ES-20I Facility: McGuire Date of Examination: June 27 30, 2011 … · 2012-12-05 · ES-201...

ES-20I - Examination Preparation Checklist - Form- ES-201 -1

Facility: McGuire Date of Examination: June 27 — 30, 2011

Examinations Developed by: Facility

Target ChiefDate* Task Description (Reference) Examiner’sInitials

-180 1. Examination administration date confirmed (C.1.a; C.2.a and b) 4 ,L-120 2. NRC examiners and facility contact assigned (C.1 .d; C.2.e) 4 L..-120 3. Facility contact briefed on security and other requirements (C.2.c) ,% “-120 4. Corporate notification letter sent (C.2.d)

[-90] [5. Reference material due (C.1 .e; C.3.c; Attachment 2)]

-75 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3,ES-301-1, ES-301-2, ES-301-5, ES-D-l’s, ES-401-112, ES-401-3, andES-401-4, as applicable (C.1.e and f; C.3.d)

-70 7. Examination outline(s) reviewed by NRC and feedback provided to facilitylicensee (C.2.h; C.3.e)

-45 8. Proposed examinations (including written, walk-through JPM5, andscenarios, as applicable), supporting documentation (including FormsES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and referencematerials due (C.1 .e, f, g and h; C.3.d)

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

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

-14 11. Examinaon approved by NRC supervisor for facility licensee review

-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) .A J-7 13. Written examinations and operating tests approved by NRC supervisor

(C.2.i; C.3.h)

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

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

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

* Target dates are keyed to the examination date identified in the corporate notification letter.They are for planning purposes and may be adjusted on a case-by-case basis in coordinationwith the facility licensee.

[ ] Applies only to examinations prepared by the NRC.

ES-201 Examination Outline Quality Checklist Form ES-201-2DRAFT (RevJLNAL)

Facility: McGuire Date of Examination: 6/27/11. InitialsItem Task Description

a b c#1. a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

b. Assess whether the outline was systematically and randomly prepared in accordance ,—..

W with Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. tc. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

T d. Assess whether the justifications for deselected or rejected K/A statements areT appropriate. if

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required numberof normal evolutions, instrument and component failures, technical specifications, and

s major transients. DL. Vr

I b. Assess whether there are enough scenario sets (and spares) to test the projected

M number and mix of applicants in accordance with the expected crew composition androtation schedule without compromising exam integrity; and ensure that each applicant

U can be tested using at least one new or significantly modified scenario, that noL scenarios are duplicated from the applicants’ audit test(s), and scenarios will not beA repeated on subsequent days. DLT c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and0 quantitative criteria specified on Form ES-301-4 and described in Appendix D. 9

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

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

(2) task repetition from the last two NRC examinations is within the limits specified on ‘ ,/the form, l’ -t.(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 PA—criteria on the form.

b. Verifythatthe 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 projected number and mix of‘ /

applicants and ensure that no items are duplicated on subsequent days. 0 z..... -ti.a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in

the appropriate exam section.

b. Assess whether the 1OCFR 55.41/43 and 55.45 sampling is appropriate.

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

d.. Check for duplication and overlap among exam sections. 4e. Check the entire exam for balance of coverage.

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

a. Author David Lazarony/Western 7ecical Services Inc. 6/10/1 1

b. Facility Reviewer (*)

c. NRC Chief Examiner (#) L . 4d. NRC Supervisor

1/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

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 <1 c.avN. ‘ as of the dateof my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by theNRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administeredthese 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 indirectfeedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee’s procedures) andunderstand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me orthe facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination securitymay 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 administeredduring the week(s) of%k’,e 2?foII From the date that I entered into this security agreement until the completion of examination administration, I did notinstruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically notedbelow and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY

1. 4Rs4

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SIGNATURE (1)

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DATE SIGNATURE (2),-’DTE NOTE

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ES-201, Page 27 of 28


1. Pre-Examinatlon

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of_‘ as of the date• of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the

NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administeredthese 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 indirectfeedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee’s procedures) andunderstand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me orthe facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination securitymay have been compromised.

2. Post-Examination

To the best of my knodge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administeredduring the week(s) ofli4n4 Z.D!I From the date that I entered into this security agreement until the completion of examination administration, I did notinstruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically notedbelow and authorized by the NRC.

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

1. si.L4 77W’2. 2.& xf.ii3 ‘4-14- 7-1-Lt3. D°uG WA’c€UL -a( -L1- Il

4

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10. P-.-’11.i 8IkL.. (A ,Cb /v..I12. 12’ 5Jalj -/1/ ?fs/u13. )‘ wte& TRf1 ht4Mr 6,.,I /;E ‘/014.15. G’a- ,,

W”/‘tfr’NOTES:

ES-201, Page 27 of 28


1. Pre-Examination

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of s of the dateof my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by theNRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administeredthese 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 indirectfeedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee’s procedures) andunderstand that violation of the conditions of this agreement may result in cancellation of the examinations anchor an enforcement action against me orthe facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination securitymay 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 administeredduring the week(s) ofJm4i1ZOif. From the date that I entered into this security agreement until the completion of examination administration, I did notinstruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically notedbelow and authorized by the NRC.

PRINTED NAME

1. ?GT €€... L. r2. AWIN PRS)o.3. uJL c.os

DATE SIGNATURE DATE NOTE

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.JOB TITLE I RESPONSIBILITY SIGNATURE (1)

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14.15.NOTES:

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ES-201, Page 27 of 28


1. Pre-Examination

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of__________ as of the dateof my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by theNRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administeredthese 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 looth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirectfeedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee’s procedures) andunderstand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me orthe facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination securitymay have been compromised.

2. Post-Examination

To the best of my knowjdge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administeredduring the week(s) of_________ From the date that I entered into this security agreement until the completion of examination administration, I did notinstruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically notedbelow and authorized by the NRC.

PRINTED NAME

1. lNc S4ADS2.JfJ) VIZ43

3. IeRe’4.5. Fi,vi’6. PhI17. l.aee-i8. 7oc.c& €LT9. I((YRNt

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JOB TITLE I RESPONSIBILITY

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NOTES:

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SIGNAT RE (1) DATE SlGNATUR7) DATE NOTE

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ES-201, Page 27 of 28

ES-201 Examination Securit,r Agreement ‘ Form S-2O14

I Pre-Examlnatlon

I acknowtedge that I have acquired specialized knowledge about the NRC hcer,sing examinations scheduled for the week(s) of [I 3-LZ/( I as of the dateof my signature I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by theNRC chief examiner I understand that I am not to instruct evaluate, or provide performance feedback to those applicants scheduled to be administeredthese licensing examinations from this date until completion of examination administration except as specifically noted below and authonzed 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 indirectfeedback) Furthermore, I am aware of the physical security measures anct requirements (as documented in the facility licensees procedures) andunderstand that violation of the conditions of this agreement may result in cancellation of the examinations anWor an enforcement action against me orthe facility licensee I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination securitymay have been compromised

2. Post-ExamInation

To the best of my knowJdge I did not drvulge to any unauthorized persons any information concerning the NRC llcensing examinations administereddunng the week(s) ofZJaa,tqzO(( From the date that I entered into this secunty agreement until the completion of examination administration I did notInstruct evaluate or provide performance feedback to those applicants who were administered these licensing examinations except as specifically notedbelow and authonzed by the NRC

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

II3t sficY

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VES2Oi, Page 27o1 2W .V . . .


1. Pre-Examination

-r 1’17j?/I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) ofi‘ — as of the dateof my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by theNRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administeredthese 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 indirectfeedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee’s procedures) andunderstand that violation of the conditions of this agreement may result in cancellation of the examinations andIor an enforcement action against me orthe facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination securitymay 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 administeredduring the week(s) of 4Zo(f From the date that I entered into this security agreement until the completion of examination administration, I did notinstruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically notedbelow and authorized by the NRC.

PRINTED NAME

1. CMits 4. M4jui2. LMYTe.J (-Iw4sr3. 7rpee,4. 5e if5.L1,2’ S6iT6. M,?etk,7 iZ.

JOB TITLE I RESPONSIBILITY

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SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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7 L— 94-,/ c

10..11.12.13.14.15.NOTES:

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ES-201, Page 27 of 28

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

Facility: McGuire Date of Examination: 6/27/11

Exam Level (circle one): RO (only) I SRO(l) I SRO (U) Operating Test No.: Ni i-i

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

. Type Code* SafetySystem / JPM Title Function

A. 010 Pressurizer Pressure Control SystemS,D,P,L 3

Place LTOP in Service

B. 028 Hydrogen Recombiner and Purge Control SystemS,D,P,EN,A 5

Manually Align Phase B HVAC Equipment

C. 004 Chemical and Volume Control SystemS,N,A I

Emergency Borate the RCS

D. EPE 074 Inadequate Core CoolingS,M,EN,A 4P

Establish NC System Feed and Bleed

E. 045 Main Turbine Generator SystemS,D,A 4S

Perform the Main Turbine Overspeed Trip Test

F. APE 067 Plant Fire On SiteS,N,A 8

Restore from a Fire in the Unit 1 Cable Spreading Room

G. 006 Emergency Core Cooling SystemS,D,EN 2

Increase Pressure in Cold Leg Accumulator 1A

H. 062 AC Electrical DistributionS,N 6

Restore Power to 6900 V Buses

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

I. 061 AuxiliarylEmergency Feedwater System

Start and Stop # I Turbine Driven CA Pump

J. 086 Fire Protection System

Manually Initiate Diesel Generator Halon

K. EPE 055 Station Blackout

Establish NC Pump Seal Injection from the SSF


ES-3d Control Room/In-Plant Systems Outline Form ES-301-2-

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

Type Codes Criteria for RO / SRO-l / SRO-U

(A)lternate path 4-6 (5) /4-6 (5) I 2-3 (2)(C)ontrol room(D)irect from bank 9 (6) / 8 (6) I 4 (2)(E)mergency or abnormal in-plant 1 (1) / 1 (1) I 1 (1)(EN)gineered Safety Feature

- / - / 1 (1) (Control Room System)

(L)ow-Power/ Shutdown 1 (1) / 1 (1)1 1 (1)(N)ew or (M)odifled from bank including 1 (A) 2 (5) / 2 (5) I 1 (3)(P)revious 2 exams 3 (2) / 3 (2)/ 2 (1) (Randomly Selected)

(R)CA 1 (1 )I1 (1)/1 (1)(S)imulator

JPM Summary

JPM A This is a bank JPM. The Operator will be placed in a situation in which Unit 1 is in acooldown and depressurization in accordance with OP/11A16100/SD-4, (Cooldown to240 Degrees F). The operator will be told that the 1A and lB NCPs are operating, thatNC System pressure is 347 psig and NC System temperature is 310-320°F. Theoperator will be asked to place the LTOP System in operation in accordance withEnclosure 4.1 of OP/1/A/6100/SO-10, (Controlling Procedure for LTOP Operation), andmonitor for proper operation.

JPM B This is a bank JPM. The operator will be told that they are the Unit 2 BOP, and that Unit1 has experienced a Large Break LOCA. The operator will be directed to check Phase BHVAC equipment in accordance with Enclosure 2, (Phase B HVAC Equipment), ofEP/1/A15000/E-0, (Reactor Trip or Safety Injection). During the performance ofEnclosure 2, the operator will recognize that neither train of the VE and VX Systemsautomatically started (Alternate Path). The operator will be expected to manually startthe both Trains of VE and VX Systems.

JPM C This is a new JPM. The operator will be told that with the plant at power, a ReactorMakeup System failure has resulted automatic Control Rod insertion, that MCBAnnunciator 1AD-2, A9, CONTROL ROD BANK LO LIMIT, has alarmed, thatAP/1/A15500/38 (Emergency Boration) has been entered, and that the lB BA TransferPump is OOS. The operator will be directed to initiate Emergency Boration byperforming Step 12 of AP/1/A15500/38 (Emergency Boration). When the operatorattempts to start the 1A BA Transfer Pump the Boric Acid Filter will become plugged(Alternate Path). The operator will be expected to establish Emergency Boration fromthe FWST.

JPM D This is a modified JPM that uses Bank JPM PS-NC-46 as its basis. The operator will betold that a Reactor Trip on Lo-Lo S/G Level has occurred due to the loss of both MainFeedwater Pumps, that the CA System will not start, that EP/1/A15000/FR-H.1 (Loss ofSecondary Heat Sink) has been implemented, and that Feed and Bleed initiation criteriahas been met. The operator will be directed to initiate an NC System Feed and Bleed byperforming Steps 22 - 28 of EP/1/A15000/FR-H.1 (Loss of Secondary Heat Sink). When

NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2DRAFT (R’LF!NALJ

the operator attempts to verify that a high pressure injection flowpath exists, it will beobserved that INI-9A and lOB (Cold Leg Injection Isolation Valves) have failed to openautomatically (Alternate Path). The operator will be expected to establish an RCS feedand bleed flowpath such that all NCP’s off, flow is High Pressure Injection flow isestablished through Nl-9/10, at least two Pzr PORVs are open.

JPM E This is Bank JPM OP-MC-GEN-EHC-154A. The operator will be told that Unit 1 isstarting up after a refueling outage, that the Turbine/Generator is off line and rolling at1800 RPM in preparation for performing PT111A14250/004C (Turbine OPC andMechanical Overspeed Trip Test), that all prerequisite conditions have been met, thattwo operators have been stationed at the Turbine as required, and that communicationshave been established with all involved. The operator will be directed to complete theTurbine OPC and Mechanical Overspeed Trip Test per PT/i /A/4250/004C (Turbine OPCand Mechanical Overspeed Trip Test), starting with Step 12.7. The operator will raiseTurbine speed to OPC setpoint, and then raise speed until the Turbine Overspeed tripshould be actuated (Alternate Path). The operator is expected to recognize the turbinehas failed to trip at the expected setpoint and then manually trip the Turbine.

JPM F This is a new JPM. The operator will be told that Unit I is at 100% power and that a firehas been reported in the Unit I Cable Spreading Room. The operator will be told thatthe crew has implemented AP/i/A15500/45 (Plant Fire) and is presently in Enclosure 17(AB 750’ Unit I Cable Spreading Room Fire Unit 1 and Unit 2 Actions. The operator willalso be told that several control room switch manipulations have been made, that theFire Brigade has reported that the fire is no longer active, and that Station Managementhas indicated that the crew may return Control Room controls to normal as identifiedwithin Enclosure 17. The operator will be directed to restore the Control Room controlsto normal by performing Step 2i.a through e of Enclosure 17 (AB 750’ Unit I CableSpreading Room Fire Unit 1 and Unit 2 Actions) of AP/i/A15500/45 (Plant Fire). Theoperator will be expected to determine that one Pzr PORV has inadvertently opened,and take action to isolate it by ensuring that its isolation valves is closed, and bydirecting that its motor breaker be opened (Alternate Path). The operator will then openthe remaining Pzr PORV isolation valves, direct that the motor breaker for 1CA-7AB beclosed, and open the manual loaders for the main Steam Line PORVs while the valvesremain closed.

JPM G This is Bank JPM ECC-CLA-69. The operator will be told that the plant is at 100% power,that the IA Cold Leg Accumulator Abnormal Press Alarm is received, and that the IACold Leg Accumulator pressure is approximately 590 psig and holding. The operator willbe directed to increase the IA Cold Leg Accumulator pressure to 625±5 psig perOP/i /A16200/009 (Accumulator Operation) Enclosure 4.3 (Adjusting AccumulatorsPressure). The operator will be expected to align N2 to CLA 1A and raise pressure togreater than 620 psig and less than 639 psig.

JPM H This is a new JPM. The operator will be told that a total loss of Offsite Power hasoccurred at both Units, that Unit 1 has tripped from 100% power, that AP/i/A/5500/07(Loss of Electrical Power), Case I (Loss of Normal Power to 1 ETA and 1 ETB) has beenimplemented and that the crew is preparing to restore power to the 6900VAC Buses.The operator will be directed to restore power to the 6900V buses by performing Steps43.n-q of AP/1/A/5500/07 (Loss of Electrical Power), Case I (Loss of Normal Power toI ETA and I ETB). The operator will be expected to re-energizes all four 6900V Busesper AP/I/A15500/07.

NUREG-I 021, Revision 9

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

JPM I This is a modified JPM that uses Bank JPM CF-CA-256. The Operator will be told thatUnit I is at 100% power when the OAC alarm M1AI 276 (Ui CA Temp at Chk Vlv ICA37) is received, that the temperature in the TD CA Pump discharge to the 1D SIG is223°F, and that the CRS has determined the #1 Turbine Driven CA Pump should bestarted to cool the piping to the 1 D SIG. The operator will be directed to locally start theUnit 1 Turbine Driven CA Pump per OPI1IA/6250/002 (Auxiliary Feedwater System),Enclosure 4.4 (Manual Operation of #1 TD CA Pump). The operator will be expected tolocally start the #1 TD CA Pump and align the CA System valves to provide the requiredcooling.

JPM J This is Bank JPM SS-RFY-019. The operator will be told that the control power for theIA DIG Halon Fire Protection System has been tagged out for Electrical Maintenance,that the Halon Bank transfer switch is selected to the “MAIN” position, that they havebeen assigned as the Fire Watch, and that a Fuel Oil fire starts in the 1A DIG Room.The operator will be directed to Initiate a MANUAL PNEUMATIC actuation of the HalonFire Suppression System to the IA DIG Room, per OP/0/A16400/002B (Halon FireProtection System) Enclosure 4.3 (Local Manual Actuation of DIG Halon). The operatorwill be expected to manually align Halon to the IA DIG Room and manually-pneumatically discharge the system into the room.

JPM K This is Bank JPM-CP-AD-O6IT. The Operator will be placed in a situation in which aLoss of All AC has occurred on Unit 1. The operator will be told that EPI1IAI5000IECA-0.0, “Loss of All AC Power’ has been implemented, and that one operator has beendispatched to 1 ETA to swap 1 EMXA4. The operator will be asked to obtain the BrownFolder at SSF and complete Enclosure I, (Unit 1 SSF-ECA-0.0 Actions), which willrequire the re-establishment of NCP Seal Water flow. The re-establishment of NCP SealWater flow is a Time Critical Task (8 minutes) as identified in PT/0/A146001113,(Operator Time Critical Task Verification), Enclosure 13.11, (Initiate SSF NCP SealInjection and Swap to the SSF).

NUREG-l 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1DRAFT (Rev_FINAL)

Facility: McGuire Date of Examination: 6/27/11

Examination Level: RO Operating Test Number: Nil-i

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

2.1.20 (4.6) Ability to interpret and execute procedureConduct of Operations steps

M,R

JPM: Perform a Manual Shutdown MarginCalculation

2.1.25 (3.9) Ability to interpret reference materials, suchConduct of Operations as graphs, curves, tables, etc.

M,R

JPM: Calculate Dilution Needed for a SpecifiedRod Change

2.2.3 (3.8) Knowledge of the design, procedural, andEquipment Control

D Roperational differences between units.

JPM: Use Main Generator Capability Curve

2.4.34 (4.2) Knowledge of RO responsibilitiesEmergency performed outside the main control roomProcedures/Plan during an emergency and the resultant

N, R operational effects.

JPM: Independently Verify Spent Fuel Pool LevelAdjustment

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking 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) (1)

(N)ew or (M)odified from bank (> 1) (3)(P)revious 2 exams ( 1; randomly selected) (0)


ES-301 Administrative Topics Outline Form ES-301-lDRAFT (Rev_FINAL)

RO Admin JPM Summary

Ala This is a modified version bank JPM ADM-NRC-AI-011. The operator will betold that Unit 1 was shutdown to Mode 3, 15 minutes ago, that they are theOATC, that the reactivity computer (REACT) is out of service, and thatpreparations are being made to commence a plant cooldown. The operator willbe directed to perform a Shutdown Margin Calculation per 0P101A161001006Enclosure 4.5 (Shutdown Margin - Unit Shutdown, Modes 5, 4, or 3 WithoutXenon Credit), and identify whether or not the cooldown can be initiated underthe present conditions. The operator by completing Enclosure 4.5 of0P111A161001006 (Reactivity Balance Calculation) will determine the EffectiveBoron Concentration to assure SDM to be 1382 ppm, and identify that the NCSystem must be borated to this value before the cooldown can be initiated.

Aib This is a modified JPM using Bank JPM OP-MC-JPM-ADM-214 as its basis. Theoperator will be given a set of initial conditions and told that it is desired to insertthe Bank D Control Rods about 35 steps. The Operator will be given the CoreData Book and asked to manually determine the amount of Reactor MakeupWater that will be necessary to add, to complete the rod height adjustment.

A2 This is Bank JPM-ADM-NRC-A2-003. The operator will told that Unit I is at 74%reactor power, given a set of Main Generator conditions, and that a powerincrease to 100% is imminent. The operator will be directed to determine themaximum permissible generator load, the maximum reactive load the desiredvoltage per the Generator Voltage Operating Schedule assuming a power factorof 0.85 is maintained constant during the power increase. The operator willselect the correct Generator Capability Curve and use it to determine themaximum permissible generator load and reactive load; and then determine thedesired voltage per the Generator Voltage Operating Schedule.

A4 The operator will be told that the Emergency Plan has been implemented due toan attack on the facility, that the hostile threat has been eliminated and the plantis now recovering, however heavy damage has been sustained. The operatorwill also be told that AP/1/A15500/24 (Loss of Plant Control Due to Fire orSabotage) has been implemented on Unit 1, that the Standby Makeup Pump isoperating to provide inventory to the NC System, and that the crew is attemptingto maintain Spent Fuel Pool Level greater than minus 2 feet in accordance withEnclosure 4.4 (Spent Fuel Pool Level Control) of OP/1/A16200/005 (Spent FuelCooling System). The operator will be provided with paperwork associated withthe control of the SFP level and other pertinent data, and then directed performan independent verification (IV) ensuring that the total desired SFP Level changeis within the guidance of the Enclosure 4.4 of OP/1/A16200/005; and then toidentify any corrections or changes that are needed. The operator will beexpected to review Table 4.4-1 of Enclosure 4.4 of OP/1/A16200/005 and identifythree errors, and make the required corrections.

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1DRAFT (Rev_FINAL)

Facility: McGuire Date of Examination: 6/27/1 1

Examination Level: SRO Operating Test Number: Nil-i

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

2.1.7 (4.7) Ability to evaluate plant performance andConduct of Operations make operational judgments based on

operating characteristics, reactor behavior,M, R and instrument interpretation.

JPM: Calculate QPTR

2.1.25 (4.2) Ability to interpret reference materials, suchConduct of Operations as graphs, curves, tables, etc.

M,R

JPM: Calculate Reactor Vessel Head VentingTime

2.2.18 (3.9) Knowledge of the process for managingEquipment Control maintenance activities during shutdown

operations, such as risk assessments, workM, R prioritization, etc.

JPM: Perform a Thermal Margin Determination

2.3.4 (3.7) Knowledge of radiation exposure underRadiation Control normal or emergency conditions.

D, R

JPM: Take On-Site Protective Actions During aGeneral Emergency

2.4.41 (4.6) Knowledge of emergency action levelEmergency thresholds and classifications.Procedures/Plan M, R

JPM: Classify an Emergency Event

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retakingonly 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) (1)(N)ew or (M)odified from bank ( 1) (4)(P)revious 2 exams ( 1; randomly selected) (0)


ES-301 Administrative Topics Outline Form ES-301-1DRAFT (Rev FINAL)

SRO Admin JPM Summary

Ala This is a modified JPM using bank JPM ADM-NRC-Al-004 as its basis. With theplant at 99% power, the operator will be told that the Unit I QAC failed and is notoperating, and that the crew has implemented PT/I/A14600/021A (Loss of OperatorAid Computer while in Mode I). The operator will be directed to calculate QPTR inaccordance with Enclosure 13.5, Part A of PT/i/A14600/21A. The operator will beexpected to calculate QPTR, and determine that Technical Specification 3.2.4(Quadrant Power Tilt Ratio) has been exceeded, and identify any required TechnicalSpecification ACTION.

Aib This is a modified JPM using Bank JPM-ADM-NRC-Al-018 as its basis. Theoperator will be told that McGuire Unit I is in a Post-Accident situation, that they areavailable for assignment within the Operational Support Center (OSC), and given aset of NC System and Containment conditions, along with a copy ofEP/1/A15000/FR-l.I (Response to Voids in Reactor Vessel). The operator will bedirected to calculate maximum head venting time in accordance with Enclosure I ofFR-I .3, and be required to calculate this time within an allowable band.

A2 This is a modified JPM using Bank JPMs ADM-NRC-A2-06 as its basis. Theoperator will be told that Unit 1 was shutdown 24 days ago for a mid-cycle outageafter 200 days of operation, that Unit I is currently in Mode 5 with the NC system is145 F and “A” Train ND in service; and that preparations are being made to lowerNC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Drainingthe NC System) of OP/i 1A161 O0/SD-20 (Draining the NC System). The operator willbe directed to complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers)to determine the new thermal margin with NC system level at 9 inches above HotLeg Centerline and make the appropriate notifications. The operator will beexpected to complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8(Shift Supervision Turnovers) with a new thermal margin calculated and documentedon Attachment 12.7 (Shutdown Assessment Status) and on MC-6, as well as makethe required notifications to the CCC and STA.

A3 This is a Bank JPM. The operator will be told that a General Emergency has beendeclared and that, as the OSM, they have initiated and completed the immediateactions of Enclosure 4.1 of RP/0/A15700/004 (General Emergency). Additionally, theoperator will be told that On-Site Protective Actions are being considered inaccordance with RP/0/A/5700/004, and that there are reports of an injured non-ambulatory person on-site. The operator will be required to select two rescuers,from among seven potential rescuers, and dispatch them to the injured individual bycompleting Enclosure 4.4, (Request for Emergency Exposure),of RP/0/A/5700/004.

A4 This is a modified form of a Bank JPM. The operator will be given a timeline ofevents that span a few hours, and asked to classify the event. The operator will beexpected to recognize that a Site Area Emergency exists upon entry into the EOPnetwork.


ES-3d Operating Test Quality Checklist Form ES-301-3(Rev_FINAL)

Facility: McGuire Date of 6/27/11 Operating Test Number: Nil-iExamination:

1. GENERAL CRITERIAInitials

a b*

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

b. There is no day-to-day repetition between this and other operating tests to be administered 9’ ‘ ,/during this examination. ‘ii 4

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

d. Overlap with the written examination and between different parts of the operating test iswithin acceptable limits. p1— \r’ 4

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

2. WALK-THROUGH CRITERIA - -

a. Each JPM includes the following, as applicable:* initial conditions

initiating cues* references and tools, including associated procedures* reasonable and validated time limits (average time allowed for completion) and specific

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

- detailed expected actions with exact criteria and nomenclature p_ 4- system response and other examiner cues

- statements describing important observations to be made by the applicant

- criteria for successful completion of the task

- identification of critical steps and their associated performance standards

- restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-l and 2) have not caused the test to deviate from any of Ithe acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC “<.0

examinations) specified on those forms and Form ES-201-2.

3. SIMULATOR CRITERIA - -

The associated simulator operating tests (scenario sets) have been reviewed in accordance with —

Form ES-301-4 and a copy is attached.

,4a. Author David Lazarony, Western Technical Services, Inc. 6/10/1 1

b. Facility Reviewer (*) o)c. NRC Chief Examiner(#) ‘,, L,

d. NRC Supervisor /F/,

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

# Independent NRC reviewer initial items in Column “c’; chief examiner concurrence required.


ES-301 Simulator Scenario Quality Checklist Form ES-301-4(Rev FINAL)

Facility: McGuire Date of Exam: 6/27/11 Scenario Numbers: 1 2 3 Operating Test No.: Nil-i

QUALITATIVE ATTRIBUTES Initials

a b*

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

2. The scenarios consist mostly of related events. CL.— j1V 4:i3. 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 ,pC•

. 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 withouta credible preceding incident such as a seismic event. Jj.L ‘t;;

5. The events are valid with regard to physics and thermodynamics. 56. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete P

evaluation results commensurate with the scenario objectives. 21— f7. If time compression techniques are used, the scenario summary clearly so indicates. Operators

‘ )have sufficient time to carry out expected activities without undue time constraints. i’) A

8. The simulator modeling is not altered. .

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance frdeficiencies or deviations from the referenced plant have been evaluated to ensure that functionalfidelity is maintained while running the planned scenarios. ,L_ I4_t’ ,

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

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

12. Each applicant will be significantly involved in the minimum number of transients and events 4specified on Form ES-301-5 (submit the form with the simulator scenarios). Pt..

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

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

1. Total malfunctions (5-8) 8 9 5 j2. Malfunctions after EOP entry (1-2) 2 2 1

3. Abnormal events (2-4) 3 4 3 j... ,/

4. Major transients 1 . —— ——— —-—

5. EOPs entered/requiring substantive actions (1-2) 1 2 1 p_. ../ .

6. EOP contingencies requiring substantive actions (0-2) 0 1 0 7t- ./

7. Critical tasks (2-3) 2 2 2


ES-301 Transient and Event Checklist Form ES-301-5(Rev_FINAL)

Facility: McGuire Date of Exam: 6/27/il Operating Test No.: Nil-i

A E ScenariosP V NO1i-i-i NOli-l-2 Nil-i -3 T MP E (Spare) 0 IL N

CREW CREW CREW T NI T POSITION POSITION POSITION A

C L MA T UN Y M(*)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 00 C P 0 C P 0 C P 0 C P

RX 0 1 1 0

NOR 1 1,2 3 1 1 1

SROU-1 I/C 2,3, 3,4, 8 4 4 24,5, 5

8

MAJ 6 6 2 2 2 1

TS 34 4 4 0 2 2

RX 2 1 1 1 0

NOR 1 1 1 1 1

SROU-2 I/C 2,3, 35 7 4 4 24,5’

8

MAJ 6 6 2 2 2 1

TS 3.4 2 0 2 2

pj( 1 1 1 1 0

NOR 1,2 2 1 1

SROI-1 I/C 2,5 3,4, 52

5

MAJ 6 6 2 2 2 1

TS 2 0 2 2

RX 1 1 1 1 0

NOR 1,2 2 1 1

SROI-2 I/C 2,5 34 5 4 4 25

MAJ 6 6 2 2 2 1

TS 2 0 2 2

Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-i event numbers for each event type; TS are not applicable for ROapplicants. ROs must service in both the “at-the-controls (ATC)” and “balance-of-plant (BOP)” positions; Instant SRO5 must serve in both the SRO and theATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per SectionC.2.a of Appendix 0. (*) 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 theapplicant’s competence count toward the minimum requirements specified for the applicant’s license level in the right-hand columns.

NUREG 1021 Revision 9

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

Facility: McGuire Date of Exam: 6/27/11 Operating Test No.: Ni i-i

A E ScenariosP V NO11-i-i NOii-i-2 Nii-i-3 T MP E (Spare) 0L N

CREW CREW CREW CREW T NI T POSITION POSITION POSITION POSITION A I

C L MA T UN Y j)T P S A B S A B S A B S A B R I U


2 1 1 1 0

NOR 1 1 1 1 1

RO-1 I/C 45 35 5 4 4 2

MAJ 6 6 2 2 2 1

TS 0 0 2 2

RX 1 1 1 0

NOR 1 1 1 1 1

RO-2 I/C 2,5 34 42

MAJ 6 6 2 2 2 1

TS 0 0 2 2

RX 2 1 1 1 0

NOR 1 1 1 1 1

RO-3 I/C 45 35 5 4 4 28

MAJ 6 6 2 2 2 1

TS 0 0 2 2

Instructions:

1. check the applicant level and enter the operating test number and Form ES-D-i event numbers for each event type; TS are not applicable for ROapplicants. 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 theATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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



ES-301 Transient and Event Checklist Form ES-301-5(Rev_FINAL)

Facility: McGuire Date of Exam: 6/27/li Operating Test No.: Nil-i

A E ScenariosP V NOii-l-l NOii-i-2 Nll-i-3 T MP E (Spare) 0L N

CREW CREW CREW T NI T POSITION POSITION POSITION A

C L MA T uN YT P 5 A B S A B S A B S A B R I U


R)( 0 1 1 0

NOR 1 2 1 1 1

SROU-1 I/C 2,3, 12, 9 4 4 24,5, 3,5

8

MAJ 6 6 2 2 2 1

TS 3,4 2,3 4 0 2 2

RX 4 1 1 1 0

NOR 1 1 1 1 1

SROU-2 I/C 2,3, 1,57 4 4 2

4,5,8

MAJ 6 6 2 2 2 1

TS A 2 0 2 2

RX 1 1 1 1 0

NOR 1 1 1 1

SROI-1 I/C 2,5 1,2, 64 2

3,5

MAJ 6 6 2 2 2 1

TS 2,3 2 0 2 2

RX 1 1 1 1 0

NOR 4 1 1 1 1

SROI-2 I/C 2,5 6 4 4 2

MAJ 6 6 2 2 2 1

TS 2,3 2 0 2 2

Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for ROapplicants. ROs must service in both the “at-the-controls (ATC)” and “balance-of-plant (BOP)” positions; Instant SRO5 must serve in both the SRO and theATC positions, including at least two instrument or component (lIC) malfunctions and one major transient, in the ATC position. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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



ES-301 Transient and Event Checklist Form ES-301-5(Rev_FINAL) - - -

Facility: McGuire Date of Exam: 6/27/il Operating Test No.: Nil-i

A E ScenariosP V NOii-i-i NOii-i-2 Nii-l-3 T MP £ (Spare) 0 IL N

CREW CREW CREW CREW T NI T POSITION POSITION POSITION POSITION A I

C L MA T uN M(*)T P S A B S A B S A B S A B R I U


RX 4 1 1 1 0NOR 1 1 1 1

RO-1 I/c 4,5, 1,5 5 4 4 28

MAJ 6 6 2 2 2TS 0 0 2 2

RX 1 1 1 1 1 0NOR 4 1 1 1 1

RO-2 I/c 2,5 2,3 44 4 2

MAJ 6 6 2 2 2 1

TS 0 0 2 2

RX 4 1 1 1 0NOR 1 1 1 1

RO-3 IC 4,5, 1,5 5 4 4 28

MAJ 6 6 2 2 2 1TS 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 ROapplicants. ROs must service in both the flat-the-controls (ATC)” and balance-of-plant (SOP) positions; Instant SRO5 must serve in both the SRO and theATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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

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


ES-301 Competencies Checklist Form ES-301-6-

(cyjINALL

Facility: McGuire Date of Examination: 6/27/11 Operating Test No.: Nil-i

APPLI CANTS

SRO (U/I) RO/ATC BOP

Competencies SCENARIO SCENARIO SCENARIO

1 2 3 4 1 2 3 4 1 2 3 4

Interpret/Diagnose 1,2,3 1,2,4 1, 2,3,4Events and 1-8 1-8 1-7 5,6, .5,6,

2,3,54,5,6 6,7, 1-7

Conditions 7,8 8 8

Comply With and Use 1,2,3 1,2,4 235 1, 244,5,6 6,7, 1-7

Procedures (1)1-8 1-8 1-7 5,6, 56

7 ‘7:8’6,7

8 8

Operate Control 1,2,51,2,4 1, 2,3,4

NA NA NA .5,6,2,3,5

4,5,6 .6,7, 1-7Boards (2) 6,7,8

.6,78 8

Communicate and18 18 17 1-8 1-8 1-7 1-8 1-8 1-7

Interact

DemonstrateSupervisory Ability 1-8 1-8 1-7 NA NA NA NA NA NA

(3)

Comply With and Use3,4 2,3 3,4 NA NA NA NA NA NA

Tech. Specs. (3)

Notes:

(1) Includes Technical Specification 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 theexaminers to evaluate every applicable competency for every applicant.


2011 MNS SR IRC ExaminationES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3

Question K/A Number K/A System Tier/Group Importance RO/SROK/A Description

SYSOO3 Al .03 Reactor Coolant Pump System (RCPS) T/G 2/1 RO 2.6 SRO 2.6

1 Ability to predict and/or monitor changes in parameters RCP motor stator winding temperatures(to prevent exceeding design limits) associated with

_______

operating the RCPS controls including: (CFR: 41.5 /45.5)

2 SYSOO3 K6.14 Reactor Coolant Pump System (RCPS) T/G 2/1 RO 2.6 SRO 2.9

2 Knowledge of the effect of a loss or malfunction on the Starting requirementsfollowing will have on the RCPS: (CFR: 41.7 / 45/5)

3 SYSOO4 A2.28 Chemical and Volume Control System T/G 2/1 RO 3.7 SRO 4.3

Ability to (a) predict the impacts of the following Depressurizing of RCS while it is hotmalfunctions or operations on the CVCS; and (b) basedon those predictions, use procedures to correct, control,or mitigate the consequences of those malfunctions oroperations: (CFR: 41.5/43/5/45/3/45/5)

4 SYSOO5 2.4.31 Residual Heat Removal System (RHRS) TIG 2/1 RO 4.2 SRO 4.1

SYSOO5 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFR:41.10/45.3)

______________ _______________

5 SYSOO5 K6.03 Residual Heat Removal System (RHRS) T/G 2/1 RO 2.5 SRO 2.6

Knowledge of the effect of a loss or malfunction on the RHR heat exchanger

________

following will have on the RHRS: (CFR: 41.7 / 457)

________

- --

________ _________________ _________

6 SYSOO6 A3.03 Emergency Core Cooling System (ECCS) T/G 2/1 RO 4.1 SRO 4.1

6 Ability to monitor automatic operation of the ECCS, ESFAS-operated valvesincluding: (CFR: 41.7 / 45.5)

______________ ________ ___________________

7 SYSOO6 K5.02 Emergency Core Cooling System (ECCS) T/G 2/1 RO 2.8 SRO 2.9

Knowledge of the operational implications of the following Relationship between accumulator volume and pressureconcepts as they apply to ECCS: (CFR: 41.5 /457)

_____________— _________________________

Pagelof 15

2011 MNS SR RC Examination

ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3

Question K/A Number K/A System Tier/Group !mportance RO/SROK/A Description

8SYSOO7 2.4.31 Pressurizer Relief TanklQuench Tank System (PRTS) T/G 2/1 RO 4.2 SRO 4.1

8 SYSOO7 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFIR:41.10 /45.3)

9SYSOIO K6.O1 Pressurizer Pressure Control System (PZR PCS) T/G 2 / 1 RO 2.7 SRO 3.1

Knowledge of the effect of a loss or malfunction of the Pressure detection systemsfollowing will have on the PZR PCS: (CFR: 41.7 / 45.7)

_______________________________ _______________

10 SYSOI2 A2.02 Reactor Protection System (RPS) T/G 2/1 RO 3.6 SRO 3.9

10 Ability to (a) predict the impacts of the following Loss of instrument powermalfunctions or operations on the RPS; and (b) based onthose predictions, use procedures to correct, control, ormitigate the consequences of those malfunctions oroperations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)

11 SYSOI2 K2.O1 Reactor Protection System (RPS) T/G 2/1 RO 3.3 SRO 3.7

11 Knowledge of bus power supplies to the following: (CFR: RPS channels, components, and interconnections41.7)

____________ ______________ __________ ____

12 SYSOI3 K2.O1 Engineered Safety Features Actuation System (ESFAS) T/G 2/1 RO 3.6* SRO 3.8

12 Knowledge of bus power supplies to the following: (CFR: ESFAS/safeguards equipment control41.7)

___________________ ___________________________________________ _____________________

13 SYSOI3 K5.02 Engineered Safety Features Actuation System (ESFAS) T/G 2/1 RO 2.9 SRO 3.

13 Knowledge of the operational implications of the following Safety system logic and reliabilityconcepts as they apply to the ESFAS: (CFR: 41.5 / 45.7)

14 SYSO22 K4.03 Containment Cooling System (CCS) T/G 2/1 RO 3.6* SRO 4.0

14 Knowledge of CCS design feature(s) and/or interlock(s) Automatic containment isolationwhich provide for the following: (CFR: 41.7)

Page2of 15

K/A NumberK/A Description

SYSO26 Al .02

Page3of 15

ES 401, Rev9

Question K/A System

2011 MNS SR. RC Examination

Combined PWR Written Examination Outline Form ES-401-2/3

Tier/Group Importance RO/SRO

15Containment Spray System (CSS) T/G 2/1 RO 3.6* SRO 3.9

15 Ability to predict and/or monitor changes in parameters Containment temperature(to prevent exceeding design limits) associated withoperating the CSS controls including: (CFR: 41.5 / 45.5)

16SYSO39 A2.05 Main and Reheat Steam System (MRSS) T/G 2/1 RO 3.3 SRO 3.6

16 Ability to (a) predict the impacts of the following Increasing steam demand, its relationship to increases in reactor powermalfunctions or operations on the MRSS; and (b) basedon predictions, use procedures to correct, control, ormitigate the consequences of those malfunctions oroperations:_(CFR: 41.5 / 43.5 / 45.3 / 45.13)

________________

17 SYSO39 K4.05 Main and Reheat Steam System (MRSS) TIG 2/1 RO 3.7 SRO 3.7

17 Knowledge of MRSS design feature(s) and/or interlock(s) Automatic isolation of steam linewhich provide for the following: (CFR: 41.7)

18 SYSO59 A3.06 Main Feedwater (MFW) System T/G 2/1 RO 3.2* SRO 3.3

18 Ability to monitor automatic operation of the MEW, Feedwater isolationincluding: (CFR: 41.7 / 45.5)

__________________ ___________________________

19 SYSO6I K2.02 Auxiliary I Emergency Feedwater (AFW) System TIG 2/1 RO 37* SRO 3.7

19 Knowledge of bus power supplies to the following: (CFR: AFW electric drive pumps41.7)

_________ _________________ __________ ________________ ____________

20 SYSO62 A4.04 AC Electrical Distribution System T/G 2/1 RO 2.6 SRO 2.7

20 Ability to manually operate and/or monitor in the control Local operation of breakersroom: (CFR: 41.7 / 45.5 / to 45.8)

____________

21 SYSO62 K3.03 AC Electrical Distribution System T/G 2 / 1 RO 3.7 SRO 3.9

21 Knowledge of the effect that a loss or malfunction of the DC systemac distribution system will have on the following: (CFR:41.7 / 45.6)

_____________________ ___________________

2011 MNSSR RC ExaminationES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-213


22 SYSO63 K3.0l DC Electrical Distribution System TIG 2/1 RO 3•7* SRO 4.1

22 Knowledge of the effect that a loss or malfunction of the ED/GDC electrical system will have on the following: (CFR:41.7 / 45.6)

23 SYSO64 Al .04 Emergency Diesel Generator (ED!G) System T/G 2/1 RO 2.8 SRO 2.9

23 Ability to predict and/or monitor changes in parameters Crankcase temperature and pressure(to prevent exceeding design limits) associated withoperating the ED/G system controls including: (CFR:41.5 / 45.5)

24 SYSO64 KI .02 Emergency Diesel Generator (EDIG) System T/G 2/1 RO 3.1 SRO 3.6*

24 Knowledge of the physical connections and/or cause- D/G cooling water systemeffect relationships between the ED/G system and thefollowing systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

25 SYSO73 KI .01 Process Radiation Monitoring (PRM) System TIG 2/1 RO 3.6 SRO 3.9

25 Knowledge of the physical connections and/or cause- Those systems served by PRMseffect relationships between the PRM system and the

_________

following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

26 SYSO76 A4.04 Service Water System (SWS) T/G 2/1 RO 35* SRO 3.5

26 Ability to manually operate and/or monitor in the control Emergency heat loadsroom: (CFR: 41.7 / 45.5 to 45.8)

27 SYSIO3 A3.01 Containment System T/G 2/1 RO 3.9 SRO 4.2

27 Ability to monitor automatic operation of the containment Containment isolationsystem, including: (CFR: 41.7/45.5)

28 SYSIO3 2.4.6 Containment System TIG 2/1 RO 3.7 SRO 4.7

28 SYS1O3 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)

Page4of 15


ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-213


29SYSOO2 KI .17 Reactor Coolant System (RCS) T/G 2/2 RO 3.5 SRO 38

29 Knowledge of the physical connections and/or cause- MT/Geffect relationships between the RCS and the followingsystems: (CFR: 41.2 to 41.9 I 45.7 to 45.8)

30SYSOI I K2.02 Pressurizer Level Control System (PZR LCS) TIG 2/2 RO 3.1 SRO 3.2:

30 Knowledge of bus power supplies to the following: (CFR: PZR heaters41.7)

31SYSOI4 K3.02 Rod Position Indication System (RPIS) T/G 2/2 RO 2.5 SRO 2.8*

31 Knowledge of the effect that a loss or malfunction of the Plant computerRPIS will have on the following: (CFR: 41.7 / 45.6)

32SYSOI6 A2.01 Non-Nuclear Instrumentation System (NNIS) T/G 2 / 2 RO 3.0* SRO 3.1*

32 Ability to (a) predict the impacts of the following Detector failuremalfunctions or operations on the NNIS; and (b) basedon those predictions, use or mitigate the consequencesof those malfunctions or operations: (CFR: 41.5 / 43.5 /45.3 I 45.5)

__________________________ ___________________________________________________

33 SYSO29 A3.01 Containment Purge System (CPS) T/G 2/2 RO 3.8 SRO 4.0

Ability to monitor automatic operation of the Containment CPS isolationPurge System including: (CFR: 41.7 I 45.5)

______________ __________________________________________

34 5YS033 Al .02 Spent Fuel Pool Cooling System (SFPCS) TIG 2/2 RO 2.8 SRO 3.3

Ability to predict and/or monitor changes in parameters Radiation monitoring systems(to prevent exceeding design limits) associated withSpent Fuel Pool Cooling System operating the controlsincluding: (CFR: 41.5 / 45.5)

Page5of 15

TIG 2/2 RO 39 SRO 4.5

Knowledge of less than or equal to one hour Technical Specification actionstatements for systems. (CFR: 41.7 /41.10/43.2 /45.13)

_____

T/G2/2 RO 3.2

MSIVs

SRO 3.6

2011 MNS SR RC ExaminationES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3


35 SYSO34 2.2.39 Fuel Handling Equipment System (FHES)

SYSO34 GENERIC

3636

SYSO35 K6.O1 Steam Generator System (SIGS)

Knowledge of the effect of a loss or malfunction on thefollowing will have on the S/GS: (CFR: 41.7 /45.7)

37 SYSO7I K5.04 Waste Gas Disposal System (WGDS) T/G 2/2 RO 2.5 SRO 3.11

Knowledge of the operational implication of the following Relationship of hydrogen/oxygen concentrations to flammabilityconcepts as they apply to the Waste Gas DisposalSystem:_(CFR: 41.5/45.7)

______________________

38 SYSO79 A4.01 Station Air System (SAS) T/G 2/2 RO 2.7 SRO 2.7

38 Ability to manually operate and/or monitor in the control Cross-tie valves with lASroom: (CFR: 41.7/45.5to45.8)

_____

39 EPEOO7 EAI .01 Reactor Trip T/G 1/1 RO 3.7 SRO 3.4

Ability to operate and monitor the following as they apply T/G controlsto a reactor trip: (CFR 41.7 / 45.5 / 45.6)

___________ _____________________________________________

40 APEOO8 AK2.01 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck 0 T/G 1/1 RO 2.7* SRO 2.7

40 Knowledge of the interrelations between the Pressurizer ValvesVapor Space Accident and the following: (CFR 41.7 /45.7)

____________ __________________

41 T/G 1/1 RO 3.0 SRO 33*

41 S/Gs

EPEOO9 EK2.03 Small Break LOCA

Knowledge of the interrelations between the small breakLOCA and the following: (CFR 41.7 / 45.7)

Page6of 15

Knowledge of the interrelations between the ReactorCoolant Pump Malfunctions (Loss of RC Flow) and thefollowing: (CFR 41.7 /45.7)

APEO22 AAI .07

ES 401, Rev9

Question K/A System


Combined PWR Written Examination Outline

TIG ill RO 4.1

Natural circulation and cooling, including reflux boiling.

Form ES-401-2/3

K/A Number Tier/Group Importance RO/SROK/A Description

42EPEOII EKIOl Large Break LOCA SRO 4.4

42 Knowledge of the operational implications of the followingconcepts as they apply to the Large Break LOCA: (CFR41.8/41.10/45.3)

43APEOI 51017 AK2.10 Reactor Coolant Pump (RCP) Malfunctions TIG 1/1 RO 18* SRO 2.8

RCP indicators and controls

44Loss of Reactor Coolant Makeup T/G 1/1 RO 2.8* SRO 2.7

Ability to operate and / or monitor the following as they Excess letdown containment isolation valve switches and indicatorsapply to the Loss of Reactor Coolant Makeup: (CFR 41.7/ 45.5 / 45.6)

_________________

45 APEO25 AA2.01 Loss of Residual Heat Removal System (RHRS) TIG 1 /1 RO 2.7 SRO

Ability to determine and interpret the following as they Proper amperage of running LPI/decay heat removal/RHR pump(s)apply to the Loss of Residual Heat Removal System:(CFR: 43.5 /45.13)

____________

46 APEO27 2.1.31 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1/1 RO 4.6 SRO 4.3

46 APEO27 GENERIC Ability to locate control room switches, controls, and indications, and todetermine that they correctly reflect the desired plant lineup. (CFR: 41.10 /45.12)

_________

47 EPEO29 2.2.25 Anticipated Transient Without Scram (ATWS) T/G 1/1 RO 3.2 SRO 4.2

EPEO29 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions foroperations and safety limits. (CFR: 41.5 / 41.7 / 43.2)

48 EPEO38 EAI .11 Steam Generator Tube Rupture (SGTR) T/G 1/1 RO 3.8 SRO 3.9’

48 Ability to operate and monitor the following as they apply S/G level indicatorstoa SGTR: (CFR41.7/45.5/45.6)

2.9

Page7of 15




49

APEO4O AK3.O1 Steam Line Rupture TIC 1/1 RO 4.2 SRO 4.5

Knowledge of the reasons for the following responses as Operation of steam line isolation valvesthey apply to the Steam Line Rupture: (CFR 41 .5,41.10 /45.6 145.13)

___________________________ _______________ ________ ____________

50 APEO54 AA2.03 Loss of Main Feedwater (MFW) TIC 1/1 RO 4.1 SRO 4.2

50 Ability to determine and interpret the following as they Conditions and reasons for AFW pump startupapply to the Loss of Main Feedwater (MFW): (CFR: 43.5 /45.13)

_________________

51 EPEO55 EK1.02 Loss of Offsite and Onsite Power (Station Blackout) TIC 1/1 RO 4.1 SRO 4.4

51 Knowledge of the operational implications of the following Natural circulation coolingconcepts as they apply to the Station Blackout: (CFR

— 41.8/41.10/45.3)

_______ ___________________________________________________

52 APEO56 2.2.40 Loss of Offsite Power TIC ill RO 3.4 SRO 4.7

52 APEO56 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5/45.3)

53 APEO57 AK3.01 Loss of Vital AC Electrical Instrument Bus TIC 1/1 RO 4.1 SRO 4.1

Knowledge of the reasons for the following responses as Actions contained in EOP for loss of vital ac electrical instrument busthey apply to the Loss of Vital AC Instrument Bus: (CFR41.5,41.10 / 45.6 / 45.13)

54 APEO62 AA2.01 Loss of Nuclear Service Water TIC 1/1 RO 2.9 SRO 3.5

Ability to determine and interpret the following as they Location of a leak in the SWSapply to the Loss of Nuclear Service Water: (CFR: 43.5 /45.13)

_______________________________________________________

Page8of 15

2011 MNS SR IRC Examination



55 APEO65 AK3.08 Loss of Instrument Air T/G 1/1 RO 3.7 SRO 3.9

Knowledge of the reasons for the following responses as Actions contained in EOP for loss of instrument airthey apply to the Loss of Instrument Air: (CFR 41.5,41.10/45.6 /45.13)

_____ _______________

56 WEO5 EKl.3 Loss of Secondary Heat Sink TIG 1/1 RO 3.9 SRO 4.1

56 Knowledge of the operational implications of the following Annunciators and conditions indicating signals, and remedial actionsconcepts as they apply to the (Loss of Secondary Heat associated with the (Loss of Secondary Heat Sink).Sink)(CFR: 41 .8/41.10, 45.3)

____ ______________

57 APEOO3 AA2.03 Dropped Control Rod T/G 1/2 RO 3.6 SRO 3

Ability to determine and interpret the following as they Dropped rod, using in-core/ex-core instrumentation, in-core or loopapply to the Dropped Control Rod: (CFR: 43.5/45.13) temperature measurements

58 APEO24 AK2.O1 Emergency Boration T/G 1/2 RO 2.7 SRO 2.7

58 Knowledge of the interrelations between Emergency ValvesBoration and the following: (CFR 41.7 / 45.7)

_______ _________

59 APEO59 AA2.05 Accidental Liquid Radioactive-Waste Release T/G 1 I 2 RO 3.6 SRO 3.9’

Ability to determine and interpret the following as they The occurrence of automatic safety actions as a result of a high PRM systemapply to the Accidental Liquid Radwaste Release: (CFR: signal43.5 / 45.13)

______________ ______________ ________________________________________

60 APEO6I AK3.02 Area Radiation Monitoring (ARM) System Alarms T/G 1/2 RO 3.4 SRO 3.6;

60 Knowledge of the reasons for the following responses as Guidance contained in alarm response for ARM systemthey apply to the Area Radiation Monitoring (ARM)System Alarms: (CFR 41.5,41.10 / 45.6 / 45.13) -

61 EPEO74 EK2.O1 Inadequate Core Cooling T/G 1/2 RO 3.6 SRO 3.8:

61 Knowledge of the interrelations between the Inadequate RCPCore Cooling and the following: (CFR 41.7 / 45.7)

______________

Page9of 15

2011 MNS SR ARC ExaminationES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-213


62 WEO8 EKl.2 Pressurized Thermal Shock T/G 1/2 RO 3.4 SRO 4.0

62 Knowledge of the operational implications of the following Normal, abnormal and emergency operating procedures associated withconcepts as they apply to the (Pressurized Thermal (Pressurized Thermal Shock).Shock)

________

(CFR:41.8/41.10,45.3) V

63 WEI 3 EKI .3 Steam Generator Overpressure T/G 1/2 RO 3.0 SRO 3.2

63 Knowledge of the operational implications of the following Annunciators and conditions indicating signals, and remedial actionsV

concepts as they apply to the (Steam Generator associated with the (Steam Generator Overpressure).Overpressure)(CFR: 41.8 /41.10, 45.3)

64 WEI4 EAI.1 High Containment Pressure T/G 1/2 RO 3.7 SRO 3.7

64 Ability to operate and / or monitor the following as they Components, and functions of control and safety systems, includingapply to the (High Containment Pressure) instrumentation, signals, interlocks, failure modes, and automatic and manual(CFR: 41.7 / 45.5 / 45.6) features.

65 WEI6 2.2.12 High Containment Radiation T/G 1/2 RO 3.7 SRO 4.1.

65 WE16 GENERIC Knowledge of surveillance procedures. (CFR: 41.10/45.13)

66 GEN2.1 2.1.17 GENERIC - Conduct of Operations T/G 3/0 RO 3.9 SRO 4.0’

66 Conduct of Operations Ability to make accurate, clear, and concise verbal reports. (CFR: 41.10 /45.12/45.13)

67 GEN2.1 2.1.34 GENERIC - Conduct of Operations TIG 3/0 RO 2.7 SRO 3.5

67 Conduct of Operations Knowledge of primary and secondary plant chemistry limits. (CFR: 41.10 / 4.5/45.12)

68 GEN2.1 2.1.37 GENERIC - Conduct of Operations T/G / 0 RO 4.3 SRO 4.6

68 Conduct of Operations Knowledge of procedures, guidelines, or limitations associated with reactivitymanagement. (CFR: 41.1 /43.6/45.6)

Page 10 of 15




69GEN2.2 2.2.14 GENERIC - Equipment Control T/G 3/0 RO 3.9 SRO 4.3;

69 Equipment Control Knowledge of the process for controlling equipment configuration or status.

_________________________

(CFR:41.10/43.3/45.13)

70GEN2.2 2.2.3 GENERIC - Equipment Control T/G / 0 RO 3.8 SRO 3.9’

70 Equipment Control (multi-unit license) Knowledge of the design, procedural, and operationaldifferences between units. (CFR: 41.5 / 41.6 / 41.7 / 41.10 / 45.12)

71GEN2.3 2.3.5 GENERIC - Radiation Control TIG 3/0 RO 2.9 SRO 2.9’

71 Radiation Control Ability to use radiation monitoring systems, such as fixed radiation monitorsand alarms, portable survey instruments, personnel monitoring equipment, etc.

________________

(CFR: 41.11 /41.12/43.4/45.9)

72 GEN2.3 2.3.7 GENERIC - Radiation Control T/G 3/0 RO 3.5 SRO 3.6;

72 Radiation Control Ability to comply with radiation work permit requirements during normalorabnormal conditions. (CFR: 41.12/45.10)

73 GEN2.4 2.4.1 GENERIC - Emergency Procedures I Plan T/G 3/0 RO 46 SRO 4.8;

Emergency Procedures / Plan Knowledge of EOP entry conditions and immediate action steps. (CFR: 41.10 /43.5/45.13)

74 GEN2.4 2.4.34 GENERIC - Emergency Procedures I Plan T/G / ° RO 4.2 SRO 4.1

Emergency Procedures I Plan Knowledge of RO tasks performed outside the main control room during anemergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13)

75 GEN2.4 2.4.4 GENERIC - Emergency Procedures I Plan T/G / 0 RO 4.5 SRO 4.7

Emergency Procedures / Plan Ability to recognize abnormal indications for system operating parameters thatare entry-level conditions for emergency and abnormal operating procedures.(CFR: 41.10/43.2 / 45.6)

Pagellof 15

2011 MNS SR JRC Examination



76SYSOO6 2.4.20 Emergency Core Cooling System (ECCS) TIG 2/1 RO 3.8 SRO 4.

76 SYSOO6 GENERIC Knowledge of the operational implications of EOP warnings, cautions, andnotes. (CFR: 41.10/43.5/45.13)

77SYSIO3 2.4.41 Containment System TIG 2/1 RO 2.9 SRO 4.6

SYSIO3 GENERIC Knowledge of the emergency action level thresholds and classifications. (CFR:

_____________________ _______________

41.10/43.5/45.11)

78 SYSO59 A2.12 Main Feedwater (MFW) System TIG 2/1 RO 3.1* SRO 32

78 Ability to (a) predict the impacts of the following Failure of feedwater regulating valvesmalfunctions or operations on the MEW; and (b) basedon those predictions, use procedures to correct, control,or mitigate the consequences of those malfunctions oroperations: (CFR: 41.5 /43.5 / 45.3 / 45.13)

79 SYSO64 A2.05 Emergency Diesel Generator (EDIG) System TIG 2/1 RO 3.1 SRO 3.2*

Ability to (a) predict the impacts of the following Loading the ED/Gmalfunctions or operations on the ED/G system; and (b)based on those predictions, use procedures to correct,control, or mitigate the consequences of thosemalfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 /45.13)

80 SYSO73 A2.02 Process Radiation Monitoring (PRM) System T/G 2/1 RO 2.7 SRO 3.2

80 Ability to (a) predict the impacts of the following Detector failuremalfunctions or operations on the PRM system; and (b)based on those predictions, use procedures to correct,control, or mitigate the consequences of thosemalfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 /45.13)

Page 12 of 15

2011 MNS SR ARC Examination

ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-213


81SYSO34 A1.02 Fuel Handling Equipment System (FHES) T/G 2/2 RO 2.9 SRO 3.7

81 Ability to predict and/or monitor changes in parameters Water level in the refueling canal(to prevent exceeding design limits) associated withoperating the Fuel Handling System controls including:(CFR: 41.5/45.5)

82 SYSO72 2.4.31 Area Radiation Monitoring (ARM) System TIG 2/2 RO 4.2 SRO 4.1

82 SYSO72 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFIR:41.10/45.3)

83 5YS086 A2.O1 Fire Protection System (FPS) TIG 2/2 RO 2.9 SRO 3.1

83 Ability to (a) predict the impacts of the following Manual shutdown of the FPSmalfunctions or operations on the Fire Protection System;and (b) based on those predictions, use procedures tocorrect, control, or mitigate the consequences of thosemalfunctions or operations: (CFR: 41.5 I 43.5 / 45.3 /45.13)

_______________

84 EPEOO7 EA2.04 Reactor Trip T/G 1/1 RO 4.4 SRO 4.6

84 Ability to determine or interpret the following as they apply If reactor should have tripped but has not done so, manually trip the reactorto a reactor trip: (CFR 41.7 / 45.5 / 45.6) and carry out actions in ATWS EOP

85 EPEOO9 EA2.11 Small Break LOCA TIG 1/1 RO 3.8 SRO 4.1

85 Ability to determine or interpret the following as they apply Containment temperature, pressure, and humidityto a small break LOCA: (CFR 43.5 /45.13)

86 EPEOI 1 2.4.31 Large Break LOCA T/G 1/1 RO 4.2 SRO 4.1

86 EPEOI 1 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFR:41.10 /45.3)

Page 13 of 15

88

88

89SYSO62 2.1.20 AC Electrical Distribution System

89 SYSO62 GENERIC

90APEOO3 AK3.04 Dropped Control Rod

90 Knowledge of the reasons for the following responses asthey apply to the Dropped Control Rod: (CFR 41 .5,41.10I 45.6 I 45.13)

_________________

91 APEO36 2.2.12 Fuel Handling Incidents

91 APEO36 GENERIC

92APEO37 AA2.10 Steam Generator (SIG) Tube Leak

92 Ability to determine and interpret the following as theyapply to the Steam Generator Tube Leak: (CFR: 43.5 /45.13)

________ ____________

93APEO67 2.2.25 Plant Fire On Site

APEO67 GENERIC

94 GEN2.1 2.1.20

Conduct of Operations

ES 401, Rev9

Question

87

87

2011 MNS SR JRC Examination

Combined PWR Written Examination Outline Form ES-401-2/3

Tier/Group Importance RO/SRO

Auxiliary feed flow

T/G 1/1 RO 4.1 SRO 4.3

T/G 1/1 RO 4.3 SRO 4.4

K/A Number K/A SystemK/A Description

APEO56 AA2.72 Loss of Offsite Power

Ability to determine and interpret the following as theyapply to the Loss of Offsite Power: (CFR: 43.5 / 45.13)

APEO57 2.1.23 Loss of Vital AC Electrical Instrument Bus

APEO57 GENERIC Ability to perform specific system and integrated plant procedures during allmodes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)

TIG 2/1 RO 4.6 SRO 4.6

________________

Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)

TIG 1/2 RO 3.8* SRO 4.11

Actions contained in EOP for dropped control rod

TIG 1/2 RO 3.7 SRO 4.11

Knowledge of surveillance procedures. (CFR: 41.10/45.13)

T/G 1/2 RO 3.2 SRO 4.11

Tech-Spec limits for RCS leakage

T/G 1/2 RO 3.2 SRO 4.

Knowledge of the bases in Technical Specifications for limiting conditions foroperations and safety limits. (CFR: 41.5 / 41.7 / 43.2)

GENERIC - Conduct of Operations T/G 3/0 RO 4.6 SRO 4.6

Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)

Page 14 of 15

2011 MNS SR ARC ExaminationCombined PWR Written Examination Outline

GENERIC - Conduct of Operations T/G 3/0 RO 2.2 SRO 3.9

______________

Knowledge of the fuel-handling responsibilities of SROs. (CFR: 41.10 I 43.7).

TIG 3/0 RO 2.6 SRO 3.9

Knowledge of the process for managing maintenance activities duringshutdown operations, such as risk assessments, work prioritization, etc. (CFR:

____________

41.10/43.5/45.13)

GENERIC - Equipment Control T/G 3/0 RO 2.3 SRO 3.4

Knowledge of maintenance work order requirements. (CFR: 41.10/43.5/

_____________

45.13)

GENERIC - Radiation Control T/G 3/0 RO 3.2 SRO 3.7

Knowledge of radiation exposure limits under normal or emergency conditions.(CFR:41.12143.4145.10)

GENERIC - Emergency Procedures! Plan T/G 3/0 RO 4.0 SRO 4.2

Knowledge of abnormal condition procedures. (CFR: 41.10 /43.5 /45.13)

GENERIC - Emergency Procedures I Plan T/G 3/0 RO 3.4 SRO 4.4

ES 401, Rev9

Question K/A System

9595

9696

K/A NumberK/A Description

GEN2.1 2.1.35

Conduct of Operations

GEN2.2 2.2.18

Equipment Control

GENERIC -

Form ES-401-213

Tier/Group Importance ROISRO

Equipment Control

GEN2.2 2.2.19

Equipment Control

9797

9898

9999

100100

GEN2.3 2.3.4

Radiation Control

GEN2.4 2.4.11

Emergency Procedures / Plan

GEN2.4 2.4.23

Emergency Procedures / Plan Knowledge of the bases for prioritizing emergency procedure implementationduring emergency operations. (CFR: 41.10 / 43.5 / 45.13)

Page 15 of 15

ES-401 Record of Rejected K/As Form ES-401-4

Tier / Randomly Reason for RejectionGroup Selected KA

2 / 1 SYSO61 K2.03 Q(19) MNS has no diesel driven AFW pumps. New K/A randomly selected by ChiefExaminer - SYS061 K2.02 (02/24/11)

2 / 2 SYS034 2.4.45 Q(35) KA rejected due to inability to write operationally valid question. New KA (SYSO34G2.2.39) randomly selected with concurrence of Chief Examiner. HCF 3/28/11

1 I 1 APEO54 AA2.08 Q(50) Rejected KA due to inability to write a discriminating question with this KA. NewKA (APEO54 AA2..03) randomly selected with concurrence from Chief Examiner. HCF3/28/11

1 / 2 APEOS9 AA2.02 Q(59) Rejected KA due to inability write a valid question for the KA. New KA (APEO59AA2.05) randomly selected with concurrence of Chief Examiner. HCF 3/28/11

1 / 2 WEO1 EA1.1 Q(62) Unable to write discrimminating RO level question for this KA. New KA (WEO8EK1.2) randomly selected with concurrence of Chief Examiner. HCF 3/30/11

1 / 2 WE14 EK3.3 Q(64) Rejected K/A due to inability to write discrimminating question. Randomly selectednew K/A (WE14 EA1.1) with concurrence of Chief Examiner. HCF 5/24/11

3 / 0 GEN2.4 2.4.32 Q(74) MNS does not have a response procedure for loss of all annunciators. New K/Arandomly selected by Chief Examiner - 2.4.34 (02/24/11)

2 / 1 SYSO22 2.4.41 Q(77) Cannont construct a question because the CCS has not link to Generic 2.4. Newsystem K/A (SYS1O3) randomly selected by the lead examinier.

1 / 1 APEO57 2.1.28 Q(88) K/A is NOT SRO-level knowledge. New K/A randomly selected by Chief Examiner -

APEO57 G2.1.23 (02/24/11)

1 / 2 APEOO3 AA2.04 Q(90) Can not match this KA at the SRO Level. New KA randomly selected withconcurrence of the Chief Examiner. HCF 3/28/11

1 / 2 APEO37 AA2.13 Q(92) K/A is NOT SRO-level. New K/A randomly selected by Chief Examiner - APEO37AA2.10 (02/24/11)

3 / 0 GEN2.1 2.1.14 Q(94) K/A is RO-level knowledge. New K/A randomly selected by Chief Examiner -

G2.1.20 (02/24/11)

3 / 0 GEN2.3 2.3.5 Q(98) K/A is RO-level knowledge. New K/A randomly selected by Chief Examiner(02/24/11)

ES-401 Written Examination Quality Checklist Form ES-401-6

Facility: McGuire Nuclear Station Date of Exam: 6/27/2011 Exam Level: RD SRO

Initial

Item Description a b* c*

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

2. a. NRC K/As are referenced for all questions.b. Facility learning objectives are referenced as available. P

3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 l,At”

4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions wererepeated from the last 2 NRC licensing exams, consult the NRR CL program office).

5. Question duplication from the license screening/audit exam was controlledas idicated below (check the item that applies) and appears appropriate:.1pe audit exam was systematically and randomly developed; or..4he audit exam was completed before the license exam was started; or

the examinations were developed independently; orthe licensee certifies that there is no duplication; orother (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified Newfrom the bank, at least 10 percent new, and the restnew or modified); enter the actual RD / SRO-onlyquestion distribution(s) at right. 22 I 9 9 / 1 44 / 15

7. Between 50 and 60 percent of the questions on the RD Memory C/Aexam are written at the comprehension/ analysis level;the SRO exam may exceed 60 percent if the randomlyselected K/As support the higher cognitive levels; enter 36 I 10 39 I 15 4fthe actual RD / SRO question distribution(s) at right.

8. References/handouts provided do not give away answersor aid in the elimination of distractors. 0’ p

9. Question content conforms with specific K/A statements in the previously approvedexamination 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. Jf %.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. \J

Printed Name / Signature Date

a. Author . • Q-tb. Facility Reviewer(*)

c. NRC Chief Examiner (#) E,LL-’,,1 Le. . Z, /d. NRC Regional Supervisor

Note: * The facility reviewer’s initials/signature are not applicable for NRC-developed examinations.# Independent NRC reviewer initial items in Column c”; chief examiner concurrence required.

ES-401 Written Examination Review Worksheet -- McGuire ROISRO 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 TIF Cred. Partial Job- Minutia #1 Back- 0= SRO B/MIN UIE/S ExplanationFocus Dist. Link units ward K/A Only

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

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

2. Enter the level of difficulty (LOD) of each question using a 1 — 5 (easy — difficult) rating scale (questions in the 2 —4 range are acceptable).3. Check the appropriate box if a psychometric flaw is identified:

• The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).• The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).• The answer choices are a collection of unrelated true/false statements.• The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.• One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if a job content error is identified:• The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).• The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).• The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).• The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

7. Based on the reviewer’s 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).

1. 2. 3._Psychometric_Flaws 4. Job Content Flaws 5. Other J 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 ExplanationFocus Dist. Link units ward K/A Only

1 H 2 f N E Change wording in bullet 3 to read: At 1400 the following NC Pump

I indications are noted:. Revised as suggested (OK)

2 F 1 N S Loll Revised stem. Licensee stated it was a requiredknowledge for the RO to understand pump startlstopoperation. Accepted question.


(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S ExplanationFocus Dist. Link units ward K/A Only

3 H 2 N S Ken had a problem. First said the question did not match k)a. thensaid distractors a and b were not plausible. Ken said he looked at itthis morning and came to that conclusion. (Reviewed questionwith S.G. Concluded that question matched the K/A anddistractors were plausible. Question is OK. (5/26).

4 H 2 X 5? Not sure why you use Only. Explain CF & E level increase.Excepted the use of only based on the possibility that therupture valve would rupture and inventory would go to CF&E.Accepted question as is. (OK).

5 H 2 1 B S Repeat from 2009 NRC exam.

Ez_____ fBS(OK)(611)

7 H? X B/M E What is the TS limit for pressure and level? Appears to be unneeded information in the stem. Based on what the question is

. asking, do you need all of the information. Could not locateinformation/set-points for accumulator actuation. Please provide.What caused the injection? Changed wording in the stem. (OK)

8 H X B E/S Need to discuss why you consider having chemistry vent the PRT isplausible. I could not locate lesson plan identified. Made changesto the stem. (OK)

9 H 2 B E Is it possible to identify the channels that failed.. Not able to locatelesson plan. Identified pressure channels as suggested. Didnot really matter based on new design. (OK)

10 U Distractors A & C are not plausible. Do not know of any indicationswhere a reactor trip would be required for the conditions given.Added information to the stem ( instrument power or controlpower). Question should not have been UNSAT. Licenseeprovided information as to why. (E only)

11 ? 1 x N U LOD. It appears that the only information need to answer thequestion is to know the bases of the OT delta T. Immediatelyeliminates two distractors. Please explain the pressure transientand why this is considered plausible. Could there be two correctanswers? What makes this a comprehension level question?Question should have been SAT not IJNSAT. Informationprovided by the licensee provided support for it being a SATquestion, (OK).

}B S (OK)(6/1)

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.Q# LOK LCD —1— — — — —

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia I #1 Back- Q SRC B/M/N U/E/S ExplanationFocus j Dist. Link js ward K/A Only

13 H? 1 N S LCD. 100 % miss rate on validation before bolding “BYPASS.”100% pass rate after bolding. (OK).

14 F [ [ [ [ N [ ? [Lou. Added information to the stem. (OK).

15 H 3 — — — — — — B/M [ s [NRC Exam 2009

16 H 2 N S? Need be make sure that this is an RO question. Concern thatapplicant may say that the actions are directed by the SRO whiletaking actions in AP. Could not locate learning objective with directtie. Although, I do think the question can be answered with systemknowledge. Information identified in Foldout page providesinstruction on what needs to be performed. The Foldout pageis given to the operator. Ok with question.

17 H 2 [ B S I201ONRCExamQ17

18 H 2 [ I [ [ B 5 12005 NRC Exam

1 I ILL _

M S NRC2007Exam

20 F 2 X B U/E There may be more than one correct answer. There appears to bea subset issue with distractors. Minor change to distractor B.Accepted question.

21 } H 2 1 B/M S NRC 2010 exam

22 F 1 N 5 LCD. Discussed on 611. Changed to 2 after discussion withlicensee. Would like to look at after validation (6111)

23 H 1 N 5 LCD. Question proved to be challenging during validation.Decided to accept bases provided by the licensee to changeLOD. Changed LOD from I to 2. (6/1)

24 F 1 [ N S LCD. Will revisit question (6/1)

25 H ] 2 j 1 B S Removed if any from the stem. (OK) (6/1)

H X T B U Failed to meet K/A. Identify what you consider emergency loads.

[ I Agreed. Wrote a new question. (OK).

..L. L — [ fNf S (OK) (6/1)

28 F 2 X B U Distractors B & D are not plausible. Why would anyone think or sayND spray is not available in cold leg rec? Provided a newquestion. OK with new question.


(F/H) (1-5) Stem Cues T/F f Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S ExplanationFocus Dist. Link units ward K/A Only

29 H X N ? Not sure distractors A and D are plausible. Need to discuss. Madechange to distractors A & D. OK with change. Question is SAT

30 H X N UIE Distractors C & D do not appear to be plausible. Three sets ofheaters?? Will look at AP-24. Will revisit on 5/20. S & I reviewedquestion in detail with licensee and concluded that questionwas acceptable. (OK). (5/26).

31 H 3 [ [ [ [ N S Changed LOD to a 3 (OK) (611)

32 F 2 X E Steam is not clear. Consider using: Which one of the followingidentifies the Minimum # of Loops Tavg detectors failures tocause and 2. Re worded stem. Will provide controlbuilders sheet. Accepted question — will look at information.Question determined to be OK.

33 f F [ — —

— N SOK_(6/1)

34 H 2—

N S[(OK) 6/1

35 H N U Distractors A & B appear to be implausible. Why would anyonethink core alteration would continue? Will bring back in themorning. Will need a new question. (5119). Reviewed proposedquestion — still need a new question. (5120). Wrote newquestion. (OK). (5125)

36 H 2 B U/E Distractor C is not plausible. Distractor D needs work. Explainwhy/or how steam line drains would be used for cooldown and whatprocedure you would use. Provided information in procedurewhich indicated TDCA could be used. Question should havebeen SAT. (OK)

___LI_38 U Distractors A and B are not plausible — Pressure only decreases to

88 psig. Changed pressure in the stem to 80 PSIG. Licenseestated that they think it was an oversite on their part. Aftermaking change the question is OK.

39 f F 1 N S [LOD - Revised stem to address concern of two possible

j ?n5w. Changed LOD . from I to 2.(OK)

40 H f 3 f [ [ J B/M S 12010 NRC Exam Q40 Modified

41 H 3 [ [ B/M S 12010 NRC Exam Q41 Modified

T[ E Sl(OK)(6h1)


(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S ExplanationFocus Dist. Link units ward K/A Only

L[r______I__(0611)44 F 1 f N S LOD. Licensee provided additional information as to why k/a

I match —agreed with reason provided. (OK).

45 F 2 B/M S? 2009 NRC Exam Q96. Identify those conditions that are consideredrun-out conditions. Increased flow rate to 3200. Concluded thatif runout condition occurred, pump amps would indicate highand remain stable. Ok with change and question. (OK)

r H [ 2 — —

—

— B S (OK) (6/1)

47 F X N U Consider using valves other that condenser steam dumps.. Steamdumps are not safety related. Revised stem to included TSBases Credited Changed addressed concern of safetyrelated VS non safety related. (OK).

zzzz:_ L±(0(611)49 H X X N U/E Stem appears to be teaching. You state the reason the main steam

isolation actuates as pressure drops from 800 to 700, however youdo not ask why this occurs. You only state that it occurs in Isecond. K/A doesn’t match. Changed stem to address concernand match KIA (OK)

I[Z[ZZZ51 H 3 N S Review question to make sure there is no unnecessary information

provided (is CA isolated to all S/G’s and VI header pressure 0PSIG needed). Removed CA from stem. (OK)

52 H N U Why is this question considered an RO question? The question isasking an RO applicant to answer the question passed on SROresponsibilities. — Did note that question is tied to learningobjective for RO. A second part needs to be added to distractorsA&B to make them plausible. Wrote new question. New questionis ok. Decided to keep the question as is based on the fact thatreferences are provided. May be challenging, however it is tiedto a LP. Question should not have been UNSAT. (OK).

53 H 2 N U/E Damage to instrumentation supplied by the batteries is not plausible.Figure out how to fix this. Need to revisit at site. Reviewed AP-7and revised question — stem and distractors. OK. (5/25)

E[E[EThEEE EEEEOK611

1 2. 3._Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.Q# LOK LOD

— —r — —

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 J Back- Q SRO B/M/N UIEIS ExplanationFocus Dist. Link unitsi ward K/A Only

55 H 3 N ? Please identify where the reasons are identified in the AP. Alsomake sure that there is not more than one correct answer. Could Cbe correct if Train B is not successful? Provided information toaddress concerns. Question is SAT.

56 H 3 x T B E Consider changing the procedure in D to match A Made chang]

I as suggested (OK).

Need to discuss power decrease verses QPTR increase to57 H 2 X N S? ensure plausibility of distractors A and B. AddressedConcerns. (OK)

58 F 2 X N E Stem of the question appears be confusing. Are the bullets reallyneeded or located in the correct place. Could we not make thequestion more challenging by not providing the valve numbers in thestem by asking the applicant to: describe the actions directed in theprocedures for establishing flow in the event in can’t be establishedvia 1 NV-265B? Revised stem and distractors. Question is OK(5123)

59 F 2 [ B S Need to change II to 2. (OK) (6/1)

60 F 2 X X N E/S? Need to look at wording for the alarms given (wording doesn’tappear to be correct). Need to look at the bases/reasons for thesteps identified in the procedure. Made correction to stem andmodified distractors. Provided documentation identifying thereasons. Question is now OK. (5123)

61 H 2 B ? Not sure how you came up with the numbers. Need to explain indetail. Do not know where 21% came from when the value given inthe table indicates 23%. Licensee provided detailed informationas to why the numbers were selected. Question is OK (5123)

62 H 3 X X N E/U/S? Delete the words ‘with regards to in the stem. Please identifystep (5) in FR-P.1 where it directs placing spray in service. Provideprocedural situation/guidance where heater would be placed inservice to prevent exceeding a parameter/limit. information whereplacing heaters in service would. Prove plausibility of distractors A& B. Not enough information provided. Changed distractorsbased on information provided in FR-P.1 that is to be performedafter the soak is completed —Step 4. Based on two implausibledistractors questions should have been a U. Revised questionis OK. 5124.

63 H 2 f f f B 5? Consider changing NR level from 99% to 95%. Made change as

j j j suggested. (OK) 5/24.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.Q# LOK LOD I —

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO B/M/N U/E/S ExplanationFocusj Dist. Link units ward K/A Only

64 F 2 X N E As written the question doesn’t appear to match the K/A. Are theconditions given in the distractors interlocks which would preventoperating components/equipment? Will select a new K/A andquestion (5124) Question should have been a U. Provided a newquestion. (OK) (5/25).

65 F 2 1 x f B/M E NRC 2009 Exam Q 66 Modified. Make sure grammar is correct is

j ] stem (is/are) Made correction. (OK) (5I25).

66 F 2 X N E/S Discuss the wording in bullets 2 & 3: is ‘seen before neededand the alarm was not expected but NOT pre-identified Youas specifically discussed —it was or it was not .... The licenseewanted to leave as is because it added creditability to thedistractors. Agreed to leave as is. (OK). (5125).

67 F 3 1 1 B S The information needed to answer the question is above the bar

j ] inTS. (OK)(6!1)

68 N U/E/S LOD. Consider writing question to identify different power levels forboth units. One unit increasing power following lowering of powerthe other unit increasing power following maintenance /specialtesting and JITT completed for all return to power Wrote newquestion. Old question should have been a U. New question isOK. (5/25)

69 F 1 N S? LOD. The procedure reads “having the Verifer observe the Doer’sinitial action is preferable to having individuals operate thecomponent.” Need to discuss. Is only needed in distractors C & D.Revised question — to address verify valve position that requiresupervisor approval. (OK). (5125)

70 M 2 B/M S 2009 NRC Exam Q73 — Modified

71 F 2 f f B S Used on 2010 McGurie Exam 071

106h1)

[i F 3 1 B S Changed to H (OK) (611)

](oK)(6I1)

75[H[3 JN J(OK)(6I1)

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 BIMIN U/E/S ExplanationFocus Dist. Link units ward K/A Only

Question can be answered with system knowledge only.76 F X N U Both caution statements which are in ES-i .3 are systemknowledge based.This Q is U because it is NOT SRO only.

Agreed with our comment. Provided a new question. Questionas provided appears to be sat. Ned to look at a few morethings. The lesson plan states that RO are responsible.Concluded new question is OK.

77 C 3 S Need to review this to MAKE sure that it is a Site and not a General.Determined classification is correct - a Site. (OK)Consider adding an indication of SG level. This should78 F 2 X E prevent the applicant from making an assumption. In whichcase, based on assumptions made regarding SG level, adifferent answer may be correct. Changed the stem toread.... Based on the above conditions, NCsystem Feedand bleed must be initiated within . Changeddistractors. Question is OK.

79 E Distractor C is not plausible. Changed distractor C. Question isOK.Given the circumstance, it is obvious that the release must80 H X U be stopped/suspended. Therefore A and B are not plausible.Please identify alarms that will be received as a result of thecount rate failing to read less than background.Consider rewriting the stem to state “in addition to stoppingthe release, which one of the following must the SRO do?May be able to add something about EMF-44 tripping andcausing WL-320, WP-35, and WM-46 to isolate.

The question is UNSAT due to two implausible distractorsBased on information provided the VQ system releasewas in progress and certain equipment was operable itwould allow for a continuous release. Question shouldnot have been UNSAT. Question OK as provided.

81 H 3 N S (OK) (5/26)— (OK)(5126)82 F 3 B S— — — — —

— 2009 NRC exam Q 92.lt is not reasonable to believe that a83 H 2 ( B U manual abort of the Halon system can’t be manually undone.Distractors B and D indicate this would occur. Thesedistractors are not plausible. The question is UNSAT due totwo implausible distractors. Is there a reset switchassociated with this? Agreed with comment and there wasoverlay with JPM. Will provide new question (5118).New question is ok. Need to provide definition ofdifferent types of fire watches (5119)

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 ExplanationFocus Dist. Link units ward K/A Only

— — — — — — — — — —

— B2 is a true statement therefore it could be argued as correct84 H X N E on an appeal. Need to make sure that it is totally incorrect.Reviewed bases and determined that distractor was ok.Also revised wording in the stem. Question is OK.

85 H 3 N S In reviewing the question, we concluded that to informationneed to answer the question comes out of the design bases,therefore it is SRO only. Reworded the stem (OK) (5126)

86 H 3 B S Reviewed step RNO 3.c to prove plausibility of Cl and Dl.Question is OK. (5126)

87 H 3 B/M S 2005 NRC Exam Q 15. (OK) (5126)

88 H X N U/S Not sure if this is SRO only. You entered a procedure based on“Loss of Vital or Aux Control Power.” Therefore, I would think thatthat procedure would provide directions to resolve the issue. Oncepower is restored, the control room operator can look at controlboard to verify system status. Changed the wording in stem.Should have been an E. As written the question is OK.

89 H 2 N S (OK) (5126)

90 F 2 N E Remove misaligned and due to xenon oscillation. What results in achange in peacking factors and what affects AFD? Made changes.Provided information on why part A.l was SRO. Question isOK.

91 H N S? I do not have a problem with the question, however, need to makesure it is not a direct lookup. Replaced .99 with .98. Nothingmajor. Question is Ok.

92 H N 5? Need additional information on how you arrived at 6 hoursassociated with T.S. based on conditions given. Provided TSinformation indicating plausibility of using 6 hours. Question isOK.

93 H X X N U 30 minutes is not a plausible distractor. Not able to locate a 30minute requirement any place in the procedure as indicated, Is it notcommon knowledge that closing the PORV block affects theoperability of PORV? Need to explain in more details why thisquestion is SRO only. Could not locate background docunment.Provided information requested which proved question wasSAT. Question should not have been a U. Question is OK.

94 H 2 B S (OK) (5126)

95 F 2 N S Changed to a 2 based on discussion.

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 UIEIS ExplanationFocus Dist. Link units ward K/A Only

96 F 2 N S Changed to a 2 based on discussion. This is the responsibilityof the SRO in the WCC.

97 F 1 N S Need to make sure there are not two correct answers based onStation Manager approval. Changed station manager to SiteV.P. Question is OK.

98 H 2 B S LOD. Made a change to the stem. Validation indicated a highmiss rate on this question. Chang LOD to 2.

99 H B U Question can be answered with RO only knowledge. TS states thatfour loops (iNCP per loop) shall be operable in Modes I & 2. ROknowledge. RO would also know that once high temperatures arereached, action must be taken to trip the pump Will provide anew question (5118). Reviewed new question. Determined itwas acceptable. (5/19)

100 F B U NRC 2009 exam, Q 93. Do not see where bases are beingaddressed. Wrote new question. Will look at question nextweek. Reviewed new question. (OK). (5126).

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

Facility: Date of Exam: ‘7/e/2c,,j Exam Level: ROf SROEJ

Initials

Item Description a b c

1. Clean answer sheets copied before grading fl’4’ /A22. Answer key changes and question deletions justified

and documented fT43 ‘VA 4 j3. Applicants’ scores checked for addition errors 1q, ,,(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 gradesare justified

6. Performance on missed questions checked for trainingdeficiencies and wording problems; evaluate validity s{y’of questions missed by half or more of the applicants

Printed Name/Signature Date

a. Grader .-

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

d. NRC Supervisor (*)

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

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ES-403, Page 6 of 6

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