ML14028A148

Initial Exam 2013-301 Final Administrative Documents

ML14028A148
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/28/2014
From:	Michael Meeks NRC/RGN-II
To:	Duke Energy Carolinas
References
50-369/13-301, 50-370/13-301
Download: ML14028A148 (73)

Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: McGuire 2013-30 1 Date of Examination: 12/02/2013 NRC Examinations Developed by:

Written / Operating Test Written / Operating Test Chief Target Task Description (Reference) Examiner s Date Initials

-180 1. Examination administration date confirmed (C. 1 .a; C.2.a and b) 06/2013

-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) 08/01/2013

-120 3. Facility contact briefed on security and other requirements (C.2.c) 08/01/2013

-120 4. Corporate notification letter sent (C.2.d) 08/01/2013

[-901 [5. Reference material due (C.1.e; C.3.c; Attachment 2)1 9/18/20 13

(-75) 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES 301-I, ES-301-2, ES-301-5, ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as 9/18/2013 applicable (C. i.e and f; C.3.d)

(-70} (7. Examination outline(s) reviewed by NRC and feedback provided to facility 9/23/2013 licensee (C.2.h; C.3.e)}

{ -45) 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-30 1-3, ES-30 1-4, 10/18/2013 ES-30l-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202) 1 1/1/20 13

-14 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202) 11/18/2013

-14 11. Examination approved by NRC supervisor for facility licensee review i 1/18/2013 (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) 11/18/2013

-7 13. Written examinations and operating tests approved by NRC supervisor 11/25/20 13 (C.2.i; C.3.h)

-7 14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent 1 1/25/20 13 (C.2.i;_Attachment 4;_ES-202,_C.2.e;_ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee i 1/25/20 13 (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions distributed to 1 1/25/20 13 NRC examiners (C.3.i)

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

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

ES2Oi Examination Outflne Quality Checklist Form ES2O1-2

- 2O13 aJu ire Date of Examination: 1212013 rtitiaIs itel b

I ask Description a, Verify that the outhne(s) fit(s) the appropriate model per ES4O1 Assess whether the outline was systematicafly and randomly prepared in accordance

-*t w with Section D.1 of ES4OI and whether al K/A categories are appropriately sampled.

c. Assess whether the outline overemphamzes any systems, evolutions, or generic topics.

T d Assess whether the justifications for deselected or rejected 1</A statements are T appropriate.

E N

2. a Using Form ES-3O1-5 verify that the proposed scenario sets cover the required number 1 of normal evolutions, Instrument and component failures, technical specifications, arid major transients S

b. Assess whether there are enough scenario sets (and spares) to test the prolectod M number and mix of applicants In accordance wIth the expected crew composition and rotation schedule without compromising exam Integrity, and ensure that each applicant U can be tested using at least one new or significantly modified scenario, that no L scenarios are duplicated from the applicants audit test(s), and scenarios will not be A repeated on subsequent days T To the extent possible, assess whether the outline(s) conform(s) with the qualitative and 0 quantitative criteria specified on Form ES-3014 and described in Appendix 0 R j 3, a. Verify that systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the eutlln(s) contain(s) the required number of control room and In-plant tasks, w distributed among the safety functions as specified on the form T (2) task repetition from the last two NRC examinations Is within the limits specified on the form, (3) no tasks are duplicated from the applicants audit test(s)

(4) the number of alternate path, low-power, emergency and RCA tasks meet the criteria art the form

b. Verify that the administrative outline meets the cnteria specified on Form ES-3D 1.-i: t (1) the tasks are distributed among the topics as specified art the form (2) at least one task is new or significantly modified

() no more then one teak ie repeated from the laSt two NRC liceri&ng evaminetions

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 plarihspeclflc priorities (Including PRA and IPE Insights) are covered In the approprIate exam section G b. Assess whether the IOCFR 55 41143 and 55.45 sampling is appropriate.

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

E d Check for duplication and overlap among exam sections.

R A e. Check the entire exam for balance of coverage.

L Assesswtiether the exam fits the appropriate jab level (RO or SRO),

a. Author

b. Fac/lity Reviewer ()

c. NRC Chief Examiner (#)

d. NRC Supervisor NOTE. # Independent NRC reviewer initial Items In Column c, chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines NUREG-1 021, Revision 9

-WRITTEN EXAM SAMPLE PL4N ONLY ES-201 Examination Outline Quality Checklist Form ES-201-2 Facity: McGuire Date of Examination: December 2013 Item Task Description Initials

1. a. Verify that the outline(s) fit(s) the appropriate model, in accord ance with ES-401.

R b. Assess whether the outline was systematically and random ly prepared in accordance with I Section 0.1 of ES-401 and whether all K/A categories are appropriately sampled.

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

d. Assess whether the justifications for deselected or

2. a. Using Form ES-301-5, verify that the proposed scenar rejected K/A statements are appropriate.

77/ q io sets cover the required number of normal evolutions, instrument and component failures, technic S al specifications, and major transients.

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

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix 0.

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 contro W l room and in-plant tasks distributed among the safety functions as specified on I the form (2) task repetition from the last two NRC examinations is T within the limits spec Wed on the form (3) no tasks are duplicated from the applicants audit test(s)

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

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

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

c. Determine if there are enough different outlines to test the protected 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.

G II E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampli ng is appropriate.

c. Ensure that K/A importance ratings (except for plant-s R d. Check for duplication and overlap among exam section pecific priorities) are at least 2.5. 0? 9 L e. Check the entire exam for balance of coverage.

s.

7

f. Assess whether the exam fits the appropriate job level (RO or SRO). 0? j

a. Author  %//4EL 4 1

t

b. Facility Reviewer () i44J) z ,

c. NRC Chief Examiner (#) rk iiL L.4ks4

/

d. NRC Supervisor fr 7JV .

Note: # Independent NRC reviewer initial items in Column

• Not applica c; chief examiner concurrence required.

ble for NRC-prepared examination outlines

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 O2 2t,3 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 andlor an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of /2-2 -/3 From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE (1) DATE SIGNATUREy,7 DATE NOT E 1

i. H. e1,k Ft.d-kr 1 MNS N? E,ctn1T.ap7 J-ead < Ji/3

2. Sfrvi L./4D.&4e1Ii- M,.JS 1IC Ecr Thrv. 3/,A3 3.Vtde. L. YSnr%i.s Wth pL.ii* 3 1 I t3

4. Vi1E

5. R. iA/(3L

. PrD(rj-3 PsIALlT *.f,4I 1/ (

1 5

6. Rec C Acs 11

7. -s,w- I<i_ I qn 8.

9. L t 4

Si 1

i/aJir y S.-pPpf

!iOF 4( f £924Z i2/(f.cJ r /acrç 1O.I4JtL 1 kt4 .

t p

11. cco rq 7 (AcF p (Csiv 7)4i\

12. S.L-i..- C+,o,LALcde7t -

.J 13 4 7-10-13 /

14. ?tI irw.

15.

AkJ :7IzI5 I i3/*) (P

.4 i

1 d r).J4 NOTES: I,

C.A/j 1

4-/k/i

( Via 514 ES-201, Page 27 of 28

ES4OI Examination Security Agreement Fomr !S4014

1. Pre-Examinatjon I acknowledge that have acquired speanlized knowledge about the NRC licensing examinations scheduled for the week(s) of f2 -o2-Zatias of the date of my signature. agree that twill not nowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examrner. I understand that I am not to insfrud, evaluate, 01 provide pefcmiance 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 onnmunicatoc is acceptable if the indMdual 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 Iicensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations andlor an enforcement action against me ci 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.

a To the best of my knowledge, I did not divulge to any unauthedzed persons any information concerning the NRC hcensing examinations administered during the week(s) of /2.2-1 3. From the date that I entered into this security agreement with the completion of examination adrnfrnstration. I did not instnict, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TIThE I RESPONSIBILiTY SIGNAE (1) DATE SIGNATURE (2) DATE NOTE

j. - 4%ci;.) .1 _,.__icç (

iz= -1__

7%1..

thhv

5. kOZ k1iS

6. AOQ C%L. 2.c

,,4 L.D TiL, 1 -

Ift.

1 8.

lt.& .1wtc pij..jS .c-L S.f+

, ,....4 -

-J 232. !i

9. c.,s 1O.1 Orrt QJç kt

11. 1AWiX. W. W 12Z

&r t3s,_ ff-ii).JJ taiLV.k.

C) z L T(

13.Lt M/J5_c,P5 T/?AJG Iaf/Lk 14.ElId Th/%fc1 M AJS rs iRv p cffI! i1121J1._

15JWvi5 -

NOTES:

V. phne ve th.

7 c) Vr I1e idkfr -

ES-201, Page 27 of 28

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

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 12 -/ . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

2. )q 8Ctcje 3R0 ti -i 113

3. Z_h-. 1ie144 Al A.kc cofJf 1.)______________________

4. DoeI uje miJS 5* e

6. Ry. l2_d-5 l)L4ak!L I. C. IO/iJ,)

7. Eiwi3Ac WOZLJ ...-

9.

10.

Ml

/kJ S e.r 9..o 4 Pq..

11(51(3 O_itjl2&M MkU fl.-i - stkbr4.

12.De*.44,%i I1A15 i I 3./I1A.LW (,LI /$lJbS Sflo tyx ii. 7c3.

14. QPVt*I4.9i M4..s /(LStp2 jI.7 15.1 t*k AJS rr 7A -

NOtES k ?on- ve4 ES-201, Page 27 of 28

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 /2-OZ- Zcr3as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of/Z -Z / 3. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY

1. OT1l-OfDj.4rt) 0P5

2. gMLc 1

/ 3L7- s-n P4 V,tp.t

4. DAJ t13 5.Ep$S c(oR1E OLo / pf.c[,frTSA- (ww

)

1 ji I t/zs/i (V -

12 -/t-/3

6. 4irk o4 SR.O LfJ Ut*1z1rLd l!4i-t

7. tj3csi.. _J aPS .S PJ 4d 7J L

4 j; ,-? -L__i1 4-__4

//J2JfL iiq 9

. t-- (?(C/VJk1 S iv.. h--1c LaJ.k1 1O.Li4, ,4v.i% CLT £Tr.. 12 - -ó A 11.( ,ricropbcriks1 tTh.. -r----, L..-- (L ;LfqR C / 1/&//,

12. p-JjSOr I - Jo vZ/ff3 13./LM I)c.{5 C I (

14.4 1)7 oP /14i9&:

15.

NOTES:

i-o jerbz+ 5L(V\

ES-201, Page 27 of 28

ES-301 Administrative Topics Outline Form ES-301-1 Final (Rev 111113)

Facility: McGuire Date of Examination: 12/2013 Examination Level: RO Operating Test Number: N13-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.25 (3.9) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

M R JPM: Determine Boric Acid Addition to FWST 2.1.7 (4.4) Ability to evaluate plant performance and Conduct of Operations make operational judgments based on operating characteristics, reactor behavior, M, R and instrument interpretation JPM: Manual AFD Calculation 2.2.43 (3.0) Knowledge of process used to track Equipment Control inoperable alarms.

N R JPM: Partial Loss of Annunciators 2.3.14 (3.4) Knowledge of radiation or contamination Radiation Control hazards that may arise during normal, abnormal, or emergency conditions or M, P, A activities.

JPM: Predict Radiation Levels While Responding to a Damaged Spent Fuel Pool 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, (0) (S)imulator, (0) or Class(R)oom (4)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (0)

(N)ew or (M)odified from bank (> 1) (4)

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

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-l Final (Rev_111113)

RO Admin JPM Summary Ala This is a modified bank JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, (FWST Makeup Using the RHT), of OP/l/A16200/014 (Refueling Water System) is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480 using the RHT in accordance with Step 3.11 of Enclosure 4.4 of OP/l/A162001014 (Refueling Water System). The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST in accordance with the attached KEY.

Alb This is a modified JPM using Bank JPM ADM-NRC-A1-021 as its basis. The operator will be told that Unit 1 is at 94% power, the OAC has been out of service for 30 minutes, that PT/1/A/4600/021 A (Loss of Operator Aid Computer While in Mode 1) is being performed, and that the Main Control Board AFD meters are INOPERABLE. The operator will be given the present current values for the Power Range upper and lower detectors and directed to calculate AFD per PT/1/A/4600/021A (Loss of Operator Aid Computer while in Mode 1), Step 12.12 for current plant conditions and verify that AFD is within the limits specified in the COLR. The operator will be expected to manually calculate AFD, and determine that the AFD calculated for N41 and N42 is in excess of the limits allowed by the COLR.

A2 This is a New JPM. The operator will be told that while Unit 1 was operating at 100% power, a lightning strike caused several of the Unit 1 Control Room Annunciators to fail requiring entry into PT/1/A4600/033 (Loss of Control Room Annunciators). The operator will be provided with a list of failed annunciators; and directed to continue with Enclosure 13.2 (Partial Loss of Annunciator Panels), and identify the affected Annunciators, if any, that have an Alternate Method for Surveillance that are applicable. The operator will be expected to determine that 11% of the Annunciators have failed in accordance with the attached Key, and identify five (5) specific annunciators that have an identified Alternative Method for Surveillance.

A3 This is a modified Bank JPM used on the 2012 NRC Exam. The operator will be given a set of conditions reflecting a damaged and leaking Spent Fuel Pool with a full core off-loaded, where attempts of makeup have failed, but are expected to be successful within four hours. The operator will also be given a present Spent Fuel Pool leak rate and level. The operator will be directed to refer to Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/1/A15500/41 (Loss of Spent Fuel Pool Cooling or Level), and determine the expected radiation levels one hour, two hours, three hours and four hours from NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301 -1 Final (Rev_ill 113) now, based on the last known leak rate. The operator will be expected to determine the expected dose rate within +/-50%.

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301 1 FINAL (Rev_il 1213)

Facility: McGuire Date of Examination: 12/2013 Examination Level: SRO Operating Test Number: N13-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.25 (4.2) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

M R JPM: Determine Boric Acid Addition to FWST 2.1.37 (4.6) Knowledge of procedures, guidelines or Conduct of Operations limitations associated with reactivity M, R management JPM: Perform an ECP 2.2.12 (4.1) Knowledge of Surveillance Procedures.

Equipment Control N, R JPM: Determine Procedure Sections that Must be Performed 2.3.14 (3.8) Knowledge of radiation or contamination Radiation Control hazards that may arise during normal, abnormal, or emergency conditions or activities.

M, P, R JPM: Calculate Spent Fuel Pool Boiloff rate and predict when Spent Fuel Pool Radiation levels will exceed 100 mrem/hour 2.4.44 (4.4) Knowledge of emergency plan protective Emergency action recommendations.

Procedures/Plan M, R JPM: Provide an updated PAR 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, (0) (S)imulator, (0) or Class(R)oom (5)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (0)

(N)ew or (M)odified from bank (> 1) (5)

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

NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 FINAL (Rev_111213)

SRO Admin JPM Summary Ala This is a modified Bank JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4 (FWST Makeup Using the RHT), of 0P111A16200/014 (Refueling Water System) is in progress and completed through Step 3.11, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Independent Verification (SRO aspect) of the calculation in Step 3.11 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480 using the RHT. The operator will discover two errors within the previous calculation, and determine the correct volume of Boric Acid to add in accordance with the attached KEY. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION. The operator will be required to identify that ACTION C is applicable after one hour.

Al b This is a modified Bank JPM. The operator will be told that Reactor Startup is an hour away, and provided with a set of initial conditions. The operator will be asked to perform an Estimated Critical Position (ECP) in accordance with OP/0/A161 00/06, Reactivity Balance Calculation, Enclosure 4.2, Estimated Critical Rod Position. During the course of the ECP, the operator will be given a set of power history conditions, and asked to perform a Shutdown Fission Product Correction calculation in accordance with OP/0/A16l 00/06, Reactivity Balance Calculation, Enclosure 4.8, Shutdown Fission Product Correction Calculation, in support of the ECP. The operator will be expected to calculate the Estimated Critical Rod Position Bank for No and Peak Xenon at time of Criticality per the attached KEY.

A2 This is a New JPM. The operator will be told that a plant startup is in progress in accordance with OP/l/A/61 00/003 (Controlling Procedure for Unit Operation),

and that the crew has just stabilized the plant at 3.6% power and in a 10 minute hold. The operator will be provided with a listing of failed OAC Alarms; and directed to assess the OAC Points using PT/l/A14600/02l B (Loss of Operator Aid Computer while in Mode 2); specifically to identify all procedure sections that must be performed, all personnel and/or organizations that must be notified, and all procedure Enclosures or other procedures that must be performed as power is raised. The operator will be expected to identify the five procedure Sections that must be performed as 12.2, 12.5, 12.9, 12.10 and 12.13; identify that the Engineering OAC Group must be notified, and that Enclosure 13.2 Part A needs to be performed.

A3 This is a modified Bank JPM used on the 2012 NRC Exam. The operator will be given a set of conditions reflecting a loss of level and cooling to the Spent Fuel Pool with a full core off-loaded, where attempts of makeup have failed. The NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301 -1 FINAL (Rev_il 1213) operator will also be given a present Spent Fuel Pool level and time since shutdown. The operator will be directed to use Enclosure 5 (Spent Fuel Pool Boiloff rate) of AP/11A15500/41 (Loss of Spent Fuel Pool Cooling or Level), and estimate how fast the Spent Fuel Pool level will go down as the pool boils; and then use this boiloff rate and Enclosure 13 (Spent Fuel Pool Radiation Level vs.

Water level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and predict when the radiation levels in the Spent Fuel Pool area will be greater than 100 mrem/hour if no makeup is added. The operator will be expected to determine that the Spent Fuel Pool level will go down at a rate of 3.1 inches/hour, and that the expected time that the Dose Rate in the Spent Fuel Area exceeds 100 mrem/hour is 41.8+/-2 hours.

A4 This is a modified Bank JPM. The operator will be placed in a post-accident condition with a Large Break LOCA with a release from the Containment. The operator will be told that a General Emergency has been declared, and provided with the initial Protective Action Recommendation (PAR). The operator will be given a subsequent set of plant conditions and meteorological data, and asked to provide an updated PAR in accordance with Enclosure 4.4 (Offsite Protective Recommendations) of RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room), and then to complete the Emergency Power Plant Emergency Notification Form. The operator will be expected to determine the PAR for the current conditions and complete the Emergency Power Plant Emergency Notification Form as reflected on the provided KEY.

NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV_i 12013)

Facility: McGuire Date of Examination: 12/2013 Exam Level (circle one): RO (only)! SRO(l) I SRO (U) Operating Test No.: Ni 3-1 Control Room Systems@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title

. Type Code* Safety Function A. 028 H2 Recombiner and Purge Control System [028 A4.01 (4.0/4.0)]

S,D,P,EN 5 Manually Align Phase B HVAC Equipment B. E02 SI Termination [E02 EA1 .1 (4.0/3.9)]

S,N,A,EN 3 Isolate the NV S/I Flowpath While Terminating Safety Injection C. 013 ESF Actuation System [013 A4.04 (4.5/4.8)]

S,M,A 2 Respond to Failed ESF Actuation D. 056 Condensate System [056 A2.04 (2.6/2.8)]

S,D,A 4S Swap Hotwell/CM Booster Pumps E. APE 025 Loss of RHR System [025 AA1.12(3.6/3.5)]

S,D,A,L 4P Respond to ND System Malfunction While at Mid Loop F. APE 067 Plant Fire On Site [067 AA2.04 (3.1/4.3)]

S,M,A 8 Restore from a Fire in the Unit 1 Cable Spreading Room G. 016 Non-Nuclear Instrumentation System [016 A4.01 (2.9/2.8)]

S,N 7 Respond to an Alternate Action on a VCT Level Channel H. EPE 007 Reactor Trip [007 EA1 .06 (4.4/4.5)]

S,D 1 Emergency Borate for Stuck Rods In-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)

I. APE 054 Loss of Main Feedwater [054 AA1.02 (4.4/4.4)]

D,R,E 4S Reset Unit 2 Turbine Driven CA Pump Stop Valve J. APE 069 Loss of Containment Integrity [069 AA1 .03 (2.8/3.0)]

D,R,E 5 Start the Hydrogen Analyzers K. EPE 055 Station Blackout [055 EK3.02 (4.3/4.6)]

D,E 6 Establish NC Pump Seal Injection From the SSF NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV_i 12013)

@ All AC and SAC-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 AC / SAC-I / SAC-U (A)Iternate path 4-6 (5) /4-6 (5) / 2-3 (3)

(C)ontrol room (D)irect from bank 9 (7) 1< 8 (6) / 4 (3)

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

(EN)gineered Safety Feature / / 1 (1) (Contrd Room System>

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

(N)ew or (M)odified from bank including 1 (A) 2 (4) / 2 (4) / 1 (2)

(P)revious 2 exams 3 (1) / 3 (1)! 2 (0) (Randomly Selected)

(A)CA 1 (2)/ 1 (2) / 1 (1)

(S)imulator JPM Summary JPM A This is a Bank JPM randomly selected from the 2011 NRC Exam. The operator will be told that they are the Unit 2 BOP, that Unit 1 has experienced a Large Break LOCA, and that the crew is implementing EP/1IAI5000IE-0 (Reactor Trip or Safety Injection). The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, (Phase B HVAC Equipment), of EP/1/A15000/E-0. During the performance of Enclosure 2, the operator will recognize that neither train of the VE and VX Systems automatically started. The operator will be expected to determine that the VENX Systems did not automatically start as expected and manually start both Trains of both systems.

JPM B This is a New JPM. The operator will be told that a plant transient at Unit 1 has resulted in a reactor trip from power and a Safety Injection actuation, that Safety Injection Termination criteria has been met and that the crew is implementing EP/1/A15000/ES-1.1 (Safety Injection Termination). The operator will be directed to isolate the NV S/I flowpath in accordance with Step 6 of EP/1/A15000/ES-1 .1 (Safety Injection Termination). While performing this task the operator will recognize that one NV Pump Recirculation Valve cannot be opened (Alternate Path). The operator will be expected to attempt to isolate NV S/I flow per EP/1/A1500/ES-1.1, recognize that this cannot be accomplished and complete Generic Enclosure 18 (Aligning Normal Charging With NV Recirc Path Isolated) to isolate NV S/I flow.

JPM C This is a modified Bank JPM. The operator will be told that Unit 1 has experienced an ATWS and a Safety Injection actuation, and that the crew is presently performing EP/1/N5000/FR-S.1 (Response to Nuclear Power Generation/ATWS). The operator will be directed to perform Enclosure 3 (Subsequent S/I Actions) of EP/1/A15000/FR-S.1 (Response to Nuclear Power Generation/ATWS), while the crew continues with the actions of EP/1/A15000/FR-S.1. When the operator attempts to verify that both RN pumps are running, the operator will observe that the lB RN Pump has tripped (Alternate Path). The operator will be expected to complete the required actions of Enclosure 3 including manually actuating the Train B of SI and Phase A CIS, reset the Train B SIS and Sequencer and dispatch an operator to stop the B Diesel Generator using the Emergency Stop Pushbutton.

NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301 -2 DRAFT (REV_il 2013)

JPM D This is a Bank JPM. The operator will be told that Unit 1 is operating at 90% power in preparation for a Condensate System Pump Swap. The operator will be directed to start the C Hotwell Pump, and place the A Hotwell Pump in standby, and then start the C Condensate Booster Pump and place the A Condensate Booster Pump in standby using Enclosure 4.5 of OP/1/A/6250/001 (Condensate and Feedwater System). The operator will be expected to swap both sets of pumps in accordance with the procedure. During the course of swapping the Condensate Booster Pumps, the operator will recognize that the C Hotwell Pump Strainer High liP Annunciator will alarm (Alternate Path). The operator will be expected to use the Annunciator Response Procedure and re-start the A Hotwell Pump, and stop the C Hotwell Pump.

JPM E This is a Bank JPM. The operator will be told that Unit 1 is in Mode 5 with the NC System drained to approximately 10 inches, that 1A ND Pump is in service to all four Cold Legs, and that ND flow has suddenly increased. The operator will be directed to implement AP/1/A15500/19 (Loss of ND or ND System Leakage). The operator will be expected to take manual action to control flow, but recognize that attempts to manually control the RHR HX Outlet Valve and the Bypass Valve are ineffective (Alternate Path).

The operator will be expected to throttle ND flow to less than 3000 gpm using the Cold Leg injection valve(s) and position the ND Heat Exchanger Outlet Manual Loaders so that when these valves are repaired, the ND flow will not be affected.

JPM F This is a modified Bank JPM. The operator will be told that Unit 1 is at 100% power and that a fire has been reported in the Unit 1 Cable Spreading Room. The operator will be told that the crew has implemented APIO/A15500/45 (Plant Fire) and is presently in Enclosure 17 (AB 750 Unit 1 Cable Spreading Room Fire Unit 1 and Unit 2 Actions).

The operator will also be told that several control room switch manipulations have been made, that the Fire Brigade has reported that the fire is no longer active, and that Station Management has indicated that the crew may return Control Room controls to normal as identified within Enclosure 17. The operator will be directed to restore the Control Room controls to normal by performing Step 21.a through e of Enclosure 17 (AB 750 Unit 1 Cable Spreading Room Fire Unit 1 and Unit 2 Actions) of AP/0/A15500/45 (Plant Fire).

The operator will determine that one Pzr PORV has inadvertently opened, and ensure that its isolation valve remains closed, by directing that its motor breaker be opened.

The operator will then open the remaining Pzr PORV isolation valves, direct that the motor breaker for 1CA-7A be closed; and open the manual loaders for the Main Steam Line PORVs while the valves remain closed. When the operator opens the 10 SM PORV manual loader, the valve will open (Alternate Path), and the operator will need to re-close the manual loader.

JPM G This is a New JPM. The operator will be told that the plant is operating at 100% power, that VCT Level instrument 1 NVP-5760 has failed high, and that VCT level has been stabilized. The operator will be directed to respond to an Alternate Action on a VCT Level Channel in accordance with Enclosure 4.1 (Remove/Returning a VCT Level Channel From/To Service) of OP/1/A161021003 (Distributed Control System Operation).

The operator will be expected to use Section 3.2 of Enclosure 4.1, and select 1 NVP 5761 for operation.

JPM H This is a Bank JPM. The operator will be told that the unit has tripped from 100% power, that the crew has entered EP/1/A/5000/E-0 (Reactor Trip or Safety Injection), and then transitions to EP/1/A15000/ES-0.1 (Reactor Trip Response), and that this procedure is NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301 -2 DRAFT (REV_112013) complete through Step 11. The operator will directed to check for adequate Shutdown Margin in accordance with Step 12 of EP/1/A15000/ES-0.1. While verifying that all Control Rods are on the bottom, the operator will discover that three Control Rods did not drop into the core. The operator will be expected to identify that there are three stuck rods, and then initiate Emergency Boration in accordance with AP/1/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution), and identify that Emergency Boration must continue for 76-87 minutes.

JPM I This is a Bank JPM. The operator will be told that Unit 2 has tripped from 100% power due to a loss of Main Feedwater, that the crew has entered EP/2/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink), and that the TD CA PUMP STOP VLV NOT OPEN alarm (2AD-5, F-3) is LIT. The operator will be directed to reset the stop valve PER EP/2/A15000/G-1 (Generic Enclosures), Enclosure 24 (Resetting TD CA Stop Valve). The operator will be expected to reset and open 2SA-3 (Unit 2 TD CA Pump Turbine Stop Valve).

JPM J This is Bank JPM. The operator will be told that Unit 1 has tripped from 100% power due to an accident, that the crew is currently in EP/1/A15000/FR-Z.1 (Response to High Containment Pressure), and that the crew is currently checking Containment Hydrogen Concentration. The operator will be directed to place the Hydrogen Analyzers in accordance with Enclosure 5 (Placing H 2 Analyzers In Service) of EP/1/A15000/G-1 (Generic Enclosures). The operator will be expected to place the 1A Hydrogen Analyzer in service.

JPM K This is a Bank JPM. The operator will be placed in a situation in which a Loss of All AC has occurred on Unit 1. The operator will be told that EP/1/A/5000/ECA-0.0, (Loss of All AC Power) has been implemented, and that one operator has been dispatched to 1 ETA to swap 1 EMXA4. The operator will be directed to obtain the Brown Folder at SSF and complete Enclosure 1, (Unit 1 SSF-ECA-0.0 Actions), which will require the re establishment of NCP Seal Water flow. The re-establishment of NCP Seal Water flow is a Time Critical Task as identified in PT/0/A/4600/1 13 (Operator Time Critical Task Verification), Enclosure 13.11 (Initiate SSF NCP Seal Injection and Swap to the SSF).

The operator will be expected to place the SSF Diesel in operation and supply power to 1SLXG, start the Standby Makeup Pump and ensure that it is supplying NCP seal injection within 7 minutes, ensure that 1SLXG is supplying power to SMXG and SMXG 1, and that Battery Chargers SDSP-1 and SDSP-2 supply breakers are closed.

NUREG-1 021, Revision 9

ES-301 Operatthg Test Quality Checklist Form ES-301-3 J2O1 Facility: McGuire Date of 1212013 Operating Test Number: N13-1 Examination:

1. GENERAL CRITERIA I Initials a b c#

a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g. 10 CFR 55,45, operational importance, safety function distribution).

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

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

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

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

2. WALK-THROUGH CRITER1A -

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 tftL designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include:

- detailed expected actions with exact criteria and nomenclature

- system response and other examiner cues

- statements describing important observations to be made by the applicant

- criteria for successful completion of the task

- identification of critical steps arid their associated performance standards

- restrictions on the sequence of steps, if applicable

b. Ensure that any changes froni the previously approved systems and administrative walk-through outlines (Forms ES-301-i and 2) have not caused the test to deviate from any of .

the acceptance criteria (e.g., Item distributIon, bank use, repetition from the last 2 NRC examinations) specIfied on those fbrms and Form ES-201-2,

3. SIMULATOR CR1ERIA -

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

ENu;j

,//3

a. Author David Lazarony, Western Thnlcal Services, Inc. 11120/13

b. Facility Reviewer()

c. NRC Chief Examiner (#)

d. NRC Supervisor LAt NOTE: The facility signature Is not applicable for NRC-developed tests.

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

NUREG-1 021 Revision 9

ES-301 Simulator Scenario Quality Checklist Form ES-3O14 (Revj 12013) 1 Facility: McGulre Date of Exam: 1212013 Scenario Numbers: 1 2 3 Operating Test No.:

QUAUTATIVE ATIRIBUTES ia1_

a b* c#

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

2. The scenarios consist mostly of related events._____

3. Each event description consists of

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

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

. the symptoms/cues that will be visible to the crew

• the expected operator actions (by shift position)

. the event termination point (If applicable)

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

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

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete 1

7.

evaluation results commensurate with the scenario objectIves.

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

.1. 9 have sufficient time to carry out expected activities without undue time constraints.

8. The simulator modeling is not altered.

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

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

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

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

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

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

1 2 3

1. Total malfunctions (5-8) 8 6 7

2. MalfunctionsafterEOPentry(1-2) 2 2 1

3. Abnormal events (2-4) 4 4 4 i..

4. Major transients (1-2) 1 1 1 5, EOPs entered/ requiring substantive actions (1-2) 1 1 1

6. EOP contingencies requiring substantive actions (0-2) oji 0 -

7. Critical tasks (2-3) 2 NUREG-1 021, Revision 9

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 (Rev_112013)

Facility McGuire e of Exam 4

Da 12120 i3 Sceriano Numbers 4 Operating Test No N13 QUALITATIVE ATTRIBUTES Initials b c#

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

2. The scenarios consist mostly of related events. 9

3. Each event description consists of

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

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

. the symptoms/cues that will be visible to the crew

. the expected operator actions (by shift position)

. the event termination point (if applicable)

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

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

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

7. If time compression techniques are used, the scenario summary dearly so Indicates. Operators have sufficient time to carry out expected activities without undue time constraints.

8. The simulator modeling is not altered.

f

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

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

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

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

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

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

1. Total malfunctions (5-6) 6 9 t

2. Malfunctions after EOP entry (1-2) 1 g.._

3. Abnormal events (2-4) 4

4. Majortransients(1-2) 1 5.

6.

EOPs entered/requiring substantive actions (1-2>

EOP contingencies requiring substantive actions (0-2) 1 f

0 r

7. CritIcal tasks (2-3)

=

a NUREG-1021, Revision 9

ES-301 Transient and Event Checklist Form ES-301-5 (Rev_I 12013)

Facility: McGuire Date of Exam: 12/2013 Operating Test No.: N13-1 A E Scenarios P V N013-1-1 N013-1-2 N13-1-4 N13-1-3 T M P E (Spare) 0 L N T N CREW CREW CREW CREW I T POSITION POSITION A I POSITION POSITION C L M A T u N Y T P S A B S A B S A B S A B R I U E R T 0 R T 0 R T 0 R T 0 9 2 L= 1 RX NOR 6

[ 4 0

2 1

1 1 0 1 1 SROU-1 1,2, 1,3 6 4 4 2 I/C 3,4 MAJ 6 2 2 2 1 TS 25 2 0 2 2 RX 0 1 1 0 NOR 6 1 2 1 1 1 SROU-2 I/C 1,2, 2.4 6 4 4 2 3,4 MAJ S 2 2 2 1 TS 2,5 2 0 2 2 RX 6 1 1 1 0 NOR 1 4 2 1 1 1 SROM I/C 1,4 2,3, 1,2, 2 4 3,5 MAJ 5 6 3 2 2 1 TS 2,4 1.2, 5 0 2 2 RX 6 1 1 1 0 NOR 1 4 2 1 1 1 SRO-2 1,4 2,3, 4 4 2 I/C 9 MAJ 5 6 3 2 2 1 TS 2,4 1,2, 5 0 2 2 3

Instructions:

1. Check the applicant level and enter the operating test number arid Form ES-C-i event numbers for each event type; TS are not applicable for RO applicants, RCa must service in both the a1-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (lIC) malfunctions and one major transient, In the ATC position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

2. ReactivIty manipulations may be conducted under normal or controlled abnomial conditions jrefer to Section D.5.d) but must be significant per Section C.2.a of Appendix C. () Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis 3, Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

NUREG 1021 Revision 9

ES-301 Transient and Event Checklist Form ES-301 -5 (Rev 1 12013)

Facility: McGuire Date of Exam: 12/2013 Operating Test No.: N13-1 A E Scenarios P V N013-1-1 N013-1-2 N13-1-4 N13-1-3 T M P E (Spare) 0 L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION A I POSITION C L M A T u N Y T P S A B S A B S A B S A B R I U E R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 1 1 1 0 NOR 6 1 2 1 1 1 SRO-3 /c 1,2. 2,3, 2,5 g 2 3,4 4 MAJ 7 5 6 3 2 2 1 TS 2,5 2,4 4 0 2 2 RX 1 1 1 1 0 NOR 1 1 1 1 RO-1 2,3 34 4 4 2 I/C MAJ 7 2 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 NOR 6 1 1 1 1 2,3 34 4 4 4 2 RO-2 I/C MAJ 7 5 2 2 2 1 TS 0 0 2 2 RX 6 1 1 1 0 NOR 1 1 1 1 1 1,4 4 4 4 2 RO-3 I/C 2,4 MAJ 2 2 2 1 TS 0 0 2 2 Instructions:

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. ROe must service in both the at-the-controls (ATC) and balance-of-plant (B0P) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (hG) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I1C malfunction can be credited toward the two IC malfunctions required for the ATC position.

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

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

NUREG 1021 Revision 9

ES3O1 Transient and Event Checklist Form ES3O1 5 (Rev_I 12013)

FacUlty: McGuire Date of Exam: 12/2013 Operating Test No.: N13-1 A E Scenarios P V N013-1-1 N01312 N13-1-4 N13-1-3 T M P E (Spare> 0 L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y T P S A B S A B S A B S A B R U E R T 0 R T 0 R T 0 R TO 0 C P 0 C P 0 C P 0 C P RX 1 1 1 1 0 NOR 6 4 2 1 1 1 6 4 4 2 RO4 I/C 2,3 MAJ 5 3 2 2 1 TS 0 0 2 2 RX 1 1 1 0 NOR 1 1 1 1 1 4 4 4 2 RO-5 I/C 2,4 2,5 MAJ 5 6 2 2 2 1 TS 0 0 2 2 RX 1 1 0 NOR 1 1 1 4 4 2 I/C MAJ 2 2 1 TS 0 2 2 RX 1 1 0 NOR 1 1 1 4 4 2 I/C MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the appflcant level and enter the operatIng test number and Form ES-D1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the at-the.controls (ATC) and balance.of.plant (BOP positions; Instant SROs must serve In both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the SOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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

3. Whenever practical, both instrument and component malfunctions should be included; only those that require veritable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level In the right.hand columns, NUREG 1021 Revision 9

ES-301 Competencies Checkllst Form ES-301-6 (Rev 1 12013)

Facility: McGuire Date of Examination: 12/2013 Operating Test No.: N13-1 APPLiCANTS SRO (U/I) RO/ATC GOP Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events and 1-10 1-8 1-8 1-10 1-10 1-8 1-8 1-10 1-10 1-8 1-8 1-10 Conditions Comply With and Use 1-10 1-8 1-8 1-10 1-10 1-8 1-8 1-10 1-10 1-8 1-8 1-10 Procedures (1)

Operate Control 1,2,3 2,3,6 1,2,4 4,6,7 1,4,6 1,3,4 1,2,4 2,4,5 1,3, Boards (2) NA NA NA NA

,7,8 ,5 7,8 ,6

,7,8, ,5,6, 6,7 ,8,9, 9,10 7,8 10 Communicate and 1-10 1-8 1-8 1-10 1-10 1-8 1-8 1-10 1-10 1-8 1-8 1-10 Interact Demonstrate Supervisory Ability 1-10 1-8 1-8 1-10 NA NA NA NA NA NA NA NA (3)

Comply With and Use 1,3 2,5 2,4 35 NA NA NA NA NA NA NA NA Tech. Specs. (3)

Notes:

(1) Includes Technical 5pecfication compliance for RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

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

NUREG-1 021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2 Facility: McGuire 2013 Date of Exam: December 2013 RO K/A Cao1Points SRO-Only_Points Tier Group K K K K K K A A A A G A2 G* Total 1234561234 Total

1. 1 333 33 318 3 3 6 Emergency & 2 1 2 2 1 2 1 9 2 2 4 Abnormal Plant Tier Totals 4 5 5 N/A 4 5 N/A 4 27 5 5 10 Evolutions

2. 2 11011111111 H 0

Plant Tier Totals 3 4 3 4 4 3 3 4 3 4 3 38 5 2 8 Systems = =

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 1 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

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

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

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

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

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

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

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

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

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

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

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

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE#/Name/SafetyFunction K K K A A2 G KIATopic(s) IR #

1 231 OO7EK1 .03, Knowledge of the operational 000007 (BW/E02&E10; CEIEO2) Reactor X implications of the trip reasons for closing the Trip Stabilization Recovery / 1 main turbine governor valve and the main turbine stop valve after a reactor trip.

000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 X 009EK2.03, Knowledge of the interrelations 3.0 between the small break LOCA and S/Gs.

X 4.7 009EG2.4.4, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

000011 Large Break LOCA/3 015AG2.1.7, Ability to evaluate plant 000015/17 RCP Malfunctions/4 X performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

022AG2.2.3, (multi-unit license) Knowledge of 000022 Loss of Rx Coolant Makeup / 2 X the design, procedural and operational differences between units.

025AA2.07, Ability to determine and interpret 000025 Loss of RHR System / 4 X pump cavitation as it applies to the Loss of Residual Heat Removal System.

026AA1 .07, Ability to operate and I or 000026 Loss of Component Cooling X monitor Flow rates to the components and 2.9 Water / 8 systems that are serviced by the CCWS and interactions among the components as they apply to the Loss of Component Cooling Water.

027AG2.4.9, Knowledge of low power or 000027 Pressurizer Pressure Control X 3.8 shutdown implications in accident (e.g. LOCA System Malfunction /

or loss of RHR) mitigation strategies.

000029 ATWS/ 1 038EA1 .27, Ability to operate and monitor 000038 Steam Gen. Tube Rupture / 3 X Steam dump valve status lights and indicators as they apply to a SGTR.

040AA2.04, Ability to determine and interpret 000040 (BW/E05; CEIEO5; WIE12) X the conditions requiring ESFAS initiation as 47 Steam Line Rupture Excessive Heat they apply to the Steam Line Rupture.

Transfer I 4

054AK1 .02, Knowledge of the operational 000054 (CEIEO6) Loss of Main X 3.6 implications of the effects of feedwater Feedwater / 4 introduction on dry SIG as they apply to Loss of_Main_Feedwater_(MFW).

055EK1.02, Knowledge of the operational 000055 Station Blackout! 6 X 41 implications of Natural circulation cooling as it applies_to_the_Station_Blackout.

056AG2.4.20, Knowledge of operational 000056 Loss of Off-site Power! 6 X 3.8 implications of EOP warnings, cautions and notes.

057AK3.01, Knowledge of the reasons for 000057 Loss of Vital AC Inst. Bus! 6 X 4.1 Actions contained in EOP for loss of vital ac electrical instrument bus as they apply to the Loss of Vital AC Instrument Bus: Actions 3.8 contained in EOP for loss of vital ac electrical instrument bus.

X 057AA2.02, Ability to determine and interpret core flood tank pressure and level indicators as they apply to the Loss of Vital AC Instrument_Bus.

058AA2.03, Ability to determine and interpret 000058 Loss of DC Power /6 X DC loads lost; impact on ability to operate and monitor plant systems as they apply to the Loss of DC Power.

062AA2.O1, Ability to determine and interpret 000062 Loss of Nuclear Svc Water! 4 X the location of a leak in the SWS as t applies 2.9 to the Loss of Nuclear Service Water.

2.9 062AA2.03, Ability to determine and interpret X the valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition as they apply to the Loss of Nuclear Service Water.

065AK3.04, Knowledge of the reasons for the 000065 Loss of Instrument Air !8 X Cross-over to backup air supplies responses 3.0 as they apply to the Loss of Instrument Air.

WEO4EK2.1, Knowledge of the interrelations W!E04 LOCA Outside Containment! 3 X between the (LOCA Outside Containment) 3.5 and components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE1 1 EK3.4, Knowledge of the reasons for W!E1 1 Loss of Emergency Coolant X 3.6 the RO or SRO function within the control Recirc. / 4 room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.as they apply to the Loss of Emergency Coolant Recirculation.

WEO5EK2.2, Knowledge of the interrelations BW!E04; W!E05 Inadequate Heat X between the Loss of Secondary Heat Sink Transfer Loss of Secondary Heat Sink!

- 4 and the facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WEO5G2.4.37, Knowledge of the lines of x authority during implementation of the 4.1 emergency plan.

077AA1 .05, Ability to operate and/or monitor 000077 Generator Voltage and Electric X 39 the Engineered Safety Features as they apply Grid Disturbances ! 6 to Generator Voltage and Electric Grid Disturbances.

CD co 0

F 0

0 0

cn cy, m

m m

m cn C)

(5 0

I 0

0)

(5 C)

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 231 000001 Continuous Rod Withdrawal / 1 OO1AA1 .07, Ability to operate and X 3.3

/ or monitor RPI as it applies to the_Continuous_Rod_Withdrawal.

000003 Dropped Control Rod / 1 005AA2.O1 Ability to determine 000005 Inoperable/Stuck Control Rod / 1 X 4.1 and interpret Stuck or inoperable rod from in-core and ex-core NIS, in-core or loop temperature measurement as it applies to the Inoperable / Stuck Control Rod 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 X 033AG2.1 .20, Ability to execute 4.6 procedure steps.

000036 (BW/A08) Fuel Handling Accident / 8 036AK3.02, Knowledge of the X 29 reasons for the Interlocks associated with fuel handling equipment as they apply to Fuel Handling Incidents.

000037 Steam Generator Tube Leak I 3 037AK1 .01, Knowledge of the X 2.9 operational implications of the Use of steam tables as it applies to Steam Generator Tube Leak.

000051 Loss of Condenser Vacuum / 4 051AA2.02, Ability to determine X 3.9 and interpret the conditions requiring reactor and/or turbine trip as they apply to the Loss of Condenser Vacuum.

000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8

= 068AA2.05, Ability to determine 000068 (BW/A06) Control Room Evac. / 8 X and interpret the availability of heat sink as it applies to the Control Room Evacuation.

000069 (WIE14) Loss of CTMT Integrity / 5 WEO7EG2.4.41 Knowledge of the 000074 (W/E06&E07) Inad. Core Cooling / 4 X

emergency action level thresholds and classifications.

. . 076AK2.Ol, Knowledge of the 000076 High Reactor Coolant Activity I 9 X 26 interrelations between the High Reactor Coolant Activity and the process radiation monitors.

WEOIEA2.l,Abilityto determine W/EO1 & E02 Rediagnosis & SI Termination / 3 X 4.0 and interpret the facility conditions and selection of appropriate procedures during abnormal and emergency operations as they apply to the Reactor Trip or Safety Injection Rediagnosis.

W/E1 3 Steam Generator Over-pressure / 4 WE1 5EG2.4.8, Knowledge of how W/E1 5 Containment Flooding / 5 X

abnormal operating procedures are used in conjunction with EOPs.

W/E16 High Containment Radiation /9 BW/E08; W/E03 LOCA /4 WEO3EK2.2, Knowledge of the Cooldown - Depress. X interrelations between the LOCA Cooldown and Depressurization and the facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

BW/E09; CE/Al 3; W/E09&El0 Natural Circ. /4 CE/All; W/E08 RCS Overcooling PTS / 4 WEO8EK3.3, Knowledge of the X

reasons for the manipulation of controls required to obtain desired operating results during abnormal and emergency situations as they apply to the (Pressurized Thermal Shock).

K/A Category Point Totals: 1 2 2 1 2/2 1/2 Group Point Total: 9/2

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System #1 Name K K K K K K A A2 A A G K/A Topic(s) lR #

1 234561 34 003A1 .03, Ability to predict 003 Reactor Coolant Pump X and/or monitor changes in 2.6 parameters (to prevent exceeding design limits) associated with operating the RCPS controls including RCP motor stator winding temperatures.

004A1.10, Ability to predict 004 Chemical and Volume X and/or monitor changes in 37 Control parameters (to prevent X exceeding design limits) associated with operating the X CVCS controls including reactor power.

3.8 004A4.08, Ability to manually operate and/or monitor in the control room: Charging 004G2.2.22, Knowledge of limiting conditions for operations and safety limits.

005K5.05, Knowledge of the 005 Residual Meat Removal X operational implications of the 2.7 plant response during solid plant: pressure change due to the relative incompressibility of water as they apply the RHRS 006K1.14, Knowledge of the 006 Emergency Core Cooling X physical connections and/or 3.0 cause-effect relationships between_the_ECCS_and_the_lAS 007K3.01, Knowledge of the 007 Pressurizer Relief/Quench X effect that a loss or malfunction 3 Tank of the PRTS will have on the Containment.

008K3.03, Knowledge of the 008 Component Cooling Water X effect that a loss or malfunction 4.1 of the CCWS will have on the RCP.

010K5.01, Knowledge of the 010 Pressurizer Pressure Control X 35 operational implications of the determination of condition of fluid in PZR, using steam tables as it applies to the PZR PCS.

012K6.10, Knowledge of the 012 Reactor Protection X effect of a loss or malfunction of 33 the permissive circuits will have on the RPS.

X 012G2.1.2, Knowledge of 4.4 operator responsibilities during all modes of plant operation.

013 Engineered Safety Features X 013K2.01, Knowledge of bus 3.6 Actuation power supplies to the X ESFAS/safeguards equipment control.

4.5 013A2.02, Ability to (a) predict the impacts of excess steam demand on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

022 Containment Cooling X 022K2.01, Knowledge of power 3.0 supplies to the containment X cooling fans.

022K4.03, Knowledge of CCS 3.6 design feature(s) and/or interlock(s) which provide for automatic containment isolation.

025K4.02, Knowledge of ice 025 Ice Condenser X condenser system design 2.8 feature(s) and/or interlock(s) which provide for system control.

026 Containment Spray X 026A4.01, Ability to manually 4.5 operate and/or monitor in the control room CSS controls.

039 Main and Reheat Steam X 039A3.02, Ability to monitor 3.1 automatic operation of the MRSS, including isolation of the MRSS.

059G2.1 .23, Ability to perform 059 Main Feedwater X specific system and integrated 4.3 plant procedures during all modes of plant operation.

X 059K3.02, Knowledge of the 3.6 effect that a loss or malfunction X of the MFW will have on the AFW system.

3.1 059A2.03, Ability to (a) predict the impacts an overfeeding event on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

061 K5.01, Knowledge of the 061 Auxiliary/Emergency X 3.6 operational implications of the Feedwater relationship between AFW flow and RCS heat transfer as it applies to the AFW.

x 061 K6.02, Knowledge of the effect of a loss or malfunction of 2.6 the pumps will have on the AFW components.

062G2.4.47, Ability to diagnose 062 AC Electrical Distribution X 4.2 and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

x 062A2.06, Ability to (a) predict 3.4 the impacts keeping the safeguards buses electrically separate on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations 063K1 .03, Knowledge of the 063 DC Electrical Distribution X 2.9 physical connections and/or cause-effect relationships between the DC electrical system and the battery charger and battery.

064 Emergency Diesel Generator X 064A4.03, Ability to manually 3.2 operate and/or monitor the synchroscope in the control room.

073 Process Radiation X 073A2.02, Ability to (a) predict 2.7 Monitoring the impacts of detector failure on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences 076 Service Water X 076A3.02, Ability to monitor 3.7 automatic operation of the x SWS, including emergency heat loads.

076K2.04, Knowledge of bus power supplies to reactor 2.5 building closed cooling water.

078K4.03, Knowledge of lAS 078 Instrument Air X 3.1 design feature(s) and/or interlock(s) which provide for securing of SAS upon loss of cooling water.

x 078A2.01, Ability to (a) predict the impacts of air dryer and 2.9 filter malfunctions On the lAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

1 03A2.04, Ability to (a) predict 103 Containment X the impacts of containment 35 evacuation (including recognition of the alarm) on the containment system and (b) based on those predictions, use procedures to correct, control, or mitiate the consecuences.

K/A Category Point Totals: 2 3 3 3 3 2 2 3/3 2 3 2/2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 234561 34 001 Control Rod Drive X 001A4.1 1, Ability to manually 3.5 operate and/or monitor in the control room: Determination of SDM.

002G2.1.19, Ability to use plant 002 Reactor Coolant X 3.8 computer to evaluate system or component status.

011 Pressurizer Level Control X 011 K2.01 Knowledge of bus 3.1 power supplies to the charging X pumps.

01 1A2.06, Ability to (a) predict 3.9 the impacts of an Inadvertent PZR spray actuation on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 01 7K4.03, Knowledge of TM 017 In-core Temperature Monitor X system design feature(s) and/or 3.1 interlock(s) which provide for the range_of temperature_indication 027 Containment Iodine Removal 028K6.01, Knowledge of the 028 Hydrogen Recombiner X effect of a loss of hydrogen 2.6 and Purge Control recombiners on CRDS components.

029 Containment Purge 033 Spent Fuel Pool Cooling

034 Fuel Handling Equipment 035A2.04, Ability to (a) predict 035 Steam Generator X the impacts Steam flow/feed 3.8 mismatch on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences 041A1 .01, Ability to predict 041 Steam Dump/Turbine X and/or monitor changes in 2.9 Bypass Control parameters (to prevent exceeding design limits) associated with operating the SDS controls including T-ave.

verification above low/low setpoint 045K5.23, Knowledge of the 045 Main Turbine Generator X operational implications of the 2.7 relationship between rod control and RCS boron concentration during T/G load increases as it applies to the MT/B System 055 Condenser Air Removal X 055G2A.4.18, Knowledge of the 3.3 specific bases for EOP5.

056K1 .03, Knowledge of the 056 Condensate X physical connections and/or 2.6 cause-effect relationships between the Condensate System and the MFW 068A2.02 Ability to (a) predict the 068 Liquid Radwaste X impacts of a, lack of tank 2.7 recirculation prior to release on the Liquid Radwaste System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences 071 Waste Gas Disposal 072A3.01, Ability to monitor 072 Area Radiation Monitoring X automatic operation of the ARM 2.9 system, including changes in ventilation_alignment 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals: 1 1 0 1 1 1 1 1/2 1 1 1/1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR lR G2.1.36, Knowledge of procedures and limitations involved in 2.1. core alterations 30 G2.1.45, Ability to identify and interpret diverse indications to 2.1. validate the response of another indication 2.1. G2. 1 1, Knowledge of conduct of operations requirements. 4.2 Conduct of Operations G2.1 .45, Ability to identify and interpret diverse indications to 2.1. validate the response of another indication 43 2.1.

2.1.

Subtotal 2 2 G2.2.18, Knowledge of the process for managing maintenance 2.2. activities during shutdown operations. 26 G2.2.38, Knowledge of conditions and limitations in the facility 2.2. license. 36 G2.2.21, Knowledge of pre- and post-maintenance operability 2.2. requirements. 41 2.

Equipment 2.2.

Control 2.2.

2.2.

Subtotal 2 G2.3.12, Knowledge of radiological safety principles pertaining to 2.3. licensed operator duties 32 G2.3.13, Knowledge of radiological safety procedures pertaining 2.3. to licensed operator duties

G2.3.4, Knowledge of radiation exposure limits under normal and 2.3. emergency conditions 3.2 G2.3.14, Knowledge of radiation or contamination hazards that 2.3. may arise during normal, abnormal, or emergency conditions or 3.8 Radiation activities Control 2.3. G2.3.6, Ability to approve release permits 3.8 2.3.

Subtotal 3 2 2.4. G2.4.1.1, Knowledge of abnormal condition procedures. 4.0 2.4. G2.4.25, Knowledge of fire protection procedures. 3.3 4.

G2.4.31 Knowledge of annunciators alarms, indications or 2.4. response procedures 4.2 Emergency Procedures! G2.4.16, Knowledge of EOP implementation hierarchy and Plan 2.4. coordination with other support procedures or guidelines.

G2.4.5, Knowledge of the organization of the operating 2.4. procedures network for normal, abnormal and emergency evolutions.

2.4.

Subtotal 3 2 Tier3PointTotal 10 10 7 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KA 2/ 1 SYSO64 A4.03 Q(23) This KA was rejected because it only lends itself to a GFES question. New KA (SYSO64 A4.05) randomly selected by Chief Examiner. HCF 11/18/13 2/ 1 SYSO78 K4.03 Q(27) KA rejected with concurrence of Chief Examiner due to feasability of writing an operationally valid question. New K/A SYS078 K4.01 randomly selected by CE. HCF 06/19/13 2/2 SYSO28 K6.01 Q(32) KA rejected due to Recombiners being abandoned in place. New KA SYSO34 K6.02 randomly selected by Chief Examiner. HCF 06/19/13 2/2 SYS05S 2.4.18 Q(35) Rejected KA with concurrence of Chief Examiner due to no EOP5 for CAR system.

New KA SYSO55 G2.4.11 randomly selected by CE. 06/19/13 2/2 SYSO68 A2.02 Q(37) KA rejected due to lack of RO involvement in LWR processing and release at MNS.

New KA SYSO68 A2.04 randomly selected by Chief Examiner. HCF 06/19/13 1 / 1 APEO65 AK3.04 Q(52) KA rejected with approval of Chief Examiner due to inability to come up with plausible distractors. New KA APEO65 AK3.03 randomly selected by Chief Examiner. HCF 09-03-13 1/ 1 APEO77 AA1.05 Q(56) Rejected due to inability to write acceptable question to match KA. New KA (APE 77 M1.03) randomly selected by Chief Examiner. HCF 11/7/13 1/ 2 APEOO1 AA1.07 Q(57) KA rejected due to inability to write a valid question to KA. New KA (APEOO5 AA1.05) randomly selected by Chief Examiner. HCF 11/8/13 1/2 WE15 2.4.8 Q(63) KA rejected due to not being able to write and operationally valid question to meet KA. New KA WE15 G2.4.4 randomly selected by Chief Examiner. HCF 06/19/13 2/ 2 SYSOO2 2.1.19 Q(81) KA rejected with approval of Chief Examiner due to inability to write discriminating SRO-level question to this KA. Replacement KA (SYSOO2 GEN 2.1.36) randomly selected by Chief Examiner. l-ICF 09-03-13 1I 1 APEO22 2.2.3 Q(85) KA rejected due to no unit differences at MNS related to CVCS (i.e. Reactor Coolant Makeup). New <A APEO22 G2.2.2 randomly selected by Chief Examiner. HCF 06/19/13 1/ 1 APEO57 AA2.02 Q(87) KA rejected due to inability to write question to match KA at the SRO level.

Replacement <A (APEO57 AA2.19) randomly selected by Chief Examiner. HCF 11/19/2013

E8401 Written ExaminatIon Quality Checklist Form E8401$

FaciUty: McGulre Nuclear Station Date of Exam; 12/17/2013 Exam Level: RD SRD

>nitlal Item Description a b* c

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

2. a. NRC K1As are referenced for all questions.

b. Facility learning objectives are referenced as available,

3. SRO quesbons are appropriate in accordance with Section D.2.d of ES401 f

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

. a examinations were developed Independently; or 1he 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 / SROonly question distribution(s) at right. 27 / 10 16 / 2 32 / 13

7. Between 50 and 60 percent of the questions on the RD Memory C/A exam are written at the comprehension! analysis level; -

the SRC) exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels, enter the actual RO / SRO question distribution(s) at right 37 / 8 38 / 17 B. References/handouts provided do not give away answers or aid In the elimination of distractors.

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

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

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

Printed Name! Signature Date

a. Author /3

b. Facility Reviewer (*)

Note: The facility reviewers Initials/signature are not applicable for NRC..developed examinations.

1. independent NRC reviewer InitIal Items In Column ca; chief examiner concurrence required.

ES-401 McGuire 2013 Written Examination Review Worksheet Final Form ES-401-9

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only Generic-All Bank questions shall have the answer (a,b,c,d) rearranged so that the answer is different than the bank answer.

Several questions on this exam are directly from 2011 and 2012 NRC Exams and MNS Audit Exams. This could make the exam predictable. Will discuss Instructions

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

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

2. Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

ES-401 2 Form ES-401-9

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus j Dist. Link units ward K/A Only H 2 M S 003A1.03 Question appears to match the K/A.

Question appears to be modified. 10/18/2013 Modified from MNS 2011 NRC question #1 SAT 11/14/2013 2 H 2 X M E 004A1.01 Question appears to match the K/A.

Question appears to be modified. Use only one parameter in the first part of question. Reactor power or RCS temperature. 10/18/2013 Modified from MNS 2010 question #2 Made changes as requested SAT 11/14/2013 3 H 2 B S 004A4.08 Question appears to match the K/A.

Question is not modified. The numbers are changed in the stem however, the answer is the same. This will be considered a bank question. Some of the underlined items is darker or bolder or a larger line size than the others (A. ONLY) all of these should be the same.

10/21/2013 CNS 2009 NRC question # 29.

Made changes as requested SAT 11/14/2013 4 H 2 N E 005K5.05 Question appears to match the K/A.

Distractor A is not plausible. The loss of a pump always causes pressure to lower (at least initially). Try something with one of the letdown valves. 10/21/2013 Made changes as requested SAT 11/14/2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues I T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus j Dist. Link units ward K/A Only 5 F 2 B S 006K1.14 Question appears to match the K/A.

2010 MNS NRC 0 #5 10/21/2013 SAT 11/14/2013 6 H 2 M E 007K3.01 Question appears to match the K/A. The first two bullets are not required. Modified 2011 MNS Audit Exam Question. 10/21/2013 Made changes as requested SAT 11/14/2013 7 H 2 B S 008K3.03 Question appears to match the K/A. 2009 MNS NRC 015 10/21/2013 SAT 11/14/2013 8 H 2 N S 010K5.01 Question appears to match the K/A. Is it an on off switch on 1-MC-10, or a start stop push-button?

Your lesson plan differs from you distractor analysis.

Just want to get it right. 10/21/2013 SAT 11/18/2013 9 H 2 B S 012K6.10 Question appears to match the K/A. This question could be modified very easily. 2008/9 CNS NRC 0 #37 10/21/2013 SAT 11/18/2013 10 F 2 B E 013K2.01 Question appears to match the K/A. Most of the items in the stem are not required. If your covered the bullets in the top of the stem, you could still ask the question beginning with WOOTF. .2010 MNS NRC 0

1. 11 10/21/2013 Change Power supply to supplies to the sequencers (ESF). Made changes as requested.

SAT 11/18/2013 11 F 2 X B U 022K2.02 Question appears to match the K/A. This appears to be a series of True/false statements. Could we put them in a situation Blackout or SI and state which fans would be running, or something similar?

2003 MNS Audit 10/2212013 Made changes as requested. SAT 11/18/2013

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- I Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A jOnly 12 H 2 X N E 022K4.03 Question appears to match the K/A. If an inadvertent SI occurs does this initiate a Phase A isolation? If so, change second part of question to read: Containment Ventilation System Supply Isolation valves ORN-3O1AC and ORN-302B will be Then use Open or Closed in the distractors.

10/2212013 Made changes as requested. SAT 11/18/2013 13 F 2 X B E 025K4.02 Question appears to match the K/A. As written distractor B is not plausible. If the applicant M

knows two signals will close the valve, the applicant would choose D. If the applicant knows only one of the signals he may choose A or C. But B is different from A, C and D and would not be chosen. By listing items in A and C and Both in delta, you are cueing that at least one of these is the answer. Need to replace B, or arrange the question in a different manner. 2010 MNS AUDIT 0 #14 10/2212013 Modified question as suggested.

SAT 11/18/2013 14 026A4.01 Question appears to match the K/A.

H 2 X M E Question does appear to be modified. However is it testing some of the same knowledge as Question # 10, in fact part of the stem from Q 10 may help to answer this question. 2012 MNS NRC 017 Modified 10/22/2013 Changed question 10 as requested.

SAT 11/1 8/2013

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 15 F 2 X N E 039A3.02 Question appears to match the K/A. Will S/G pressure get <775 psig, prior to RCS getting less than P-i 1? (question appeal) This could open up some questions. Need to rephrase stem to eliminate this concern. 10/22/2013 Made changes to question stem, SAT 11/18/2013 This is now a fundamental level question.

16 H 2 X N E 059G2.1.23 Question appears to match the K/A.

Change turbine inlet pressure to 480 psig, then question is OK. AP states with turbine inlet pressure greater than 400-410 psig. (states this is 56%)

10/22/2013 Change turbine inlet pressure to 510, then sat. SAT 11/18/2013 17 H 2 X B U 059K3.01 Question appears to match the K/A. The way this question is asked is very confusing. The original questions in distractors C and D stated following...

That makes a little more sense. Why would CA pumps start any time they are in defeat, unless the defeat signal cleared? Why is tave listed in the stem, it does not mean anything in this case (except to insinuate you are still heating up (nothing was done to stop that). I know this was used on a previous exam but it does not appear to me that distractors C or D are plausible.

2009 MNS NRC Retake 018 H 2 N S 10/22/2013 Completely rewrote question. New question matches the K/A. SAT 11/18/2013.

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 18 F 2 X N E 061 K5.0l Question kind of matches KJA. It would be better if we were talking about AFW flow versus S/G level, but the level rise is due to AFW flow. Would RCS pressure be at 1350 psig with CETs at 584°F? I realize this is approximately psat/tsat but will a loss of feed the RCS pressure rarely drops to this level and as the S/G level lower it tends to increase. Is there a steam leak present (How did CTMT pressure get to 2.1 psig? This question needs a little more work.

10/22/2013 Completely changed the stem. SAT 11/18/2013 19 H 2 B E 061 K6.02 Question appears to match the K/A. This is essentially the same question as the one asked on the 2012 MNS NRC exam. Only the unit and train has changed. The Unit change did not matter, and the answer is the same for the other train. ES 401 page 8 of 33. Is there some other item we could test to meet this K/A?

2012 MNS NRC 0 #20 10/22/2013 Discussed with licensee, why is 450 gpm to each S/G plausible? Changed C and D to 150 gpm each.

SAT 11/18/2013 20 H 2 N S 062G2.4.47 Question appears to match the K/A.

Changes made to question as discussed, are we too close on the third value. I will let you decide. Will discuss. Otherwise question is SAT.

10/22/2013 Discussed with licensee. SAT 11/18/2013

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 21 F 2 B E 062A2.06 Question appears to match the KJA.

Recommend removing distractor A and replace it with all items in answer D plus verifying the B DIG is operable. Or you could just add the D/G operability to A. Will Discuss. 2012 MNS Audit Exam 021 10/22/2013 Made suggested changes. SAT 11/18/2013 22 F 1 B U 063K1.03 Question appears to match the K/A. Not very discriminating. This is really GFES. LOD=1. This question is listed as higher cog, and it appears to be a fundamental question. Need to fix or replace.

2011 MNS AUDIT 022 10/22/2013 Replaced Question. SAT 11/18/2013 23 F 1 B U 064A4.03 Question appears to match the K/A. Not very discriminating. This is really GFES. LOD=1 Not higher cog, if you are paralleling the DG, it is in speed droop mode. 2005 MNS NRC 10/22/2013 Licensee requested new K/A. Changed to 064A4.05 11/18/2013 Replaced question. Replacement question appears to match K/A. Distractor B is not plausible.

11/20/2013 Upon further discussion, the D/G switch does have an Auto position. Question is SAT 11/25/2013

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 BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only 24 F 2 B S 073A2.02 Question appears to match the K/A.

Question is not significantly modified, an additional annunciator was added, however, it is in all of the choices, and this is essentially the same as the original bank question. 2011 MNS AUDIT Exam 0 #24 10/22/2013 relisted as bank. SAT 11/18/2013 25 F 1 B U 076A3.02 Question appears to match the K/A. What is the normal cooling water for the AFW pumps. If it is normally RN then this is a LOD=1. It appears that from objective 10 of Lesson Plan OP-MG-CF-CA, The train related RN pump will automatically start upon any start (including Manual) of the corresponding CA pump to provide necessary cooling to the CA pump motor. RN cools the pumps all of time, whenever started, so it will always be the right answer. Need to Replace question.

2011 MNS NRC 026 10/23/2013 Replaced question with Bank question. Changed distractor D to mechanically failed. SAT. 11/18/2013 26 F X N U 076K2.04 Question appears to match the K/A.

However answer C is the only distractor that is a 4160V. Busses 1TA and 1TC are 6.9 Ky, and Bus 1 EMXA is 600V. None of these are plausible. Question needs some work. 10/23/2013 Replaced question but two distractors may not be plausible. Will discuss.

Need to fix distractors 11/18/2012 Replaced question again question matches the KJA.

Do not believe distractor B is plausible. 11/20/2013 Upon further discussion with licensee and other examiners, determined distractor B was acceptable.SAT 11/25/2013.

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

Q# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F I Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN UIFJS Focus Dist. Link units! ward K/A Only 27 F N N S 078K4.01 Question kind of matches the K/A, will allow.

10/23/2013 SAT 11/18/2013 28 H 2 X M E 103A2.04 Question appears to match the K/A.

Change: The Containment Evacuation alarm JjJ be activated, to The Containment Evacuation alarm Li) automatically actuate. Change responses to will and will not.

Is it wrong to enter AP 40, will this procedure mitigate the event? If this procedure will not mitigate the event, maybe would should state: Based on the above conditions (2) will mitigate the event.

Question appears to be modified.

2010 MNS AUDIT Exam 0 #58 10/23/2013 Add in second part, after the 2to mitigate the event. 11/18/2013 Added as requested. SAT 11/18/2013 29 F 2 N S 001A4.11 Question appears to match the K/A.

10/23/2013 SAT 11/18/2013 30 F 2 B S 011K2.01 Question appears to match the K/A. This question is not significantly modified only the unit was changed, and the answer is still the same. 2009 MNS Audit 0 #31 10/23/2013 Changed to Bank SAT 11/18/2013 31 F 2 N S 017K4M3 Question appears to match the K/A.

10/23/2013 SAT 11/18/2013

Q# LOK 2.

LOD

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

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= ISRO B/M/N U/E/S Explanation j Focus Dist. Link units ward K/A Only 32 F 2 M E 034K6.02 Question appears to match the K/A. Swap distractors B and D. Question appears to be significantly modified. 2005 MNS NRC 050 10/23/2013 Made changes as requested. SAT 11/18/2013 33 F 2 N S 041 Al .01 Question kind of matches K/A. 10/23/2013 SAT 11/18/2013 34 H 2 B E 045K5.23 Question kind of matches K/A.

Some of the information given is in conflict with student reference given. Student reference state restrictions are required when > 50% power, part of the question analysis states > 40% power.

Second half of question does not really make sense.

In order to keep i2l in the correct band a dilution is always required. I know this question was used on an NRC exam in the past, but a dilution is always required when going from 20% to 100% power.

Need to fix the second half of the question.

V 2010 MNS NRC 0 #37 10/23/2013 Replaced question, new question kind of matches the K/A. Very involved, This could be an admin JPM. Will discuss. 11/18/2013 Go back to the original Went back to original question, rewrote stem.

Question is acceptable. SAT 11/20/2013

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- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 35 H 2 B S 055G2.4.11 Question appears to match the K/A. 2009 MNS NRC 025 10/23/2013 Rotated answers as requested. SAT 11/18/2013.

36 F 2 N E 056K1.03 Question appears to match the K/A. Change 330 psig to 280 psig. If standby pumps start at 330 psig, the pump trip would be lower. 10/23/2013 Made changes as requested. SAT 11/18/2013 37 H 2 B E 068A2.04 Question appears to match the K/A. The ARP directions are different from the distractor analysis. Your distractor analysis states if 1-WP-35 will not close from the control room, direct the radwaste to close 1 -WP-35 locally. But the ARP stated for radwaste to close 1-WM-45.

Can 1-WP-35 be closed locally?

Suggest:

Change distractors A and C second part to ensure 1-WP-35 is closed. Change distractors B and D second part to Direct lRadwaste to close 1-WM-45 (EMF49 Outlet Isolation to RC).

Or something similar that is correct and cannot be appealed.

2009 MNS Audit Exam. 10/23/2013 Made changes as requested. SAT 11/18/2013 38 F 2 B S 072A3.01 Question appears to match the K/A. 2005 MNS NRC 052 10/23/2013 SAT 11/18/2013

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

Q# LOK L0D (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N IJ/E/S Explanation Focus Dist. Link units ward K/A Only 39 F 2 M S OO7EK1.03 Question appears to match the K/A.

Question appears to be modified. 2011 MNS NRC 0

1. 39 Modified. 10/23/2013 SAT 11/18/2013 40 H 2 B S 009K203 Question appears to match the K/A. 2010 MNS NRC 0 #41 10/23/2013 SAT 11/18/2013 41 F 2 X B E 015G2.1.7 Question appears to match the K/A.

Change shaft vibration in stem to motor shaft vibration.

This will make the 5 mils a little more plausible. 2006 CNS NRC 05 10/23/2013 Made changes as requested. SAT 11/18/2013 42 H 2 N S 025AA2.07 Question appears to match the K/A.

10/23/2013 SAT 11/18/2013 43 F 2 M S 026AA1 .07 Question appears to match the K/A.

Question appears to be modified. Question is very wordy, are all of these required? 2012 MNS NRC Exam 045 Modified 10/23/2013 Made some minor changes to stem to reduce wordiness. Otherwise SAT 11/18/2013

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 44 H 2 B E 027AG2.4.9 Question appears to match the K/A.

Suggest the following:

A SBLOCA occurred coincident with a loss of Off-site power.

• ES 1.2 has been entered and the NCS has been cooled down to 51 0°F.

• NC System Pressure is 1600 psig

• Pressurizer level is 2%

• Containment Pressure peaked at 3.1 psig and is now 1.9 psig and stable Which One of the following describes how RCS pressure will be reduced in accordance with ES-i .2, and when pressure reduction will be stopped?

a. Using normal pressurizer sprays pressure reduction can be terminated as soon as pressurizer level exceeds 25%

b. Using normal pressurizer sprays, pressure reduction can be terminated as soon as pressurizer level exceeds 50%

c. Using one PORV pressure reduction can be terminated as soon as pressurizer level exceeds 25%

d. Using one PORV pressurizer pressure reduction can be terminated as soon as pressurizer level exceeds 50%

Question would then be modified.

2008 MNS Audit Exam 040 10/23/2013 Made changes as requested. Modified. SAT 11/18/2013

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

Q# LOK L0D (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- 0= SRO B/M/N lJ/E/5 Explanation Focus Dist. Link units ward K/A Only 45 F 2 N S 038EA1.27 Question appears to match the K/A.

10/23/2013 SAT 11/18/2013 46 H 2 B E 054AK1.02 Question appears to match the KJA.

Unit 1 has established feed and bleed while performing the actions of FRH.1 The TDAFW pump has been started and is available to feed the SGs.

All SG WR levels are 0%

Which one of the following describes the criteria for restoring feed water flow and why?

a. Restore cooling to ALL intact S/Gs at a rate not to exceed 100 GPM, to minimize thermal stress to the reactor vessel.

b. Restore cooling to ALL intact S/Gs at a rate not to exceed 100 GPM, to minimize thermal stress to the steam generator components.

c. Restore cooling to one intact S/G at a rate not to exceed 100 GPM, to minimize thermal stress to the reactor vessel.

d. Restore cooling to One intact S/G at a rate not to exceed 100 GPM, to minimize thermal stress to the steam generator components.

This is essentially the same question with fewer words.

It is still a bank question. 2010 MNS NRC Q #47 10/23/2013 Made changes to stem and distractors.

SAT 11/18/2013

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

Q# LOK L0D (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 47 H 2 M S 055EK1.02 Question kind of matches the K/A. Not sure it is operationally valid. If the unit has lost all AC for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, plant conditions would have degraded more. I doubt a transition to ECA 0.1 could be made.

Furthermore, One items in the in your description of the question states that power is not available, however if you have transitioned out of ECAO.0, then power is available. I know this was used before; however I do not think these plant conditions can be achieved.

While reviewing McGuires ECA 0.0 I believe the S/Gs would have been depressurized to 290 psig if a loss of all AC lasted 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Will discuss.

2011 MNS NRC Exam 05110/23/2013 Removed bullet in stem referring to a loss of all AC lasting 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Question is modified. SAT 11/1812013 48 F 2 X X N E 056AG2.4.20 Question kind of matches the K/A. All of the information in the stem prior to In accordance with ECA 0.0 can be removed, it is not needed. The first part of the first question is teaching and is not needed.

Start with: Vital batteries are sized to .The second part can remain as written. (Way too many words) 10/23/2013 Made changes as requested. SAT 11/18/2013 49 F 2 N U 057AK3.01 Not sure this meets the K/A. Referred question to two other examiners. Two other examiners reviewed this question, together it was determined that the question did not meet the K/A. (The reason being tested refers to the 4160v emergency bus, not the 120v Vital Instrument bus). The first half of distractors B and D are not plausible. 10/23/2013 5 Replaced question. New question is SAT 11/18/2013

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

Q# LOK L0D (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N IJ/EJS Explanation Focus Dist. Link units ward K/A Only 50 H 2 B S 058AA2.03 Question kind of matches the K/A.

2005 MNS NRC Exam 02 10/23/2013 SAT 11/18/2013 51 F 2 B S 062AA2.01 Question appears to match the K/A.

2011 MNS NRC 0 #54 10/24/2013 Discuss repeat questions. SAT 11/18/2013 52 H 2 N S 065AK3.03 Question appears to match the K/A.

10/24/2013 SAT 11/18/2013 53 F 2 N S WEO4EK2.l Question appears to match the K/A.

10/24/2013 SAT 11/18/2013 54 F 2 B E WE11EK3.4 Question kind of matches the K/A. This is a tough K/A. Will allow. Change stem to read: Which one of the following lists all the reasons for the cooldown and depressurization of the RCS in ECA 1.1 .1 really dont know if this is better, but it reads a little easier. Need to ensue # 1 is not a reason.

CNS BANK 10/24/2013 Changed stem as requested still need to determine if 1 is NOT a reason.

Licensee states that # 1 is not a correct reason.

SAT 11/18/2013

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- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward KJA Only 55 H 2 N E WEO5EK2.2 Question appears to match the K/A. Not sure the second part is worded correctly. One SG at 36%, or 2, or 3, etc. Need to work on the second part.

Maybe add required SG levels decrease to a level of...

10/24/2013 Made changes requested. SAT 11/18/2013 56 F 2 X X B E 077AA1.05 Question may not match the K/A. Will get a second opinion. What is the difference between committed sequence and accelerated sequence? After reading your lesson material is appears that the accelerated sequence is always used on a sequence run and the committed sequence is only used when the accelerated sequence fails. Therefore distractor C is not plausible. MNS 2011 AUDIT 053 10/24/2013 Replaced question with Bank question from 2008 Catawba exam. Just state that initially the power factor is .99. Removed the PF meter from the question (teaching in stem) SAT 11/18/2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F J Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. j Link units ward K/A Only 57 H 2 X N U 001 Al .07 Do not believe this meets the K/A. The KJA asks about continuous rod motion but the question asks about rod position indication after the motion is stopped. You could remove all of the question stem above A Data failure occurs on Rod D-4 and ask the same question. Furthermore, did rod motion stop?

Try writing a question that asks about rod motion and which indication would be more accurate as to rod position when rods are stopped (group vrs individual) If we cant develop an acceptable question here we will have to change the K/A. 10/24/2013 Changed K/A to OO5AA1 .05 Licensee submitted new question.

Changed second part to be green/orange. SAT 11/18/2013 58 F 2 X N U 036K3.02 Question does not meet the K/A. The containment hatches are not fuel handling equipment, 10/24/2013 Wrote new question on manipulator crane. SAT 11/18/2013 59 H 2 N E 037AK1.01 Question appears to match the K/A. All of these conditions indicate subcooled conditions, so remove the portion of the stem that states while maintaining the NC system subcooled. What you are really looking at is tiP between RCS and SG.

10/24/2013 Made changes as requested. SAT 11/18/2013

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 BIM/N UIEIS Explanation Focus Dist. Link units ward K/A Only 60 H 2 X B E 051AA2.02 Question kind of matches K/A. Why is 23 plausible, your distractor analysis states vacuum alarm comes in at less than 23, if so this value is not plausible? What is the trip setpoint if power is less than 100%? 2011 MNS AUDIT Q58 10/24/2013 Licensee made changes to the second part of the stem. SAT 11/18/2013 61 F 2 B S 068AA2.05 Question appears to match the K/A.

2011 MNS AUDIT 061 10/24/2013 SAT 11/18/2013 62 F 2 X X N U 076AK2.01 Question does not appear to match the K/A. This is a systems question for rad monitors. Again you could remove the top of the stem and the question could still be asked as is. Use AP-18 and ask what radiation monitor will require entry in to AP. Second part of question is acceptable. As written the question is also teaching in the stem (location of rad monitor).

That is what this K/A is really looking for.

10/24/2013 S Reworded question to test more of the Radiation monitor and loctation SAT 11/18/2013 63 H 2 X B E WE15G2.2.2 Question appears to meet the K/A.

Second part of distractors C and D may not be plausible, are these safety related?

2011 MNS AUDIT 065 10/24/2013 upon further discussion C and D were safety related. Appear to be plausible.

SAT 11/18/2013

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 64 F 2 M S WEO3EK2.2 Question appears to match K/A.

Question appears to be modified.

2009 CNS NRC Q23 MODIFIED 10/24/2013 SAT 11/18/2013 65 F 2 X N E WEO8EK3.3 Question appears to match K/A. First part of the question is asking the same thing that has been asked before although it was reset SI only.

Distractors A and D are not plausible as written.

Resetting the sequencer only does not make sense when you are terminating SI. Need to change/fix the first part of the question.

10/24/2013 Changed first part to reset SI only. This makes a little more sense. SAT 11/18/2013 66 F 2 B S G2.1.36 Question appears to match K/A. Not very discriminating. CNS Exam Bank 10/24/2013 67 H 2 X B U G2.1.45 Question appears to match K/A. I realize this is a bank question off of a previous NRC exam but distractors C and D are not plausible. 2011 MNS NRC Exam 0 #4 10/24/2013 Replaced with a new question SAT 11/18/2013 68 F 2 N S G2.2.18 Question appears to match K/A. 10/24/2013 SAT 11/18/2013

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 BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 69 H 2 B U G2.2.38 Question appears to match K/A. Three distractors contain operable, and one available. I dont think TS talks about available. Therefore as written distractors A and B are essentially subsets. If both trains were required and both were not operable, then would you not be in 3.0.3? Therefore distractor C is not plausible. This question needs some work. 2009 MNS NRC 017 10/24/2013 Need to work on this some more Replaced question, not very discriminating but acceptable. SAT 11/20/2013 70 F 2 B E G2.3.12 Question appears to match K/A. Distractors B and D are not plausible. I have never seen a flashing sign, and I would not pick these choices. I did not give you an unsat on this question because this is easily fixed. Would also add locked or guarded.

ONS Bank Question 10/24/2013 Made changes to question SAT 11/18/2013 71 F <1 N U G2.3.13 Question kind of matches the K/A. Not discriminating. LOD=1. This K/A is really asking about response to radiation monitors in the plant, not PEDs.

There are many other questions out there that are more discriminating and match the K/A better.

Replace Question. 10/24/2013 Modified Bank Catawba question appears to be acceptable. SAT 11/18/2013 72 H 2 N S G2.3.4 Question appears to match K/A. 10/24/2013 SAT 11/18/2013

1 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 #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 73 F 2 X B S G2.4.11 Question appears to match the K/A. 2005 MNS NRC Exam 10/24/2013 SAT 11/18/2013 74 F 2 B U G2.4.25 Question appears to match the K/A. Will a jockey pump start if taken to start? Are these separate switches (manual and start)? As written distractors A, B and C do not make sense 2011 MNS AUDIT 0 #68 1 0/24/2013 Rewrote question SAT 11/18/2013 75 H 2 B E G2.4.31 Is there a situation that allows EVDB to be connected to EVDA or EVDC to EVDA? If not A and B distractors are not plausible? How would connecting EVDB to EVDA help the EVDC battery? 2007 MNS NRC Exam 052 changed distractor A and rearranged distractors. SAT 11/18/2013 SAT 31 UNSAT14 Enhancements 30

ES-401 McGuire 2013 Written Examination Review Worksheet Final (SRO) Form ES-401-9 1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only Generic-All Bank questions shall have the answer (a,b,c,d) rearranged so that the answer is different than the bank answer.

Please explain the process of how the bank questions were selected.

Instructions

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

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

2. Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

ES-401 2 Form ES-401-9 SRO Questions 76 H 2 X X B S 004G2.2.22 Question does not appear to match the K/A.

The K/A is for the charging system and the question refers to actions required in a SGTL event. Appears to be asking an SRO topic.

The TS listed is for standby shutdown system, not the CVCS system.

This question is slightly different than the original bank question. Charging flow is 85 gpm, not 78 as listed in the original question and your distractor analysis. This makes distractors B and D not plausible.

2011 MNS NRC Exam Q92 10/24/2013 After discussion it appears the standby makeup pump is part of the CVCS system. Agree with the changes to the second part of the distractors. SAT 11/19/2013 77 H 2 B S 012G2.1.2 Question appears to match the K/A.

2009 MNS NRC Exam 0 # 77. 10/28/2013 SAT 11/19/2013 78 H 2 X N E 013A2.02 Question appears to match the K/A.

Appears to be SRO only. Change the 22% in train A at 0205 to 23% it is still wrong and make the choice a little more plausible. 10/28/2013 Made changes as requested. SAT 11/19/2013

79 F 2 X N E 059A2.03 Question appears to match the K/A. Do not think it is SRO only. (Asked two other Examiners for help). Entry conditions into CSFs are RO knowledge, and notes in E-O are RO knowledge. 10/28/2013 Question is not SRO only need new question. The first part is still an entry condition, and the second half is procedure /EOP usage. Typically a note in E-0 that states do not implement CSFs in E-0. Changed Unsat designation to Enhancement based on previous chief examiner comments. 11/19/2013.

Licensee changed second part of question to test background document reason for the setpoint.

SAT 11/25/2013 80 H 2 X X B E 078A2.01 Question appears to match the K/A. Does not appear to be SRO only. The first part of the question is systems knowledge (RO knowledge). The second part of the question is just common sense.

Second part of distractors C and D are not plausible as written. Why would you have a valve automatically close, and then send someone to verify it closed?

Therefore the applicant need only understand that the bypass will automatically open at 85 psig (RO knowledge) and will correctly answer the question.

2011 MNS AUDIT 0 #80 10/28/2013 Made changes to second part of question. Tough K/A to reach at SRO level will allow. SAT 11/19/2013

81 F 2 X N U 002G2,1.36 Question does relate to fuel handling, but how does it relate to the reactor coolant system?

Question does not appear to match the KJA. Question does have an SRO aspect to it. Question needs to relate to the RCS. Most of the stem could be removed and the question could still be asked. 10/28/2013 Second attempt of the question does relate to the RCS (basis statement for having a boron concentration high enough to have Keff be .95.

However the .99 (greater than or less than) number is not plausible. This is the typical value that is maintained in Mode 1, 2, or 3, 4, or 5 when refueling is not in progress (listed in your definitions). So why would anyone think this acceptable during refueling?

Try asking a question on TS 3.9.5 involving RCS flow or requirements for having RHR in operations etc. Licensee replace question with new question.

SAT 11/25/2013.

82 F 2 N E 011A2.06 Question kind of matches the K/A. Good attempt at a tough K/A. Appears to have an SRO aspect to it. Not sure it is operationally valid. What is causing pressurizer level to rise? (Just the spray valve lowering pressure and SI flow filling the Pressurizer?)

Will discuss. 10/28/2013 After discussion determined question to be SAT 11/19/2013

83 H 2 X N E 035A2.04 Question appears to match the K/A.

Appears to have an SRO aspect to it. Second part of distractors A and B do not appear to be very plausible on a complete loss of CF from one pump @ 100%

power. Suggest changing them to: immediately trip the reactor and enter E-0. 10/28/2013 Add: the crew will be directed to... then SAT 11/19/2013 84 H 2 X N E OO9EAG2.4.4 Question appears to match the K/A.

Appears to have an SRO aspect to it. Fourth bullet in step states NC pumps have been secured due to loss of subcooling. This is cueing. Just state NC pumps have been secured. Second part of distractors c and d not very plausible with these conditions (yes you will transition to ES1 .3 sooner or later if not completely cooled down and on RHR. But it will be way later. Will discuss. 10/28/2013 Made changes as requested SAT 11/19/2013 85 H 2 X B E 022AG2.2.22 Question appears to match the K/A. May have an SRO aspect to the question. Currently as written there appears to be two correct answers.

Without a time line, both A and C are correct. If the loss of charging and therefore letdown lasts longer than 60 minutes, the letdown depressurization must be done locally. With no time listed one could argue that both are correct. 2010 MNS NRC 0 #85 10/28/2013 Reviewed question again and agree. Question is SAT 11/19/2013

86 H 2 X M U 040AA2.04 Question appears to match the K/A.

Question appears to be modified. Does not appear to be SRO only. Knowing only one train of ESF is required to satisfy the design requirements is RO knowledge. This may be in the basis, but it is also the system function. Objectives 2 and 3 of the ECC-Nl lesson plan. 2009 MNS NRC 0 #56 Modified 10/28/2013 Licensee revised question, however it now has a combination of ECCS actuation, and Main steam line actuation. Suggest rewriting first part to test if one or both trains of MSLI will occur, and the MSIVs must be closed within XX seconds.

Will attempt to change 11/19/2013 Licensee rewrote question, changed to MSLI and time for MSIVs to close. SAT 11/25/2013 87 H 4 X N U 057AA2.02 Question does not appear to match the K/A. What vital AC electrical instrument bus was lost, and how did that loss affect the CLAs? Question may not be SRO only. (Requested verification from other examiners). The fact that one accumulator is expected to be loss out of the break is ECCS functional knowledge and is typically RO knowledge. The first part of the question regarding CLA level is TS entry level and is RO knowledge. 10/28/2013 Changed K/A to 057AA2.07 or 2.19 or 2.20 Licensee rewrote new question for 057AA2.19 Question is SAT. 11/25/2013 88 F 2 B S 062AA2.03 Question appears to match the K/A.

Appears to have an SRO aspect to it. MNS Exam Bank 0 #3171 10/28/2013

89 H 2 N E WEO5G2.4.37 Question appears to match the K/A.

Appears to be SRO only. Use Alert instead of General Emergency it is more plausible. Will Discuss.

10/28/2013 Made changes as requested 11/19/2013 90 H 2 N S 005AA2.01 Your assessment was correct, the K/A is not exactly met; however, it does address the use of NIs in the AOP and enclosure. I believe the question requires SRO knowledge to answer. I am inclined to allow the question as written.

10/28/2013 91 H 2 N S 033AG2.1.20 Question appears to match the K/A.

Appears to be SRO only. 10/28/2013 92 H 2 M S WEO7G2.4.41 Question appears to match the K/A.

Appears to be SRO only. 2012 MNS Audit 0 #92 10/28/2013 93 H 2 N S WEO1 EA2.1 Question appears to match the K/A.

Appears to be SRO only. 10/28/2013 94 F 2 B S G2.1.1 Question appears to match the K/A. Appears to be SRO only. Not very discriminating. 2010 MNS Audit Exam 095 10/28/2013

95 F 2 N S G2.1 .45 Question appears to match the KJA. This is a different way to match this K/A. I also tend to believe this is SRO only knowledge. Need to make sure the RO question on this K/A does not help the SRO applicants to answer this question. (May need to change the RO K/A if this cannot be done)

Question could be made a little less confusing by rewording stem to state:

Indications:

• S/G NR level rising in an uncontrolled manner

• S/G or Steam line EMF is above normal

• Comparison of SIG Secondary Chemistry samples

1. Comparison of RP frisk of main steam lines

2. S/G CF flow comparison

3. Comparison of RP frisk of S/G Cation Columns A. 1 only B. 3 only C. land2 D. 2and3 Made changes as requested. SAT 10/28/2013 Made changes as requested. 11/19/2013 96 F 2 B S G2.2.21 Question appears to match the K/A. Appears to be SRO only. The second and fourth bullets are not needed. In place of the fourth bullet use the 2A boric acid pump in placed in recirc as required. 2009 MNS Audit Exam 0 #99 10/28/2013 Made changes as requested. 11/19/2013

B E G2.3.14 Question really does not match the K/A.

97 H 2 X Appears to be SRO only. If you take away the top of the stem, and begin with the chemistry sample, you could ask the question the answer would be the same and there would be no reference to radiation or contamination hazards that may arise during plant operation. Need to get closer to the K/A. RO question 62 is also testing this topic. 2008 MNS NRC 0 #97 10/29/2013 Put the alarms back in the question, I did not mean for you to remove them, they would be in alarm if activity were at this level. Agree with assessment that the procedure is attempting to mitigate the radiation hazard. Keep the other bullets as you have them in the new version. Then question will be SAT 11/19/2013 98 F 2 X B U G2.3.6 Question appears to match the K/A. This is an SRO task. Distractor C is not plausible; this cannot be done from the control room. Distractors C and D are both limits, (essentially subsets).

2007 MNS NRC Retake 0 #97 10/29/2013 Replaced distractor C. Question is not very discriminating but SAT 11/19/2013 99 H 2 B E G2.4.16 Question appears to match the K/A. Appears to be SRO only. Distractor B is not plausible. ERPs are never suspended unless going to a higher priority procedure.

2011 MNS NRC 0 #94 10/29/2013 Made change to distractor B. Now SAT 11/19/2013

100 H 2 B U G2.4.5 Question kind of matches the K/A. Question has an SRO aspect to it. Distractors C and D are not plausible. AOPs never have priority over ERGs, and the previous question just tested that AOP can be used in conjunction with ERGS. Need to develop two new distractors, or replace question. Replaced Question made some changes to replacement SAT 11/19/2013 2007 MNS NRC Q #99 10/29/2013 SAT- 10, Enhancements- 10, Unsatisfactory- 5

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist 7

Facility: McGuire Date of Exam: 12/12/2013 Exam Level: RO L1 SRO Ri Initials Item Description a b

1. Clean answer sheets copied before grading iV,4 d

2. Answer key changes and question deletions justified and documented

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

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

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

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of_questions_missed_by_half_or more of the_applicants Printed Name/Signature Date

a. Grader

b. Facility Reviewer(*) 4 A6 AJ/A

c. NRC Chief Examiner (*)

d. NRC Supervisor (*) tL 5

;?Lfr-__.

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