target . Chief Task Description (Reference) a e Examiners Initials

-180 1. Examination administration date confirmed (Cia; C.2.a and b) .7

-150 2. NRC examiners and facility contact assigned (C.1 .d; C.2.e) 77

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

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

[-1201 5. Reference material due (C.i.e; C.3.c; Attachment 3)

{-90} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1, ES-401-1!2, ES-401 N-1/2, ES-401-3, ES-401 N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and 1; 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 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

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

-14 13. Final license applications due and Form ES-201-4 prepared (C.1.l; 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/written exam administration guidelines reviewed with facility licensee (C.3.k)

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

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

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

- F/N/IL A1 YT %PFIeOVAL ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Catawba Nuclear Station Date of Examination: May 2016 Item Initials Task Description a b c#

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

, 41

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.

L4.1

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

N

d. Assess whether the justifications for deselected or rejected KJA statements are appropriate.

..4

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the requited 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 c 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 Lcy

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

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

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks 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 I the form.

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

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

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

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

E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 1

c. Ensure that KJA importance ratings (except for plant-specific priorities) are at least 2.5. j 1

d. Check for duplication and overlap among exam sections. t.1 L e. Check the entire exam for balance of coverage.

r .....i.

)r WI

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

Date

a. Author 05/11/16 b Facility Reviewer (*)

05/11/16

c. NRC Chief Examiner (#) O//j/,? /

d NRC Supervisor 5,*op Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines.

F/N,,lt &F,?A7wL 7sr ,41me vIL -

Wi?/ 7TEv 1ExA-E5-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Catawba Nuclear Station Date of Examination: May 2016 Item Initials Task Description a b c#

1 a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401N. 41

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/Acategorias are appropriately sampled. t WI tl

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

N tvy ,,,

d. Assess whether the justifications for deselected or rejected KJA statements are appropriate.

% M

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major 1 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 LLI T applicants audit test(s), and that scenarios will not be repeated on subsequent days.

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

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks 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. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

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

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

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

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

E tk 07

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. t41 R d. Check for duplication and overlap among exam sections. 1 L e. Check the entire exam for balance of coverage. t1 7

1. Assess whether the exam fits the appropriate job level (RO or SRO). ?tr 14 Printed me/Sign e Date

a. Author Bruce Boyette / 05/11/16

b. Facility Reviewer (*) Walter Hunnicutt / b 05/11/16

c. NRC Chief Examiner (#)

d. NRC Supervisor

1. ,Cd%AE

&eC

/tEfk5 f

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

Not applicable for NRC-prepared examination outlines.

%/flEA1

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 m To the best of my nowlqdg9, Co I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during r.) the week(s) of 57/4 - 7.23 / tt,o . From the date that I entered into this security agreement until the completion of examination administration, I did instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing not examinations, except as specifically noted

-D 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 date of my signature. I agree that I will not knowingly divulge any information about these for the week(s) of 252%. of the examinations to any persons who have n6t been authdrized 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 kpowlede, I did

0) not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of /z3% .

ci From the date that I entered into this security agreement until the completion of examination administratio n, I did not

-s instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted

-U below and authorized by the NRC.

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NOTES:

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 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 knowlede, l1did not divulge CD to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 57 .7Z4 From the date that I entered into this security agreement until the completion of c examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations

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

1. Pre-Examination

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I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of s /(,

Y (/AI / /thS of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who havenot 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

Cl) To the best of my kçiowledg9, I d not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during rJ the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not C instruct, evaluate, or provide erformance 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-301 Administrative Topics Outline Form ES-301-J NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2016 Examination Level: RO SRO Operating Test Number: 2016301 Administrative Topic Tvne

• Describe activity to be performed (See Note) Code Determine Status of NC System Fill and Vent Conduct of Operations R,N G2.1 .25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9/4.2 Calculate FWST makeup Conduct of Operations R,N G2.1 .23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.3/4.4 Classify a DG start and complete log entry Equipment Control R,D G2.2.12 Knowledge of surveillance procedures. 3.7/4.1 Determine RP Requirements G2.3.7 Ability to comply with radiation work permit Radiation Control R,D,P requirements during normal or abnormal

. conditions. 3.5/3.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

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

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

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

ES 301, Page 22 ot 27

Admin JPMs JPM Al-i Determine Status of Reactor Coolant system Fill and Vent (Common RO & SRO) NEW JPM K/A Generic 2. 7.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR 47.70/43.5/45.72) RO 3.9 SRO 4.2 Initial conditions are that initial venting of the Reactor Coolant System has been completed following a refueling outage. The applicant will use supplied information to determine if the system has reached a Loops Filled condition in accordance with OP/1/N6150/001 (Filling and Venting the Reactor Coolant System). The applicant will perform calculations directed by the procedure to determine change in Volume Control Tank level by subtracting final from initial level indications and performing a conversion of 3/4 level to gallons. This value will then be summed with makeup volume required to pressurize the system. The total volume will be used (based on system temperature) for comparison with a curve contained within an enclosure of this procedure. Once complete, applicant will determine that the system has NOT reached a Loops Filled condition.

JPM A.i-2R Calculate boric acid and water addition to FWST. (RO ONLY) New JPM K/A Generic 2.7.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR 47.70 / 43.5 / 45.2 / 45.6) RO 4.3 SRO 4.4 Initial conditions are that an improper valve lineup has decreased Unit 1 FWST level. The valve lineup issue has been corrected to stop the level decrease. The applicant is directed to calculate a makeup to the FWST to restore level to a value above the Tech Spec minimum.

JPM A.2 Classify a DIG Start and Complete a Logbook Entry (Common RO & SRO) Bank JPM DG3-10 K/A Generic 2.2.72 Knowledge of surveillance procedures. (CFR 47.70/45.73) RO 3.7 SRO 4.7 Initial conditions are that a surveillance test of the 2B D/G has been conducted. Start times, frequency and voltage information, and generator loading times are supplied. Also supplied, the time at which the engine tripped due to malfunction of an oil pressure switch. The applicant will be required to determine the classification of this surveillance test in accordance with OMP 2-28 (Diesel Generator Logbook) and complete the associated Log Sheet.

JPM A.3 Determine Radiation Protection Requirements for an Activity (Common RO & SRO) Bank JPM (2015 NRC Exam)

K/A Generic 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR 47.72/45.70) RO 3.5 SRO 3.6 Initial conditions are that Unit 1 has entered AP/1/A15500/019 (Loss of Residual Heat Removal).

The CRS has sent the applicant to the 1A ND pump room to stand by in a low exposure waiting area and await word to vent 1A ND pump. The applicant is given a copy ot RWP # 5021 (ECCS venting) and a copy of a plan view for 1A ND pump room and a timeline for the evolution. They are directed to calculate their total dose received for the job and to determine the latest time that they could finish the venting without exceeding any of the RWP requirements (In this case 25 mRem dose).

ES-301 Administrative Topics Outline Form ES-301-J NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2076 Examination Level: RO fl SRO Operating Test Number: 2016307 Administrative Topic Tvne

• Describe activity to be performed (See Note) Code Determine Status of NC System Fill and Vent Conduct of Operations R,N G2.1 .25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9/4.2 Calculate FWST makeup and Tech Spec actions Conduct of Operations R,N G2.1 .23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.3/4.4 Classify a DG start and complete log entry Equipment Control R,D G2.2.12 Knowledge of surveillance procedures. 3.7/4.1 Determine RP Requirements Radiation Control G2.3.7 Ability to comply with radiation work permit R,D requirements during normal or abnormal conditions. 3.5/3.6 Determine PARs Emergency Procedures/Plan R,N G2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. 2.7/4.5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

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

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

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

ES 301, Page 22 of 27

Admin JPMs JPM A.1-1 Determine Status of Reactor Coolant system Fill and Vent (Common RO & SRO) NEW JPM K/A Generic 2. 1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR 41.10/43.5/45.12) RO 3.9 SRO 4.2 Initial conditions are that initial venting of the Reactor Coolant System has been completed following a refueling outage. The applicant will use supplied information to determine if the system has reached a Loops Filled condition in accordance with 0P111A161501001 (Filling and Venting the Reactor Coolant System). The applicant will perform calculations directed by the procedure to determine change in Volume Control Tank level by subtracting final from initial level indications and performing a conversion of % level to gallons. This value will then be summed with makeup volume required to pressurize the system. The total volume will be used (based on system temperature) for comparison with a curve contained within an enclosure of this procedure. Once complete, applicant will determine that the system has NOT reached a Loops Filled condition.

JPM A.1-2S Calculate boric acid and water addition to FWST and determine applicable Tech Spec actions. (SRO ONLY) New JPM K/A Generic 2.7.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR 47.70/43.5/45.2/45.6) RO 4.3 SRQ 4.4 Initial conditions are that an improper valve lineup has decreased Unit 1 FWST level. The valve lineup issue has been corrected to stop the level decrease. The applicant is directed to calculate a makeup to the FWST to restore level to a value above the Tech Spec minimum. Following makeup calculation, the applicant is required to address Tech Specs action at the time of discovery and one hour later. The applicant will conclude an action statement existed at time of discovery due to level below minimum required. One hour later, with a given makeup flowrate, the applicant will determine that level remains below minimum. This will require entry into another action due to inability to restore operability within one hour, as well as remaining in original action statement.

JPM A.2 Classify a D/G Start and Complete a Logbook Entry (Common RO & SRO) Bank JPM DG3-10 K/A Generic 2.2.72 Knowledge of surveillance procedures. (CFR 47.70/45.73) RO 3.7 SRO 4.7 Initial conditions are that a surveillance test of the 2B DIG has been conducted. Start times, frequency and voltage information, and generator loading times are supplied. Also supplied, the time at which the engine tripped due to malfunction of an oil pressure switch. The applicant will be required to determine the classification of this surveillance test in accordance with OMP 2-28 (Diesel Generator Logbook) and complete the associated Log Sheet.

Admin JPMs 1PM A.3 Determine Radiation Protection Requirements for an Activity (Common RO & SRO) Bank JPM (2015 NRC Exam)

K/A Generic 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR 47.72/45.10) RO 3.5 SRO 3.6 Initial conditions are that Unit 1 has entered AP/1/N5500/019 (Loss of Residual Heat Removal).

The CRS has sent the applicant to the 1A ND pump room to stand by in a low exposure waiting area and await word to vent 1A ND pump. The applicant is given a copy of RWP # 5021 (ECCS venting) and a copy of a plan view for 1A ND pump room and a timeline for the evolution. They are directed to calculate their total dose received for the job and to determine the latest time that they could finish the venting without exceeding any of the RWP requirements (In this case 25 mRem dose).

1PM A.4 Determine Protective Action Recommendations per RP/0/A/5000/005 (General Emergency)

(SRO ONLY) NEW JPM K/A Generic 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. (CFR 47. 70 /

43.5/45.77) RO 2.7 SRO 4.5 Initial conditions are that a series of events have occurred which results in the declaration of a General Emergency. The applicant is required to determine Protective Action Recommendations per RP/0/N5000/005 (General Emergency), step 2.3. This step will direct the applicant to an enclosure containing a flow chart. The first decision point is to determine if this is a Rapidly Progressing Severe Accident (RPSA). The applicant will be required to review RPSA criteria and then compare information supplied in the initial conditions with Containment Barrier criteria (both Loss and Potential Loss) contained in RP/0/N5000/001 (Classification of Emergency). Once the applicant has determined that the RPSA criteria does apply, they will proceed through the flow chart and be directed to another enclosure containing recommendations for evacuation and shelter. The candidate will then perform a calculation in order to determine correct wind direction and list associated PARs contained within a table.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2016 Exam Level: RD SAD-I SRO-U E Operating Test Number: 2016301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Fn

a. Respond to Inadvertent Dilution While Shutdown AL N S 1 004 A2.06

b. Transfer to Hot Leg Recirc. A N EN,L,S 2 013 A2.01

c. Initiate RCS Bleed and Feed N,L,S 4P E05 EA1.1 U. Isolate Cold Leg Accumulators during Shutdown LOCA AD L P S 3 006 A1.13

e. Operate Containment Cooling Fans N,S 5 022 A4.01

f. Shift operating Condenser Circulating Water Pumps A,N,S 8 075 02.1.23

g. Initiate a VO Release (Containment Air Release) D,S 7 073 A4.03

h. Verify Blackout Busses Energized D,S 6 062 A4.01 In-Plant Systems© (3 for RO); (3 for SAD-I); (3 or 2 for SRO-U)

i. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF) D,E,L,R 5 028 G2.1.30

j. Energize 1SLXG A,D,E 6 062 A2.01

k. Unit 2 Spent Fuel Pool makeup from RN D,E,R 8 033 A2.03

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

• Type Codes Criteria for RD / SRD-I / SAC-U (A)lternate path 4-6 / 4-6 I 2-3 (5/5/3)

(C)ontrol room (D)irect from bank < 9 / < 8 / < 4 (6/5/2)

(E)mergency or abnormal in-plant 1 / 1 / 1 (3/3/2)

(EN)gineered safety feature - / - I 1 (1/1/1)

(L)ow-Power / Shutdown > 1 / > 1 / > 1 (5/5/4)

(N)ew or (M)odified from bank including 1 (A) 2 / 2 I 1 (5/5/3)

(P)revious 2 exams < 3 < 3 / < 2 (1/1/0)

(R)CA > 1 / > 1 I > 1 (2/2/1)

(S) i mu lator ES-3d, Page 23 of 27

Simulator JPMs JPM a Respond to an Inadvertent Dilution While Shutdown New JPM - Alternate Path K/A 004 A2. 06 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent boration/dilution (CER: 47.5/43/5/45/3/45/5)R042/SRO4.3 Initial conditions are that the unit is in Mode 3, with Shutdown banks withdrawn, and a boron dilution event in progress. The applicant is directed to perform Case II of AP/1/N5500/013 (Boron Dilution).This procedure will direct the applicant to manually trip the reactor and align the charging system for normal boration. During system alignment, the boric acid to blender control valve will fail to open to begin the ALTERNATE PATH. Once verification that no boric acid flow exists, the applicant will transition to the procedure RNO and open the emergency boration supply valve to complete this JPM.

JPM b Transfer the ECCS to Hot Leg Recirculation NEW JPM - Alternate Path K/A 073 A2. 07 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on ability of those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; LOCA.

(CFR: 41.5/43.5/45.3/45.73) RO 4.6/SRO 4.8 Initial conditions are that a LOCA has been in progress for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The CRS instructs the applicant to transfer to Hot Leg Recirculation lineup per EP/1/N5000/ES-1.4 (Transfer to Hot Leg Recirculation). The applicant will successfully secure the 1A Safety Injection Pump and begin valve manipulations to align this train for HLR. When attempted, the Hot Leg Injection isolation valve (1NI-121A) will not open beginning the ALTERNATE PATH. The applicant will then transition to the RNO and attempt to align lB train Safety Injection for HLR while dispatching an operator to manually open 1NI-121A. Upon alignment, the lB Safety Injection Pump will fail to start. The applicant will receive notification that 1NI-121A is open, transition to the required procedure step, complete alignments, and successfully place 1A Safety Injection System in HLR.

JPM c Initiate RCS Bleed and Feed following loss of Secondary Heat Sink New JPM K/A E05 EA 7.7 Ability to operate and/or monitor the following as they apply to the (Loss of Secondary Heat Sink); Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR 47.7 / 45.5 / 45.6) RO 4. 1 SRO 4.0 Initial conditions are that a Reactor Trip has occurred due to a loss of both main feed pumps.

The Auxiliary Feedwater Pumps will not function. EP/1/N5000/FR-H.1 has been entered and Bleed and Feed initiation criteria has been met. The applicant is directed to initiate Bleed and Feed in accordance with FR-H.1 Applicant will initiate both trains of Safety Injection, open 2 pressurizer PORVs, and align Cold Leg Accumulator nitrogen to the PORVs.

Simulator JPMs JPM U - Isolate Cold Leg Accumulators Following a Shutdown LOCA Bank JPM - Alternate Path K/A 006 Al. 73 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration) (CFR: 47.5/45.5) RO 3.5 SRQ 3.7 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/i/N5500/027 (Shutdown LOCA) to address the LOCA. The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 14 (Isolating Cold Leg Accumulators) of AP/27. The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1A and 1D will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will isolate the Nitrogen supply to the lB and 1C Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. This JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take 30 minutes.

JPM e Operate Containment Cooling System Fans NEW JPM K/A 022 A4.07 Ability to manually operate and/or monitor in the control room: CCS fans (CFR 47.7 /

45.5 to 45.8) RO 3.6 SRQ 3.6 Initial conditions are that a secondary steam leak is occurring. The CRS directs the applicant to perform step 9 of AP/i/N5500/028 (Secondary Steam Leak). The applicant will determine, based on conditions specified in the procedure, that the leak is occurring inside containment.

The applicant will then start one additional Lower Containment Ventilation Unit, three additional Upper Containment Ventilation Units, and place all eight operating ventilation units in MAX cooling mode.

JPM f Shift operating Condenser Circulating Water (RC) Pumps - New Alternate Path K/A 075 G2. 7.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR 47.70/43.5/45.2/45.6) RO 4.3 SRO 4.4 Initial conditions are that Unit 1 is at 100% power. The CRS directs the applicant to start 1 D RC Pump and secure lB RC Pump in accordance with OP/i /B/6400/OO1A (Condenser Circulating Water). The applicant will start 1 D RC Pump at which time the associated discharge valve will fail to automatically open beginning the ALTERNATE PATH. The applicant will manually open the discharge valve and attempt to secure lB RC Pump by closing the discharge valve (pump automatically trips following closure of discharge valve). The lB RC Pump will fail to automatically secure upon closure of the associated discharge valve requiring the applicant to manually secure the pump.

JPM g Initiate a Containment air (VQ) release - Bank JPM k/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel (CFR 47.7/45.5 to 45.8) RO 3.7SRO 3.7 Initial conditions are that Unit 1 is at 100% power. The CRS directs the applicant to initiate a containment air release. The applicant will perform the following actions to successfully complete this JPM: verify and document proper EMF setpoints, verify release valve controller setpoint, reset the release totalizer, unisolate release path and start the applicable fan.

Simulator JPMs JPM h Verify Blackout Buses Energized - Bank JPM k/A 062 A4.07 Ability to manually operate and/or monitor in the control room: All breakers (including available switchyard) (CFA 47.7 / 45.5 to 45.8) RO 3.3 SRO 3.1 Initial conditions are that a B train blackout has occurred. The 1 B DIG is supplying essential bus 1ETB. The CRS directs the applicant to perform step 10 of API1/N5500/007 (Loss of Normal Power to an Essential Train) to verify blackout busses energized. The applicant will determine, based on procedural guidance, that blackout bus 1FTB is de-energized, transition to the RNO and align power to this bus.

Plant ]PMs

]PM I Operate 2A Hydrogen Igniters from SSF power supply Bank JPM (RCA entry required)

K/A 028 G.2. 7.30 Ability to locate and operate components, including local controls (CFR 47.7/45.7) RO 4.4 SRO 4.0 Initial conditions are that Unit 2 has entered AP/O/N55001048 (Extensive Damage Mitigation) following an event. The CRS instructs the applicant to align 2A Hydrogen Igniters to the alternate source per OPIOIBI6100IO13 (Standby Shutdown Facility Operations), Enclosure 4.9 (2A Hydrogen Igniters Operation from SSF). The applicant will align alternate power via simulated operation of station breakers, manual transfer switch, and applicable Hydrogen Igniter Start switch.

]PM j Energize 1 SLXG from SSF DIG Bank JPM Alternate Path K/A 062 A2.07 Ability to predict the impacts of the following malfunction or operations on the ac distribution system; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Types of loads that, if de-energized, would degrade or hinder plant operation (CFR 47.5/43.5/45.3/45.73) RO 3.4 SRO 3.9 Initial conditions are Unit 1 has experienced a loss of all Offsite power. The CRS instructs the applicant to energize 1SLXG per AP/11N5500I007 (Loss of Normal Power), Enclosure 24 (Energize 1SLXG). The applicant will attempt to start the SSF DIG in order to energize 1SLXG.

However, the D/G will fail to start beginning the ALTERNATE PATH. The applicant will then engage the Manual Override fuel supply knob and successfully start the SSF D/G. The applicant will complete this JPM by removing 1SLXG loads, closing the D/G supply breaker, and loading 1SLXG.

JPM k Makeup to the Unit 2 Spent Fuel Pool from Nuclear Service Water (RN) Bank JPM K/A 033 A2. 03 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level. (CFR 4 7.5/43.5/45.3/45. 73) RO 3.7 SRQ 3.5 Initial conditions are that Unit 2 Spent Fuel Pool has experienced an un-isolable leak due to a crack caused by a seismic event. The CRS instructs the applicant to initiate a makeup to the Unit 2 Spent Fuel Pool from the 2A train of RN. The applicant will align makeup water flow via operation of plant valves.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2016 Exam Level: RO El SRO-l SRO-U El Operating Test Number: 2076307 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Eu nction

a. Respond to Inadvertent Dilution While Shutdown ALN S 1 004 A2.06

b. Transfer to Hot Leg Recirc. A,N EN L,S 2 013 A2.01

c. Initiate RCS Bleed and Feed N LS 4P EO5EA1.1

d. Isolate Cold Leg Accumulators during Shutdown LOCA A DLP S 3 006 A1.13

e. Operate Containment Cooling Fans N,S 5 022 A4.01

f. Shift operating Condenser Circulating Water Pumps AN S 8 075 G2.1.23

g. Initiate a VQ Release (Containment Air Release) D,S 7 073 A4.03 In-Plant Systems© (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

i. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF) D,E,L,R 5 028 G2.1.30

j. Energize 1SLXG A,D,E 6 062 A2.01

k. Unit 2 Spent Fuel Pool makeup from RN D,E,R 8 033 A2.03

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

• Type Codes Criteria for RO / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (5/5/3)

(C)ontrol room (D)irectfrom bank <9/ <8 / <4 (6/5/2) fE)mergency or abnormal in-plant > 1 / 1 / 1 (3/3/2)

(EN)gineered safety feature - / - / 1 (1/1/1)

(L)ow-Power / Shutdown > 1 / > 1 / > 1 (5/5/4)

(N)ew or (M)odified from bank including 1 (A) > 2 / > 2 / 1 (5/5/3)

(P)revious 2 exams < 3 < 3 / < 2 (1 /1 /0)

(R)CA >1 / >1 / >1 (2/2/1)

(S)imulator ES-301, Page 23 of 27

Simulator JPMs 1PM a Respond to an Inadvertent Dilution While Shutdown New JPM - Alternate Path K/A 004 A2. 06 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent boration/dilution (CFR: 47.5/43/5/45/3/45/5)R04.2/SRO4.3 Initial conditions are that the unit is in Mode 3, with Shutdown banks withdrawn, and a boron dilution event in progress. The applicant is directed to perform Case II of AP/1/N5500/013 (Boron Dilution).This procedure will direct the applicant to manually trip the reactor and align the charging system for normal boration. During system alignment, the boric acid to blender control valve will fail to open to begin the ALTERNATE PATH. Once verification that no boric acid flow exists, the applicant will transition to the procedure RNO and open the emergency boration supply valve to complete this JPM.

1PM b Transfer the ECCS to Hot Leg Recirculation NEW JPM - Alternate Path K/A 073 A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on ability of those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; LOCA.

(CFR: 47.5/43.5/45.3/45.73) RO 4.6/SRO 4.8 Initial conditions are that a LOCA has been in progress for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The CRS instructs the applicant to transfer to Hot Leg Recirculation lineup per EP/1/N5000/ES-1.4 (Transfer to Hot Leg Recirculation). The applicant will successfully secure the 1A Safety Injection Pump and begin valve manipulations to align this train for HLR. When attempted, the Hot Leg Injection isolation valve (1NI-121A) will not open beginning the ALTERNATE PATH. The applicant will then transition to the RNO and attempt to align lB train Safety Injection for HLR while dispatching an operator to manually open 1NI-121A. Upon alignment, the lB Safety Injection Pump will fail to start. The applicant will receive notification that 1NI-121A is open, transition to the required procedure step, complete alignments, and successfully place 1A Safety Injection System in HLR.

1PM c Initiate RCS Bleed and Feed following toss of Secondary Heat Sink New JPM K/A EQS EA 1.7 Ability to operate and/or monitor the following as they apply to the (Loss of Secondary Heat Sink); Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR 47.7 / 45.5 / 45.6) RO 4. 7 SRO 4.0 Initial conditions are that a Reactor Trip has occurred due to a loss of both main feed pumps.

The Auxiliary Feedwater Pumps will not function. EP/1/N5000/FR-H.1 has been entered and Bleed and Feed initiation criteria has been met. The applicant is directed to initiate Bleed and Feed in accordance with FR-H.1 Applicant will initiate both trains of Safety Injection, open 2 pressurizer PORVs, and align Cold Leg Accumulator nitrogen to the PORVs.

Simulator JPMs JPM U - Isolate Cold Leg Accumulators Following a Shutdown LOCA Bank JPM - Alternate Path K/A 006 Al. 73 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration) (CFR: 47.5 / 45.5) RO 3.5 SRO 3.7 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/1/N5500/027 (Shutdown LOCA) to address the LOCA. The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 14 (Isolating Cold Leg Accumulators) of AP/27. The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1A and 1D will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will isolate the Nitrogen supply to the lB and 1C Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. This JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take 30 minutes.

JPM e Operate Containment Cooling System Fans NEW JPM K/A 022 A4.07 Ability to manually operate and/or monitor in the control room: CCS fans (CFR 47.7 /

45.5 to 45.8) RO 3.6 SRQ 3.6 Initial conditions are that a secondary steam leak is occurring. The CRS directs the applicant to perform step 9 of AP/1!N5500/028 (Secondary Steam Leak). The applicant will determine, based on conditions specified in the procedure, that the leak is occurring inside containment.

The applicant will then start one additional Lower Containment Ventilation Unit, three additional Upper Containment Ventilation Units, and place all eight operating ventilation units in MAX cooling mode.

JPM f Shift operating Condenser Circulating Water CRC) Pumps - New Alternate Path K/A 075 G2. 7.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR 47.70/43.5 / 45.2/45.6) RO 4.3 SRO 4.4 Initial conditions are that Unit 1 is at 100% power. The CRS directs the applicant to start 1D RC Pump and secure lB RC Pump in accordance with OP/1/B/6400/OO1A (Condenser Circulating Water). The applicant will start 1 D AC Pump at which time the associated discharge valve will fail to automatically open beginning the ALTERNATE PATH. The applicant will manually open the discharge valve and attempt to secure lB RC Pump by closing the discharge valve (pump automatically trips following closure of discharge valve). The lB AC Pump will fail to automatically secure upon closure of the associated discharge valve requiring the applicant to manually secure the pump.

JPM g Initiate a Containment air (VQ) release Bank JPM K/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel (CFR 4 1.7/45.5 to 45.8) RO 3.7 SRO 3.7 Initial conditions are that Unit 1 is at 100% power. The CRS directs the applicant to initiate a containment air release. The applicant will perform the following actions to successfully complete this JPM: verify and document proper EMF setpoints, verify release valve controller setpoint, reset the release totalizer, unisolate release path and start the applicable fan.

Plant ]PMs JPM i Operate 2A Hydrogen Igniters from SSF power supply Bank JPM (RCA entry required) k/A 028 G.2. 7.30 Ability to locate and operate components, including local controls (CFR 47.7/45.7) RO 4.4 SRQ 4.0 Initial conditions are that Unit 2 has entered AP/O/N5500/048 (Extensive Damage Mitigation) following an event. The CRS instructs the applicant to align 2A Hydrogen Igniters to the alternate source per OP/O/B161001013 (Standby Shutdown Facility Operations), Enclosure 4.9 (2A Hydrogen Igniters Operation from SSF). The applicant will align alternate power via simulated operation of station breakers, manual transfer switch, and applicable Hydrogen Igniter Start switch.

JPM I Energize 1 SLXG from SSF DIG Bank JPM Alternate Path K/A 062 A2.07 Ability to predict the impacts of the following malfunction or operations on the ac distribution system; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Types of loads that, if de-energized, would degrade or hinder plant operation (CFR 47.5/43.5/45.3/45.73) RO 3.4 SRO 3.9 Initial conditions are Unit 1 has experienced a loss of all Offsite power. The CRS instructs the applicant to energize 1SLXG per API1IN5500/007 (Loss of Normal Power), Enclosure 24 (Energize 1SLXG). The applicant will attempt to start the SSF DIG in order to energize 1SLXG.

However, the DIG will fail to start beginning the ALTERNATE PATH. The applicant will then engage the Manual Override fuel supply knob and successfully start the SSF DIG. The applicant will complete this JPM by removing 1SLXG loads, closing the DIG supply breaker, and loading 1SLXG.

JPM k Makeup to the Unit 2 Spent Fuel Pool from Nuclear Service Water (RN) Bank JPM K/A 033 A2. 03 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level. (CFR 47.5 / 43.5 / 45.3 / 45.73) RO 3.7 SRO 3.5 Initial conditions are that Unit 2 Spent Fuel Pool has experienced an un-isolable leak due to a crack caused by a seismic event. The CRS instructs the applicant to initiate a makeup to the Unit 2 Spent Fuel Pool from the 2A train of RN. The applicant will align makeup water flow via operation of plant valves.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2016 Exam Level: RD LI SRD-l LI SRO-U Operating Test Number: 2016301 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Function

a. Respond to Inadvertent Dilution While Shutdown ALNS 1 004 A2.06

b. Transfer to Hot Leg Recirc. A N EN L S 2 073 A2.01

c. Initiate RCS Bleed and Feed N,L,S 4P E05 EA1.1 In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

i. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF) D,E,L,R 5 028 02.1.30

j. Energize 1SLXG A,D,E 6 062 A2.01

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

• Type Codes Criteria for RO / SRO-l / SRO-U (A)Iternate path 4-6 / 4-6 / 2-3 (5/5/3)

(C)ontrol room (D)irect from bank < 9 / < 8 / < 4 (6/5/2)

(E)mergency or abnormal in-plant 1 I 1 / 1 (3/3/2)

(EN)gineered safety feature - / - / 1 (1/1/1)

(L)ow-Power I Shutdown > 1 I > 1 I > 1 (5/5/4)

(N)ew or (M)odified from bank including 1 (A) 2 I 2 / 1 (5/5/3)

(P)revious 2 exams < 3 < 3 / < 2 (1/1/0)

(R)CA >1 / >1 / >1 (2/2/1)

(S)imulator ES-30 I, Page 23 of 27

Simulator JPMs JPM a Respond to an Inadvertent Dilution While Shutdown New JPM - Alternate Path k/A 004 A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent boration/dilution (CFR: 47.5/43/5/45/3/45/5)R04.2/SRO4.3 Initial conditions are that the unit is in Mode 3, with Shutdown banks withdrawn, and a boron dilution event in progress. The applicant is directed to perform Case II of AP/1/N5500/013 (Boron Dilution).This procedure will direct the applicant to manually trip the reactor and align the charging system for normal boration. During system alignment, the boric acid to blender control valve will fail to open to begin the ALTERNATE PATH. Once verification that no boric acid flow exists, the applicant will transition to the procedure RNO and open the emergency boration supply valve to complete this JPM.

1PM b Transfer the ECCS to Hot Leg Recirculation NEW JPM - Alternate Path k/A 073 A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on ability of those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; LOCA.

(CFR: 47.5/43.5/45.3/45.73) RO 4.6/SRO 4.8 Initial conditions are that a LOCA has been in progress for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The CRS instructs the applicant to transfer to Hot Leg Recirculation lineup per EP/1/N5000/ES-1.4 (Transfer to Hot Leg Recirculation). The applicant will successfully secure the 1A Safety Injection Pump and begin valve manipulations to align this train for HLR. When attempted, the Hot Leg Injection isolation valve (1NI-121A) will not open beginning the ALTERNATE PATH. The applicant will then transition to the RNO and attempt to align lB train Safety Injection for HLR while dispatching an operator to manually open 1NI-121A. Upon alignment, the lB Safety Injection Pump will fail to start. The applicant will receive notification that 1NI-121A is open, transition to the required procedure step, complete alignments, and successfully place 1A Safety Injection System in HLR.

1PM c Initiate RCS Bleed and Feed following loss of Secondary Heat Sink New JPM k/A E05 EA7. 7 Ability to operate and/or monitor the following as they apply to the (Loss of Secondanj Heat Sink); Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR 47.7 / 45.5 / 45.6) RO 4. 7 SRO 4.0 Initial conditions are that a Reactor Trip has occurred due to a loss of both main feed pumps.

The Auxiliary Feedwater Pumps will not function. EP/1/N5000/FR-H.l has been entered and Bleed and Feed initiation criteria has been met. The applicant is directed to initiate Bleed and Feed in accordance with FR-H.l Applicant will initiate both trains of Safety Injection, open 2 pressurizer PORVs, and align Cold Leg Accumulator nitrogen to the PORVs.

Plant JPMs 1PM I Operate 2A Hydrogen Igniters from SSF power supply Bank JPM (RCA entry required) k/A 028 G.2. 7.30 Ability to locate and operate components, including local controls (CFR 47.7/45.7) RO 4.4 SRO 4.0 Initial conditions are that Unit 2 has entered AP/01N5500/048 (Extensive Damage Mitigation) following an event. The CRS instructs the applicant to align 2A Hydrogen Igniters to the alternate source per OP/O/B161001013 (Standby Shutdown Facility Operations), Enclosure 4.9 (2A Hydrogen Igniters Operation from SSF). The applicant will align alternate power via simulated operation of station breakers, manual transfer switch, and applicable Hydrogen Igniter Start switch.

1PM i Energize 1SLXG from SSF DIG Bank JPM Alternate Path k/A 062 A2.07 Ability to predict the impacts of the following malfunction or operations on the ac distribution system; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Types of loads that, if de-energized, would degrade or hinder plant operation (CFR 47.5/43.5/45.3/45.73) RO 3.4 SRO 3.9 Initial conditions are Unit 1 has experienced a loss of all Offsite power. The CRS instructs the applicant to energize 1SLXG per AP/11N55001007 (Loss of Normal Power), Enclosure 24 (Energize 1SLXG). The applicant will attempt to start the SSF DIG in order to energize 1SLXG.

However, the DIG will fail to start beginning the ALTERNATE PATH. The applicant will then engage the Manual Override fuel supply knob and successfully start the SSF DIG. The applicant will complete this JPM by removing 1 SLXG loads, closing the DIG supply breaker, and loading 1SLXG.

- cPE RA 71AJ& Thsr A?peovi,t Operating Test Quality Checklist Form ES-30f-3 Facility: Catawba Nuclear Station Date of Examination: May 2016 Operating Test Number:2016301

. . Initials

1. General Critena 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 14y during this examination. =

c. The operating test shall not duplicate items from the applicants audit test(s). (see Section Di a.) Z .L L 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. WalkThrough Criteria -- --

a. Each JPM includes the following, as applicable:

• initial conditions

• initiating cues

• references and tools, including associated procedures

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

• operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant crileria for successful completion of the task /

identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

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

3. Simulator Criteria --

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

Printed Name I Si nature Date

a. Author Bruce Bo ette / 05/11/16

b. Facility Reviewer(*) Walter Hunnicutt / 05/11/16

c. NRCChiefExaminer(#) ffhQ/ i_ #% ,4c

d. NRC Supervisor Ce 3 \C 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.

oPE,?T7/W 7T

• FNAL oP Aff,o vdL ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Catawba Nuclear Station Date of Exam: May 2016 Scenario Numbers 1 I 2! 3 /4 Operating Test No.: 2016301 QUALITATIVE ATTRIBUTES inhials a b c#

1 The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. k%( 7

2. The scenarios consist mostly of related events. %Y 144

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

• the expected operator actions (by shift position)

. the event termination point (if applicable)

4. The events are valid with regard to physics and thermodynamics. Aq tuft

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. w 47

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 competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

11. The scenario set provides the opportunity for each applicant to be evaluated in each of the applicable rating factors. (Competency Rating factors as 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, Target Quantitative Attributes f Per Scenario; See Section D.5.d) Actual Attributes -- --

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

2. Abnormal events t2-4) 4/4 I 414 W

3. Major transients (12) 1 II II II 1A4

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

5. EOP contingencies requiring substantive actions (0-2) 0 I 2! 0 I 0 Ø j_

6. EOP based Critical tasks (23) 2 /2/ 3 I 2 144 NOTE: The facility signature is not applicable for NRC-developed tests.

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

oP. 7sr VAt

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: May 2016 Operating Test No.: 2016301 A E Scenarios P V T M Scenario 1 Scenario 2 Scenario 3 r C 0 I L N I T CREW CREW CREW CREW C POSITION POSITION POSITION POSITION A T A S A A B S A B U N Y R T C R T 0 R T C R T C M 0 C P 0 C P 0 C P 0 C RI U E

ROl AX 4 1 110 NCR 1 1 2171 SAC-I I/C 3,46 3,5,9 1,5,7 9 4 4 2 SAC-U MAJ 6 6 6 3 2 2 1 TS 0022 R02 RX 4 1 710 NOR 1 1 117 SAC-Il I/C 3,5,9 1,5,7 6 4 4 2 SAC-U MAJ 8 6 2221 TS 0022 R03 AX 4 1 110 NOR 1 1 111 SAC-I I/C 3,5,9 1,5,7 6 4 4 2 SAC-U MAJ 6 6 2221 TS 0022 R04 AX 1 1110 NOR 4 1111 SAC-I I/C 2,5,7 2,3,8 6 4 4 2 SRO-U MA] 6 5 2221 TS 0 022 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SACs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to

(*) Reactivity and normal Section D.5.d) but must be significant per Section C.2.a of Appendix D.

evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: May 2076 Operating Test No.: 2016301 A E Scenarios P V T M

Scenario 1 Scenario 2 Scenario 3 E 0 I L N T N r CREW CREW CREW CREW A I C POSITION POSITION POSITION POSITION L M A T A A B S A U N Y R T 0 A T 0 R T 0 R T 0 Mf 0 C P 0 C P 0 C P 0 C P RI U E

RO AX 4 7110 NOR 4 7 1 1 1 SRO-I1 I/C 2,6,7 1,2,3,5, 7 4 4 2 SRO-U MA] 8 6 22 21 TS 2,3 2 022 AO RX 4 7110 NOR 4 7 111 SRO-12 I/C 2,6,7 1,2,3,5, 7 4 4 2 SRO-U MAJ 8 6 2 2 2 1 TS 2,3 2 022 RO AX 4 1110 NOR 4 7 111 SRO-13 I/C 2,6,7 1,2,3,5, 7 4 4 2 SAO-U MA] 8 6 2221 TS 2,3 2 022 Instructions:

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

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

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: May 2016 Operating Test No.: 2016301 A E Scenarios P V T M Scenario 1 Scenario 2 Scenario 3 F-0 I C N I T CREW CREW CREW CREW A I C POSITION POSITION POSITION POSITION L M A T j u N R T 0 R T 0 R T 0 R T 0 M 0 C P 0 C P 0 C P 0 C R IU E

RD RX 0110 NOR i 1 1 1 1 SRO-I I/C 2,3,4,5, 5 4 4 2 SRO-U 1 6 MAJ 8 1 227 TS 4,5 2 022 RO RX 0110 NOR 1 4 2111 SRO-I I/C 2,3,4,5, 2,3,8 8 4 4 2 6

SRO-U 2 MAJ 8 6 2221 TS 4,5 2 022 RD RX 0170 NOR I 4 2111 SRO-I I/C 2,3,4,5, 2,3,8 8 4 4 2 6

SRO-U 3 MAJ 8 6 2221 TS 45 2 022 RD RX 0110 NOR 1 1111 SRO-I I/C 2,3,4,5 4 4 4 2 SRO-U4 MAJ 6 1 2 2 1 TS 2,3 2 022 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RD applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component fl/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to

(*) Reactivity and normal Section D.5.d) but must be significant per Section C.2.a of Appendix D.

evolutions may be replaced with additional instrument or component malfunctions on a 1 -for-i basis.

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

I ES-301 Competencies Checklist Form ES-301-6 Facility: Catawba Date of Examination: May 2016 Operating Test No:201 6301 APPLICANTS RO RO RO SRO-I D SRO-l

• SRO-I D SRO-U D SRO-U D SRO-U

• Competencies SCENARIO SCENARIO SCENARIO____

1 2 3 1 2 3 1 2 3 Interpret/Diagnose 2345 23456 123 23456 123 2345 23456 123 Events and Conditions 678 789 5678 789 5678 678 789 5678 Comply With and ALL ALL ALL ALL ALL ALL ALL ALL Use Procedures (1)

Operate Control ALL ALL ALL ALL ALL Boards (2)

Communicate ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate ALL ALL ALL Supervisory Ability (3)

Comply With and 23 23 45 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- 7 and ES-303-3.)

FN& cAM ES-401 .Rev.1O PWR Examination Outline - FormES4Ol-2l Facility: CATA(AJ Date of Exam: IIIAY cj0/

RO K/A Category Points SRO-Only Points Tier Group A2 G* Total KKKKKKAAAAG 1 2 3 4 5 6 1 2 3 4 Total

= =

= I = I 333 33 3 18 3 3 6

1. 1 Emergency &

I 1

I 9 2 2 4 2 1 Abnormal Plant ... N/A 21 N/A Evolutions 5 4 5 4 5 4 27 5 5 10 Tier Totals

I =

1 23323223332 28 3 2 5

2. I

.?

2 1 1 1 1 1 1 1 1_I__0 1 1 10 1 3 Plant Systems Tier Totals 3 4 4 3 4 3 3 4 3 4 3 38 3 8

3. Generic Knowledge and Abilities Categories I

I 2 f 3 4 10 1 2__J 3 4 7 ii 2[2 2 L 2 2 3 SRO

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and except for one category in Tier 3 of the SRO-only, the Tier Totals in each K/A category shall not be only outlines (i.e.,

less than two). (One Tier 3 Radiation Control K/A is allowed if the KIA is replaced by a K/A from another Tier 3 Category).

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

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

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

do not apply

3. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that 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 ES4OI for guidance regarding the elimination of inappropriate K/A statements.

group before

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

be selected.

5. Absent a plant-specific priority, only those K/As having an importance rating (lR) of 2.5 or higher shall 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 K/A categories.

7. *The generic (G) KIAs in Tiers I 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 ES-401 for the applicable KAs.

ratings (IRs)

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals fuel handling equipment is sampled in other than Category A2 or G* on the for each category in the table above; if SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..

FORM ES-407-2 ES-401, REV 70 T1G7 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA NAME / SAFETY FUNCTION:

RO SRO 3.8 n PRY level pressure and temperature OO8AA1 08 Pressurizer Vapor Space Accident / 3 3.8 4.1 4.4 Reactor trip and safety initiation 009EK3.03 Small Break LOCA /3 3.7 Difference between overcooling and LOCA indications O11EA2.13 Large Break LOCA/3 3.7 3 Reason for changing from manual to automatic control of 022AK1 .04 Loss of Rx Coolant Makeup / 2 2.9 charging flow valve controller RHR heat exchangers 025AA1 .23 Loss of RHR System / 4 2.8 2.9 2.8 Controllers and positioners 027AK2.03 Pressurizer Pressure Control System 2.6 DEEDED Malfunction / 3 Breakers, relays, and disconnects.

ATWS / 1 2.9 3.1 jj J DEEDED 029EK2.06 4.2 Natural circulation 038EK1 .03 Steam Gen. Tube Rupture / 3 3.9 DEE ELIDED 4.4 4.6 Actions contained in EOP5 for loss of MFW 054AK3.04 Loss of Main Feedwater / 4 DDEEDEED Actions necessary to restore power Station Blackout / 6 3.9 4.7 DDE DEE 055EA2.03 4.4 Auxiliary feed pump (running) 056AA2.77 Loss of Off-site Power / 6 4.1 LI LI E LI LI LI LI LI LI LI 11/02/2016 2:03PM Page 1 of 2

T1GJ PWR EXAMINATION OUTLINE FORM ES-401-2 ES-407, REV 10 IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA NAME / SAFETY FUNCTION:

RO SRO 3.6 4.6 Ability to determine operability and/or availability of safety 057AG2.2.37 Loss of Vital AC Inst. Bus /6 related equipment 3.4 3.7 J Use of dc control power by D/Gs 058AK3.Ol Loss of DC Power /6 LI LI LI LI LI LI LI LI 3.3 3.4 Under-excitation 077AK1 .03 Generator Voltage and Electric Grid Disturbances / 6 4.0 4.0 jj j Components and functions of control and safety WEO4EA1 .1 LOCA Outside Containment /3 systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

- 3.9 4.2 Facilitys heat removal systems, including primary WEO5EK2.2 Inadequate Heat Transfer Loss of LI LI LI LI LI LI LI LI LI LI coolant, emergency coolant, the decay heat removal Secondary Heat Sink / 4 systems and relations between the proper operation of these systems to the operation of the facility.

3.8 4.3 Knowledge of operational implications of EOP warnings, well EG2.4.2 Loss of Emergency Coolant Recirc. / 4 LI LI LI LI LI LI LI LI LI LI cautions and notes.

- Excessive Heat 4.4 4.7 j Ability to evaluate plant performance and make wel2EG2.l.7 Steam Line Rupture LI LI LI LI LI LI LI LI LI LI operational judgments based on operating Transfer / 4 characteristics, reactor behavior and instrument interpretation.

Page 2 of 2 11/02/2016 2:03PM

T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 ES-401, REV 70 IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA NAME/SAFETY FUNCTION:

RO SRO 3.6 3.4 Controls and components necessary to recover rod 003AA1 .02 Dropped Control Rod /1 H 3.1 3.9 [J Flux tilt 005AK1 .02 Inoperable/Stuck Control Rod / 1 4.2 4.4 Actions contained in EOP for emergency boration 024AK3.02 Emergency Rotation! 1 U 2.7 3.1 Power supplies, including proper switch positions 032AK2.01 Loss of Source Range NI / 7 U 3.3 3.4 Intermediate range channel operability 033AA2.08 Loss of Intermediate Range NI / 7 4.2 4.0 Ability to verify system alarm setpoints and operate 061AG2.4.50 ARM System Alarms / 7 controls identified in the alarm response manual.

2.5 3.3 Steps called out in the site fire protection plan, FPS 067AK3.02 Plant Fire On-site / B H H H H H H H H H H manual and fire zone manual 4.5 4.9 Processes for removing decay heat from the core 074EK1 .03 Inad. Core Cooling / 4 H H H H H H H H H H 3.0 3.4 H U H Adherence to appropriate procedures and operation WE13EA2.2 Steam Generator Over-pressure / 4 H H H H H H within the limitations in the facilitys license and amendments.

Pagelof 1 11/02/2016 2:03PM

ES-401, REV 70 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: JR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K5.02 Reactor Coolant Pump 2.8 3.2 Effects of RCP coastdown on RCS parameters 003K6.14 Reactor Coolant Pump 2.6 2.9 Starting requirements 004K3.06 Chemical and Volume Control 3.4 3.6 RCS temperature and pressure 005K5.05 Residual Heat Removal 2.7 3.1 Plant response during solid plant: pressure change due to the relative incompressibility of water 006A4.02 Emergency Core Cooling 4.0 3.8 Valves 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 Method of forming a steam bubble in the PZR 008A2.07 Component Cooling Water 2.5 2.8 Consequences of high or low CCW flow rate and tempera- ture; the flow rate at which the CCW standby pump will start 008K3.03 Component Cooling Water 4.1 4.2 D RCP 010K1.0l Pressurizer Pressure Control 3.9 4.1 RPS 012A2.02 Reactor Protection 3.63.9 Loss of instrument power 012K2.0l Reactor Protection 3.3 3.7 RPS channels, components and interconnections Page 1 of 3 11/02/2016 2:03PM

T2GJ PWR EXAMINATION OUTLINE FORM ES-407-2 ES-401, REV 10 NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA RO SRO Engineered Safety Features Actuation 3.6 3.8 H H H ESFAS/safeguards equipment control 013K2.01 4.3 4.5 Auxiliary feed actuation signal 013K4.04 Engineered Safety Features Actuation H

- lnitia tion of safeguards mode of operation 022A3.01 Containment Cooling 4.1 4.3 3.4 3.4 Isolation valves 025A3.02 Ice Condenser 3.8 3.8 Containment O25KiollceCondenser 4.3 4.5 Pump starts and correct MOV positioning 026A3.0l Containment Spray H H H H H H 3.8 3.9 Emergency teedwater pump turbines 039A4.04 Main and Reheat Steam 2.7 3.1 Overfeeding event 059A2.03 Main Feedwater 2.6 2.7 Pumps 061K6.02 Auxiliary/Emergency Feedwater 2.5 2.8  !

Effect on instrumentation and controls of switching power 062A1 .03 AC Ectricai Distribution H H H H H H HHH supplies 3.9 4.5 Knowledge of less than one hour technical specification 0626a2.39 AC EctricalDisffibution H H H H H H H HHH action statements for systems.

Page 2 of 3 11/02/2016 2:03PM

T2GJ PWR EXAMINATION OUTLINE FORM ES-401-2 ES-407, REV 70 IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA NAME / SAFETY FUNCflON:

HO SRO 2.5 3.3 Battery capacity as it is affected by discharge rate 063A1 .01 DC Electrical Distribution 4.6 4.6 j Ability to execute procedure steps.

064G2.1 .20 Emergency Diesel Generator 3.7 3.7 Radiation monitoring system control panel 073A4.02 Process Radiation Monitoring 2.5 2.6 Reactor building closed cooling water 076K2.04 Service Water LI LI LI LI LI 3.3 3.4 Containmentair 078K1.03 InstrumentAir LI LI LI LI LI LI LI LI LI LI 3.0 3.7 Vacuum breaker protection 103K4.01 Containment LI LI LI LI LI LI LI LI LI Page 3 of 3 11/02/2016 2:03 PM

FORM ES-401-2 ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA NAME I SAFETY FUNCTION:

RD SRO 3.7 3.9 li j Relationship of temperature average and ioop differential 002K512 ReactorCoolant temperature to ioop hot-let and cold-leg temperature indications 3.5 3.8 Axial and radial power distribution 014A1.04 Rod Position Indication El El El El El El 2.7 3.0 Sensors and detectors 017K6.01 In-core Temperature Monitor 3.1 3.4 Fans 027K2.0l Containment Iodine Removal El El El El El DEDI 2.9 3.1 L7 Containment air cleanup and recirculation system 029K1.05 Containment Purge El El El El El 3.8 4.0 L7 Knowledge of local auxiliary operator tasks during 033G2.4.35 Spent Fuel Pool Cooling El El El El El El emergency and the resultant operational effects 2.5 3.3 Fuel movement 034K4.02 Fuel Handling Equipment El El El El El 4.5 4.6 S/G isolation on steam leak or tube rupture/leak 035A4.06 Steam Generator El El El El El El 3.2 3.2 ARM and PRM systems 071K3.05 Waste Gas Disposal El El El El El 2.9 3.2 Cross-connection with lAS 079A2.01 Station Air Page 1 of 1 11/02/2016 2:03PM

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

KA NAME/SAFETY FUNCTION:

P0 SRO 4.4 Knowledge of operator responsibilities during all modes G2.1.2 Conductof operations 4.1 D D fl Li of plant operation.

3.0 4.1 ji Knowledge of procedures and limitations involved in core G2.l.36 Conduct of operations alterations 4.1 4.3 Ability to use procedures to determine the effects on G2.l.43 Conduct of operations reactivity of plant changes 3.7 4.1 Knowledge of surveillance procedures.

G2.2.12 Equipment Control 3.9 4.6 Ability to recognize system parameters that are entry-G22.42 Equipment Control Li Li level conditions for Technical Specifications 3.4 3.8 Knowledge of radiation or contamination hazards that G2.3.14 Radiation Control may arise during normal, abnormal, or emergency conditions or activities 3.2 3.7 Knowledge of radiation exposure limits under normal and G2.3.4 Radiation Control Li Li Li Li Li Li Li Li Li Li emergency conditions 3.4 4.4 Knowledge of the bases for prioritizing emergency G2.4.23 Emergency Procedures/Plans Li Li Li Li Li Li Li Li Li Li procedure implementation during emergency operations.

3.1 4.4 Knowledge of the emergency plan.

G24.29 Emergency Procedures/Plans Li Li Li Li Li Li Li H Li 3.2 3.8 i Knowledge of emergency communications systems and G2.4.43 Emergency Procedures/Plans techniques.

Page 1 of 1 11/02/2016 2:03PM

FORM ES-401-2 ES-40J, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE Jfl Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA NAME / SAFETY FUNCTION:

RD SRO 3.4 3.5 Rod bank step counters and RPI 029EA2.08 AIWS / 1 3.8 4.0 Ability to explain and apply all system limits and 038EG2.1 .32 Steam Gen. lube Rupture / 3 precautions.

3.6 3.6 j (multi-unit) Ability to explain the variations in control 054AG2.2.4 Loss ot Main Feedwater / 4 board layouts, systems, instrumentation and procedural actions between units at a facility.

3.9 4.7 Actions necessary to restore power 055EA2.03 Station Blackout / 6 D El Ej 3.8 4.3 Knowledge of operational implications of EOP warnings, 058AG2.4.20 Loss of DC Power /6 El El El El El El El El El El cautions and notes.

3.5 3.6 Operating point on the generator capability curve 077AA2.0l Generator Voltage and Electric Grid El El El Disturbances /6 Page 1 of 1 11/02/2016 2:03PM

SRO Ti G2 PWR EXAMINATION OUTLINE FORM ES-401-2 ES-401, REV 10 NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA RO SRO Pressurizer Level Malfunction / 2 3.4 3.6 PZR level indicators and alarms 028AA2.0l ARM System Alarms / 7 3.6 4.5 Knowledge of conditions and limitations in the facility 061 AG2.2.38 license.

- Depress. / 4 4.1 4.1 Knowledge of the purpose and function of major system weO3EG2.l .28 LOCA Cooldown components and controls.

Natural Circ. / 4 3.1 3.8 Facility conditions and selection of appropriate WEO9EA2.1 procedures during abnormal and emergency operations.

Page 1 of 1 11/02/2016 2:03 PM

SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-407-2 ES-407, REV 10 IR Kl K2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:

KA NAME/SAFETY FUNCTION:

RO SRO 3.1 3.2 Faulty or erratic operation of detectors and function 012A2.05 Reactor Protection generators 2.4 2.7 Decrease in turbine load as it relates to steam escaping 039A2.02 Main and Reheat Steam from relief valves 3.4 3.1 Effect on plant of de-energizing a bus 062A2.04 AC Electrical Distribution 3.7 4.7 Knowledge symptom based EOP mitigation strategies.

063G2.4.6 DC Electrical Distribution 4.0 4.7 j Knowledge of limiting conditions for operations and 103G2.2.22 Containment safety limits.

Page 1 of 1 11/02/2016 2:03PM

SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-407-2 ES-407, REV 10 NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

KA RO SRO 3.6 4.2 [j Erroneous ECP calculation 001A2.12 Control Rod Drive D 3.4 3.9 j Misaligned rod Ol4A2.04 Rod Position Indication 3.6 4.5 Knowledge of conditions and limitations in the facility 028G2.2.38 Hydrogen Recombiner and Purge license.

Control Page 1 of 1 11/02/2016 2:03 PM

FORM ES-401-2 ES-401, REV 70 SRO T3 PWR EXAMINATION OUTLINE JR K1 K2 K3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

KA NAME / SAFETY FUNCTION:

RO SAC 3.7 Knowledge of the refueling processes G2.1 .41 Conduct of operations 2.8 El 3.8 Knowledge of the process for managing maintenance G2.2.18 Equipment Control 2.6 El El El El El El activities during shutdown operations.

Ability to apply technical specifications for a system.

G2.2.40 Equipment Control 3.4 El El El El El El El El El El 3.7 Knowledge of radiological safety principles pertaining to Radiation Control 3.2 G2.3.12 licensed operator duties i Knowledge of radiation or contamination hazards that Radiation Control 3.4 3.8 El G2.3.14 may arise during normal, abnormal, or emergency conditions or activities 4.0 Knowledge of the specific bases for EOPs.

Emergency Procedures/Plans 3.3 El El El El El El El El El El G2.4.18 Knowledge of events related to system operations/status Emergency Procedures/Plans 2.7 4.1 El El El El El El El El El El G2.4.30 that must be reported to internal orginizations or outside agencies.

11/02/2016 2:03 PM Page 1 of 1

ES-401, Rev. 10 Record of Rejected K/As Form ES-401 -4 Tier / Randomly Selected Reason for Rejection Group K/A 1 / 1 APEO25 AAJ .13 Unable to write discriminating question due to plant design. CNS has no direct tie between the SWS radiation monitors and the Residual Heat Removal System.

K/A changed to APEO25 AA1 .23 via random and systematic process from Chief Examiner.

1/2 W/E16EK2.1 Unable to write discriminating question based on Westinghouse YELLOW path procedure FR-Z.3 at the RO level.

K/A changed to EPEO74EK1 .03 via random and systematic process from Chief Examiner.

2/ 1 5YS064 2.2.4 Unable to write discriminating question due to plant design. CNS has no variations in control board layouts, systems, instrumentation, or procedural actions between the two Units Emergency Diesel Generators.

K/A changed to SYSO64 2.1 .20 via random and systematic process from Chief Examiner.

2/1 5YS073 K4.02 Unable to write discriminating question due to plant design. CNS has no letdown isolation on high RCS activity.

K/A changed to SYSO73 A4.02 via random and systematic process from Chief Examiner.

SRO 2 / 2 SYSO79 A2.01 Unable to write a discriminating question at the SRO level for this K/A. This exact K/A is also being tested on the RO portion of the exam.

K/A changed to SYSO14 A2.04 via random and systematic process from Chief Examiner.

SRO 3 GEN2.2 2.2.13 Unable to write a discriminating question at the SRO level for this K/A.

K/A changed to GEN2.2 2.2.18 via random and systematic process from Chief Examiner.

SRO 1 I 2 APEO51 AA2.02 Unable to write a discriminating question at the SRO level for this K/A.

K/A changed to APEO28 AA2.01 via random and systematic process from Chief Examiner.

SRO 2 / 2 SYSO71 A2.02 Unable to write a discriminating question at the SRO level for this K/A.

K/A changed to SYSOO1 A2.12 via random and systematic process from Chief Examiner.

XA m ,i77k,c/ 77O/l)

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Catawba Nuclear Station Date of Exam: May 2016 Exam Level: RD X 3RD X Initial Item Description a b c

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

2. a. NRC KIAs are referenced for all questions,

b. Facility learning objectives are referenced as available.

3. 3RD questions are appropriate in accordance with Section D.2.d of ES-401 ;1f 1.41

4. The sampling process was random and systematic (If more than 4 RD or 2 3RD questions were repeated from the last 2 NRC licensing exams, consult the NRR DL program office).

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

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

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

new or modified); enter the actual RD / SRO-only question distribution(s) at right.

37% / 24% 7% /4% 56% 1 72%

tiá

7. Between 50 and 60 percent of the questions Memory C/A on the RD exam are written at the comprehensionl analysis level; the 3RD exam may exceed 60 4,43/, 36% 56% I 64%

percent if the randomly selected K/As support I A the higher cognitive levels; enter the actual RD I 3RD question distribution(s) at right.

(A/

7

8. References/handouts provided do not give away answers ,,

or aid in the elimination of distractors. 11

9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; 4/ ,j1 deviations are justified.

10, Question psychometric quality and format meet the guidelines in ES Appendix B. 1

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

Printed Name / Signa re Date

a. Author Bruce Boyette / 05/11/16 47 ZoL%/1y

(#)

d. NRC Regional Supervisor Cttg / s/cqiJ.4(o Note: The facility reviewers initials/signature are not applicable for NRC-developed examinations,

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

FINI9L 7TE1iJ %vr/aRi M774i/

Catawba Nuclear Station May 2016 ILO Exam 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 (F/H) (1-5) Stem Cues I/F Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 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.

difficult) rating scale (questions in the 24 range are acceptable).

2. Enter the level of difficulty (LOD) of each question using a 1 5 (easy

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 ciuestions 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).

t 1 C

Catawba Nuclear Station May 2016 ILO Exam

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 #1 Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A OO8Mi .08 H 2 X X Y N B E

1. Q=K/A, 0 is on RO level.

2. Fifth bullet can be deleted, it lessens the plausibility of the A distractor

3. Recommend slight editorial change to 0 statement to read: Which ONE (1) of the following identifies the approximate temperature that is indicated on the leaking safety valve discharge RTD?

0 appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 009EK3.03 2 H 2 X Y N N E

1. QK/A, 0 is on RO level.

2. Recommend adding an automatic to the first part 0 statement so it reads isted time that an automatic reactor trip signal...

3. Would recommend to state the reference/source for the second part 0 statement, one possibility is as follows: In accordance with the Emergency Core Cooling System (ECCS) acceptance criteria, established by 10 CFR 50.46, peak cladding temperatures are required to be maintained less than a MAXIMUM of (2) following a small

% break LOCA.

f- Q appears E at this time.

J Facility licensee modified 0 as requested, now ready for administration. MKM K/A O11EA2.13 3 F 2 X Y N B E

1. Q=K/A, Q is on RO level.

2. We need to ensure that the correct answer is completely technically correct.

Specifically, it could be argued for this Q that FR-P.i checks for two parameters to verify LELOCA (therefore potential for no correct answer). Easy fix though, recommend 0 statement as follows: FR-Ri uses the parameters of NC pressure and (2) to check if a large break LOCA has occurred.

3. Recommend distractor A state NC I-cold temperatures and distractor C state ND flow rate to cold legs to more closely parallel the specific procedural language.

Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM

( 2 L .1

Catawba Nuclear Station May 2016 ILO Exam

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 #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A 022AK1.04 4 H 2 X X X Y N N E

1. QK/A, Q is on RO level

2. Cog level based on first part Q analysis of conditions, believe this Q is mote correctly classified as higher cognitive. Second part 0 is lower cog/retention.

3. Recommend adding a new second bullet under subsequently that states Pzr level was restored to programmed level.

4. IT is a logical TRUE that NV-294 must be in AUTO for the second part 0. Better to just ask the difference, as follows: In order for the charging Low Flow Limit (LM) to be active, Pzr level master controller [is/isNOT] required to be in AUTO.

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM LJ_

K/A 025AA1.23 (original sample plan K/A 025AA1.13) 5 F 2 Y N N S

1. QK/A, 0 is on RO level.

0 appears S at this time.

4 K/A 027AK2.03 6 H 2 Y N M S

1. QK/A, Q is on RO level.

Q appears S at this time.

t 3

)

Catawba Nuclear Station May_2016 ILO Exam

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

LOK LCD (F/H) (1-5) Stem Cues I/F I Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A 029EK2.06 7 H 2 Y N N

1. Q=K/A, Q is on RO level.

2. Distractors A(1) and C(1) are non-plausible; there are no conditions or exceptions given in the stem that would lead an applicant to think that only the shunt trip failed to operate. A(2) and B(2) distractors are weakly plausible because there is no reason for the operator to not also open the MG set breakers.

Q as submitted is U due to multiple non plausible distractors.

Potential fix recommendation:

Given the following initial conditions on Unit 1:

-Power stable at 100% with surveillance testing in progress

-Reactor Trip Breaker A (RTA) and Bypass Breaker B (BYB) are racked-in and closed.

The following sequence of events occurs:

-A complete loss of feedwater occured

-All efforts to trip the Reactor from the control room were unsuccessful

-Operators entered EP/1/N5000/FR-S.1 (Response to Nuclear Power Generation/ATWS)

-An AC was dispatched to locally trip the Reactor Based on the given conditions, Reactor Trip Breaker A (RTA) (1) coil(s) failed to operate as designed.

If the AC is successful in opening all Reactor Trip and Bypass breakers, then per FR-S.1 it [is/is NOT] required to open the MG set breakers locally.

Facility licensee modified Q as requested, now ready for administration. MKM t 4 *1 1

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- 0= SRO B/MIN UIE/S Explanation Focus Dist. Link units ward K/A Only K/A 038EK1 .03 8 H 2 X Y N N E

1. QKIA, 0 is on RO level.

2. There is some level of overlap between this Q and SRO 084; believe this is acceptable because the reason for natural circulation flow is different (RCP trip criteria vs. loss of offsite power). Lets discuss during in-office review to ensure everyone is in agreement.

3. Recommend changing first part 0 statement to read NC System Integrity status is (1). This moves us away from the will be considered language which is imprecise.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 054AK3.04 9 F 2 Y N B

1. Q=K/A, Q is on RO level.

2. Distractors C(2) and D(2) are non plausible. When the reactor trips, operators are making a MODE change no matter what the previous conditions of the unit were; therefore, it does not make sense that ensuring an inadvertent mode change does not occur would be a reason for a reactor trip function setpoint.

I 0 as submitted is U due to multiple non plausible distractors.

acuity licensee submitted new 0, now ready for administration. MKM K/A 055EA2.03 10 F 2 x x Y N N E

1. Q=KIA, 0 is on RO level.

2. Distractor C is not plausible when compared to distractor Ait doesnt make sense that you would wait on starting the D/Gs from the control room to dispatch an operator to try for local actions when the question asks for FIRST action attempted.

3. Distractor D is weakly plausible. Recommend adding a bullet to stem such as Unit 2 was unaffected by the loss of offsite power on Unit 1. Giving some benefit of the doubt here.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM

( 5 I. J

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK LOD (F/H) ( 1-5) Stem Cues I/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only KIAO56AA2.77 11 H 2 X X Y N N E

1. QK/A, 0 is on RO level.

2. Recommend adding bullet to given conditions as follows: Safety Injection (SI) is gg actuated.

3. As worded the first part Q is a logical true that the lB CA pump received a Blackout start signal (at least) and the only difference is whether or not AMSAC also sent an auto-start signal. Lets just test this specific knowledge and remove the teaching in the distractors, recommend re-writing the first part 0 statement as follows: Based on the given conditions, lB CA pump Idid/did NOT] receive an automatic start signal from AMSAC.

0 appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A057AG2.2.37 12 F 2 X Y N N E

1. QK/A, 0 is on RO level.

2. Recommend minor addition to beginning of second part 0 statement: With no operator action, RN pump suction and discharge Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 058AK3.O1 13 F 2 Y N N S

, 1. QK/A, Q is on RO level.

E1f Q appears S at this time.

K/A 077AA1 .03 14 H 2 Y N N S

1. QK/A, Q is on RO level.

0 appears S at this time.

61

Catawba Nuclear Station May 2016 ILO Exam

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 #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only KIAWEO4EA1.1 15 H 2 X Y N B E

1. QK/A, Q is on RO level.

2. Distractors A(2) and C(2) are weakly plausible: an unisolable LOCA is in progress, at some point its likely that the Pzr will empty and Pzr level will be useless as parameter.

Recommend modifications to Q statements as follows:

Containment Phase A Isolation signal (1) automatically actuated.

In accordance with ECA-1 .2, the parameter(s) used to check if the LOCA has been isolated is/are [Pzr level or RVLIS level/NC pressure] trend.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM KIAWEO5EK2.2 16 H 2 Y N B s

1. QK/A, Q is on RO level.

4 0 appears S at this time.

K/A WE1 1 EG2.4.20 2 N N F

g 1. Q=K/A, Q is on RO level.

0 appears S at this time.

i.

KIAWE12EG2.1.7 18 H 2 X X Y N N E

1. QK/A, Q is on RO level.

4th

2. For better procedural language parallelism, maybe tweak bullet to read:

Cooldown rate based on NC T-colds in the last hour is 150 °F

3. Distractors A(2) and C(2) lowering CA fiowrates to some unspecified value less than 75 gpm to all? S/Gs weakly plausible. Recommend re-writing second part Q statement as follows: In accordance with ECA-2.1, CA flow to all but one S/G [is/is NOT] required to be isolated to address the cooldown rate Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM 7

J

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred Partial Job Minutia #1 Back Q SRO B/M/N UIEIS Explanation Focus st.Unk 19 H 2 Y N M s1K/A003A1.02

1. QKIA, Q is on RD level.

Q appears S at this time.

K/A OO5AK1 .02 20 F 2 Y N N

1. QK/A, Q is on RD level.

2. Job link and Minutia: second part Q is asking a 2-hour Tech Spec action statement from memory, reference would be required but then it would likely be direct look-up as written.

Q is evaluated as U at this time due to job-link/minutia concerns (asking greater than one hour TS actions statements w/no reference).

Based on facility licensee comments, it was determined that actual specification asked in the Q statement was actually a 30 minute spec and therefore within the bounds of being asked from memory without a reference. Q is no longer counted as UNSAT; Q as submitted appears ready to be administered on the NRC exam.

K/A024AK3.02 21 H 2 X Y N B E

1. QzK/A, Q is on RD level.

2. Recommend slight tweak to Q statement to get away from what crew will do type language as follows: Based on the given conditions, and in accordance with FR-Si, the crew is required to (1) to ensure a MINIMUM boration flow of(2).

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 032AK2.01 22 H 2 x Y N B E

1. QK/A, Q is on RD level.

2. Recommend slight modification to Q statement as follows: A loss of N-31 j1L.

will result in an automatic reactor trip, and operators are required to enter (2).

Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM t 2 L .1

Catawba Nuclear Station May 2016 ILO Exam

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

LOD Q# LOK (F/H) (1-5) Stem Cues I/F Cred. Partial Job- Minutia #/ Back- 0= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A 033M2.08 23 H 3 Y N N S

1. Q=KIA, Q is on RO level.

Q appears S at this time.

K/A 061G2.4.50 24 F 2 Y N N s

1. Q=K/A but weak. Discussion: CE will allow this K/A match based on the fact that knowledge of alarm response operator actions is somewhat equivalent to operation of controls, as long as the knowledge is derived directly from the alarm response

• 7J4 procedure. Q is on RO level.

2. Initial Q submittal one of the initial 10 pre-review Qs.

0 appears S at this time.

K/A 067AK3.02 25 F 2 X Y N N E

1. QK/A, Q is on RO level.

2. Recommend slight improvement to A(2) and C(2) distractors to state C02 actuation in this area is ONLY initiated manually Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A WE13EA2.2 26 F 3 Y N N s

1. Q=K/A, Q is on RO level.

0 appears S at this time.

t 1 L )

Catawba Nuclear Station May 2016 ILO Exam

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

LOK LCD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q SRO B/M/NIU/E/S Explanation Focus Dist. Link units ward K/A K/A WE1 6EK2.1 27 F 2 N

1. Q does not meet K/A. Any WE16 question is requited to be linked to the Westinghouse YELLOW path procedure FR-Z.3, Response to High Containment Radiation Level.

I 0 as submitted is U due to not meeting the K/A.

Facility licensee requested new K/A statement due to inability to develop discriminating question based upon FR-Z.3 New K/A: 074EK1 .03

1. QK/A, Q is on RO level.

Q appears S at this time. MKM K/A 003K5.02 28 F Y N N

1. Q=K/A, 0 is on RD level

2. First part 0 is worded awkwardly, if asked w/no multiple choice I would probably answer that the flywheel ensures proper coastdown time of the NC pumps; its hard for me to make sense of a statement that a particular reactor trip ensures a pump coasts down.

3. Level of difficulty 1/GFES knowledge and credible distractorslogically second part 0 can be answered by GEES-level reasoning and logic as follows: when operating at normal at-power conditions, actual heat flux is some value lower than critical heat flux.

After a trip, if actual heat flux decreases at a lower rate, it stays closer to critical heat flux which is worse, therefore A(2) and C(2) non plausible. The converse makes sense:

after a trip, if the critical heat flux limit decreases at a lower rate, no matter what actual heat flux is it is better.

O as submitted is U due to LOD=1/distractor plausibility issues as discussed.

Facility licensee and NRC collaborated on newly submitted bank 0. New 0 appears ready to administer at this time. MKM.

K/A003K6.14 29 H Y N B S

1. QK/A, Q is on RD level.

0 appears S at this time.

t 10 L

Catawba Nuclear Station May 2016 ILO Exam

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

LOK LOD Q#

(F/H) (1-5) Stem Cues I/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N UIEIS Explanation Focus Dist. Link units ward K/A Only K/A 004K3.06 30 H 2 Y N N s

1. Q=K/A, Q is on RO level.

1% Q appears S at this time.

K/A 005K5.05 31 H 2 X Y N B E

1. Q=K/A, Q is on RO level.

2. Recommend slight tweak to distractor B to enhance plausibility: PORVs 1 NC-32B and 1NC-34A would be cycling to lower NC pressure.

Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 006A4.02 32 F 2 X Y N N E

1. Q=K/A, Q is on RO level.

2. Recommend slight editorial changes to first part Q statement: change should have been to read are required to be.

3. Recommend slight editorial change to second part 0 statement and distractors to get away from the what will happen phrasing: Auxiliary Feedwater flow j2)_ [is/is NOT]

required to be isolated to the lB & 1C S/Gs.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 007K5.02 33 F 2 X X Y N B E

1. QK/A, 0 is on RO level.

2. Second part distractors are not psychometrically balanced A(2) and B(2) deal with comparing two temperatures, C(2) and D(2) deal with comparing a level trend and a pressure trend. Hard to determine plausibility of A(2)/B(2) vs. the correct choice when dealing with drawing a pressurizer bubble. Recommend more closely paralleling the language in the procedure for second part Q as follows: In accordance with OP/1/N6100/001 (Unit Startup), N2 venting is considered complete when PRT pressure

[does/does NOT] increase with a corresponding PRT level increase.

O appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM t 11 J

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK LOD r (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N UIEIS Explanation I units ward K/A Only Focus Dist. Linky 008207 34 F 2 X Y N N E

1. Q=K/A, Q is on RO level.

2. Recommend slight tweak to change will refer the crew to refers the crew.

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A008K3.03 35 H 2 X Y N B E

1. QK/A, Q is on RO level.

2. I like the additional bulleted information provided in the original MNS exam question, recommend adding them to this Q.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM KJAO1OK1.O1 36 H 2 X Y N B E

1. Q=K/A, Q is on RO level.

2. For the second part Q, recommend bolding, underlining, or all caps the word setpoint for emphasis.

, C appears E at this time.

• Facility licensee modified C as requested, now ready for administration. MKM K/A012A2.02 37 H 2 Y N B S

. 1. Q=K/A, Q is on RO level.

.q C appears S at this time.

K/A012K2.O1 38 F 2 Y N B S

1. QK/A, Q is on RO level.

C appears S at this time.

12

}

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A 013K2.01 39 H 2 Y N B S

1. QK/A, Q is on RO level.

I1 Q appears S at this time.

K/A 013K4.04 40 H 2 Y N N s

1. QK/A, Q is on RO level.

0 appears S at this time.

K/A 022A3.01 41 F 2 X Y N N E

1. QK/A, 0 is on RO level.

2. 0 stem specifically states that the SI was caused by high containment pressure.

Would a phase-B containment isolation change the answer? May need to give a peak containment pressure value.

3. Please provide designation and nomenclature for the bypass cooling water valve in second part 0.

4. Recommend slight edits to Q statements as follows:

Five minutes after the Safety Injection, with no operator action:

The 2A, 2B, & 2C LCVUs will be operating in (1) speed.

2XYZ-123 (LCVU Byp Cool Wtr) [site provide correct nomenclature for this valve please]

is Which ONE (1)of the following completes the statements above?

0 appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 025A3.02 42 F 2 X Y N M E

1. QK/A, Q is on RO level.

2. Recommend modify 4. to read Loss of DC power to 1 NF-228A Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM

Catawba Nuclear Station May 2016 ILO Exam

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- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A 025K3.0i 43 F 2 X X Y N M E

1. QK/A, Q is on RD level.

2. Potential subset issues? Does an Sp signal cause an St or vice-versa (i.e. a high-high containment pressure that causes a phase-B isolation will also cause a phase-A isolation). May be able to get around any issues of this sort with language in the second bullet such as: A spurious automatic signal caused 1NF-233B ( ...)to inadvertently close during the testing.

0 appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 026A3.01 44 H 3 X X x Y N N E

1. QK/A, Q is on RD level.

2. Cog level: believe this is more correctly classified as higher cog due to requiring the applicant to analyze the conditions and predict the responses.

3. Units: please ensure B(1), D(1) distractors read 0.90 for parallelism with other two first part distractors.

4. Cues: the last bullet (operator manually starts the 1A NS pump) is a big cue that significantly affects the plausibility of the C(2), D(2) distractors. Plausibility of the C(2),

D(2) distractors would be further enhanced by giving an operationally valid situation where auto-start of the pumps would be desirable. Recommend modifications as follows:

[initial stuff as submittedi

-Containment sump level is 5 feet

-1A NS pump is running

-BOP operator has just completed ES-i .3 Enclosure 2 (Aligning NS for Recirculation)

Based on the given conditions:

iA NS pump will automatically stop when the CPCS signal decreases to a MAXIMUM of (1) PSIG.

After the 1A NS pump automatically stops, if containment pressure quickly increases to 2 PSIG due to a large hydrogen burn in containment, the iA NS pump (2) automatically start.

Which ONE (1) of the following completes the statements above?

O appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM t 14 I

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A039A4.04 45 H 2 X Y N B E

1. QK/A, 0 is on RO level.

2. One of the initial pre-submitted Qs.

3. Recommend slight modifications to Q statement as follows:

With no operator actions, after a 5 second time delay from the receipt of the above alarms,:

CAPT #1 will automatically (1) lB CApumpwillautomatically_(2)__.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 059A2.03 46 F 2 X Y N B E

1. Q=K/A, 0 is on RO level.

2. Cog level: this 0 is close enough to asking setpoints that it could be memory-level.

3. Recommend giving another bullet that lists all other S/G N/R levels, maybe have it read something like: All other S/G NR levels are 38%. Is it cleat enough that this is an actual S/G level and not a single channel instrument failure?

4. Use of will be for future human actionsrecommend rewriting second part Q statement to read In order to mitigate the above condition, operators are required to enter procedure (2).

Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 061K6.02 47 H 2 X Y N N E

1. QK/A, Q is on RO level.

2. Is it possible to reset the trip throttle valve from the control room? Plausibility of B(2),

D(2) appears low. May be able to work around the common knowledge of the trip throttle valve reset by asking the following in the second part Q: #2 CAPT (2)

[can/can NOT] be restarted from the control room without local operator actions.

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM t 15 *1

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK LOD

( F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only K/A062A1.03 48 H 2 Y N B s

1. QKIA,QisonROlevel.

0 appears S at this time.

K/A 062G2.2.39 49 F 2 X Y N N E

1. Q=KIA, Q is on RO level.

2. Recommend adding of declaring 1A DIG inoperable afterwithin one hour.

3. Plausibility of distractors B and D can be improved by mote closely paralleling the TS language as follows:

B. Determine the OPERABLE 1 B DIG is not inoperable due to common cause failure C. las submitted]

D. Declare the 1A NI pump inoperable, because it is a required redundant feature supported by the inoperabTe 1A DIG, and declare entry into LCO 3.0.3 0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 063A1.01 50 F 2 Y N B s

1. 0=1</A, Q is on RO level.

0 appears S at this time.

K/A 064G2.1.20 (original sample plan K/A 064G2.2.4) 51 H 2 X Y N N E

1. Q=KIA, Olson RO level.

2. When compared to the other distractors, D is non-plausible. With DIG voltage already higher than line voltage, why would the required action be to make the difference even bigger?

Q appears E at this time due to one non-plausible distractor.

Facility licensee modified Q as requested, now ready for administration. MKM 16

-(

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A 073A4.02 (original written exam sample plan K/A 073K4.02) 52 H 2 X Y N N E

1. Q=K/A, Q is on RD level.

2. Operational validity will be enhanced by giving the actual tripl and trip2 values (numbers) already in the module and having the BOP attempt to input a higher tripi number for the first part 0.

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 076K2.04 53 F 2 V N N s

1. Q=K/A, Q is on RO level.

0 appears S at this time.

K/A 078K1.03 54 H 2 X Y N N E

1. Q=K/A, Q is on RD level.

2. When compared to the other three distractors, A appears non-plausible; there are enough instrument air valves in containment that it in non plausible that a loss of air has not effect on ventilation. Why dont we make the distractors increase/decrease for the first part and fail open/fail closed for the second part 0?

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 103K4.Q1 55 F 2 X Y N N E

1. Q=K/A, 0 is on RD level.

2. Please add automatically after the first part blank. (automatically closes)

Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 002K5.12 56 H 2 Y N N S

1. Q=K/A, Q is on RD level.

Q appears S at this time.

t 17

Catawba Nuclear Station May 2016 ILO Exam

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

Q# LOK LCD r (F/H) (1-5) Stem Cues I TIE Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIE/S Explanation Focus j Dist. Link units ward K/A Only K/A 014A1.04 57 H 2 Y N N s

1. QK/A, C is on RD level.

Q appears S at this time.

K/A 017K6.01 58 H 2 Y N B s

1. QK/A, Q is on RD level.

Q appears S at this time.

During discussions with facility and NRC supervisor, it was determined that the Q may not be technically correct for the plant configuration of reference junction temperatures all going through the same electrical box. C was extensively modified and new C generated to meet the K/A on the RD level. Modified new question appears ready for administration on the NRC exam.

K/A 027K2.01 59 F 2 Y N B s

1. Q=KIA, Q is on RD level.

C appears S at this time.

K/A 029K1.05 60 F 2 Y N N s

1. QK/A, Q is on RD level.

Q appears S at this time.

K/A 033G2.4.35 61 H 2 X X Y N N E

1. Q=K/A, C is on RD level.

2. Fifth bullet given temperature of 100 degrees results in a direct lookup on the chart, recommend using 105 degrees, dont think answer changes.

3. Plausibility of one hour required actions during performance of E-0 is low.

Recommend re-writing first part C to state: Per E-0, Spent Fuel Pool level and temperature monitoring [is/is NOT] required within two hours of event.

C appears E at this time.

Facility licensee modified C as requested, now ready for administration. MKM 18

Catawba Nuclear Station May 2016 ILO Exam

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

LOK LOD Q#

(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 034K4.02 Y N M [ J 1. QKJA, 0 is on RO level.

Q appears S at this time.

K/A 035A4.06 63 F 2 X X Y N N U A 1. Q=K/A, 0 is on RO level.

. Need to add containment pressure value and/or trend to differentiate between normal and adverse containment EOP setpoints; otherwise applicant must assume the plant conditions.

3. Distractors A and D are non plausible; are there any S/G NR level setpoints in EOPs for 0% and 39%? (downscale and normal at power level?)

0 as submitted is U due to two non plausible distractors.

Potential fix: 2x2 with 11% and 29% first part Q, second part 0 statement as follows:

During the maximum rate cooldown in E-3, if the 1 C S/G N/R level drops below the above limit, operators lare/are NOT] required to restore CA flow to the 1C S/G.

Based on discussion with facility licensee personnel, facility proposed another version of the A distractor and provided further information as to why the D distractor was plausible during implementation of EOP procedures. Chief Examiner concurred that facility proposed modifications were acceptable, 0 appears ready to administer on the NRC exam at this time.

K/A 071 K3.05 64 F 2 x Y N N E

1. QK/A, 0 is on RO level.

2. Recommend slight modification to 0 statement to read: With no operator actions, which ONE (1) of the following EMFs being in Trip 2 automatically caused the VA alignment listed above?

O appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM r 19 L J

Catawba Nuclear Station May 2016 ILO Exam

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 #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A079A2.O1 65 F 3 X Y N N E

1. QKIA, 0 is on RO level.

2. Q construct of will or will not do with respect to future human actions: recommend slight modifications to Q statements as follows:

Based on the given conditions, and per AP/O/N5500/022 (Loss of VI),

Operators (1) [are/are NOT] required to be dispatched to ensure 1VI-499 (VI Compressor D to VS Header) is closed.

1VS-78 (VS Auto Backup to VI) (2) automatically open.

Which ONE (1) of the following completes the statements above?

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A G2.1.2 66 H 3 X X x Y N B E

1. Q=KIA, 0 is on RO level.

2. Phrasing in Q statement to address the power increase is a slight cue; recommend changing it to read to address the above conditions.

3. Distractor D is non oplausible because Tave and Tref values not provided in the 0 stem.

As submitted, 0 is E due to one non plausible distractor.

Recommendations:

-add plausible Tave and Tref values to Q stem that are 2-3 degrees apart Distractors:

C. No actions required by the AD-OP-ALL-0203 procedure, because reactor power was maintained less than 100% throughout the transient.

D. Insert rods to restore Tave within 1.5 degrees of Tref.

Facility licensee modified Q as requested, now ready for administration. MKM 20

Catawba Nuclear Station May 2016 ILO Exam

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

LOK LCD Q#

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only K/A G2.1.36 67 F 2 Y N N

1. Q=K/A, Q is on RO level.

2. Distractors B and C are non plausible when compared with A and especially D. Both B and C are written in terms of direct or approve to be incorrect answers, but these are functions that are normally performed by supervisory positions not ROs.

Furthermore, in order for someone to choose A,B, or C they would have to conclude that D is wrongbut whenever is monitoring SR instwmentation not a good idea?

Q as submitted is U due to multiple non plausible distractors.

Facility licensee proposed a new Q based upon IMMEDIATE time Technical Specifications, following additional discussions and modifications of the various associated distractors, newly modified C appears ready to administer on the NRC exam.

K/A G2.1.43 68 H 2 X Y N B E

1. QK/A, Q is on RO level.

2. Are we sure of the correct first part answer? The procedural references provided did not seem to be explicitly clear (specific reason) why the ECP was unacceptable. Need to add the procedural reference to first part C statement in any event.

3. Recommend slight changes to Q statements as follows:

If there is no change to NC system boron concentration:

Per OP/0/N6100/006 (Estimated Critical Position (ECP)), the existing (0800 startup)

ECP (1) be used for the 1100 Reactor startup.

The actual critical rod height for the 1100 Reactor startup will be (2) than Control Bank D at 90 steps.

O appears E at this time.

Facility licensee modified C as requested, now ready for administration. MKM

( 21 I. I

Catawba Nuclear Station May 2016 ILO Exam

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

LOK LOD Q#

(1-5) Back- 0= SRO B/M/N U/E/S Explanation (F/H) Stem Cues I/F Cred. Partial Job- Minutia #/

Focus Dist. Link units ward K/A Only F37YNN2212

1. Q=KIA, Q is on RO level.

2. Is it required to memorize all MODE 2 vs. other MODE surveillance limit values? Not sure if this question is operationally validbelieve a minutia argument would be effective. For Tier 3 Generics, its always better to try to hit concepts instead of asking specific values. For this question, can we ask something more conceptual, for example is preconditioning during a valve stroke time test allowed? Or maybe when performing a stroke time test, do you start the stopwatch when the button is pressed, or when the light changes, something like that is a more pure K/A topical hit for Tier 3 questions.

0 as submitted is U due to minutia/job-link/operational validity concerns (requiring memorization of surveillance values in every MODE).

Facility licensee proposed new 0 to meet this K/A, new Q appears ready to administer on the exam. MKM K/A G2.2.42 70 H 3 X Y N B E

1. QK/A, 0 is on RO level.

2. Recommend slight changes to distractors C and D to state Pzr Heater Capacity instead of Pzr Heater Operability.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A G2.3.14 71 H 2 X Y N B E

1. QK/A, 0 is on RO level.

2. First part Q is fine, second part Q is similar to A.3 JPM. For second part 0, can we just ask PD-RP-ALL-OOOl states that an EXCLUDE flag is notification that an individual reached (2) or greater of established administrative limit. Toggle between 80%

and 90%. If you go with this recommendation, Q cognitive level can be changed to memory/fundamental.

O appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM

( 72 L - )

Catawba Nuclear Station May 2016 ILO Exam

4. Job Content Flaws 5. Other 6. 7. 8.

2. 3. Psychometric Flaws Q# Explanation (F/H) (1-5) lflCred. Parbal Job- tiTJack- Q SRO B/M/N UIEIS Focus Link units ward K/A Only

[ Dist. [

K/A G2.3.4 72 H 2 X Y N B E

1. Q=K/A, Q is on RO level.

2. Question: is the additional information in the original bank question (airborne activity, hot spots, surface contamination levels etc.) needed to answer this one? Lets discuss, otherwise the submitted Q looks o.k.

Facility licensee modified Q as requested, now ready for administration. MKM K/A G2.4.23 73 H 2 X Y N B E

1. QK/A, 0 is on RO level.

2. Please include FR-C.2. procedural title.

3. Please re-write first and second part 0 statements to a is/is NOT required format vice will/will NOT.

0 appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A G2.4.29 74 F 2 Y N M s

1. Q=K/A, 0 is on RO level.

0 appears S at this time.

K/A 02.4.43 75 H 2 X Y N N E

1. Q=K/A, Q is on RO level.

2. Recommend slight change to first part 0 statement to more closely parallel the procedural language as follows: AP/17 requires a licensed operator be dispatched to the (1) to maintain Hot Standby conditions on Unit 1 Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM SRO Questions t 23 L )

Catawba Nuclear Station May 2016 ILO Exam

4. Job Content Flaws 5. Other 6. 7. 8.

1. 2. 3. Psychometric Flaws Q# LOK LCD Explanation (F/H) (1-5) Stem Cues I/F Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N U/E/S Focus Dist. Link units ward K/A Only K/A 029EA2.08 76 H 2 Y Y N S

1. Q=[QA, Q is on SRO-only level.

2. One of the initial 10 preliminary questions.

C appears S at this time.

K/A 038EG2.1.32 77 F 2 X X Y Y N E

1. QK/A, C is on SRO-only level.

2. a minimum of 0 degrees subcooling is weakly plausible as submitted; believe that the enhancement recommended below to the first part C statement will enhance plausibility.

3. First bullet in Given information can be deleted; all needed information is provided by second and third bullets.

4. Recommend slight revisions to the C statements as follows:

In accordance with the E-3 basis document, the purpose of the initial cooldown of the NC system is to establish a MINIMUM of (1) of subcooling, including allowances for subcooling uncertainties.

If the above amount of subcooling cannot be maintained after the cooldown is stopped, E-3 requires the operators to GO TO (2).

Q as submitted is evaluated as E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A 054G2.2.4 78 H 3 Y Y N s

1. QK/A, C is on SRO-only level.

. One of the initial 10 preliminary questions.

) appears S at this time.

in office review, made slight change to bold N/R and W/R, C still S at this time.

I 24 1 L J

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

2. 3. Psychometric Flaws 4. Job Content Flaws LOK LCD Explanation (F/H) 1-5) Stem Cues TJF Cred. Partial Job- Minutia #1 Back- SRO B/M/N U/E/S Focus Dist. Link units ward K/A Only K/A 055EA2.03 Y B E 79 H 2 x x

1. Q=K/A, Q is on SRO-only level.

two

2. The Given conditions mix conditions in time, I think we need to separate the times as, for example, in my recommendation below.

need to

3. First bullet in Given conditions may be deleted, second bullet provides all we know.

of the

4. As written the AP/007 distractor is slightly less plausible than needed because AP logical imbalance between selecting an ECA-Q.O enclosure vs. selecting an entire procedure; see below proposed Q for an improvement (?)

to,

5. 0 statements ask for what CRS will direct and what the crew will transition recommend re-stating this in a what does the procedure require format.

the

6. The formatting of Q79(PROCEDURE LEGEND) and WOOlF above procedure legenddoe s not match the formatting of Q77, which just says Given: and choose, has the WOOTF below the listed procedure titles. Dont care which format you just please use a consistent format for this throughout the test.

Recommend the following:

Given the following initial conditions on Unit 1:

-The crew is performing EP/1/N5000/ECA-O.O (Loss of All AC Power)

-The Standby Makeup Pump is ON

-The crew was NOT able to start EITHER Diesel Generator

-It is desired to align Unit 1 alternate power to 1 ETA through SATA Given the following current conditions on Unit 1:

-The crew is at the last step of ECA-O.O

-NCS subcooling is 8 degrees F

-Pzr level is 4% and decreasing slowly CLOSED

-lNl-9A (NV Pmp C/L lnj Isol) and 1NI-JOB (NV Pmp C/L lnj Isol) are both Based on the initial conditions, ECA-O.O required that the crew REFER TO _(1)..._

Based on the current conditions, ECA-O.D requires that the crew GO TO _(2)_..

Which ONE (1) of the following completes the statements above?

PROCEDURE LEGEND:

-AP/1/N5500/007 (Loss of Normal Power)

-EP/1/N5000/ECA-O.1 (Loss of All AC Power Recovery Without S/I Required)

-EP/1/N5000/ECA-O.2 (Loss of All AC Power Recovery With S/I Required) or First part answer ECA-O.O End 9 (Aligning Unit 1 Alternate Power to 1 ETA (SATA))

AP/007 End 5 (Aligning Alternate Power to 1ETA)

Second part answer ECA-O.1 or ECA-O.2 requested.

C as submitted is evaluated as E at this time. Licensee made changes as Facility licensee modified Q as requested, now ready for administration. MKM 25

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws Q# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/MIN U/E/S Focus Dist. Link units ward K/A Only K/A 058AG2.4.20 V Y N E 80 F 2 X

1. QK/A, Q is on SRO only level.

to

2. The Given statement and the two bullets can be deleted, they do not contribute the 0.

in the

3. Recommend re-writing first part 0 to more closely parallel the language procedure, as follows:

capable AP/1/N55/029 (Loss of Vital or Aux Control Power) states that vital batteries are of carrying their associated loads for at least (1) hours.

As submitted, this 0 is evaluated to be E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 077M2.01 V V B E 81 H 2 X

1. Q=K/A, 0 is on SRO only level.

the procedure

2. Recommend changes to the Q statements to more closely parallel with language as follows:

Based on the given conditions, AP/37 FIRST requires the crew to attempt to lower

( 1 ).

AP/37 states that WHEN jumpers are installed per AM/1/N5100/008 (4Kv Essential NOT]

Power (EPC) System Degraded Voltage Logic), THEN Unit 1 __(2)_ [can/can exit L.C.O. 3.8.1 due to both trains of offsite power inoperable.

As submitted, this Q is evaluated to be E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM t 76 1 I. - J

Catawba Nuclear Station May 2016 ILO Exam

4. Job Content Flaws 5. Other 6. 7. 8.

2. 3. Psychometric Flaws LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- 0= SRO B/M/N U/E/S Focus Dist. Link units ward K/A Only k/A 0028AA2.01 (original written exam sample plan K/A 051M2.02) 2 x Y Y N E 82 H x

1. This 0 has a new K/A resulting from the initial 10 question pre-review.

2. QK/A, 0 is on SRO only level.

3. Do we need to provide NC pressure value for this 0 to enhance distractor plausibility? As submitted, C(2) distractor is non-plausible because applicant would need pressure value.

4. 0 is psychometrically imbalanced with a 2x1 first part and 4 separate (unique) choices for the second part 0; however, the format is acceptable in this case because the first and second parts are strongly related.

5. Recommend changes to the 0 statements and answer choices as follows:

Based on the above conditions, an automatic Reactor Trip (1 )_ occurred.

When discussing the design of this Reactor Trip function, TS 3.3.1 Bases states that (2)

Which ONE (1) of the following completes the statements above?

A. 1. has

2. any liquid water release through the PZR Safeties should be prevented B. 1. has

2. reactor coolant system pressure control may be challenged by repetitive cycling of PZR PORVs C. 1. has NOT

2. design analysis demonstrated that a single channel of PZR spray was sufficient to mitigate the full range of postulated transients D. 1. has NOT

2. the operator will have sufficient time to evaluate unit conditions and take corrective actions As submitted, this Q is evaluated to be E at this time.

Facility licensee made changes based on NRC comments. 0 appears SAT at this time.

27

{

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

2. 3. Psychometric Flaws 4. Job Content Flaws Q# LOK LCD Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- 0= SRO B/M/N U/E/S Focus Dist. Link units ward K/A Only K/A 061AG2.2.38 Y Y N U 83 F 3

1. Q=KIA, C is on SRO only level.

to

2. Minutia: without a reference, essentially the first part C requires the applicants I do have TS Table 3.3.3-1 memorized, but this is a 30-day LCO spec; in other words, not believe it is operationally valid to ask this C without a reference, but a reference would likely make it a DLU.

that

3. As submitted disttactots C(2) and D(2) are non plausible; it does not make sense clad the basis of a high range containment area rad monitor would be to detect fuel leakers.

C appears U at this time due to multiple non plausible distractors.

Facility licensee modified C as requested, now ready for administration. MKM KIA WEO3EG2.1.28 84 H 2

1. Q is on SRO-only level, QK/A; although weak K/A match its acceptable.

procedure Discussion: the system associated with this K/A is a specific Westinghouse

... of major procedure components (steps)

(Es-i .2), therefore knowledge of the purpose is acceptable K/A match in my opinion.

2. This was one of the initial 10 pre submittal questions.

C appears S at this time.

K/A WEO9EA2.1 Y Y N 85 F 2 x

1. Q=K/A, C is on SRO only level.

plant

. Recommend revising third bullet to state The TSC has notified the crew that conditions require a cooldown at 75°F/hour

3. Recommend revising first part C statement to state Based on the given conditions, Circulation the CRS [is/is NOTI required to transition to EP/1/N5000/ES-0.3 (Natural Cooldown with Steam Void in Vessel).

of ES-

4. Distractors A(2) and C(2) are non plausible; the applicant knows from the title 0.3 that a steam void in vessel will be allowedthe refore how would maintaining a maintained for bubble remain a priority? Potential fix (?) maybe optimal conditions are reflux boiling mode of heat transfer C appears U at this time due to multiple non plausible distractors.

is During in-office review, facility licensee heavily modified distractors and conditions. C not apparently ready for administratio n on NRC exam. MKM t 28 *1

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

2. 3. Psychometric Flaws 4. Job Content Flaws t

Q# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Focus Dist. Link units ward K/A 101y KJAO12A2.05 Y Y B E 86 H 2 X

1. Q=KJA, Q is on SRO only level.

faulty

2. Recommend adding automatic to the Subsequently bullet as follows: A automatic Containment Pressure bistable has initiated an automatic Reactor Trip and Safety injection to me,

3. Second part Q statement will direct the SI termination sequence is unclear that SI termination conditions are met or does it mean does it refer to just establishing actually terminating SI and restoring the normal charging lineup? Based on this, recommend modification as follows to be more clear (?) Based on the given conditions, located in the procedural steps to terminate SI and establish normal charging are procedure (2).

Q appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/A 039A2.02 x Y Y N 87 H 2 x

1. QKIA, Q is on SRO only level.

due to

2. Plausibility of MW staying the same is low, plausibility of PORV inoperable seat leak by is low. Recommend modifications as follows:

Given the following conditions on Unit 1:

-Stable at 100% RTP, no equipment INOPERABLE

-Main Turbine Load is [insert value for 100%J MW The following sequence of events occur:

-1D S/G PORV (iSV-i) begins to fail OPEN

-The CRS reports NI power at 101%

PORV

-The OATC closes 1 SV-25B (S/G ID PORV Isol) to isolate the failed S/G main turbine load When NI power was at 101% due to the throttled open SIG PORV,

[was/was NOT) less than [insert same value for 100% as above) MW.

In accordance with TS 3.7.4 Bases, closing 1 SV-25B (2) render 1 D S/G PORV line INOPERABLE.

Which ONE (1) of the following completes the statements above?

Q appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM t 29

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws Q# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO B/M/N U/E/S Focus Dist. Link units ward K/A Only YYNuJK/A062A2.04 TT 1. Q=KIA, Q is on SRO only level.

2. Stem focusneed to provide plant power level to ensure correct MODE of applicability

3. If distractors A or D were correct, then you would also be required to enter 3.8.1 CONDITION A and B as well to meet the MINIMUM Tech Spec Conditions per TS rules of usage. Because this is not an available option, it makes distractors A and D non plausible.

NOTE

4. Be careful with the analysis textldistractor write-ups for this Ql believe the before 3.8.1. Condition D does not apply for the given plant conditions (bus I EDE is listed in LCO 3.8.9 as a DC train subsystem, not as an AC source to a distribution of system). Also, I would need to be entering 3.8.1 Condition D to invoke the provisions the NOTE (instead of independentl y/directly entering 3.8.9 due to the loss of power to a required DC train).

Q as submitted is U due to multiple non plausible distractors.

During in office review, facility licensee and NRC made additional changes to a newly proposed Q. Changed 0 now appears read to administer on the NRC exam.

A 063G2.4.6 Y Y N S 89 H 2 ]

1. Q=KIA, 0 is on SRO only level.

2. One of the initial pre-submitted questions.

Q appears S at this time.

K/A 103G2.2.22 x Y Y N E 90 H 2

1. Q=K/A, Q is on SRO only level.

3.0.3

2. The first part Q statement specifically asks whether or not the actions of LCO as are required to be entered. Technically, one could enter LCO 3.0.3 administratively asking required, close the door in an hour, and not perform an action. Recommend just LCO 3.0.3 [is/is NOT] required to be entered.

Giving

3. The second part 0 is a subset, which makes all second part answers correct.

(Reactor benefit of the doubt here, recommend asking The requirements of LCO 3.6.16 Building) [are/are NOTJ required to be met in MODE 4.

O as submitted appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM t *1 L J

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 04 LOK LCD r Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Focus Link units ward K/A Only j Dist.

K/A 028G2.2.38 Y Y N E 91 F 2 X

1. QK/A, 0 is on SRO only level.

recommend minor

2. Since we are not testing what the required actions of LCO 3.6.9, re-write as follows:

Igniters failed the

-third bullet state Maintenance reports 2 of the 35 A train Hydrogen surveillance.

lgniters is

-first part 0 ask Based on the given conditions, the A train Hydrogen

)_ [OPERABLE /INOPERAB LE].

0 appears E at this time.

K/AOOIA2.12 X Y Y B E 92 F 2 X

1. QKIA, Q is on the SRO only level.

First part distractor

2. Im a little unsure as to what to do with this 0, it has a few issues.

given the RiL analysis talks about compliance with LCO 3.1.6, and the applicant is banks, you are back curves as a reference. However, once you have inserted all control and the LCO 3.1.6 boration require ment no longer in MODE 2 whh keff less than 1.0 9, which will applies. Also, the first part Q specifically asks what is required by PT/01 boration eventually was this the knowledge that was intend ed to be asked?

require a case where the use of the word ONLY to take care of the Also, this is probably a require lots of other subset problem is not the right way to goPT/019 will obviously tor is currently steps no matter what the initial action(s) is/are. The way the distrac implies insertion of control banks and simult aneous boration, which is not worded almost what I think is directed by the PT/019 proced ure.

and effect

3. Distractor A is non plausible, because there is no direct cause relationship betwee n control rod position and SDM.

with SDM

4. Distractors C(2) and D(2) are weakly plausible when compared hening these requirements due to the low power condition. Recommend strengt limits due to the distractors by using something like ensure FQ(X,Y,Z) remains within slow time respon se of both the moder ator temper ature coefficient and the Doppler (fuel) temperature coefficient reactivity feedba ck at low power conditions.

Q appears E at this time.

NRC and facility Facility licensee proposed different editorial changes to modified 0, part distractors.

licensee made additional modifications to 0 statement and second Final modified Q now appears ready to administer on the NRC exam.

t 31

.1 L

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws Q# LOK LODr Explanation (F/H) (1-5) Stem Cues I/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Dist. Link units ward K/A Only Focus KJAO14A2.04 Y Y N E 93 H 2 X

1. QK/A, Q is on SRO only level

2. Recommend adding after the plant is stable after the second full bullet (OATC notes....)

C(1)

3. Change B(1)and D(1) to be 15.0 inches for parallelism with A(1) and statement: rod is or is not OPERABLE , what it is considered is

4. Second part 0 irrelevant, recommend asking Based on the given conditions, rod M4 is

[OPERABLE/INOPERABLEJ 0 appears E at this time.

MKM Facility licensee modified 0 as requested, now ready for administration.

K/A G2.1.41 x Y Y N E 94 F 3 x x

1. QK/A, Olson SRO only level.

the same as above

2. Second bullet states refueling cavity water level is 23 feet is this the flange? How is cavity water level normally displayed?

the fourth

3. Can delete the submitted second bullet under subsequently, and modify continuous bullet under Given to state 2A ND train is OPERABLE and has been in operation for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

LE

4. Add new last bullet under Given to state 2B ND train is INOPERAB SRO expects to

5. Add new second bullet under subsequently to state Fuel Handling is verified restart the 2A ND pump in approximately 15 minutes, after the fuel assembly inserted.

recommend

6. Giving the title of the TS is a big cue to the correct answer as submitted, deleting the title and stating in accordance with the appropriate Tech Spec

6. Recommend modifications to 0 statements as follows:

Tech Spec:

Based on the given conditions, and in accordance with the appropriate required to enter one When the 2A ND pump is stopped, the crew _(1 )_ [is/is NOTI or more Tech Spec CONDITIONs/REQUIRED ACTIONs.

, because Tech Spec bases states that only one RHR loop is required to be OPERABLE above the reactor vessel flange/the Spent Fuel Cooling (2) [the volume of water system] provides adequate backup decay heat removal capability.

Which ONE (1) of the following completes the statements above?

Q appears E at this time.

MKM Facility licensee modified Q as requested, now ready for administration.

C 32

Catawba Nuclear Station May 2016 ILO Exam

4. Job Content Flaws 5. Other 6. 7. 8.

2. 3. Psychometric Flaws Q# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Focus Dist. Link units ward K/A Only K/AG2.2.18 95 F 2 Y Y N s

1. QK/A, Q=SRO only

2. This was one of the initial pre submitted Qs.

Q as submitted appears S at this time.

K/A 0 2.2.40 X Y Y B E 96 H 3

1. Q=K/A, QSRO only

2. general question since leak rate value is such a big issue with the 0, should we also provide RCP seal injection flows/seal return flows as well (based on whatever indications/instruments are available in the control room that would be used in an actual situation). This modification may not be needed, lets discuss during the in-office review.

Q as submitted appears E at this time.

During discussion with facility licensee, agreed w/facility that normal values for RCP seal return are reasonable to be known for the purposes of calculating leak rates tor this Q.

Q now appears ready to be administered on the NRC exam.

K/AG2.3.12 X Y Y M E 97 H 3

1. QK/A, QSRO only level

2. First part Q statement, recommend bolding/underlining/capitalizing (whatever you would prefer) the word required, I just dont want any applicant to miss reading this word.

0 as submitted appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM K/AG2.3.14 2 X Y Y N E 98 H

1. QK/A, Q=SRO-only level.

2. Recommend adding a statement like disregard any dose received in transit to and from 2N1-184B somewhere in the first part 0.

3. Recommend C(1) and D(1) read 5.0 for parallelism with A(1) and B(1) distractors.

Q as submitted appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM

{ r

Catawba Nuclear Station May 2016 ILO Exam

5. Other 6. 7. 8.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws Q# LOK LCD I Explanation (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- C SRO B/M/N U/E/S Dist. Link IUmfhts ward K/A Only Focusi K/AG 2.4.18 x Y Y N E 99 F 2

1. QK/A, QSRO only level.

2. Due to the psychometric structure of the second part Q and distractors, it is a logical true that ND is required, and the only question is whether or not NV and NI are also NI required along with ND flow. Plausibility of one ND pump flow rate vs. ND, NV, and rate is low. Recommend asking the Q a little more close to the language in pump flow the basis document as tollows:

is that, The basis for allowing one train of ND to be used for Aux Containment Spray a

after the above time limit, adequate ECCS flow via Cold Leg Recirc is provided by single train of(2) [NV and NI/NV or NI]

0 as submitted appears E at this time.

Facility licensee modified Q as requested, now ready for administration. MKM K/A G 2.4.30 X X Y Y B E H 3

1. QK/A, QSRO only level.

2. 0 may be o.k. as submitted, my concern is requiring detailed knowledge of RP/06A provide (without providing the reference) and also not being able (on a written exam) to the other indications that would be available to the SM during an event. Lets discuss operational validity during in-office review. Worst case would be to need to develop another second part Q.

0 as submitted appears E at this time.

Facility licensee modified 0 as requested, now ready for administration. MKM t *1 L J

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Date of Exam: 0%0/Exam Level: RO SRO Item Description Initials a b c

1. Clean answer sheets copied before grading 4f /ii/,%

2. Answer key changes and question deletions justified and documented /t;;

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

07

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail if /t7, L

5. All other failing examinations checked to ensure that grades are justified 4/7,

,Øf

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of .

41/,,

questions missed by half or more of the applicants 11/ Itt Date Printed Name/Signature

a. Grader //it %6/L/(

N/AIf /9

b. Facility Reviewer(*)

c. NRC Chief Examiner (*) .

d. NRC Supervisor (*) .

7)2)fk

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

ILT 2016 - NRC SRO Written Exam Answer Key 1 D 26 0 51 B 76 A 2 D 27 52 B 77 C 3 C 28 A 53 A 78 C

- =

4 D 29 A 54 D 79 C 5 A 30 B 55 A 80 B 6 A 31 D 56 C 81 B D 32 B 57 0 82 D 7

8 B 33 C 58 C 83 B 9 B 34 0 59 C 84 D 10 A 35 C 60 B 85 D C

11 A 36 A 61 B 86 12 A 37 B 62 A 27 B

- C 13 D 38 A 63 A $8 14 D 39 A 64 C 89 B D

15 B 40 D 65 A 90 16 C 41 B 66 B 91 B 17 A 42 D 67 B 92 B

=

18 B 43 C 68 D 93 B 19 A 44 A 69 C 94 A

-- C 45 B 70 C 95 C 21 C 46 C 71 B 96 A 22 C 47 A 72 D 97 C 23 C 48 0 73 C 98 C 1

a4%L ,r

ILT 2016 - NRC RO Written Exam Answer Key 1 D 26 D 51 B B

2 D 27 C 52 ciS (F

i 25 D 50 41uf M4W 1C

Kelvin Henderson

( DUKE Vice President ENERGY Catawba Nuclear Station Withhold from Duke Energy Public Disclosure Under 10 CFR Z390 CNO1VP 14800 Concord Road York, SC 29745 (RIC 0:803.701.4251 f:803.701.3221 February 11,2016 U.S. Nuclear Regulatory Commission, Region II Mr. Michael Meeks, Senior Operations Engineer Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit I and 2 Docket Nos.: 50-413 and 50-414 Reactor and Senior Reactor Operator Initial Examinations Outlines (Preliminary)

Reference:

Letter from NRC to Duke Energy Corporation; Reactor and Senior Reactor Operator Initial Examinations, Catawba Nuclear Station, 0500041 3/2016301 and 05000414/2016301, dated December 22, 2015 The examination materials for the Catawba Nuclear Station initial license examination scheduled to begin on May 16, 2016 as listed below, are enclosed for your review.

a. ES 201-2 Examination Outline Quality Checklist (Preliminary)

b. ES 201-3 Examination Security Agreement

c. ES 301-1 Administrative Topics Outline (Reactor Operator)

U. ES 301-1 Administrative Topics Outline (Senior Reactor Operator)

e. ES 301-2 Control Room/In-Plant Systems Outline (Reactor Operator)

f. ES 301-2 Control Room/In-Plant Systems Outline (Senior Reactor Operator)

g. ES 301-2 Control Room/In-Plant Systems Outline (Instant Senior Reactor Operator)

h. ES 301-5 Transient and Event Checklist (Preliminary)

i. ES D-1 Forms for 4 (four) Simulator Scenario Outlines

j. ES 401-2 PWR Examination Outline. Please Note: The sample plans for the reactor and senior operator written exams were selected for us by the Nuclear Regulatory Commission office

k. ES 401-4 Record of Rejected K/As

U.S. Nuclear Regulatory Commission February 11,2016 Page 2of3 The enclosed material contents shall be withheld from public disclosure until after the 2016 Catawba Nuclear Station Initial Examinations are complete. If you have any questions or need any additional information, please contact Mr. Steven Tripi, Nuclear Training Supervisor at 803-701-3770 or Mr. Al Honeggar, Operations Training Manager at 803-701-3523.

Sincerely, Kelvin Henderson Site Vice President xc: U.S. Nuclear Regulatory Commission Gerald McCoy, Chief U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission Eugene Guthrie, Branch Chief U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-001 G.A. Hutto, III, Senior Resident Inspector Catawba CNOINC

U.S. Nuclear Regulatory Commission February 11,2016 Page 3 of 3 xc: without attachments B. Leonard CTOIA A. Honeggar CIO1A S. Tripi CTOJA K. Alcorn CTO1A ELL EC2ZF bxc: cover letter with correspondence review documentation only CN-940.00 CNO4DM

fm, DUKE Kelvin Henderson Vice President ENERGY Catawba Nuclear Station Withhold from Duke Energy Public Disclosure Under 10 CFR 2.390 CNO1VP 14800 Concord Road York, SC 29745 0: 803.701.4251 f: 803.701.3221 CNS-1 6-019 March 14, 2016 Mr. Michael Meeks, Senior Operations Engineer U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos.: 50-413 and 50-414 Reactor and Senior Reactor Operator Initial Examination Submittal

Reference:

Letter from NRC to Duke Energy Corporation; Reactor and Senior Reactor Operator Initial Examinations, Catawba Nuclear Station, 05000413/2016301 and 05000414/2016301, dated December 22, 2015 The examination materials for the Catawba Nuclear Station initial license examination scheduled to begin on May 16, 2016 as listed below, are enclosed for your review.

a. ES 201-2 Examination Outline Quality Checklist

b. ES 201-3 Examination Security Agreement (updated copy)

c. ES 301-1 Administrative Topics Outline (Reactor Operator)

d. ES 301-1 Administrative Topics Outline (Senior Reactor Operator)

e. ES 301-2 Control Room/In-Plant Systems Outline (Reactor Operator)

f. ES 301-2 Control Room/In-Plant Systems Outline (Senior Reactor Operator)

g. ES 301-2 Control Room/In-Plant Systems Outline (Instant Senior Reactor Operator)

h. ES 301-3 Operating Test Quality Checklist

i. ES 301-4 Simulator Scenario Quality Checklist

j. ES 301-5 Transient and Event Checklist

k. ES 301-6 Competencies Checklist I. ES D-1 Forms for 4 (four) Simulator Scenario Outlines

m. ES 401-4 Record of Rejected K/As

n. ES 401-6 Written Exam Quality Checklist

o. RO Written Exam questions Seventy-Five (75) questions with references

p. SRO Written Exam question Twenty-Five (25) questions with references

U.S. Nuclear Regulatory Commission March 14, 2016 Page 2 of 3

q. Eleven (11) System Job Performance Measures, Four (4) RO Administrative Job Performance Measures, and Five (5) SRO Administrative Job Performance Measures

r. Simulator Scenarios 1, 2, 3 and 4

s. Plant Reference Documents The enclosed material contents shall be withheld from public disclosure until after the 2016 Catawba Nuclear Station Initial Examinations are complete. If you have any questions or need any additional information, please contact Steven Tripi, Nuclear Training Supervisor at 803-701-3770 or Al Honeggar, Operations Training Manager at 803-70 1 -3523.

Srely, Kelvin Henderson Site Vice President xc: Gerald McCoy, Chief U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Eugene Guthrie, Branch Chief U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-001 G. A. Hutto, III, Senior Resident Catawba CNOI NC

U.S. Nuclear Regulatory Commission March 14, 2016 Page 3of3 xc: without attachments A. Honeggar CTO1A B. Leonard CTO1A K. Alcorn CTOIA ELL EC2ZF bxc: cover letter with correspondence review documentation only CN-940.00 CNO4DM

Kelvin Henderson DUKE Vice President ENERGY Catawba Nuclear Station Duke Energy CNO1VP I 4800 Concord Road York, SC 29745 0:803.701.4251 ft 803.701.3221 Personal Information Withhold from Public Disclosure Under JO CFR 2.390 CNS-1 6-039 June 1,2016 Mr. Gerald McCoy, Branch Chief U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257

SUBJECT:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Units I and 2 Docket Numbers: 50-413 and 50-414 Post Examination Documentation The post examination materials for the Catawba Nuclear Station initial license examination completed on May 26, 2016 submitted in accordance with NUREG 1021 ES 501 C.1 .a, as listed below, are enclosed.

Enclosure A: Original examination answer sheets, one clean copy and examination cover sheets Enclosure B: Master examinations and answer keys Submitted Electronically Enclosure C: Questions asked by applicants during exam Enclosure D: Substantive comments made by applicants following the written examination Enclosure E: Written examination seating chart Enclosure F: Completed Form ES-403-1, Written Examination Grading Quality Checklist; one sheet for RO and one sheet for SRO Enclosure C: Written Examination Performance Analysis Enclosure H: Form ES-201-3, Examination Security Agreement (preliminary)

Enclosure I: Post Exam Comments

U. S. Nuclear Regulatory Commission June 1,2016 Page 2 A follow up submittal of Form ES-201-3, Examination Security Agreement will be provided to include all required signoffs.

If you have any questions or need additional information, please contact Steve Tripi, Training Supervisor at (803) 701-3770 or Al Honeggar, Operations Training Manager at (803) 701-3523.

,rel Kelvin Henderson Vice President, Catawba Nuclear Station xc: without attachments Eugene Guthrie, Branch Chief U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 G. A. Hutto, Ill Senior NRC Resident Catawba CNO1NC

U. S. Nuclear Regulatory Commission June 1,2016 Page 3 bxc: without attachments A. Honeggar CTOIA Marie Morgan CTOIA (Records)

ELL EC2ZF bxc: cover letter with correspondence review documentation only CN-940.00 CNO4DM